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Sample records for solve specific technical

  1. 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)

  2. New usable technical specifications

    International Nuclear Information System (INIS)

    Webster, S.A.; Tomasi, L.T.; Bernier, R.A.

    1989-01-01

    After 2 yr of preparation, 1988 finally saw the nuclear industry writing operator-oriented technical specifications. This effort is a continuation of previous efforts to develop improved and usable standard technical specifications (STSs), and is being conducted by the four nuclear steam supply system vendor owners' groups under the auspices of the Nuclear Management Resources Council. Each participant is currently preparing a set of improved STSs based on a writer's guide that was developed through a combined industry effort. In May of 1987, a Human Factors Improvements to Technical Specifications (HFITS) task group was formed to prepare a writer's guide for improved, industrywide STSs. This task group was composed of two representatives from each owners' group, one with a human factors background and one with some operations background. Two documents were prepared in 6 months, a human factors report laying the groundwork for the considerations to go into technical specifications and a writer's guide for their preparation. This paper reports on the application of this writer's guide to the writing of improved STS

  3. Technical specification use and application

    International Nuclear Information System (INIS)

    Williamson, D.; Hoffman, D.R.

    1991-01-01

    Since early 1988 intensive efforts have been under way to produce a new and improved Standard Technical Specification. The program involves a coordinated effort between utility personnel representing each of the four nuclear steam supply system (NSSS) product lines, the NSSS vendors, and the US Nuclear Regulatory Commission (NRC). This intensive work period is actually the culmination of a decade of rhetoric about shortcomings of the existing technical specifications. Work on the improved technical specifications provided a unique forum for intense philosophical discussions between the users and enforcers of technical specifications, the outcome of which could have an impact on all licensees. Some of the more intriguing difficulties in the use and application of existing technical specifications, as well as discussions of the resolutions being applied in the improved technical specifications and the dilemmas remaining to be resolved are discussed in the paper

  4. 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.

  5. Synthesizing Huber's Problem Solving and Kolb's Learning Cycle: A Balanced Approach to Technical Problem Solving

    Science.gov (United States)

    Kamis, Arnold; Khan, Beverly K.

    2009-01-01

    How do we model and improve technical problem solving, such as network subnetting? This paper reports an experimental study that tested several hypotheses derived from Kolb's experiential learning cycle and Huber's problem solving model. As subjects solved a network subnetting problem, they mapped their mental processes according to Huber's…

  6. 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

  7. Trojan technical specification verification project

    International Nuclear Information System (INIS)

    Bates, L.; Rickenback, M.

    1991-01-01

    The Trojan Technical Specification Verification (TTSV) project at the Trojan plant of Portland General Electric Company was motivated by the recognition that many numbers in the Trojan technical specifications (TTS) potentially lacked the consideration of instrument- and/or process-related errors. The plant setpoints were known to consider such errors, but many of the values associated with the limiting conditions for operation (LCO) did not. In addition, the existing plant instrument error analyses were based on industry values that do not reflect the Trojan plant-specific experience. The purpose of this project is to ensure that the Trojan plant setpoint and LCO values include plant-specific instrument error

  8. 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. 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--3.9 of the improved STS

  9. 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. 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 unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

  10. 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

  11. Conversion of NEK standard technical specifications into improved technical specifications

    International Nuclear Information System (INIS)

    Glaser, B.

    2003-01-01

    Neck is currently using a standard format of operation's Technical Specifications - STS (based on NUREG-0452), which are planned to be converted into Improved Technical Specifications - ITS (based on NUREG-1431). To facilitate the development of individual ITS, each reactor vendor owners group (OG) and the NRC staff developed improved standard TS (ISTS). For Westinghouse plants, the ISTS are published as NUREG-1431, and this document is going to be the basis for the new NEK ITS. It has been recognized that nuclear safety in all plants would benefit from improvement and standardization of ITS, so this was also addressed and recognized by the NRC. There are several plants around Europe and US, which have replaced the format into ITS which brings a lot of improvements and practical value in operations. The main objective of conversion is to completely rewrite, reformat, and streamline the existing STS. Emphasis is placed on human factors principles to improve clarity and understanding. The Bases section will be significantly expanded to clarify and better explain the purpose and foundation of each specification. There might be some proposed changes to the existing STS that deviated from the ITS in NUREG-1431 and constitute a relaxation of the existing STS. Each of these additional proposed changes will be described and evaluated in amendment application and justified on a case-by-case basis. Since the NEK is going to operate for more than 20 year without considering life extension, such conversion will be beneficial for operation personnel as well as regulation, surveillance and focus on operation's safety. At the present, only preliminary plan of STS conversion exists, showing the time frame of approximately 2 years of conversion process and numerous tasks that need to be performed. The plan is to begin with process in year 2004 and finish project in 2006, which means use of new ITS in main control room in year 2007. Beside the main process of conversion, there are

  12. 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

  13. Comparison of Traditional and Innovative Techniques to Solve Technical Challenges

    Science.gov (United States)

    Perchonok, Michele

    2011-01-01

    This slide presentation reviews the use of traditional and innovative techniques to solve technical challenges in food storage technology. The planning for a mission to Mars is underway, and the food storage technology improvements requires that improvements be made. This new technology is required, because current food storage technology is inadequate,refrigerators or freezers are not available for food preservation, and that a shelf life of 5 years is expected. A 10 year effort to improve food packaging technology has not enhanced significantly food packaging capabilities. Two innovation techniques were attempted InnoCentive and Yet2.com and have provided good results, and are still under due diligence for solver verification.

  14. 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

  15. Technical specifications for the Bulk Shielding Reactor

    International Nuclear Information System (INIS)

    1982-04-01

    Technical specifications are presented concerning the safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

  16. 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

  17. Guidelines for writing user friendly technical specifications

    International Nuclear Information System (INIS)

    Webster, S.A.; Braun, J.C.; Pearce, R.T.

    1986-01-01

    This study investigates some of the ergonomic considerations of writer's guides for the preparation of instructions. It is a precedent for the preparation of such a writer's guide for technical specifications for nuclear power plants. This writer's guide will be part of a revision to the industry's standard ANSI/ANS 58.4, Criteria for Technical Specifications for Nuclear Power Stations

  18. Improvements to Technical Specifications surveillance requirements

    International Nuclear Information System (INIS)

    Lobel, R.; Tjader, T.R.

    1992-12-01

    In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power

  19. 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

  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. 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. 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

  3. High Flux Isotope Reactor technical specifications

    International Nuclear Information System (INIS)

    1985-11-01

    This report gives technical specifications for the High Flux Isotope Reactor (HFIR) on the following: safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

  4. 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

  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. Technical specifications for the pool critical assembly

    International Nuclear Information System (INIS)

    1978-07-01

    Technical specifications for the ORNL-PCA Reactor are presented concerning safety limits and limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls

  7. Technical specifications and performance of CANDU fuel

    International Nuclear Information System (INIS)

    Sejnoha, R.

    1997-01-01

    The relations between Technical Specifications and fuel performance are discussed in terms of design limits and margins. The excellent performance record of CANDU reactor fuel demonstrates that the fuel design defined in the Technical Specifications (and with it other components of the procurement cycle, such as fuel manufacturing), satisfy the requirements. New requirements, changing conditions of fuel application and accumulating experience make periodic updates of the Technical Specifications necessary. Under the CANDU Owners Group (COG) Working Party 9, a Work Package has been conducted to support the review of the Specifications and the documentation of the rationales for their requirements. So far, the review has been completed for 4 Specifications: 1 for Zircaloy tubing, and 3 for uranium dioxide powder. It is planned to complete the review of all 11 currently used specifications by 1999. The paper summarizes the results achieved to mid 1997. (author)

  8. Technical specifications: Health Physics Research Reactor

    International Nuclear Information System (INIS)

    1979-02-01

    The 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. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

  9. Technical specifications: Tower Shielding Reactor II

    International Nuclear Information System (INIS)

    1979-02-01

    The technical specifications define the key limitations that must be observed for safe operation of the Tower Shielding Reactor II (TSR-II) and an envelope of operation within which there is reasonable assurance that these limits cannot be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

  10. Development of technical specifications for research reactors

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    This standard identifies and establishes the content of technical specifications for research reactors. Areas addressed are: definitions, safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features and administrative controls. Sufficient detail is incorporated so that applicable specifications can be derived or extracted

  11. 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

  12. 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

  13. 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 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. This document 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, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE 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. This document 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

  15. Standard Technical Specifications, Combustion Engineering plants

    International Nuclear Information System (INIS)

    1992-09-01

    This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE 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 SM. 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--3.9 of the improved M

  16. 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

  17. Technical specifications requirements: Automated reasoning applications

    International Nuclear Information System (INIS)

    Lidsky, L.M.; Dobrzeniecki, A.B.

    1990-03-01

    Several software systems were developed and tested to determine what advantages could be gained from explicitly translating complicated regulatory requirements into computerized relationships. The Technical Specifications for US nuclear power plants were chosen as the test-bed application domain, and two analysis systems were developed to monitor plant compliance with operational limits, and track and schedule equipment test and maintenance activities mandated by Technical Specifications. Choosing PROLOG as the computer language to represent these regulatory requirements resulted in a natural match between the semantic structure of the written specifications and the corollary coded rules. Additional research results affirmed the utility of declarative programming styles, explicit management of problem complexity, and attention to the robustness and flexibility of the overall software systems. 5 refs., 2 figs

  18. Risk based technique for improving technical specifications

    International Nuclear Information System (INIS)

    Kim, I. S.; Jae, M. S.; Kim, B. S.; Hwang, S. W.; Kang, K. M.; Park, S. S.; Yu, Y. S.

    2001-03-01

    The objective of this study is to develop the systematic guidance for reviewing the documents associated with the changes of technical specifications. The work done in this fiscal year is the following : surveys in TS requirements, TS improvements and TS regulations in foreign countries as well as Korea, surveys on the state-of-the-art of RITSs and their use in Korea, development of a decision-making framework for both the licensee and the regulation agency, description of risk measures, assessment methodology on STI/AOT, and adverse effects caused by periodic maintenance, which are explained in appendix. The results of this study might contribute to enhancing the quality of the current technical specifications and contribute to preparing the risk informed regulation program using the decision-making framework developed in this study

  19. 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

  20. 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

  1. Standardized Technical Specifications for Westinghouse PWRs

    International Nuclear Information System (INIS)

    1978-01-01

    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 (1) with 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. 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

  2. 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

  3. 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)

  4. Development of a problem solving evaluation instrument; untangling of specific problem solving assets

    Science.gov (United States)

    Adams, Wendy Kristine

    The purpose of my research was to produce a problem solving evaluation tool for physics. To do this it was necessary to gain a thorough understanding of how students solve problems. Although physics educators highly value problem solving and have put extensive effort into understanding successful problem solving, there is currently no efficient way to evaluate problem solving skill. Attempts have been made in the past; however, knowledge of the principles required to solve the subject problem are so absolutely critical that they completely overshadow any other skills students may use when solving a problem. The work presented here is unique because the evaluation tool removes the requirement that the student already have a grasp of physics concepts. It is also unique because I picked a wide range of people and picked a wide range of tasks for evaluation. This is an important design feature that helps make things emerge more clearly. This dissertation includes an extensive literature review of problem solving in physics, math, education and cognitive science as well as descriptions of studies involving student use of interactive computer simulations, the design and validation of a beliefs about physics survey and finally the design of the problem solving evaluation tool. I have successfully developed and validated a problem solving evaluation tool that identifies 44 separate assets (skills) necessary for solving problems. Rigorous validation studies, including work with an independent interviewer, show these assets identified by this content-free evaluation tool are the same assets that students use to solve problems in mechanics and quantum mechanics. Understanding this set of component assets will help teachers and researchers address problem solving within the classroom.

  5. Palisades technical specification conversion from custom to new industry standard

    International Nuclear Information System (INIS)

    Foley, D.J.; Young, B.

    1990-01-01

    Consumers Power Company's (CPCo) Palisades plant is in the process of converting from custom technical specifications to the new industry standard, Restructured Standard Technical Specifications (RSTS). Custom technical specifications were the precursor to standard technical specifications, being issued to plants built prior to 1972. In May 1989, each of the four light water reactor owners' groups completed topical reports presenting their version of Restructured Standard Technical Specifications to the Nuclear Regulatory Commission (NRC). After approval of the owners' groups versions of the RSTs by the NRC, individual operating reactors will begin to make the conversion to the RSTS. Each owners' group has designated a lead plant, which will be the first of that vendor type to convert. All of the lead plants currently operate under standard technical specifications. The content of the RSTS was determined by comparing the standard technical specifications with selection criteria specified in the Commissions Interim Policy Statement

  6. The needs analysis of learning Inventive Problem Solving for technical and vocational students

    Science.gov (United States)

    Sai'en, Shanty; Tze Kiong, Tee; Yunos, Jailani Md; Foong, Lee Ming; Heong, Yee Mei; Mohaffyza Mohamad, Mimi

    2017-08-01

    Malaysian Ministry of Education highlighted in their National Higher Education Strategic plan that higher education’s need to focus adopting 21st century skills in order to increase a graduate’s employability. Current research indicates that most graduate lack of problem solving skills to help them securing the job. Realising the important of this skill hence an alternative way suggested as an option for high institution’s student to solve their problem. This study was undertaken to measure the level of problem solving skills, identify the needs of learning inventive problem solving skills and the needs of developing an Inventive problem solving module. Using a questionnaire, the study sampled 132 students from Faculty of Technical and Vocational Education. Findings indicated that majority of the students fail to define what is an inventive problem and the root cause of a problem. They also unable to state the objectives and goal thus fail to solve the problem. As a result, the students agreed on the developing Inventive Problem Solving Module to assist them.

  7. 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.

  8. Technical specifications for the Oak Ridge Research Reactor

    International Nuclear Information System (INIS)

    1982-03-01

    Technical specifications are presented concerning safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

  9. Synergy of Technical Specification, functional specifications and scenarios in requirements specifications

    NARCIS (Netherlands)

    Miedema, J.; van der Voort, Mascha C.; Lutters, Diederick; van Houten, Frederikus J.A.M.; Krause, Frank-Lothar

    2007-01-01

    In the (mechanical) design process, the requirements specification is a formal registration of the conditions that are imposed on a new or altered product design, both preceding as well as during the corresponding product development cycle. For a long time, the use of technical specifications has

  10. Opening remarks: regulatory initiatives toward improved technical specifications

    International Nuclear Information System (INIS)

    Edison, G.E.

    1985-01-01

    In order to deal with the numerous problems that have evolved over the years with nuclear power plant technical specifications, the Nuclear Regulatory Commission has undertaken some initiatives for improvement: 1) new operating licenses, 2) change to existing operating reactor technical specifications, 3) a broad-scoped reconsideration of the content of technical specifications, and 4) rule changes. It is believed that reliability and risk assessment techniques can be used in conjunction with manufacturer's recommendations and engineering judgment to better define the appropriate scope and depth for technical specification resulting in focusing attention on high risk-worth systems and avoidance of plant shutdown transients both intentionally and unintentionally through provisions of technical specifications

  11. Iteration and Prototyping in Creating Technical Specifications.

    Science.gov (United States)

    Flynt, John P.

    1994-01-01

    Claims that the development process for computer software can be greatly aided by the writers of specifications if they employ basic iteration and prototyping techniques. Asserts that computer software configuration management practices provide ready models for iteration and prototyping. (HB)

  12. PROBLEM-SOLVING METHODS OF PROJECT MANAGEMENT OF TECHNICAL DEVELOPMENT FOR AGRICULTURAL PRODUCERS

    Directory of Open Access Journals (Sweden)

    Александр Васильевич СИДОРЧУК

    2015-05-01

    Full Text Available There have been proposed projects of technical development for agricultural producers. The conclusions about system features research projects that underlie the problem-solving methods of project management, have been made. There have been proved these projects (systems that can be simulated with the help of the research and formalization of many events. These events are components of the seven main factors of the agricultural production. The conclusion about the using the research method of the probabilistic nature events in the field of the crops projects with the help of the statistical and imitational models, have been developed. There have been considered the relation between the forecasting of functional marks of the technological systems and the estimation of their cost. And there have been found the optimum correspondence between parameters of the technical supply and planned features of the crops projects.

  13. Specific Cognitive Predictors of Early Math Problem Solving

    Science.gov (United States)

    Decker, Scott L.; Roberts, Alycia M.

    2015-01-01

    Development of early math skill depends on a prerequisite level of cognitive development. Identification of specific cognitive skills that are important for math development may not only inform instructional approaches but also inform assessment approaches to identifying children with specific learning problems in math. This study investigated the…

  14. 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

  15. Radiological Effluent Technical Specifications (RETS) implementation, Kewaunee Nuclear Power Plant

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) for the Kewaunee Nuclear Power Plant was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7'' of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual and the Radiological Environmental Monitoring Manual were reviewed and generally found to be in compliance with the NRC review guidelines

  16. Technical specification for IR rig manufacture

    Energy Technology Data Exchange (ETDEWEB)

    Han Hyon Soo; Cho, W. K.; Kim, S. D.; Park, U. J.; Hong, S. B.; Yoo, K. M

    2000-10-01

    IR Rig is one of the equipments are required in HANARO core for a radioisotope target. The various conditions like high radiation, high heat, rapid flow and vibration may cause swelling, Brittleness and acceleration of corrosion in HANARO core. These specific problems can be prevented and the safety of such equipment are prerequisite as well as durableness and surveillance. Therefore, the selection of material has to be made on the basis of small cross-section area, low energy emission by the gamma ray due to the absorption of neutron and short half life. The body is consist of aluminum and Inconel-750 was used for the internal spring(coil) which is known to be durable. The whole production process including the purchase of accessory, mechanical processing, welding and assembly was carried out according to the standard procedure to meet the requirement. A design, manufacture, utilization of reactor core and the other relevant uses were fit to class ''T'' to certify the whole process as general. And design, fabrication, analytical test, materials and accessory were carried out based on the ASME, ASTM, ANSI, AWS, JIS and KS standard.

  17. 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

  18. Technical specification upgrading at the Fast Flux Test Facility (FFTF)

    International Nuclear Information System (INIS)

    Baird, Q.L.; Franz, G.R.; Absher, K.R.

    1985-01-01

    The FFTF Technical Specifications were generated in 1977 and 1978 following submittal of the FSAR in 1976. A phased implementation program served to prepare the specifications for each stage of the plant startup with the complete specifications approved and implemented late in 1980 for the first ascent to full power. In January, 1983 WHC undertook an upgrading effort to implement changes to the FFTF technical specifications. This program has been pursued with appropriate attention to the CFR and industry standards and practice. Examples of these changes, discussion of the methods and planned activities for the future will be presented. Technical data will be provided to support the impact of specific limits. The benefits of changes and the criteria for change will be elaborated

  19. Standard technical specifications for Babcock and Wilcox pressurized water reactors. Revision 4. Technical report

    International Nuclear Information System (INIS)

    Virgilio, M.J.

    1980-10-01

    The Standard Technical Specifications for Babcock and Wilcox Pressurized Water Reactors (BandW-STS) is a generic document prepared by the U.S. NRC for use in the licensing process. The BandW-STS provide applicants with model specifications to be used in formulation plant-specific technical specifications required by 10 CFR Part 50, Section 50.36, which set forth the specific characteristics of the facility and the conditions for its operation that are required to provide adequate protection to the health and safety of the public. This document is revised periodically to reflect current licensing requirements

  20. PVUSA model technical specification for a turnkey photovoltaic power system

    Energy Technology Data Exchange (ETDEWEB)

    Dows, R.N.; Gough, E.J.

    1995-11-01

    One of the five objectives of PVUSA is to offer U.S. utilities hands-on experience in designing, procuring, and operating PV systems. The procurement process included the development of a detailed set of technical requirements for a PV system. PVUSA embodied its requirements in a technical specification used as an attachment to its contracts for four utility-scale PV systems in the 200 kW to 500 kW range. The technical specification has also been adapted and used by several utilities. The PVUSA Technical Specification has now been updated and is presented here as a Model Technical Specification (MTS) for utility use. The MTS text is also furnished on a computer disk in Microsoft Word 6.0 so that it may be conveniently adapted by each user. The text includes guidance in the form of comments and by the use of parentheses to indicate where technical information must be developed and inserted. Commercial terms and conditions will reflect the procurement practice of the buyer. The reader is referred to PG&E Report Number 95-3090000. 1, PVUSA Procurement, Acceptance and Rating Practices for Photovoltaic Power Plants (1995) for PVUSA experience and practice. The MTS is regarded by PVUSA as a use-proven document, but needs to be adapted with care and attention to detail.

  1. 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

  2. Technical specifications for the Oak Ridge Critical Experiments Facility

    International Nuclear Information System (INIS)

    Stinnett, R.M.

    1986-01-01

    These Technical Specifications for the Oak Ridge Critical Experiments Facility (CEF) delineate limiting conditions of operation for the facility. The CEF is used primarily for testing the High Flux Isotope Reactor (HFIR) fuel assemblies. Specifically, the Criticality Testing Unit, Liquid (CTUL), located in the CEF, is used for the HFIR fuel assembly test. The test is performed to satisfy the surveillance requirements of the HFIR Technical Specifications. The test is used to determine the water-submerged shutdown margin for each fuel assembly. 11 refs

  3. Technical problems to be solved before the solid oxide fuel cell will be commercialized

    Energy Technology Data Exchange (ETDEWEB)

    Bagger, C.; Hendriksen, P.V.; Mogensen, M. [Riso National Lab., Roskilde (Denmark)

    1996-12-31

    The problems which must be solved before SOFC-systems are competitive with todays power production technology are of both technical and economical nature. The cost of SOFC stacks at the 25 kW level of today is about 30,000 ECU/kW and it is bound to come down to about 500 ECU/kW. The allowable cost of a SOFC system is anticipated to be around 1500 ECU/kW. As part of the Danish SOFC program (DK-SOFC) a 0.5 kW stack was built and tested during the second half of 1995. Based upon the experience gained, an economic analysis has been made. The tools required to approach an economically acceptable solution are outlined below.

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

    International Nuclear Information System (INIS)

    Kimura, C.Y.

    1989-01-01

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

  5. 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

  6. 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/4, 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 specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

  7. 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

  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. Case studies: Risk-based analysis of technical specifications

    International Nuclear Information System (INIS)

    Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

    1987-01-01

    The SOCRATES computer program uses the results of a Probabilistic Risk Assessment (PRA) or a system level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at a plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns with no adverse impacts on risk. Three summaries of case study applications are included to demonstrate the types of results that can be achieved through risk-based evaluation of technical specifications. (orig.)

  10. Technical specifications for mechanical recycling of agricultural plastic waste

    International Nuclear Information System (INIS)

    Briassoulis, D.; Hiskakis, M.; Babou, E.

    2013-01-01

    Highlights: • Technical specifications for agricultural plastic wastes (APWs) recycling proposed. • Specifications are the base for best economical and environmental APW valorisation. • Analysis of APW reveals inherent characteristics and constraints of APW streams. • Thorough survey on mechanical recycling processes and industry as it applies to APW. • Specifications for APW recycling tested, adjusted and verified through pilot trials. - Abstract: 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

  11. 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

  12. 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

  13. 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

  14. 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/4, 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. 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. 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. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document 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

  16. An episodic specificity induction enhances means-end problem solving in young and older adults.

    Science.gov (United States)

    Madore, Kevin P; Schacter, Daniel L

    2014-12-01

    Episodic memory plays an important role not only in remembering past experiences, but also in constructing simulations of future experiences and solving means-end social problems. We recently found that an episodic specificity induction-brief training in recollecting details of past experiences-enhances performance of young and older adults on memory and imagination tasks. Here we tested the hypothesis that this specificity induction would also positively impact a means-end problem-solving task on which age-related changes have been linked to impaired episodic memory. Young and older adults received the specificity induction or a control induction before completing a means-end problem-solving task, as well as memory and imagination tasks. Consistent with previous findings, older adults provided fewer relevant steps on problem solving than did young adults, and their responses also contained fewer internal (i.e., episodic) details across the 3 tasks. There was no difference in the number of other (e.g., irrelevant) steps on problem solving or external (i.e., semantic) details generated on the 3 tasks as a function of age. Critically, the specificity induction increased the number of relevant steps and internal details (but not other steps or external details) that both young and older adults generated in problem solving compared with the control induction, as well as the number of internal details (but not external details) generated for memory and imagination. Our findings support the idea that episodic retrieval processes are involved in means-end problem solving, extend the range of tasks on which a specificity induction targets these processes, and show that the problem-solving performance of older adults can benefit from a specificity induction as much as that of young adults. (PsycINFO Database Record (c) 2014 APA, all rights reserved).

  17. 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

  18. Prototype for an automated technical specification information system

    International Nuclear Information System (INIS)

    Quinn, E.L.; Mills, R.H.; Groves, J.E.

    1985-01-01

    The Southern California Edison (SCE) Automated Technical Specification Information System (ATSIS) at the San Onofre nuclear generating station (SONGS) has been developed as a prototype for an on-line information management system. This system provides an appropriate level of update, inquiry, and report generation capabilities to help support plant operators at SONGS in their efforts to anticipate, identify, document, and track certain actions and activities associated with plant technical specifications and associated limiting conditions of operation (LCOs). Substantially increased emphasis is being placed on adherence to nuclear regulatory requirements and commitments contained on the operating licenses of nuclear power plants. Additionally, as each year passes, such requirements are becoming increasingly detailed and complex, making it more and more difficult to track and ensure total compliance with the many and varied requirements. To assist the operations department at SONGs in meeting their regulatory commitments, in January 1985 SCE commenced gathering together the leading technical expertise available in the industry to develop a computerized system to track all technical specification-related equipment for operability and impact on LCOs

  19. Approval Procedure for Technical Specifications for Procurement by Quotation and Tender

    International Nuclear Information System (INIS)

    Shaharum Ramli; Izhar Abu Hussin; Ying, K.K.

    2015-01-01

    Technical specifications for procurement requires the approval of the Jawatankuasa Penyemak Spesifikasi Teknikal Tender/ Sebutharga Agensi Nuklear Malaysia. This paper provides guidance for those who have to prepare a technical specification. In addition, the technical specification online library is introduced to facilitate them to re-use old technical specifications for new procurements or to make those the bases for drafting new specifications. (author)

  20. The Effects of Experience Grouping on Achievement, Problem-Solving Discourse, and Satisfaction in Professional Technical Training

    Science.gov (United States)

    Mulcahy, Robert Sean

    2010-01-01

    Learners inevitably enter adult technical training classrooms--indeed, in all classrooms--with different levels of expertise on the subject matter. When the diversity of expertise is wide and the course makes use of small group problem solving, instructors have a choice about how to group learners: they may distribute learners with greater…

  1. 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.

  2. 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

  3. Use of probabilistic methods for the improvement of technical specifications

    International Nuclear Information System (INIS)

    Gros, G.; Mattei, J.M.

    1987-11-01

    The technical specifications set the requirements related to the availability of equipment. In order to limit the risk when an unavailability is noticed during power operation, an allowed outage time is determined based on a fixed limit imposed on the increase of calculated core melt probability when the equipment is considered as unavailable. An example related to the main electric equipment is presented. In case of cold shutdown condition, the operations carried out lead to numerous programmed unavailabilities of equipment. For the examination of a project of technical specifications defining the necessary equipment in the diffrent phases encountered, evaluation of the increase of the core melt probability due to the unavaibilities has been made

  4. 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.

  5. Risk impact of BWR technical specifications requirements during shutdown

    International Nuclear Information System (INIS)

    Staple, B.D.; Kirk, H.K.; Yakle, J.

    1994-10-01

    This report presents an application of probabilistic models and risk based criteria for determining the risk impact of the Limiting Conditions of Operations (LCOs) in the Technical Specifications (TSs) of a boiling water reactor during shutdown. This analysis studied the risk impact of the current requirements of Allowed Outage Times (AOTs) and Surveillance Test Intervals (STIs) in eight Plant Operational States (POSs) which encompass power operations, shutdown, and refueling. This report also discusses insights concerning TS action statements

  6. 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.

  7. 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

  8. 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

  9. Standard technical specifications for combustion engineering pressurized water reactors

    International Nuclear Information System (INIS)

    1979-08-01

    This Standard Technical Specification (STS) has been structured for the broadest possible use on Combustion Engineering 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

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

    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 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

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

    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 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

  12. Sealed radionuclide sources - new technical specifications and current practice

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D

    1987-03-01

    Basic technical specifications are discussed valid in Czechoslovakia for sealed radionuclide sources, based on international ISO and CMEA standards. Described are the standardization of terminology, relationships of tests, testing methods, types of sealed sources and their applications, relations to Czechoslovak regulations on radiation protection and to IAEA specifications for radioactive material shipment, etc. Practical impact is shown of the introduction of the new standards governing sealed sources on the national economy, and the purpose is explained of various documents issued with sealed sources. (author). 2 figs., 45 refs.

  13. 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)

  14. 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.)

  15. 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.

  16. Audit of Wolf Creek Generating Station, Unit 1 technical specifications. Final technical evaluation report

    International Nuclear Information System (INIS)

    Stromberg, H.M.

    1985-07-01

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

  17. 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

  18. Probabilistic analysis of 900 MWe PWR. Shutdown technical specifications

    International Nuclear Information System (INIS)

    Mattei, J.M.; Bars, G.

    1987-11-01

    During annual shutdown, preventive maintenance and modifications which are made on PWRs cause scheduled unavailabilities of equipment or systems which might harm the safety of the installation, in spite of the low level of decay heat during this period. The pumps in the auxiliary feedwater system, component cooling water system, service water system, the water injection arrays (LPIS, HPIS, CVCS), and the containment spray system may have scheduled unavailability, as well as the power supply of the electricity boards. The EDF utility is aware of the risks related to these situations for which accident procedures have been set up and hence has proposed limiting downtime for this equipment during the shutdown period, through technical specifications. The project defines the equipment required to ensure the functions important for safety during the various shutdown phases (criticality, water inventory, evacuation of decay heat, containment). In order to be able to judge the acceptability of these specifications, the IPSN, the technical support of the Service Central de Surete des Installations Nucleaires, has used probabilistic methodology to analyse the impact on the core melt probability of these specifications, for a French 900 MWe PWR

  19. 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 motivation was similar between conditions. This mental fatigue significantly reduced running distance in the Yo-Yo IR1 (P performance time were not different between conditions; however, penalty time significantly increased in the mental fatigue condition (P = 0.015). Mental fatigue also impaired shot speed (P = 0.024) and accuracy (P performance.

  20. The use of PROLOG for computerized Technical Specifications

    International Nuclear Information System (INIS)

    Lidsky, L.M.; Lanning, D.D.; Dobrzeniecki, A.B.; Meyers, K.; Reese, T.G.

    1987-01-01

    The task of deciding whether a particular nuclear plant condition is in compliance with its Technical Specifications is, in principle, algorithmic. However, the implicit algorithm is so complex and the required level of confidence in code validity is so high that traditional methods of computerized analysis have proven unsatisfactory. PROLOG provides a close match to the explicit semantic structure of the written specifications, a good tool for analysis of the implicit subsystem operability trees and, by virtue of its declarative style and imbedded logical structure, greatly simplifies the problem of code validation. LCOM, a PROLOG representation of a subset of BWR Technical Specifications, was developed to explore the applicability of PROLOG in this problem domain and to provide benchmark data for full-scale implementations. The declarative style and built-in unification mechanism of PROLOG does substantially simplify the process of program construction and validation. Extrapolations indicate processing times for a complete Tech Spec implementation of ≤ 1 minute in systems capable of ≥ 20 KLIPS

  1. 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

  2. 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

  3. Utilization of a technical review group during a BWR owners group technical specification improvement study

    International Nuclear Information System (INIS)

    Hansell, H.F.; Moyer, D.P.

    1986-01-01

    A BWR Owners' Group Technical Specification Improvement (TSI) Committee was formed in late 1983. A primary goal of this Committee was to encourage the development of a probabilistic methodology for technical specification improvements which could be readily applied by utilities. The TSI Committee elected to hire a Contractor to develop and demonstrate a method. After the Contractor was selected and has started work, the committee decided to establish a Technical Review Group (TRG) to efficiently and effectively review the Contractor's analyses. The TRG met frequently with the Contractor as the analyses were being performed. These meetings were held at the Contractor's facility in order to allow direct contact between reviewers and individuals performing the work. The TRG was also involved with all major interactions with the NRC. The significance and merit of using a peer review group in this manner is the theme of this paper. In order to present a discussion of the significance and merit of the TRG, the activities are described. The summary of the analytical approach is provided to more full understand the TRG activities

  4. Worrying about the future: An episodic specificity induction impacts problem solving, reappraisal, and well-being.

    Science.gov (United States)

    Jing, Helen G; Madore, Kevin P; Schacter, Daniel L

    2016-04-01

    Previous research has demonstrated that an episodic specificity induction--brief training in recollecting details of a recent experience--enhances performance on various subsequent tasks thought to draw upon episodic memory processes. Existing work has also shown that mental simulation can be beneficial for emotion regulation and coping with stressors. Here we focus on understanding how episodic detail can affect problem solving, reappraisal, and psychological well-being regarding worrisome future events. In Experiment 1, an episodic specificity induction significantly improved participants' performance on a subsequent means-end problem solving task (i.e., more relevant steps) and an episodic reappraisal task (i.e., more episodic details) involving personally worrisome future events compared with a control induction not focused on episodic specificity. Imagining constructive behaviors with increased episodic detail via the specificity induction was also related to significantly larger decreases in anxiety, perceived likelihood of a bad outcome, and perceived difficulty to cope with a bad outcome, as well as larger increases in perceived likelihood of a good outcome and indicated use of active coping behaviors compared with the control. In Experiment 2, we extended these findings using a more stringent control induction, and found preliminary evidence that the specificity induction was related to an increase in positive affect and decrease in negative affect compared with the control. Our findings support the idea that episodic memory processes are involved in means-end problem solving and episodic reappraisal, and that increasing the episodic specificity of imagining constructive behaviors regarding worrisome events may be related to improved psychological well-being. (c) 2016 APA, all rights reserved).

  5. 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

  6. Automation of technical specification monitoring for nuclear power plants

    International Nuclear Information System (INIS)

    Lin, J.C.; Abbott, E.C.; Hubbard, F.R.

    1986-01-01

    The complexity of today's nuclear power plants combined with an equally detailed regulatory process makes it necessary for the plant staff to have access to an automated system capable of monitoring the status of limiting conditions for operation (LCO). Pickard, Lowe and Garrick, Inc. (PLG), has developed the first of such a system, called Limiting Conditions for Operation Monitor (LIMCOM). LIMCOM provides members of the operating staff with an up-to-date comparison of currently operable equipment and plant operating conditions with what is required in the technical specifications. LIMCOM also provides an effective method of screening tagout requests by evaluating their impact on the LCOs. Finally, LIMCOM provides an accurate method of tracking and scheduling routine surveillance. (author)

  7. 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

  8. Evaluation of Watts Bar Nuclear Plant 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 Watts Bar Nuclear Plant Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumption 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 Watts Bar T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Watts Bar Nuclear Plant Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  9. Evaluation of Shoreham Nuclear Power 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 Shoreham Nuclear Power Station Unit 1 Technical Specifications (T/S), which govern plant systems configurations and operations, are in conformance with the assumptions 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 Shoreham T/S. Several discrepancies were identified and subsequently resolved through discussions with the cognizant NRC reviewer, NRC staff reviewers and/or utility representatives. The Shoreham Nuclear Power Station Unit 1 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  10. Evaluation of Waterford Steam Electric Station Unit 3 technical specifications

    International Nuclear Information System (INIS)

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

    1985-09-01

    This document was prepared for the Nuclear Regulatory Commission (NRC) to assist them in determining whether the Waterford Steam Electric Station Unit 3 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 Waterford T/S. Several discrepancies were identified and subsequently resolved by the cognizant NRC reviewer. Pending completion of the resolutions noted in Part 3 of this report, the Waterford Steam Electric Station Unit 3 T/S, to the extent reviewed, are in conformance with the FSAR and SER

  11. 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...

  12. Assessment of the technical specifications for a flip-standard TRIGA core

    International Nuclear Information System (INIS)

    Feltz, D.E.; Randall, J.D.

    1974-01-01

    The Technical Specifications for the Texas A and M University mixed, FLIP-Standard TRIGA core were the first submitted and approved under the draft version of Standard ANS-15.1. According to one AEC official these were the best Technical Specifications ever issued to a Research Reactor. The Technical Specifications are evaluated after operating under them for over seven months. (author)

  13. Assessment of the technical specifications for a flip-standard TRIGA core

    Energy Technology Data Exchange (ETDEWEB)

    Feltz, D E; Randall, J D [Texas A and M University (United States)

    1974-07-01

    The Technical Specifications for the Texas A and M University mixed, FLIP-Standard TRIGA core were the first submitted and approved under the draft version of Standard ANS-15.1. According to one AEC official these were the best Technical Specifications ever issued to a Research Reactor. The Technical Specifications are evaluated after operating under them for over seven months. (author)

  14. Solving Problems in Hawaiian-American Classrooms: Excellent Teaching and Cultural Factors. Technical Report #2.

    Science.gov (United States)

    Gallimore, Ronald; And Others

    This paper describes a community research project which preceded the development of the Kamehameha Early Education Project (KEEP). The community project was designed to assist teachers in solving classroom behavior and academic problems. The initial focus on workshops and theories proved inadequate for dealing with daily classroom problems. A…

  15. Optimization Strategy of the APR+ BOP Technical Specifications

    International Nuclear Information System (INIS)

    Cho, Yoon Sang; Lee, Jae Gon; Han, Sung Heum

    2016-01-01

    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

  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. Computer-aided System of Semantic Text Analysis of a Technical Specification

    OpenAIRE

    Zaboleeva-Zotova, Alla; Orlova, Yulia

    2008-01-01

    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 the model of the analysis of the text of the technical project is submitted, the attribute grammar of a technical specification, intended for formalization of limited Ru...

  18. Web Based Technical Problem Solving for Enhancing Writing Skills of Secondary Vocational Students

    Science.gov (United States)

    Papantoniou, Eleni; Hadzilacos, Thanasis

    2017-01-01

    We discuss some aspects of a pilot e-learning technical writing course addressed to 11th grade vocational high school students in Greece. The application of this alternative teaching intervention stemmed from the researcher-instructor's reflections relating to the integration of a problem based e-pedagogy that aims not just to familiarize students…

  19. Technical specification for fabrication of HANARO pool cover

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Jeong Soo; Woo, Sang Ik

    2001-06-01

    This technical specification details the requirements and the acceptance criteria for design, seismic analysis, function test, installation and quality assurance for HANARO pool cover which will be installed at the top of reactor pool. The pool cover is classified as non-nuclear safety, seismic category II and quality class T. The basic design of the pool cover for increasing HANARO applications has been carried out for supporting the driving devices which can load, unload and rotate the irradiation targets in the in-core and out-core vertical irradiation holes under on-power operation. The comments of HANARO user group related with irradiation tests have optimally considered in the process of design. The interference between fuel handling and control absorber units in the reactor pool and activities to load, unload and rotate the irradiation targets at the top of the reactor pool have been minimized. The pool cover can be moved for maintenance and can protect the reactor pool from unexpected drop of foreign materials. It provides the space to vertical access of driving devices for NTD, CT/IR and OR4/OR5 under on-power operation. And the pool cover assembly must maintain its structural integrity under seismic load. Based on the above design concept, the HANARO pool cover has been proposed as supporting structure of driving devices for NTD, fission moly and RI production under on-power operation.

  20. 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

  1. Alternative approaches to risk-based technical specifications

    International Nuclear Information System (INIS)

    Atefi, B.; Gallagher, D.W.; Liner, R.T.; Lofgren, E.V.

    1987-01-01

    Four alternative risk-based approaches to Technical Specifications are identified. These are: a Probabilistic Risk Assessment (PRA) oriented approach; a reliability goal-oriented approach; an approach based on configuration control; a data-oriented approach. Based on preliminary results, the PRA-oriented approach, which has been developed further than the other approaches, seems to offer a logical, quantitative basis for setting Allowed Outage Times (AOTs) and Surveillance Test Intervals (STIs) for some plant components and systems. The most attractive feature of this approach is that it directly links the AOTs and STIs with the risk associated with the operation of the plant. This would focus the plant operator's and the regulatory agency's attention on the most risk-significant components of the plant. A series of practical issues related to the level of detail and content of the plant PRAs, requirements for the review of these PRAs, and monitoring cf the plant's performance by the regulatory agency must be resolved before the approach could be implemented. Future efforts will examine the other three approaches and their practicality before firm conclusions are drawn regarding the viability of any of these approaches

  2. Understanding the technical content of requirements in specification document

    DEFF Research Database (Denmark)

    Sudin, Mohd Nizam Bin; Ahmed-Kristensen, Saeema

    2011-01-01

    development process, is essential to be devised in advance. To achieve this aim, understanding how to formulate a good requirement is necessary and it is only possible if design engineers understand the technical content of a requirement. In aiming to understand the technical content of a requirement...

  3. Problem-based learning for technical students on the base TRIZ (theory of inventive problem solving

    Directory of Open Access Journals (Sweden)

    Babenko Oksana

    2016-01-01

    Full Text Available The basis of modern educational technology in teaching is problem-based learning through the use of educational technologies Powerful Thinking - Theory of Inventive Problem Solving (TRIZ, including a systematic approach to the complex organization of independent work of search and research character. Developed by systemic administration of the physical features workshops on the basis TRIZ in the cycle of the natural sciences with the implementation of all aspects of the educational activities - substantive, procedural and motivational. A new model of the physical design of the workshop and its form of organization, which is based on problem-based learning with the use of TRIZ Interactive form of organization of the workshop allows you to get high-quality substantive and personality of the students who have a significant role in the formation of professional competencies and affect the quality of produce practice-oriented specialists.

  4. Comparing effectiveness and efficiency in technical specifications and maintenance optimization

    International Nuclear Information System (INIS)

    Martorell, Sebastian; Sanchez, Ana; Carlos, Sofia; Serradell, Vicente

    2002-01-01

    Optimization of technical specification requirements and maintenance (TS and M) has been found interesting from the very beginning at Nuclear Power Plants (NPPs). However, the resolution of such a kind of optimization problem has been limited often to focus only on individual TS and M-related parameters (STI, AOT, PM frequency, etc.) and/or adopting an individual optimization criterion (availability, costs, plant risks, etc.). Nevertheless, a number of reasons exist (e.g. interaction, similar scope, etc.) that justify the interest to focus on the coordinated optimization of all of the relevant TS and M-related parameters based on multiple criteria. The purpose of this paper is on signifying benefits and improvement areas in performing the coordinated optimization of TS and M through reviewing the effectiveness and efficiency of common strategies for optimizing TS and M at system level. A case of application is provided for a stand-by safety-related system to demonstrate the basic procedure and to extract a number of conclusions and recommendations from the results achieved. Thus, it is concluded that the optimized values depend on the particular TS and M-related parameters being involved and the solutions with the largest benefit (minimum risk or minimum cost) are achieved when considering the simultaneous optimization of all of them, although increased computational resources are also required. Consequently, it is necessary to analyze not only the value reached but also the performance of the optimization procedure through effectiveness and efficiency measures which lead to recommendations on potential improvement areas

  5. SPECIFIC REGULATIONS REGARDING THE SOLVING OF LABOR DISPUTES IN ROMANIAN LEGAL SYSTEM

    Directory of Open Access Journals (Sweden)

    Onica -Chipea Lavinia

    2012-01-01

    Full Text Available The paper aims to briefly review specific provisions of labor legislation for the solving of labor disputes. Those rules are found in matters of discrimination in the payment settlements, the public sector staff as well as some personnel status or disciplinary (work stops at Status of Teachers and established a derogationfrom the common law (Labor Code Law nr.62/2011 of Social Dialogue in resolving individual labor conflicts(former conflicts of rights. The role and importance of these regulations is that they give the parties the employment relationship, particularly employees, way, way more for rights enshrined in law. Appeals, complaints or expressions of individual grievances be settled outside the judicial system organ (the courts,authorizing officers, judicial administrative organs, which aim at restoring order violated.

  6. 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

  7. 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.

  8. Regulatory aspects of the use of PSA to evaluate technical specifications

    International Nuclear Information System (INIS)

    Rumpf, J.

    1991-01-01

    Based on experiences gained in PSA activities the regulatory body of the GDR initiated a programme to investigate the feasibility of using PSA for the evaluation of technical specifications. This programme is just under work. In addition, to improve PSA, the GDR takes part in a programme which is aimed at performing plant specific level 1, PSA as well as and which enables operating organizations to carry out PSA on their own. The most important of some preliminary general findings presented in this paper are: - Technical specifications form a well established envelope of operational conditions and procedures. A total re-evaluation is not considered necessary; Probabilistic evaluation of technical specifications should be an integrated part of PSA activities (at least level 1). Single assessment is not considered reasonable; Probabilistic evaluation of technical specifications has to be based on plant specific information and realistic accident sequence calculations; Up to now no quantitative probabilistic criteria for technical specifications have been established. (author)

  9. New Airborne Sensors and Platforms for Solving Specific Tasks in Remote Sensing

    Science.gov (United States)

    Kemper, G.

    2012-07-01

    A huge number of small and medium sized sensors entered the market. Today's mid format sensors reach 80 MPix and allow to run projects of medium size, comparable with the first big format digital cameras about 6 years ago. New high quality lenses and new developments in the integration prepared the market for photogrammetric work. Companies as Phase One or Hasselblad and producers or integrators as Trimble, Optec, and others utilized these cameras for professional image production. In combination with small camera stabilizers they can be used also in small aircraft and make the equipment small and easy transportable e.g. for rapid assessment purposes. The combination of different camera sensors enables multi or hyper-spectral installations e.g. useful for agricultural or environmental projects. Arrays of oblique viewing cameras are in the market as well, in many cases these are small and medium format sensors combined as rotating or shifting devices or just as a fixed setup. Beside the proper camera installation and integration, also the software that controls the hardware and guides the pilot has to solve much more tasks than a normal FMS did in the past. Small and relatively cheap Laser Scanners (e.g. Riegl) are in the market and a proper combination with MS Cameras and an integrated planning and navigation is a challenge that has been solved by different softwares. Turnkey solutions are available e.g. for monitoring power line corridors where taking images is just a part of the job. Integration of thermal camera systems with laser scanner and video capturing must be combined with specific information of the objects stored in a database and linked when approaching the navigation point.

  10. NEW AIRBORNE SENSORS AND PLATFORMS FOR SOLVING SPECIFIC TASKS IN REMOTE SENSING

    Directory of Open Access Journals (Sweden)

    G. Kemper

    2012-07-01

    Full Text Available A huge number of small and medium sized sensors entered the market. Today's mid format sensors reach 80 MPix and allow to run projects of medium size, comparable with the first big format digital cameras about 6 years ago. New high quality lenses and new developments in the integration prepared the market for photogrammetric work. Companies as Phase One or Hasselblad and producers or integrators as Trimble, Optec, and others utilized these cameras for professional image production. In combination with small camera stabilizers they can be used also in small aircraft and make the equipment small and easy transportable e.g. for rapid assessment purposes. The combination of different camera sensors enables multi or hyper-spectral installations e.g. useful for agricultural or environmental projects. Arrays of oblique viewing cameras are in the market as well, in many cases these are small and medium format sensors combined as rotating or shifting devices or just as a fixed setup. Beside the proper camera installation and integration, also the software that controls the hardware and guides the pilot has to solve much more tasks than a normal FMS did in the past. Small and relatively cheap Laser Scanners (e.g. Riegl are in the market and a proper combination with MS Cameras and an integrated planning and navigation is a challenge that has been solved by different softwares. Turnkey solutions are available e.g. for monitoring power line corridors where taking images is just a part of the job. Integration of thermal camera systems with laser scanner and video capturing must be combined with specific information of the objects stored in a database and linked when approaching the navigation point.

  11. Reduced memory specificity predicts the acquisition of problem solving skills in psychoeducation.

    Science.gov (United States)

    Van Daele, Tom; Van den Bergh, Omer; Van Audenhove, Chantal; Raes, Filip; Hermans, Dirk

    2013-03-01

    Research has shown that overgeneral autobiographical memory (OGM) is a valid predictor for the course of depression. It is not known, however, whether OGM also moderates information uptake and consolidation in a psychoeducation program to prevent stress, anxiety and depression. The present study was designed to investigate whether the Autobiographical Memory Test (AMT; Williams, & Broadbent, 1986) is a valid predictor for the actual unfolding of skills learned through psychoeducation. The questionnaire included primarily the AMT and the Stress Anxiety Depression Means-Ends Problem Solving Questionnaire (SAD-MEPS). It was filled in prior to and after the psychoeducational course by 23 participants. Correlations were calculated for the AMT at baseline and the differences between the pre and post measurements on the SAD-MEPS. Significant correlations were observed between the number of specific responses and the changes in the number of relevant means (r = .49, p < .01). The sample size was rather small, but several checks were able to reduce the chance of spurious findings. These findings may have important implications for the guidance to and the setup of psychoeducational interventions. Suggestions include screening and memory specificity training prior to course commencement. Copyright © 2011 Elsevier Ltd. All rights reserved.

  12. 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

  13. 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…

  14. 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...

  15. 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

  16. Social problem-solving in high-functioning schizophrenia: specific deficits in sending skills.

    Science.gov (United States)

    Vaskinn, Anja; Sundet, Kjetil; Hultman, Christina M; Friis, Svein; Andreassen, Ole A

    2009-02-28

    This study examined social problem-solving performance in high-functioning schizophrenia (n=26) and its relation to neurocognition. Ten healthy controls were used as a comparison group. Social problem-solving was assessed with the Assessment of Interpersonal Problem Solving Skills (AIPSS) method. The schizophrenia group was outperformed by healthy controls on all AIPSS measures, reaching statistical significance for sending skills. Exploration of the internal relationship between different aspects of social problem-solving showed that identification of an interpersonal problem (a receiving skill) was not correlated with formulating solutions to the problem (processing skills) or successfully role-playing solutions (interpersonal sending skills). Non-verbal performance in the role-play (an interpersonal sending skill) was not significantly correlated with identification of an interpersonal problem or the generation of solutions. This suggests a dissociation of social problem-solving processes. Social problem-solving was significantly associated with psychomotor speed, verbal learning, semantic fluency and cognitive flexibility. Clinical implications are that remediation of social problem-solving skills should focus on role-playing (nonverbal) interpersonal behaviors, rather than on verbally analyzing an interpersonal problem and clarifying alternative solutions.

  17. 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)

  18. 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...

  19. 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

  20. Technical specification of the NRPB Nuclear Emulsion Dosemeter

    International Nuclear Information System (INIS)

    Bartlett, D.T.; Bird, T.V.

    1978-08-01

    This document is a formal specification of the NRPB Nuclear Emulsion Dosemeter. The dosemeter specified in this report replaces the NRPB Fast Neutron Personal Dosemeter specified in NRPB-R50. (author)

  1. 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

  2. The EDF catalogue of technical specifications (reference HN), standardization center; Catalogue des specifications techniques EDF (reference HN) centre de normalisation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    A list of EDF technical specifications, valid at the 01/01/1996 date, is presented. Specifications domains such as electrical installations, equipment and materials, uninsulated and insulated conductors, measurement, control and command, electric power generating or transforming equipment, electrical appliances, telecommunications, electronic and computer systems, are covered

  3. Towards a Standard-based Domain-specific Platform to Solve Machine Learning-based Problems

    Directory of Open Access Journals (Sweden)

    Vicente García-Díaz

    2015-12-01

    Full Text Available Machine learning is one of the most important subfields of computer science and can be used to solve a variety of interesting artificial intelligence problems. There are different languages, framework and tools to define the data needed to solve machine learning-based problems. However, there is a great number of very diverse alternatives which makes it difficult the intercommunication, portability and re-usability of the definitions, designs or algorithms that any developer may create. In this paper, we take the first step towards a language and a development environment independent of the underlying technologies, allowing developers to design solutions to solve machine learning-based problems in a simple and fast way, automatically generating code for other technologies. That can be considered a transparent bridge among current technologies. We rely on Model-Driven Engineering approach, focusing on the creation of models to abstract the definition of artifacts from the underlying technologies.

  4. Radiological Effluent Technical Specifications (RETS) implementation: Zion Generating Station Units 1 and 2

    International Nuclear Information System (INIS)

    Serrano, W.; Akers, D.W.; Duce, S.W.; Mandler, J.W.; Simpson, F.B.; Young, T.E.

    1985-06-01

    A review of the Radiological Effluent Technical Specifications (RETS) of the Zion Generating Station Units 1 and 2 was performed. The principal review guidelines used were NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,'' and Draft 7 of NUREG-0472, Revision 3, ''Radiological Effluent Technical Specifications for Pressurized Water Reactors.'' Draft submittals were discussed with the Licensee by both EG and G and the NRC staff until all items requiring changes to the Technical Specifications were resolved. The Licensee then submitted final proposed RETS to the NRC which were evaluated and found to be in compliance with the NRC review guidelines. The proposed Offsite Dose Calculation Manual was reviewed and generally found to be consistent with the NRC review guidelines. 35 refs., 2 figs., 1 tab

  5. 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

  6. Brain Hyper-Connectivity and Operation-Specific Deficits during Arithmetic Problem Solving in Children with Developmental Dyscalculia

    Science.gov (United States)

    Rosenberg-Lee, Miriam; Ashkenazi, Sarit; Chen, Tianwen; Young, Christina B.; Geary, David C.; Menon, Vinod

    2015-01-01

    Developmental dyscalculia (DD) is marked by specific deficits in processing numerical and mathematical information despite normal intelligence (IQ) and reading ability. We examined how brain circuits used by young children with DD to solve simple addition and subtraction problems differ from those used by typically developing (TD) children who…

  7. Relations between Young Students' Strategic Behaviours, Domain-Specific Self-Concept, and Performance in a Problem-Solving Situation

    Science.gov (United States)

    Dermitzaki, Irini; Leondari, Angeliki; Goudas, Marios

    2009-01-01

    This study aimed at investigating the relations between students' strategic behaviour during problem solving, task performance and domain-specific self-concept. A total of 167 first- and second-graders were individually examined in tasks involving cubes assembly and in academic self-concept in mathematics. Students' cognitive, metacognitive, and…

  8. 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)

  9. Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

    International Nuclear Information System (INIS)

    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

  10. Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

    International Nuclear Information System (INIS)

    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

  11. Risk-based analysis methods applied to nuclear power plant technical specifications

    International Nuclear Information System (INIS)

    Wagner, D.P.; Minton, L.A.; Gaertner, J.P.

    1989-01-01

    A computer-aided methodology and practical applications of risk-based evaluation of technical specifications are described. The methodology, developed for use by the utility industry, is a part of the overall process of improving nuclear power plant technical specifications. The SOCRATES computer program uses the results of a probabilistic risk assessment or a system-level risk analysis to calculate changes in risk due to changes in the surveillance test interval and/or the allowed outage time stated in the technical specification. The computer program can accommodate various testing strategies (such as staggered or simultaneous testing) to allow modeling of component testing as it is carried out at the plant. The methods and computer program are an integral part of a larger decision process aimed at determining benefits from technical specification changes. These benefits can include cost savings to the utilities by reducing forced shutdowns and decreasing labor requirements for test and maintenance activities, with no adverse impacts on risk. The methodology and the SOCRATES computer program have been used extensively toe valuate several actual technical specifications in case studies demonstrating the methods. Summaries of these applications demonstrate the types of results achieved and the usefulness of the risk-based evaluation in improving the technical specifications

  12. 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

  13. Specification and implementation of a belief-desire-joint-intention architecture for collaborative problem solving

    OpenAIRE

    Jennings, NR

    1993-01-01

    Systems composed of multiple interacting problem solvers are becoming increasingly pervasive and have been championed in some quarters as the basis of the next generation of intelligent information systems. If this technology is to fulfill its true potential then it is important that the systems which are developed have a sound theoretical grounding. One aspect of this foundation, namely the model of collaborative problem solving, is examined in this paper. A synergistic review of existing mo...

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

  15. Does Problem-Based Learning Improve Problem Solving Skills?--A Study among Business Undergraduates at Malaysian Premier Technical University

    Science.gov (United States)

    Kadir, Z. Abdul; Abdullah, N. H.; Anthony, E.; Salleh, B. Mohd; Kamarulzaman, R.

    2016-01-01

    Problem-based Learning (PBL) approach has been widely used in various disciplines since it is claimed to improve students' soft skills. However, empirical supports on the effect of PBL on problem solving skills have been lacking and anecdotal in nature. This study aimed to determine the effect of PBL approach on students' problem solving skills…

  16. 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

  17. Technical evaluation report on the proposed design modifications and technical-specification changes on grid voltage degradation for the San Onofre Nuclear Genetating 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 changes for protection of Class 1E equipment from grid voltage degradation for the San Onofre Nuclear Generating Station, Unit 1. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation finds that the proposed design modifications and Technical Specification changes will ensure that the Class 1E equipment will be protected from sustained voltage degradation

  18. The applies specific technical requirements to the services of radiological protection according to the 17025

    Energy Technology Data Exchange (ETDEWEB)

    Marrero Garcia, M.; Fernandez Gomez, I. M.; Prendes Alonso, M.; Molina Perez, D.

    2004-07-01

    The employment in the Center of Radiation Protection and Hygiene (CRPH) of Cuba, of the standard 17025 for the administration of the quality of the calibration laboratories and test that offer services of radiological protection requires of a technical complement to really determine the technical competence. In the standard 17025, the specific requirements, are mentioned in the annex B (with informative character), where it points out that: {sup T}he requirements specified in the standard 17025 are established in general terms and, although they can be applied to all the test laboratories and applications, they could be necessary applications{sup .} In the CRPH these applications are translated in indispensable technical requirements to evaluate the performance of the services of radiological protection that offers, specifically those of personal monitoring, the calibration of instruments and the metrology of radionuclides. Although the standard 17025 is quite rigorous in the evaluation of technical requirements, to have specific materials not serves alone of tool to the laboratories, but also for the body of accreditation . In the CRPH the permanent employment of this tool has not constituted a practice, but had been good before our clients certain nonconformities to evaluate the performance of the laboratory and to achieve the recovery of the trust in its results. With this work we seek to expose some of these experiences. The experiences of the application of some of the technical requirements, in our case, they have been applied to the service of personal monitoring that offers the Laboratory of Personal Dosimetry. This laboratory is accredited by the National Accreditation Board of the Republic of Cuba (NABC) and besides fulfilling that settled down in 17025, the Approaches of Accreditation for test laboratories and calibration and it should also implant that settled down as specific technical requirements for the recognition of technical competence. (Author

  19. 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

  20. Technical evaluation report on the 120 Vac vital instrument buses and inverter Technical Specifications Issue B71

    International Nuclear Information System (INIS)

    St Leger-Barter, G.; White, R.L.

    1982-01-01

    The operation of a Pressurized Water Reactor (PWR) with one of its 120 Vac vital buses energized in an off-normal mode was analyzed. A Probabilistic Risk Assessment was made to determine the increment of risk by energizing a vital bus from an off-site source directly vs energizing it from its normal, uninterruptible source (i.e., a battery/inverter arrangement). The calculations were made based on uninterruptible source energized vital buses as the normal mode. The analysis indicated that a reduction in the incremental risk increase (caused by plant operation with a vital bus being energized in an off-normal mode) can be accomplished by limiting the time permitted in that condition. Currently, the time that a vital bus can be energized in the off-normal mode is not universally time-limited by plant Technical Specifications. Several alternatives for the reduction in incremental risk were examined and their value/impacts were derived. These data indicate that a recommendation be made for a Technical Specification time limitation of 72 hours per year for off-normal energizing a vital bus during operation of a PWR

  1. 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

  2. To solve the specific emissions of locomotive diesel engines. Final report

    International Nuclear Information System (INIS)

    Korhonen, R.; Maeaettaenen, M.

    1999-01-01

    Ministry of Transport has made a goal to create an uniform system to make it possible to compare emissions of different transport forms. Kymenlaakso Polytechnic was supported by the Mobile Research Programme to measure the specific emissions of locomotive diesel engines. VR Osakeyhtioe has also supported economically the research work. During the research specific emissions of three diesel engines used in locomotives and calculated according to ISO 8178 standard were measured. In all, emissions of 14 engines were measured. For 12 engines measurements were made after the engine shop repair and for two engines before the repairing. Gaseous emissions: nitric oxide, carbon monoxide, carbon dioxide and total hydrocarbons contents were measured. Based on measured emissions and sulphur contents of the oil the weighted emissions were calculated in units g/kWh and g/kg fuel . Particular emissions were measured with dilution method and specific emissions were calculated in same units as for gaseous emissions

  3. 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

  4. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Science.gov (United States)

    2010-01-01

    ...; 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... the design, construction, and operation of nuclear power reactors indicates that compliance with the...

  5. Technical specifications, Limerick Generating Station, Unit No. 2 (Docket No. 50-353)

    International Nuclear Information System (INIS)

    1989-07-01

    The Limerick, Unit 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set 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

  6. Technical Specifications, Limerick Generating Station, Unit No. 2 (Docket No. 50-353)

    International Nuclear Information System (INIS)

    1989-08-01

    The Limerick, Unit 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set 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. Self-Explanations: How Students Study and Use Examples in Learning To Solve Problems. Technical Report No. 9.

    Science.gov (United States)

    Chi, Michelene T. H.; And Others

    A study examined in detail the initial encoding of worked-out examples of mechanics problems by "good" and "poor" students, and their subsequent reliance on examples during problem solving. The subjects, three males and five females, were selected from responses to a university campus advertisement. Six of them were working…

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

    Energy Technology Data Exchange (ETDEWEB)

    Tait, J.C.; Johnson, L.H. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

    1997-07-01

    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{sub 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 {sup 14}C and {sup 36}C1, which after {sup 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)

  9. 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)

  10. Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.

    1979-12-01

    The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

  11. Use of experience for the improvement of technical specifications for operation

    International Nuclear Information System (INIS)

    Schweitz, J.P.; Seveon, J.J.

    1987-11-01

    The lessons drawn from experience led EdF to define in 1980 a national specification standard, to be applied to the first standardized series of 900 MWe units and to be adapted to the later 1300 MWe units. This document is periodically revised, every two years or so, to take into account new trends in safety thinking and lessons learnt from operating experience. In this paper we present the main developments in the field of technical specifications, particularly: the definition of rules applicable in the event of unavailability of safety-related equipment, the integration of plant unit operating feedback for specifications optimization

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

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R.; Demitrack, T.; Schiele, R.; Jones, J.C. [EXCEL Services Corporation, 11921 Rockville Pike, Suite 100, Rockville, MD 20852 (United States)]. e-mail: donaldh@excelservices.com

    2004-07-01

    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)

  13. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

    Kulak, R F [Argonne National Laboratory, Argonne, IL (United States)

    1992-07-01

    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 thatthe 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)

  15. 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

  16. 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)

  17. Technical Specifications, Comanche Peak Steam Electric Station, Unit 1 (Docket No. 50-445)

    International Nuclear Information System (INIS)

    1990-04-01

    The Technical Specifications for Comanche Peak Steam Electric Station, Unit 1 were prepared by the US Nuclear Regulatory Commission. They set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility, as set forth in Section 50.36 of Title 10 of the Code of Federal Regulations Part 50, for the protection of the health and safety of the public

  18. 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

  19. 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

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

  1. 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

  2. Technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation (Part A) for the Pilgrim Nuclear Power Station, Unit 1

    International Nuclear Information System (INIS)

    White, R.L.

    1980-01-01

    This report documents the technical evaluation of the proposed design modifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Pilgrim Nuclear Power Station. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

  3. 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

  4. Standard Technical Specifications for General Electric Boiling Water Reactors (BWR/5)

    International Nuclear Information System (INIS)

    Bottimore, R.R.

    1980-12-01

    The Standard Technical Specifications for General Electric Boiling Water Reactors (GE-STS) is a generic document prepared by the US NRC for use in the licensing process of current General Electric Boiling Water Reactors. The GE-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 Part 50 for the protection of the health and safety of the public. The document is revised periodically to reflect current licensing requirements

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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.

  10. 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.

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

    DEFF Research Database (Denmark)

    Zahedi, Mansooreh; Babar, Muhammad Ali

    2014-01-01

    Context: Software engineering is a knowledge intensive activity that is supported by documenting and sharing the required knowledge through a wide variety of artifacts. Global Software Development (GSD) teams heavily rely on artifacts as a vital means of knowledge sharing. However, there is little...... empirical knowledge about the key reasons and practices of using artifacts in GSD for knowledge sharing to support common understanding of technical specifications. Objective: This study aims at empirically studying the key motivators, practices, and drawbacks of artifact-based knowledge sharing...... 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...

  13. Technical Specifications, Clinton Power Station, Unit No. 1 (Docket No. 50-461). Appendix ''A'' to License No. NPF-55

    International Nuclear Information System (INIS)

    1986-09-01

    This report presents information on the technical specifications of the Clinton Unit No. 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

  14. Technical specifications review of nuclear power plants: a risk-informed evaluation

    International Nuclear Information System (INIS)

    Saldanha, Pedro Luiz da Cruz; Sousa, Anna Leticia; Frutuoso e Melo, Paulo Fernando Ferreira; Duarte, Juliana Pacheco

    2012-01-01

    The use of risk information by a regulatory body as part of an integrated decision making process addresses the way in which risk information is being used as part of an integrated process in making decisions about safety issues at nuclear plants – commonly referred to as risk-informed decision making. The risk-informed approach aims to integrate in a systematic manner quantitative and qualitative, deterministic and probabilistic safety considerations to obtain a balanced decision. Probabilistic Safety Assessment (PSA) is a methodology that can be applied to provide a structured analysis process to evaluate the frequency and consequences of accidents scenarios in nuclear power plants. Technical Specifications (TS) are specifications regarding the characteristics of nuclear power plants (variables, systems or components) of overriding importance to nuclear safety and radiation protection, which is an integral part of plant operation authorization. Limiting Conditions of Operation (LCO) are the minimum levels of performance or capacity or operating system components required for the safe operation of nuclear plants, as defined in technical specifications. The Maintenance Rule (MR) is a requirement established by the U. S. Nuclear Regulatory Commission (NRC) to check the effectiveness of maintenance carried out in nuclear plants, and plant configuration control. The control of plant configuration is necessary to verify the impact of the maintenance of a safety device out of service on plant safety. The Electric Power Research Institute (EPRI) has assessed the role of probabilistic safety analysis in the regulation of nuclear power plants with the following objectives: a) to provide utilities with an approach for developing and implementing nuclear power station risk-managed technical specification programs; and b) to complement and supplement existing successful configuration risk management applications such as MR. This paper focuses on the evaluation of EPRI

  15. 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

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

    International Nuclear Information System (INIS)

    1995-04-01

    This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand 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 ampersand 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

  17. Using a site-specific technical error to establish training responsiveness: a preliminary explorative study.

    Science.gov (United States)

    Weatherwax, Ryan M; Harris, Nigel K; Kilding, Andrew E; Dalleck, Lance C

    2018-01-01

    Even though cardiorespiratory fitness (CRF) training elicits numerous health benefits, not all individuals have positive training responses following a structured CRF intervention. It has been suggested that the technical error (TE), a combination of biological variability and measurement error, should be used to establish specific training responsiveness criteria to gain further insight on the effectiveness of the training program. To date, most training interventions use an absolute change or a TE from previous findings, which do not take into consideration the training site and equipment used to establish training outcomes or the specific cohort being evaluated. The purpose of this investigation was to retrospectively analyze training responsiveness of two CRF training interventions using two common criteria and a site-specific TE. Sixteen men and women completed two maximal graded exercise tests and verification bouts to identify maximal oxygen consumption (VO 2 max) and establish a site-specific TE. The TE was then used to retrospectively analyze training responsiveness in comparison to commonly used criteria: percent change of >0% and >+5.6% in VO 2 max. The TE was found to be 7.7% for relative VO 2 max. χ 2 testing showed significant differences in all training criteria for each intervention and pooled data from both interventions, except between %Δ >0 and %Δ >+7.7% in one of the investigations. Training nonresponsiveness ranged from 11.5% to 34.6%. Findings from the present study support the utility of site-specific TE criterion to quantify training responsiveness. A similar methodology of establishing a site-specific and even cohort specific TE should be considered to establish when true cardiorespiratory training adaptations occur.

  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. 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.)

  1. [Formulation of technical specification for national survey of Chinese materia medica resources].

    Science.gov (United States)

    Guo, Lan-Ping; Lu, Jian-Wei; Zhang, Xiao-Bo; Zhao, Run-Huai; Zhang, Ben-Gang; Sun, Li-Ying; Huang, Lu-Qi

    2013-04-01

    According to the process of the technical specification (TS) design for the fourth national survey of the Chinese materia medica resources (CMMR), we analyzed the assignment and objectives of the national survey and pointed out that the differences about CMMR management around China, the distribution of CMMR and their habitat, the economic and technological level, and even enthusiasm and initiative of the staff, etc. are the most difficult points for TS design. And we adopt the principle of combination of the mandatory and flexibility in TS design. We fixed the key points which would affect the quality of national survey first, then proposed the framework of TS which including 3 parts of organization and 11 parts of technique itself. The framework will serve and lead the TS preparation, which will not only provide an action standard to the national survey but will also have a profound influence to the popularization and application of the survey technology of CMMR. [Key words

  2. 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

  3. 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

  4. Technical Note: Harmonic analysis applied to MR image distortion fields specific to arbitrarily shaped volumes.

    Science.gov (United States)

    Stanescu, T; Jaffray, D

    2018-05-25

    Magnetic resonance imaging is expected to play a more important role in radiation therapy given the recent developments in MR-guided technologies. MR images need to consistently show high spatial accuracy to facilitate RT specific tasks such as treatment planning and in-room guidance. The present study investigates a new harmonic analysis method for the characterization of complex 3D fields derived from MR images affected by system-related distortions. An interior Dirichlet problem based on solving the Laplace equation with boundary conditions (BCs) was formulated for the case of a 3D distortion field. The second-order boundary value problem (BVP) was solved using a finite elements method (FEM) for several quadratic geometries - i.e., sphere, cylinder, cuboid, D-shaped, and ellipsoid. To stress-test the method and generalize it, the BVP was also solved for more complex surfaces such as a Reuleaux 9-gon and the MR imaging volume of a scanner featuring a high degree of surface irregularities. The BCs were formatted from reference experimental data collected with a linearity phantom featuring a volumetric grid structure. The method was validated by comparing the harmonic analysis results with the corresponding experimental reference fields. The harmonic fields were found to be in good agreement with the baseline experimental data for all geometries investigated. In the case of quadratic domains, the percentage of sampling points with residual values larger than 1 mm were 0.5% and 0.2% for the axial components and vector magnitude, respectively. For the general case of a domain defined by the available MR imaging field of view, the reference data showed a peak distortion of about 12 mm and 79% of the sampling points carried a distortion magnitude larger than 1 mm (tolerance intrinsic to the experimental data). The upper limits of the residual values after comparison with the harmonic fields showed max and mean of 1.4 mm and 0.25 mm, respectively, with only 1.5% of

  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. Standard technical specifications: Combustion engineering 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 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

  7. 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

  8. Standard Technical Specifications General Electric plants, BWR/4: Bases (Sections 2.0-3.3). Volume 2, 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 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 ST 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 I contains the Specifications for all chapters and sections of the improved STS. This document, 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

  9. Technical evaluation report on the proposed amendment to the technical specifications on the reactor protection system and the engineered safety features actuation system for Ft. Calhoun, Unit No. 1

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the application to amend the Technical Specifications for the Ft. Calhoun Unit No. 1 Nuclear Generating Plant. The review criteria are based on the Technical Specifications of St. Lucie and Calvert Cliffs, IEEE Standards, Combustion Engineering Standard Technical Specifications, and the Code of Federal Regulations. The evaluation compares the submittal made by the licensee with the NRC staff position and the review criteria and presents the reviewer's conclusion on the acceptability of the application to amend the Technical Specifications

  10. Radiation Dose Effects into LCO in Technical Specification by Iodine in Hanul units 1,2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hye Min; Lee, Seung Chan [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    This study estimates the impact of the 1-th coolant system in NPP to the LCO (Limiting Condition of Operation) limits which is in the site boundary. Dose limit is merged into the effective dose from whole body and thyroid dose limits, that is possible to combine the two LCOs to a unified LCO. To estimate the limits, the radiation dose of one of the designed accidents should be chosen to check the radiation dose response. The selected accident is based on Seung Chan Lee's study at KHNP in 2011. Using the selected accident, Iodine dose effect is reviewed depending on the LCO limiting responsibility and the specific behavior. In order to evaluate the radiation dose effect in Technical Specification of Hanul 1,2, SGTR is selected for some sensitivity analysis. From the results, in Hanul site, the case of LOOP plus ADV plus GIS is the most severe case and the dose limit margin is about 110% in LCO.

  11. 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

  12. 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

  13. 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

  14. Autobiographical memory specificity and the persistence of depressive symptoms in HIV-positive patients: rumination and social problem-solving skills as mediators.

    Science.gov (United States)

    Yanes, Paula K; Morse, Gene; Hsiao, Chiu-Bin; Simms, Leonard; Roberts, John E

    2012-01-01

    Individuals infected with human immunodeficiency virus (HIV) are at elevated risk for depressive conditions, which in turn can negatively impact health-related behaviours and the course of illness. The present study tested the role of autobiographical memory specificity and its interaction with perceived stress in the persistence of depressive symptoms among dysphoric HIV-positive individuals. Additionally, we examined whether rumination and social problem solving mediated these effects. Results indicated that memory specificity moderated the impact of perceived stress, such that perceived stress was more strongly associated with follow-up depressive symptoms among those with greater memory specificity. Rumination, but not social problem solving, mediated this effect. Implications of these findings are discussed.

  15. 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

  16. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    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.

  18. Early assessment of feasibility and technical specificities of transoral robotic surgery using the da Vinci Xi.

    Science.gov (United States)

    Gorphe, Philippe; Von Tan, Jean; El Bedoui, Sophie; Hartl, Dana M; Auperin, Anne; Qassemyar, Quentin; Moya-Plana, Antoine; Janot, François; Julieron, Morbize; Temam, Stephane

    2017-12-01

    The latest generation Da Vinci ® Xi™ Surgical System Robot released has not been evaluated to date in transoral surgery for head and neck cancers. We report here the 1-year results of a non-randomized phase II multicentric prospective trial aimed at assessing its feasibility and technical specificities. Our primary objective was to evaluate the feasibility of transoral robotic surgery using the da Vinci ® Xi™ Surgical System Robot. The secondary objective was to assess peroperative outcomes. Twenty-seven patients, mean age 62.7 years, were included between May 2015 and June 2016 with tumors affecting the following sites: oropharynx (n = 21), larynx (n = 4), hypopharynx (n = 1), parapharyngeal space (n = 1). Eighteen patients were included for primary treatment, three for a local recurrence, and six for cancer in a previously irradiated field. Three were reconstructed with a FAMM flap and 6 with a free ALT flap. The mean docking time was 12 min. "Chopsticking" of surgical instruments was very rare. During hospitalization following surgery, 3 patients experienced significant bleeding between day 8 and 9 that required surgical transoral hemostasis (n = 1) or endovascular embolization (n = 2). Transoral robotic surgery using the da Vinci ® Xi™ Surgical System Robot proved feasible with technological improvements compared to previous generation surgical system robots and with a similar postoperative course. Further technological progress is expected to be of significant benefit to the patients.

  19. 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.)

  20. 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

  1. A Development of Technical Specification of a Research Reactor with Plate Fuels Cooled by Upward Flow

    International Nuclear Information System (INIS)

    Park, Sujin; Kim, Jeongeun; Kim, Hyeonil

    2016-01-01

    The contents of the TS(Technical Specifications) are definitions, safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. TS for Nuclear Power Plants (NPPs) have been developed since many years until now. On the other hands, there are no applicable modernized references of TS for research reactors with many differences from NPPs in purpose and characteristics. Fuel temperature and Departure from Nuclear Boiling Ratio (DNBR) are being used as references from the thermal-hydraulic analysis point of view for determining whether the design of research reactors satisfies acceptance criteria for the nuclear safety or not. Especially for research reactors using plate-type fuels, fuel temperature and critical heat flux, however, are very difficult to measure during the reactor operation. This paper described the outline of main contents of a TS for open-pool research reactor with plate-type fuels using core cooling through passive systems, where acceptance criteria for nuclear safety such as CHF and fuel temperature cannot be directly measured, different from circumstances in NPPs. Thus, three independent variables instead of non-measurable acceptance criteria: fuel temperature and CHF are considered as safety limits, i.e., power, flow, and flow temperature

  2. Method for the determination of technical specifications limiting temperature in EBR-II operation

    International Nuclear Information System (INIS)

    Chang, L.K.; Hill, D.J.; Ku, J.Y.

    2004-01-01

    The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analyses and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. Design safety criteria for steady-state normal and transient off-normal operations were developed to ensure structural integrity of the fuel pin. The maximum allowable coolant outlet temperatures and powers of subassemblies for steady-state normal operation conditions were first determined in a row-by-row basis by a thermal-hydraulic and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum subassembly coolant outlet temperatures and powers that satisfy the design safety criteria for steady-state normal operation conditions. The limiting steady-state temperature and power were then used as the initial subassembly thermal conditions for the off-normal transient analysis to assess the safety performance of the fuel pin for anticipated, unlikely and extremely unlikely events. If the design safety criteria for the off-normal events are not satisfied, then the initial steady-state subassembly temperatures and/or powers are reduced and an iterative procedure is employed until the design safety criteria for off-normal conditions are satisfied, and the initial subassembly outlet coolant temperature and power are the technical specification limits for reactor operation. (author)

  3. 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

  4. Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

    International Nuclear Information System (INIS)

    Anderson, F.D.

    1984-06-01

    Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

  5. Influence of some design and operating parameters of conveyor with suspended belt and distributed drive on the technical specifications

    OpenAIRE

    Tolkachev E.N.

    2017-01-01

    The influence of several design and operating parameters of conveyor on the individual components of the stretching tension in the belt of conveyor with suspended belt and distributed drive was analyzed. The analysis of influence a number design and operating parameters on the technical specifications of conveyor with suspended belt and distributed drive was done. Recommendations on the choice of rational parameters were formulated.

  6. Technical Specifications: Clinton Power Station, Unit No. 1 (Docket No. 50-461): Appendix ''A'' to License No. NPF-62

    International Nuclear Information System (INIS)

    1987-04-01

    The Clinton Power Station, Unit No. 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  7. 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

  8. 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

  9. The development of technical literature for the specification of fume extraction systems

    Energy Technology Data Exchange (ETDEWEB)

    Gibbons, A [Plastic Fabrications and Environmental Technology Ltd., Armagh (United Kingdom)

    1996-12-31

    The processes involved in producing technical literature to assist in the selection of fans are discussed. Desktop publishing has been found to provide an effective method of matching the detail of the literature to the needs of the customer. (author)

  10. 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

  11. Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

    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 Indian Point Nuclear Power Plant, Unit 3. 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

  12. 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

  13. 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

  14. Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

    International Nuclear Information System (INIS)

    Baeckstroem, Ola; Haeggstroem, Anna; Maennistoe, Ilkka

    2010-04-01

    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

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

    International Nuclear Information System (INIS)

    Baeckstroem, O.; Haeggstroem, A.; Maennistoe, I.

    2010-10-01

    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

  16. 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

  17. Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

    Energy Technology Data Exchange (ETDEWEB)

    Baeckstroem, Ola; Haeggstroem, Anna (Scandpower AB, Stockholm (Sweden)); Maennistoe, Ilkka (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

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

    International Nuclear Information System (INIS)

    Baeckstroem, O.; Haeggstroem, A.; Simola, K.

    2008-07-01

    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

  19. Exploring the Domain Specificity of Creativity in Children: The Relationship between a Non-Verbal Creative Production Test and Creative Problem-Solving Activities

    Directory of Open Access Journals (Sweden)

    Ahmed Mohamed

    2012-12-01

    Full Text Available AbstractIn this study, we explored whether creativity was domain specific or domain general. The relationships between students’ scores on three creative problem-solving activities (math, spa-tial artistic, and oral linguistic in the DIS-COVER assessment (Discovering Intellectual Strengths and Capabilities While Observing Varied Ethnic Responses and the TCT-DP (Test of Creative Thinking-Drawing Produc-tion, a non-verbal general measure of creativi-ty, were examined. The participants were 135 first and second graders from two schools in the Southwestern United States from linguisti-cally and culturally diverse backgrounds. Pearson correlations, canonical correlations, and multiple regression analyses were calcu-lated to describe the relationship between the TCT-DP and the three DISCOVER creative problem-solving activities. We found that crea-tivity has both domain-specific and domain-general aspects, but that the domain-specific component seemed more prominent. One im-plication of these results is that educators should consider assessing creativity in specific domains to place students in special programs for gifted students rather than relying only on domain-general measures of divergent think-ing or creativity.

  20. 76 FR 16785 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2011-03-25

    ... designed as an interactive forum where PSOs and software developers can provide input on these technical... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability.... Throughout the meeting there will be interactive discussion to allow meeting participants not only to provide...

  1. 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... Specifications (STS) to define a new time limit for restoring inoperable RCS leakage detection instrumentation to... operability of the RCS leakage detection instrumentation. The CLIIP model SE will facilitate expedited...

  2. 75 FR 79048 - Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task...

    Science.gov (United States)

    2010-12-17

    ... [boiling water reactor] Operability Requirements and Actions for RCS [reactor coolant system] Leakage... Specifications (STS) to define a new time limit for restoring inoperable RCS leakage detection instrumentation to... operability of the RCS leakage detection instrumentation. The CLIIP model SE will facilitate expedited...

  3. 76 FR 66763 - Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-510...

    Science.gov (United States)

    2011-10-27

    ....'' TSTF-510, Revision 2, is available in the Agencywide Documents Access and Management System (ADAMS... SG Tube Integrity specification (Limiting Condition for Operation (LCO) 3.4.17, LCO 3.4.20, and LCO 3... address implementation issues associated with the inspection periods, and address other administrative...

  4. Using auditory pre-information to solve the cocktail-party problem: electrophysiological evidence for age-specific differences.

    Science.gov (United States)

    Getzmann, Stephan; Lewald, Jörg; Falkenstein, Michael

    2014-01-01

    Speech understanding in complex and dynamic listening environments requires (a) auditory scene analysis, namely auditory object formation and segregation, and (b) allocation of the attentional focus to the talker of interest. There is evidence that pre-information is actively used to facilitate these two aspects of the so-called "cocktail-party" problem. Here, a simulated multi-talker scenario was combined with electroencephalography to study scene analysis and allocation of attention in young and middle-aged adults. Sequences of short words (combinations of brief company names and stock-price values) from four talkers at different locations were simultaneously presented, and the detection of target names and the discrimination between critical target values were assessed. Immediately prior to speech sequences, auditory pre-information was provided via cues that either prepared auditory scene analysis or attentional focusing, or non-specific pre-information was given. While performance was generally better in younger than older participants, both age groups benefited from auditory pre-information. The analysis of the cue-related event-related potentials revealed age-specific differences in the use of pre-cues: Younger adults showed a pronounced N2 component, suggesting early inhibition of concurrent speech stimuli; older adults exhibited a stronger late P3 component, suggesting increased resource allocation to process the pre-information. In sum, the results argue for an age-specific utilization of auditory pre-information to improve listening in complex dynamic auditory environments.

  5. Using auditory pre-information to solve the cocktail-party problem: electrophysiological evidence for age-specific differences

    Directory of Open Access Journals (Sweden)

    Stephan eGetzmann

    2014-12-01

    Full Text Available Speech understanding in complex and dynamic listening environments requires (a auditory scene analysis, namely auditory object formation and segregation, and (b allocation of the attentional focus to the talker of interest. There is evidence that pre-information is actively used to facilitate these two aspects of the so-called cocktail-party problem. Here, a simulated multi-talker scenario was combined with electroencephalography to study scene analysis and allocation of attention in young and middle-aged adults. Sequences of short words (combinations of brief company names and stock-price values from four talkers at different locations were simultaneously presented, and the detection of target names and the discrimination between critical target values were assessed. Immediately prior to speech sequences, auditory pre-information was provided via cues that either prepared auditory scene analysis or attentional focusing, or non-specific pre-information was given. While performance was generally better in younger than older participants, both age groups benefited from auditory pre-information. The analysis of the cue-related event-related potentials revealed age-specific differences in the use of pre-cues: Younger adults showed a pronounced N2 component, suggesting early inhibition of concurrent speech stimuli; older adults exhibited a stronger late P3 component, suggesting increased resource allocation to process the pre-information. In sum, the results argue for an age-specific utilization of auditory pre-information to improve listening in complex dynamic auditory environments.

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

    Energy Technology Data Exchange (ETDEWEB)

    E Davis, B Rasmussen

    2004-12-31

    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.

  7. Influence of some design and operating parameters of conveyor with suspended belt and distributed drive on the technical specifications

    Directory of Open Access Journals (Sweden)

    Tolkachev E.N.

    2017-03-01

    Full Text Available The influence of several design and operating parameters of conveyor on the individual components of the stretching tension in the belt of conveyor with suspended belt and distributed drive was analyzed. The analysis of influence a number design and operating parameters on the technical specifications of conveyor with suspended belt and distributed drive was done. Recommendations on the choice of rational parameters were formulated.

  8. Technical Specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-76

    International Nuclear Information System (INIS)

    1988-03-01

    The South Texas Project, Unit No. 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 50 for the protection of the health and safety of the public. This report is Appendix A to License No. NPF-76

  9. 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.)

  10. 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.

  11. Specificity of problem-solving skills training in mothers of children newly diagnosed with cancer: results of a multisite randomized clinical trial.

    Science.gov (United States)

    Sahler, Olle Jane Z; Dolgin, Michael J; Phipps, Sean; Fairclough, Diane L; Askins, Martha A; Katz, Ernest R; Noll, Robert B; Butler, Robert W

    2013-04-01

    Diagnosis of cancer in a child can be extremely stressful for parents. Bright IDEAS, a problem-solving skills training (PSST) intervention, has been shown to decrease negative affectivity (anxiety, depression, post-traumatic stress symptoms) in mothers of newly diagnosed patients. This study was designed to determine the specificity of PSST by examining its direct and indirect (eg, social support) effects compared with a nondirective support (NDS) intervention. This randomized clinical trial included 309 English- or Spanish-speaking mothers of children diagnosed 2 to 16 weeks before recruitment. Participants completed assessments prerandomization (T1), immediately postintervention (T2), and at 3-month follow-up (T3). Both PSST and NDS consisted of eight weekly 1-hour individual sessions. Outcomes included measures of problem-solving skill and negative affectivity. There were no significant between-group differences at baseline (T1). Except for level of problem-solving skill, which was directly taught in the PSST arm, outcome measures improved equally in both groups immediately postintervention (T2). However, at the 3-month follow-up (T3), mothers in the PSST group continued to show significant improvements in mood, anxiety, and post-traumatic stress; mothers in the NDS group showed no further significant gains. PSST is an effective and specific intervention whose beneficial effects continue to grow after the intervention ends. In contrast, NDS is an effective intervention while it is being administered, but its benefits plateau when active support is removed. Therefore, teaching coping skills at diagnosis has the potential to facilitate family resilience over the entire course of treatment.

  12. 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

  13. Technical specifications of variable speed motors for negative pressure control in hot cell area

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seon Duk; Bang, H. S.; Cho, W. K

    2002-01-01

    Hot cells are the facilities for handling the high radioactive materials and various R and D activities are performed using hot cells. Therefore the control of air flow in hot cell area is very important technology and it is started with the variable speed motor(VSM) controlling the air handling system in that area. This report describes various technical aspects of VS motors and will be useful for understanding the practical technologies of VS motors and also for optimization of the negative pressure controls in hot cell area.

  14. Proceedings of a NEA/CSNI-UNIPEDE specialist meeting on improving technical specifications for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-07-01

    This CSNI specialist meeting on improving technical specifications for nuclear power plants is sponsored by the OECD Nuclear Energy Agency jointly with UNIPEDE. Technical specifications for nuclear power plants are in a way a prescription which has a direct bearing on the success or failure of the particular installation, and on the success or failure of fission energy around the world. It is therefore highly important that these prescriptions are made as clear and as concise as possible and that it distinguishes requirements which are essential for public health and safety, from the many others which are less important accordingly. The conference was held in september 1987 in madrid (Spain); it is composed of about 40 papers grouped into 8 sessions: invited papers (6 papers), international survey results (1 paper), limiting conditions for operation (8 papers), maintenance and testing (4 papers), actions statements and allowed outage times (8 papers), methodology and technical justification (8 papers), future trends and alternative approaches (4 papers), and a final panel

  15. 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

  16. Scientific profile and professional responsibility of Court-appointed Medical Technical Consultants in Italy: time for a specific educational curriculum?

    Science.gov (United States)

    Conti, Andrea Alberto

    2014-08-20

    Court-appointed Technical Consultants (CTCs) are fundamental figures in the Italian judicial system. CTCs are experts appointed by judges in order to supplement their activities by ascertaining, collecting and analyzing facts concerning the specific subject of a lawsuit. These experts formulate opinions, gather motivations and perform checks to provide clear, objective and irrefutable answers to the questions posed by judges. With direct reference to the medical field, while police doctors (specialists in forensic medicine) follow an academic, dedicated, well-structured educational curriculum, the University specialty school in Forensic Medicine, other medical CTCs, though not infrequently luminaries with one or many medical specialties and professional acknowledgments, may have no specific legal-medicine and juridical expertise, precisely because a similar expertise is not formally required of them. In the light of these considerations, in Italy some professionals of the legal world, and of the health context too, have proposed for medical CTCs targeted educational pathways, which would provide these experts with formal specific qualifications. In synthesis and in conclusion, a full knowledge and a rigorous respect of the rules of legal proceedings emerge as increasingly important characteristics for current and future Court-appointed Technical Consultants, together with a specific educational curriculum.

  17. 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...

  18. Technical specifications (Docket No. 50-400): Appendix ''A'' to License No. NPF-63

    International Nuclear Information System (INIS)

    1987-01-01

    This report presents specifications concerning the Shearon Harris Nuclear Power Plant in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  19. Technical specifications for monitoring Community trends in zoonotic agents in foodstuffs and animal populations on request from EFSA

    DEFF Research Database (Denmark)

    Borck Høg, Birgitte; Chriél, Mariann; Korsgaard, Helle

    of criteria for the selection of the zoonotic agent/animal or food category combinations where trend analyses would be justified. Based on data available from 2004 to 2007, the following combinations are suggested for trend analyses: Salmonella in fresh broiler and pig meat, flocks of laying hens and broilers......Technical specifications are proposed for the monitoring of temporal trends in zoonotic agents in animal and food populations at Community or Member State group level in the framework of Directive 2003/99/EC. Two types of trend monitoring are identified: trend watching, which covers general...

  20. STEPS: source term estimation based on plant status phase 0 - the technical specifications of the containment module

    International Nuclear Information System (INIS)

    Vamanu, D.V.

    1998-01-01

    In the framework of Project RODOS (Real-Time On-Line Decision Support System for Nuclear Emergencies in Europe), the European Atomic Energy Community (EAEC) of the Commission of the European Communities has commissioned the development of a unified concept, body of knowledge, models and software package meant to assist the evaluation of the source term of severe nuclear accidents in light water reactors of the types prevailing on the Continent. Code-named STEPS, for 'Source Term Estimation based on Plant Status', the project has evolved as Contract RODOS D (FI4P-CT96-0048), between EAEC and consortium of expert European centres including Commissariat a l'Energie Atomique, Institut de Protection et de Surete Nucleaire, (CEA-DPI-SEAC) as Coordinator and Forschungszentrum Karlsruhe GmbH (FZK-INR), the Finnish Centre for Radiation and Nuclear Safety, (STUK-NSD), the Technical Research Centre of Finland, Energy, Nuclear Energy (VTT-ET-NE), and Eidgenossische Technische Hochschule - ETH Zurich, Centre of Excellence (ETH-CERS) as Contractors. For the Phase 0 of the project, an IFIN-HH expert has been assigned by ETH-CERS to develop the Technical Specifications of the delivery component of the intended STEPS package, the CONTAINMENT Module. Sponsored by ETH-CERS headquarters in Zurich, the work was done on the premises and with the logistic support of CEA D PI-SEAC at Fontenay-aux-Roses, with the feedback processing and computer code development subsequently performed in Bucharest. The Technical Specifications of the STEPS CONTAINMENT Module were guided by specific terms of reference, including: (i) the capability of the software to function as a source term interface between targeted nuclear power plants and the RODOS System; (ii) the comparable capability of the system to be operated as a stand-alone assessment and decision support tool for a comprehensive variety of plants, nuclear emergency classes. On the technical side, the specifications had to focus on the possible

  1. 75 FR 16817 - Meeting for Software Developers on the Technical Specifications for Common Formats for Patient...

    Science.gov (United States)

    2010-04-02

    ... and electronically comparable. This meeting is designed as an interactive forum where PSOs and... contact the Food and Drug Administration (FDA) Office of Equal Employment Opportunity and Disability... specifications. Throughout the meeting there will be interactive discussion to allow meeting participants not...

  2. 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.

  3. 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.

  4. Series: The research agenda for general practice/family medicine and primary health care in Europe. Part 4. Results: specific problem solving skills.

    Science.gov (United States)

    Hummers-Pradier, Eva; Beyer, Martin; Chevallier, Patrick; Eilat-Tsanani, Sophia; Lionis, Christos; Peremans, Lieve; Petek, Davorina; Rurik, Imre; Soler, Jean Karl; Stoffers, Henri Ejh; Topsever, Pinar; Ungan, Mehmet; van Royen, Paul

    2010-09-01

    The 'Research Agenda for General Practice/Family Medicine and Primary Health Care in Europe' summarizes the evidence relating to the core competencies and characteristics of the Wonca Europe definition of GP/FM, and its implications for general practitioners/family doctors, researchers and policy makers. The European Journal of General Practice publishes a series of articles based on this document. The previous articles presented background, objectives, and methodology, as well results on 'primary care management' and 'community orientation' and the person-related core competencies of GP/FM. This article reflects on the general practitioner's 'specific problem solving skills'. These include decision making on diagnosis and therapy of specific diseases, accounting for the properties of primary care, but also research questions related to quality management and resource use, shared decision making, or professional education and development. Clinical research covers most specific diseases, but often lacks pragmatism and primary care relevance. Quality management is a stronghold of GP/FM research. Educational interventions can be effective when well designed for a specific setting and situation. However, their message that 'usual care' by general practitioners is insufficient may be problematic. GP and their patients need more research into diagnostic reasoning with a step-wise approach to increase predictive values in a setting characterized by uncertainty and low prevalence of specific diseases. Pragmatic comparative effectiveness studies of new and established drugs or non-pharmaceutical therapy are needed. Multi-morbidity and complexity should be addressed. Studies on therapy, communication strategies and educational interventions should consider impact on health and sustainability of effects.

  5. Socio-technical Systems as Place-specific Matters of Concern

    DEFF Research Database (Denmark)

    Jensen, J. S.; Fratini, C. F.; Cashmore, M. A.

    2016-01-01

    that urban governance of the wastewater system was influenced by a particular concern with developing attractive and competitive urban spaces. The wastewater system emerged as a ‘place-bound’ and even ‘place-making’ governance concern; as such, the boundaries and functions of the system were subject...... to continuous redefinition at the city level. This urban framing conflicted with the national-level, efficiency-oriented framing of the wastewater system as homogenous, without regard to place-specific differences. The research findings suggest that a distinct characteristic of urban-level governance is concern...... for place-specific development; this concern can be transformative because it leads to ongoing reinterpretation of traditional boundaries and dependencies between large-scale systems and local contexts....

  6. 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

  7. Technical specifications, Vogtle Electric Generating Plant, Unit No. 1 (Docket No. 50-424): Appendix ''A'' to license No. NPF-61

    International Nuclear Information System (INIS)

    1987-01-01

    This technical specifications report presents information concerning the Vogtle Electric Generating Plant in the following areas: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  8. 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

  9. Proposed design modifications and technical specification changes on grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2 (Docket Nos. 50-266 and 50-301). Technical evaluation report

    International Nuclear Information System (INIS)

    White, R.L.

    1981-01-01

    This report documents the technical evaluation of the proposed design mofifications and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Point Beach Nuclear Plant, Units 1 and 2. The review criteria are based on several IEEE standards and the Code of Federal Regulations. The evaluation compares the submittals made by the licensee with the NRC staff positions and the review criteria and presents the reviewer's conclusion on the acceptability of the proposed system

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

    International Nuclear Information System (INIS)

    Sommer, C. M.; Lemm, G.; Hohenstein, E.; Bellemann, N.; Stampfl, U.; Goezen, A. S.; Rassweiler, J.; Kauczor, H. U.; Radeleff, B. A.; Pereira, P. L.

    2013-01-01

    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 2 before RF ablation vs. 47.2 ± 11.9 ml/min/1.73 m 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.

  11. 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.

  12. Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

    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 Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 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 ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

  13. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-04-01

    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 {open_quotes}immediate{close_quotes} shutdown of the plant. In this paper, we 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.

  15. [Evaluation of residual osteomuscular function using computerised movement analysis for building sector workers: specificity and technical problem].

    Science.gov (United States)

    D'Orso, M I; Centemeri, R; Latocca, R; Riva, M; Cesana, G

    2012-01-01

    Occupational Health Doctors active in building sector firms frequently have to evaluate residual workers' osteomuscular function in patients coming back to work after an accident happened during work time or free time. Definition of their specific individual work suitability is usually carried out utilizing semeiotic tests in which subjective evaluation of every single Medical Doctor is real important in definition of final results and this fact can cause legal controversies. In our research we describe the application of computerised movement analysis on 10 workers of building sector. In every patient examined this technical method has been able to study objectively the tridimensional ranges of motion of most important osteomuscular districts. The possibility to have an objective evaluation of residual osteomuscular function has a relevant importance both in definition of workers' work suitability at the moment in which they start again their activities and in possible future legal conflicts.

  16. 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

  17. Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

    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 Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 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 ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre

  18. Risk-based evaluation of technical specification problems at the La Salle County Nuclear Station: Final report

    International Nuclear Information System (INIS)

    Bizzak, D.J.; Trainer, J.E.; McClymont, A.S.

    1987-06-01

    Probabilistic risk assessment (PRA) methods are used to evaluate alternatives to existing requirements for three operationally burdensome technical specifications at La Salle Nuclear Station. The study employs a decision logic to minimize the detailed analysis necessary to show compliance with given acceptance criteria; in this case, no risk increase resulting from a proposed change. The analyses provide insights to choose from among alternative options. The SOCRATES computer code was used for the probabilistic analysis. Results support a change to less frequent diesel generator testing, eliminations of one reactor scram setpoint, and establishing an allowed out-of-service time for valves in a reactor scram system. In each case, the change would result in a safety improvement

  19. Herd-specific interventions to reduce antimicrobial usage in pig production without jeopardising technical and economic performance.

    Science.gov (United States)

    Collineau, L; Rojo-Gimeno, C; Léger, A; Backhans, A; Loesken, S; Nielsen, E Okholm; Postma, M; Emanuelson, U; Beilage, E Grosse; Sjölund, M; Wauters, E; Stärk, K D C; Dewulf, J; Belloc, C; Krebs, S

    2017-09-01

    Pig farmers are strongly encouraged to reduce their antimicrobial usage in order to reduce the risk of antimicrobial resistance. Herd-level intervention is needed to achieve national and European reduction targets. Alternative, especially preventive measures, have to be implemented to reduce the need for antimicrobial treatments. However, little is known about the feasibility, effectiveness and return on investment of such measures. The objective of this study was to assess, across four countries, the technical and economic impact of herd-specific interventions aiming at reducing antimicrobial usage in pig production while implementing alternative measures. An intervention study was conducted between February 2014 and August 2015 in 70 farrow-to-finish pig farms located in Belgium, France, Germany and Sweden. Herd-specific interventions were defined together with the farmer and the herd veterinarian. Farms were followed over one year and their antimicrobial usage and technical performance were compared with values from the year before intervention. Compliance with the intervention plan was also monitored. Changes in margin over feed cost and net farm profit were estimated in a subset of 33 Belgian and French farms with sufficient data, using deterministic and stochastic modeling. Following interventions, a substantial reduction in antimicrobial use was achieved without negative impact the overall farm technical performance. A median reduction of 47.0% of antimicrobial usage was achieved across four countries when expressed in terms of treatment incidence from birth to slaughter, corresponding to a 30.5% median reduction of antimicrobial expenditures. Farm compliance with intervention plans was high (median: 93%; min-max: 20; 100) and farms with higher compliance tended to achieve bigger reduction (ρ=-0.18, p=0.162). No association was found between achieved reduction and type or number of alternative measures implemented. Mortality in suckling piglets, weaners and

  20. 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

  1. 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.

  2. 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)

  3. 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

  4. 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

  5. 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

  6. 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

  7. Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 2 (Docket No. 50-529). Appendix A to License No. NPF-51

    International Nuclear Information System (INIS)

    1986-04-01

    Information is presented concerning the technical specifications for the Palo Verde-2 Reactor. 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. 19 figs., 62 tabs

  8. 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

  9. Technical specifications: Grand Gulf Nuclear Station, Unit No. 1. Docket No. 50-416, Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1982-06-01

    Technical specifications are presented concerning safety limits; limiting safety system settings; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; site; and administrative controls

  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. 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.

  12. Technical specifications for Grand Gulf Nuclear Station, Unit 1 (Docket No. 50-416). Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1984-08-01

    The Grand Gulf Nuclear 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 facility as set forth in Section 50.36 of 10 CFR part 50 for the protection of the health and safety of the public

  13. Influence analysis of design parameters of suspensions on the technical specifications of conveyor with suspended belt and distributed drive

    Directory of Open Access Journals (Sweden)

    Lagerev A.V.

    2016-09-01

    Full Text Available Using the basic design of the conveyor with suspended belt and distributed drive, a series of numerical calculations was performed. As a result, the influence of friction and mass-dimensional design parameters of suspensions on the main technical parameters of the conveyor was established. Recommendations on the choice of rational parameters were formulated.

  14. [Medical surveillance in university: organizational difficulties, legal problems, scientific e technical specificities. Experience of University of Milan Bicocca].

    Science.gov (United States)

    D'Orso, M I; Giuliani, C; Assini, R; Riva, M A; Cesana, G

    2012-01-01

    Our research describes activities of Occupational Health carried out during last year in University of Milan Bicocca by Occupational Doctors. We describe results of medical surveillance in 1153 employees or students exposed to occupational risks for health and safety. We report results obtained, technical difficulties, organizational problems, and preventive actions decided to improve functionality of our activity. Students seem to be less protected and consequently seem to have higher professional safety and health risks.

  15. Development of a methodology for optimization of technical specifications using PSA based techniques. Development of methodology for evaluation of STI (Surveillance Test Interval) and AOT (Allowed Outage Time) in technical specifications using PSA techniques

    International Nuclear Information System (INIS)

    Jong In Lee; Dae Wook Chung; Sok Chul Kim

    1997-01-01

    In Korea, continued improvement of the safety of nuclear power plants has been set as national policy for the construction and operation of NPPs. Safety Related regulatory requirements under the Korea's Atomic Energy Laws are strictly observed in the design, fabrication, construction, and operation of NPPs. Safety regulation as regulatory concepts, efficient management of regulatory organizations, and rationalization will be improved further through the improvement of regulatory systems, introduction of to technical standards. The following improvements are considered: Periodical safety reevaluation of the operating plants; licensing system allowing certification for standard design and comprehensive site approval; and severe accident policies and criteria established for next generation reactors

  16. Simon on problem solving

    DEFF Research Database (Denmark)

    Foss, Kirsten; Foss, Nicolai Juul

    2006-01-01

    as a general approach to problem solving. We apply these Simonian ideas to organisational issues, specifically new organisational forms. Specifically, Simonian ideas allow us to develop a morphology of new organisational forms and to point to some design problems that characterise these forms.......Two of Herbert Simon's best-known papers are 'The Architecture of Complexity' and 'The Structure of Ill-Structured Problems.' We discuss the neglected links between these two papers, highlighting the role of decomposition in the context of problems on which constraints have been imposed...

  17. Technical Specifications, Byron Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-454 and STN 50-455). Appendix A to license No. NPF-37

    International Nuclear Information System (INIS)

    1985-02-01

    The Byron Station, Unit No. 1 and Unit No. 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. Specifications are presented for limiting conditions for operation for the reactor control system, power distribution limits, instrumentation, primary coolant circuit, ECCS, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring

  18. 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...

  19. 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

    and possible recycling hereof. The assessment is based on an inventory of inputs and outputs (resource/material consumption and generation of energy and emissions) for all the processes that occur as part of the product life-cycle. A model is developed to estimate the inputs and outputs associated...... 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...

  20. 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.

  1. 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

  2. Technical specifications: Byron Station Unit No. 1 (Docket No. STN 50-454). Appendix A to License No. NPF-23

    International Nuclear Information System (INIS)

    1984-10-01

    Specifications are presented concerning safety limits; reactor control systems; instrumentation; coolant circuits; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; design features; and administrative controls

  3. 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

  4. 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

  5. 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

  6. Resolution 197/012. It replaces the wording of Annex III of the Regulation of Technical Specifications for Quality of Liquid Fuels, approved by Resolution of the URSEA 150/008

    International Nuclear Information System (INIS)

    2012-01-01

    This resolution is about modifications made in the regulation of technical specifications in the quality of liquid fuels, approved by Resolution of the URSEA 150/008. These modifications concern to the Especial Oil gas

  7. Simon on Problem-Solving

    DEFF Research Database (Denmark)

    Foss, Kirsten; Foss, Nicolai Juul

    as a general approach to problem solving. We apply these Simonian ideas to organizational issues, specifically new organizational forms. Specifically, Simonian ideas allow us to develop a morphology of new organizational forms and to point to some design problems that characterize these forms.Keywords: Herbert...... Simon, problem-solving, new organizational forms. JEL Code: D23, D83......Two of Herbert Simon's best-known papers are "The Architecture of Complexity" and "The Structure of Ill-Structured Problems." We discuss the neglected links between these two papers, highlighting the role of decomposition in the context of problems on which constraints have been imposed...

  8. 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.

  9. 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.

  10. Assessment of Technical Skills in Young Soccer Goalkeepers: Reliability and Validity of Two Goalkeeper-Specific Tests

    Directory of Open Access Journals (Sweden)

    Ricardo Rebelo-Gonçalves, António J. Figueiredo, Manuel J. Coelho-e-Silva, Antonio Tessitore

    2016-09-01

    Full Text Available The purpose of this study was to evaluate the reproducibility and validity of two new tests designed to examine goalkeeper-specific technique. Twenty-six goalkeepers (14.49 ± 2.52 years old completed two trial sessions, each separated by one week, to evaluate the reproducibility of the Sprint-Keeper Test (S-Keeper and the Lateral Shuffle-Keeper Test (LS-Keeper. Construct validity was assessed among forty goalkeepers (14.49 ± 1.71 years old by competitive level (elite versus non-elite, after controlling for chronological age. All participants were examined in vertical jump (CMJ and CMJ-free arms, acceleration (5-m and 10-m sprint and goalkeeper-specific technique. The S-Keeper requires the goalkeeper to accelerate during 3 m and dive over a stationary ball after performing a change of direction in a total distance of 10 m. The LS-Keeper involves three changes of direction and a diving save over a stationary ball, in a total distance of 12.55 m. Performance was respectively measured as total time for the right and left sides in each protocol. Bivariate correlations between repeated measures were high and significant (r = 0.835 – 0.912. Test-retest results for the S-Keeper and LS-Keeper showed good reliability (reliability coefficients > 0.88, intra-class correlation coefficient > 0.908 and coefficients of variation < 4.37%, even though participants tended to improve performance when diving to their right side (p < 0.05. Both tests were able to detect significant differences between elite and non-elite goalkeepers, particularly to the left side (p < 0.05. These findings suggest that the S-Keeper and LS-Keeper are reliable and valid tests for assessing goalkeeper-specific technique. Both protocols can be used as a practical tool to provide relevant information about the influence of several components of performance in the overall execution of a diving save, particularly movement patterns, take-off movements and possible asymmetries.

  11. 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.

  12. 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)

  13. A technical assessment of the porcine ejaculated spermatozoa for a sperm-specific RNA-seq analysis.

    Science.gov (United States)

    Gòdia, Marta; Mayer, Fabiana Quoos; Nafissi, Julieta; Castelló, Anna; Rodríguez-Gil, Joan Enric; Sánchez, Armand; Clop, Alex

    2018-04-26

    The study of the boar sperm transcriptome by RNA-seq can provide relevant information on sperm quality and fertility and might contribute to animal breeding strategies. However, the analysis of the spermatozoa RNA is challenging as these cells harbor very low amounts of highly fragmented RNA, and the ejaculates also contain other cell types with larger amounts of non-fragmented RNA. Here, we describe a strategy for a successful boar sperm purification, RNA extraction and RNA-seq library preparation. Using these approaches our objectives were: (i) to evaluate the sperm recovery rate (SRR) after boar spermatozoa purification by density centrifugation using the non-porcine-specific commercial reagent BoviPure TM ; (ii) to assess the correlation between SRR and sperm quality characteristics; (iii) to evaluate the relationship between sperm cell RNA load and sperm quality traits and (iv) to compare different library preparation kits for both total RNA-seq (SMARTer Universal Low Input RNA and TruSeq RNA Library Prep kit) and small RNA-seq (NEBNext Small RNA and TailorMix miRNA Sample Prep v2) for high-throughput sequencing. Our results show that pig SRR (~22%) is lower than in other mammalian species and that it is not significantly dependent of the sperm quality parameters analyzed in our study. Moreover, no relationship between the RNA yield per sperm cell and sperm phenotypes was found. We compared a RNA-seq library preparation kit optimized for low amounts of fragmented RNA with a standard kit designed for high amount and quality of input RNA and found that for sperm, a protocol designed to work on low-quality RNA is essential. We also compared two small RNA-seq kits and did not find substantial differences in their performance. We propose the methodological workflow described for the RNA-seq screening of the boar spermatozoa transcriptome. FPKM: fragments per kilobase of transcript per million mapped reads; KRT1: keratin 1; miRNA: micro-RNA; miscRNA: miscellaneous

  14. Interactive problem solving using LOGO

    CERN Document Server

    Boecker, Heinz-Dieter; Fischer, Gerhard

    2014-01-01

    This book is unique in that its stress is not on the mastery of a programming language, but on the importance and value of interactive problem solving. The authors focus on several specific interest worlds: mathematics, computer science, artificial intelligence, linguistics, and games; however, their approach can serve as a model that may be applied easily to other fields as well. Those who are interested in symbolic computing will find that Interactive Problem Solving Using LOGO provides a gentle introduction from which one may move on to other, more advanced computational frameworks or more

  15. 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…

  16. Effects of the SOLVE Strategy on the Mathematical Problem Solving Skills of Secondary Students with Learning Disabilities

    Science.gov (United States)

    Freeman-Green, Shaqwana M.; O'Brien, Chris; Wood, Charles L.; Hitt, Sara Beth

    2015-01-01

    This study examined the effects of explicit instruction in the SOLVE Strategy on the mathematical problem solving skills of six Grade 8 students with specific learning disabilities. The SOLVE Strategy is an explicit instruction, mnemonic-based learning strategy designed to help students in solving mathematical word problems. Using a multiple probe…

  17. Environmental problem-solving: Psychosocial factors

    Science.gov (United States)

    Miller, Alan

    1982-11-01

    This is a study of individual differences in environmental problem-solving, the probable roots of these differences, and their implications for the education of resource professionals. A group of student Resource Managers were required to elaborate their conception of a complex resource issue (Spruce Budworm management) and to generate some ideas on management policy. Of particular interest was the way in which subjects dealt with the psychosocial aspects of the problem. A structural and content analysis of responses indicated a predominance of relatively compartmentalized styles, a technological orientation, and a tendency to ignore psychosocial issues. A relationship between problem-solving behavior and personal (psychosocial) style was established which, in the context of other evidence, suggests that problem-solving behavior is influenced by more deep seated personality factors. The educational implication drawn was that problem-solving cannot be viewed simply as an intellectual-technical activity but one that involves, and requires the education of, the whole person.

  18. Measuring Problem Solving Skills in "Portal 2"

    Science.gov (United States)

    Shute, Valerie J.; Wang, Lubin

    2013-01-01

    This paper examines possible improvement to problem solving skills as a function of playing the video game "Portal 2." Stealth assessment is used in the game to evaluate students' problem solving abilities--specifically basic and flexible rule application. The stealth assessment measures will be validated against commonly accepted…

  19. Technical note: Avoiding the direct inversion of the numerator relationship matrix for genotyped animals in single-step genomic best linear unbiased prediction solved with the preconditioned conjugate gradient.

    Science.gov (United States)

    Masuda, Y; Misztal, I; Legarra, A; Tsuruta, S; Lourenco, D A L; Fragomeni, B O; Aguilar, I

    2017-01-01

    This paper evaluates an efficient implementation to multiply the inverse of a numerator relationship matrix for genotyped animals () by a vector (). The computation is required for solving mixed model equations in single-step genomic BLUP (ssGBLUP) with the preconditioned conjugate gradient (PCG). The inverse can be decomposed into sparse matrices that are blocks of the sparse inverse of a numerator relationship matrix () including genotyped animals and their ancestors. The elements of were rapidly calculated with the Henderson's rule and stored as sparse matrices in memory. Implementation of was by a series of sparse matrix-vector multiplications. Diagonal elements of , which were required as preconditioners in PCG, were approximated with a Monte Carlo method using 1,000 samples. The efficient implementation of was compared with explicit inversion of with 3 data sets including about 15,000, 81,000, and 570,000 genotyped animals selected from populations with 213,000, 8.2 million, and 10.7 million pedigree animals, respectively. The explicit inversion required 1.8 GB, 49 GB, and 2,415 GB (estimated) of memory, respectively, and 42 s, 56 min, and 13.5 d (estimated), respectively, for the computations. The efficient implementation required <1 MB, 2.9 GB, and 2.3 GB of memory, respectively, and <1 sec, 3 min, and 5 min, respectively, for setting up. Only <1 sec was required for the multiplication in each PCG iteration for any data sets. When the equations in ssGBLUP are solved with the PCG algorithm, is no longer a limiting factor in the computations.

  20. 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

  1. The technical supervision interface

    CERN Document Server

    Sollander, P

    1998-01-01

    The Technical Control Room (TCR) is currently using 30 different applications for the remote supervision of the technical infrastructure at CERN. These applications have all been developed with the CERN made Uniform Man Machine Interface (UMMI) tools built in 1990. However, the visualization technology has evolved phenomenally since 1990, the Technical Data Server (TDS) has radically changed our control system architecture, and the standardization and the maintenance of the UMMI applications have become important issues as their number increases. The Technical Supervision Interface is intended to replace the UMMI and solve the above problems. Using a standard WWW-browser for the display, it will be inherently multi-platform and hence available for control room operators, equipment specialists and on-call personnel.

  2. 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.

  3. Problem Solving and Learning

    Science.gov (United States)

    Singh, Chandralekha

    2009-07-01

    One finding of cognitive research is that people do not automatically acquire usable knowledge by spending lots of time on task. Because students' knowledge hierarchy is more fragmented, "knowledge chunks" are smaller than those of experts. The limited capacity of short term memory makes the cognitive load high during problem solving tasks, leaving few cognitive resources available for meta-cognition. The abstract nature of the laws of physics and the chain of reasoning required to draw meaningful inferences makes these issues critical. In order to help students, it is crucial to consider the difficulty of a problem from the perspective of students. We are developing and evaluating interactive problem-solving tutorials to help students in the introductory physics courses learn effective problem-solving strategies while solidifying physics concepts. The self-paced tutorials can provide guidance and support for a variety of problem solving techniques, and opportunity for knowledge and skill acquisition.

  4. Teaching Creative Problem Solving.

    Science.gov (United States)

    Christensen, Kip W.; Martin, Loren

    1992-01-01

    Interpersonal and cognitive skills, adaptability, and critical thinking can be developed through problem solving and cooperative learning in technology education. These skills have been identified as significant needs of the workplace as well as for functioning in society. (SK)

  5. 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.

  6. Technical Specifications: Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-79

    International Nuclear Information System (INIS)

    1989-02-01

    The Vogtle Electric Generating Plant, 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 facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  7. Technical Specifications, Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-81

    International Nuclear Information System (INIS)

    1989-03-01

    The Vogtle Electric Generating Plant, 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 facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  8. 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

  9. 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

  10. 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

  11. Energy saving in the design and operation of fans; The development of technical literature for the specification of fume extraction systems

    Energy Technology Data Exchange (ETDEWEB)

    Gibbons, A [Plastic Fabrications and Environmental Technology Ltd., Armagh, Northern Ireland (United Kingdom)

    1995-12-01

    The processes involved in producing technical literature to assist in the selection of fans are discussed. Desktop publishing has been found to provide an effective method of matching the detail of the literature to the needs of the customer. (author)

  12. Problem solving skills for schizophrenia.

    Science.gov (United States)

    Xia, J; Li, Chunbo

    2007-04-18

    The severe and long-lasting symptoms of schizophrenia are often the cause of severe disability. Environmental stress such as life events and the practical problems people face in their daily can worsen the symptoms of schizophrenia. Deficits in problem solving skills in people with schizophrenia affect their independent and interpersonal functioning and impair their quality of life. As a result, therapies such as problem solving therapy have been developed to improve problem solving skills for people with schizophrenia. To review the effectiveness of problem solving therapy compared with other comparable therapies or routine care for those with schizophrenia. We searched the Cochrane Schizophrenia Group's Register (September 2006), which is based on regular searches of BIOSIS, CENTRAL, CINAHL, EMBASE, MEDLINE and PsycINFO. We inspected references of all identified studies for further trials. We included all clinical randomised trials comparing problem solving therapy with other comparable therapies or routine care. We extracted data independently. For homogenous dichotomous data we calculated random effects, relative risk (RR), 95% confidence intervals (CI) and, where appropriate, numbers needed to treat (NNT) on an intention-to-treat basis. For continuous data, we calculated weighted mean differences (WMD) using a random effects statistical model. We included only three small trials (n=52) that evaluated problem solving versus routine care, coping skills training or non-specific interaction. Inadequate reporting of data rendered many outcomes unusable. We were unable to undertake meta-analysis. Overall results were limited and inconclusive with no significant differences between treatment groups for hospital admission, mental state, behaviour, social skills or leaving the study early. No data were presented for global state, quality of life or satisfaction. We found insufficient evidence to confirm or refute the benefits of problem solving therapy as an additional

  13. Learning Matlab a problem solving approach

    CERN Document Server

    Gander, Walter

    2015-01-01

    This comprehensive and stimulating introduction to Matlab, a computer language now widely used for technical computing, is based on an introductory course held at Qian Weichang College, Shanghai University, in the fall of 2014.  Teaching and learning a substantial programming language aren’t always straightforward tasks. Accordingly, this textbook is not meant to cover the whole range of this high-performance technical programming environment, but to motivate first- and second-year undergraduate students in mathematics and computer science to learn Matlab by studying representative problems, developing algorithms and programming them in Matlab. While several topics are taken from the field of scientific computing, the main emphasis is on programming. A wealth of examples are completely discussed and solved, allowing students to learn Matlab by doing: by solving problems, comparing approaches and assessing the proposed solutions.

  14. Technical writing versus technical writing

    Science.gov (United States)

    Dillingham, J. W.

    1981-01-01

    Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

  15. Writing a technical note.

    Science.gov (United States)

    Ng, K H; Peh, W C G

    2010-02-01

    A technical note is a short article giving a brief description of a specific development, technique or procedure, or it may describe a modification of an existing technique, procedure or device applicable to medicine. The technique, procedure or device described should have practical value and should contribute to clinical diagnosis or management. It could also present a software tool, or an experimental or computational method. Technical notes are variously referred to as technical innovations or technical developments. The main criteria for publication will be the novelty of concepts involved, the validity of the technique and its potential for clinical applications.

  16. Methods of solving sequence and series problems

    CERN Document Server

    Grigorieva, Ellina

    2016-01-01

    This book aims to dispel the mystery and fear experienced by students surrounding sequences, series, convergence, and their applications. The author, an accomplished female mathematician, achieves this by taking a problem solving approach, starting with fascinating problems and solving them step by step with clear explanations and illuminating diagrams. The reader will find the problems interesting, unusual, and fun, yet solved with the rigor expected in a competition. Some problems are taken directly from mathematics competitions, with the name and year of the exam provided for reference. Proof techniques are emphasized, with a variety of methods presented. The text aims to expand the mind of the reader by often presenting multiple ways to attack the same problem, as well as drawing connections with different fields of mathematics. Intuitive and visual arguments are presented alongside technical proofs to provide a well-rounded methodology. With nearly 300 problems including hints, answers, and solutions,Met...

  17. 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

  18. Distributed Problem-Solving

    DEFF Research Database (Denmark)

    Chemi, Tatiana

    2016-01-01

    This chapter aims to deconstruct some persistent myths about creativity: the myth of individualism and of the genius. By looking at literature that approaches creativity as a participatory and distributed phenomenon and by bringing empirical evidence from artists’ studios, the author presents a p......, what can educators at higher education learn from the ways creative groups solve problems? How can artists contribute to inspiring higher education?......This chapter aims to deconstruct some persistent myths about creativity: the myth of individualism and of the genius. By looking at literature that approaches creativity as a participatory and distributed phenomenon and by bringing empirical evidence from artists’ studios, the author presents...... a perspective that is relevant to higher education. The focus here is on how artists solve problems in distributed paths, and on the elements of creative collaboration. Creative problem-solving will be looked at as an ongoing dialogue that artists engage with themselves, with others, with recipients...

  19. Solving Environmental Problems

    DEFF Research Database (Denmark)

    Ørding Olsen, Anders; Sofka, Wolfgang; Grimpe, Christoph

    2017-01-01

    for Research and Technological Development (FP7), our results indicate that the problem-solving potential of a search strategy increases with the diversity of existing knowledge of the partners in a consortium and with the experience of the partners involved. Moreover, we identify a substantial negative effect...... dispersed. Hence, firms need to collaborate. We shed new light on collaborative search strategies led by firms in general and for solving environmental problems in particular. Both topics are largely absent in the extant open innovation literature. Using data from the European Seventh Framework Program...

  20. Analysis of the influence of design parameters of vertically-closed track conveyor with suspended belt and distributed drive on the technical specifications

    Directory of Open Access Journals (Sweden)

    Tolkachev E.N.

    2016-12-01

    Full Text Available Using the basic design of the conveyor with suspended belt and distributed drive, a series of numerical calcu-lations was performed. As a result, the influence of design parameters of vertical loop route on the main tech-nical parameters of the conveyor was established. Recommendations on the choice of rational parameters were formulated.

  1. Introspection in Problem Solving

    Science.gov (United States)

    Jäkel, Frank; Schreiber, Cornell

    2013-01-01

    Problem solving research has encountered an impasse. Since the seminal work of Newell und Simon (1972) researchers do not seem to have made much theoretical progress (Batchelder and Alexander, 2012; Ohlsson, 2012). In this paper we argue that one factor that is holding back the field is the widespread rejection of introspection among cognitive…

  2. Problem Solving in Practice

    Science.gov (United States)

    Greene, Kim; Heyck-Williams, Jeff; Timpson Gray, Elicia

    2017-01-01

    Problem solving spans all grade levels and content areas, as evidenced by this compilation of projects from schools across the United States. In one project, high school girls built a solar-powered tent to serve their city's homeless population. In another project, 4th graders explored historic Jamestown to learn about the voices lost to history.…

  3. Solving Linear Differential Equations

    NARCIS (Netherlands)

    Nguyen, K.A.; Put, M. van der

    2010-01-01

    The theme of this paper is to 'solve' an absolutely irreducible differential module explicitly in terms of modules of lower dimension and finite extensions of the differential field K. Representations of semi-simple Lie algebras and differential Galo is theory are the main tools. The results extend

  4. Solving a binary puzzle

    NARCIS (Netherlands)

    Utomo, P.H.; Makarim, R.H.

    2017-01-01

    A Binary puzzle is a Sudoku-like puzzle with values in each cell taken from the set {0,1} {0,1}. Let n≥4 be an even integer, a solved binary puzzle is an n×n binary array that satisfies the following conditions: (1) no three consecutive ones and no three consecutive zeros in each row and each

  5. Electric Current Solves Mazes

    Science.gov (United States)

    Ayrinhac, Simon

    2014-01-01

    We present in this work a demonstration of the maze-solving problem with electricity. Electric current flowing in a maze as a printed circuit produces Joule heating and the right way is instantaneously revealed with infrared thermal imaging. The basic properties of electric current can be discussed in this context, with this challenging question:…

  6. Transport equation solving methods

    International Nuclear Information System (INIS)

    Granjean, P.M.

    1984-06-01

    This work is mainly devoted to Csub(N) and Fsub(N) methods. CN method: starting from a lemma stated by Placzek, an equivalence is established between two problems: the first one is defined in a finite medium bounded by a surface S, the second one is defined in the whole space. In the first problem the angular flux on the surface S is shown to be the solution of an integral equation. This equation is solved by Galerkin's method. The Csub(N) method is applied here to one-velocity problems: in plane geometry, slab albedo and transmission with Rayleigh scattering, calculation of the extrapolation length; in cylindrical geometry, albedo and extrapolation length calculation with linear scattering. Fsub(N) method: the basic integral transport equation of the Csub(N) method is integrated on Case's elementary distributions; another integral transport equation is obtained: this equation is solved by a collocation method. The plane problems solved by the Csub(N) method are also solved by the Fsub(N) method. The Fsub(N) method is extended to any polynomial scattering law. Some simple spherical problems are also studied. Chandrasekhar's method, collision probability method, Case's method are presented for comparison with Csub(N) and Fsub(N) methods. This comparison shows the respective advantages of the two methods: a) fast convergence and possible extension to various geometries for Csub(N) method; b) easy calculations and easy extension to polynomial scattering for Fsub(N) method [fr

  7. On Solving Linear Recurrences

    Science.gov (United States)

    Dobbs, David E.

    2013-01-01

    A direct method is given for solving first-order linear recurrences with constant coefficients. The limiting value of that solution is studied as "n to infinity." This classroom note could serve as enrichment material for the typical introductory course on discrete mathematics that follows a calculus course.

  8. Expressive/Exploratory Technical Writing (XTW) in Engineering: Shifting the Technical Writing Curriculum

    Science.gov (United States)

    Warnock, Scott; Kahn, Michael

    2007-01-01

    While the importance of "expressive writing," or informal, self-directed writing, has been well established, teachers underutilize it, particularly in technical writing courses. We introduce the term expressive/exploratory technical writing (XTW), which is the use of informal, self-directed writing to problem-solve in technical fields. We describe…

  9. 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.

  10. Toward Solving the Problem of Problem Solving: An Analysis Framework

    Science.gov (United States)

    Roesler, Rebecca A.

    2016-01-01

    Teaching is replete with problem solving. Problem solving as a skill, however, is seldom addressed directly within music teacher education curricula, and research in music education has not examined problem solving systematically. A framework detailing problem-solving component skills would provide a needed foundation. I observed problem solving…

  11. Creativity and Problem Solving

    DEFF Research Database (Denmark)

    Vidal, Rene Victor Valqui

    2004-01-01

    This paper presents some modern and interdisciplinary concepts about creativity and creative processes of special relevance for Operational Research workers. Central publications in the area Creativity-Operational Research are shortly reviewed. Some creative tools and the Creative Problem Solving...... approach are also discussed. Finally, some applications of these concepts and tools are outlined. Some central references are presented for further study of themes related to creativity or creative tools....

  12. Creativity and problem Solving

    Directory of Open Access Journals (Sweden)

    René Victor Valqui Vidal

    2004-12-01

    Full Text Available This paper presents some modern and interdisciplinary concepts about creativity and creative processes of special relevance for Operational Research workers. Central publications in the area Creativity-Operational Research are shortly reviewed. Some creative tools and the Creative Problem Solving approach are also discussed. Finally, some applications of these concepts and tools are outlined. Some central references are presented for further study of themes related to creativity or creative tools.

  13. Intelligent Personal Supercomputer for Solving Scientific and Technical Problems

    Directory of Open Access Journals (Sweden)

    Khimich, O.M.

    2016-09-01

    Full Text Available New domestic intellіgent personal supercomputer of hybrid architecture Inparkom_pg for the mathematical modeling of processes in the defense industry, engineering, construction, etc. was developed. Intelligent software for the automatic research and tasks of computational mathematics with approximate data of different structures was designed. Applied software to provide mathematical modeling problems in construction, welding and filtration processes was implemented.

  14. Design and Diagnosis Problem Solving with Multifunctional Technical Knowledge Bases

    Science.gov (United States)

    1992-09-29

    Knowledge in Device Design .......................................................... 145 QP is More Than SPQR and Dynamical Systems Theory: Response to...More Than SPQR and Dynamical Systems Theory: Response to Sacks and Doyle," to appear in Computational Intelligence. [53] B. Chandrasekaran and N. Hari...More Than SPQR and Dynamical Systems Theory:I Response to Sacks and Doyle B. Chandrasekaran Dept of Computer & Information Science The Ohio State

  15. 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....

  16. 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.

  17. Appreciative Problem Solving

    DEFF Research Database (Denmark)

    Hansen, David

    2012-01-01

    Many industrial production work systems have increased in complexity, and their new business model scompete on innovation, rather than low cost.At a medical device production facility committed to Lean Production, a research project was carried out to use Appreciative Inquiry to better engage...... employee strengths in continuou simprovements of the work system. The research question was: “How can Lean problem solving and Appreciative Inquiry be combined for optimized work system innovation?” The research project was carried out as a co-creation process with close cooperation between researcher...

  18. Planning and Problem Solving

    Science.gov (United States)

    1982-10-01

    Artificial Intelig ~ence (Vol. III, edited by Paul R. Cohen and’ Edward A.. Feigenbaum)’, The chapter was written B’ Paul Cohen, with contributions... Artificial Intelligence (Vol. III, edited by Paul R. Cohen and EdWard A. Feigenbaum). The chapter was written by Paul R. Cohen, with contributions by Stephen...Wheevoats"EntermdI’ Planning and Problem ’Solving by Paul R. Cohen Chaptb-rXV-of Volumec III’of the Handbook of Artificial Intelligence edited by Paul R

  19. Specification of technical means for implementation of supervisory algorithms of the status of a nuclear reactor and of the main coolant pump of a NPP

    International Nuclear Information System (INIS)

    Jirsa, P.

    2000-11-01

    Inclusion into the programming of inputs of the supervisory algorithm (data collection from the monitoring system, transmission of diagnostic output fro other system and transmission of technological data), of the supervisory process proper based on the data obtained (data analysis) and of the output (presentation of the results to the operator, communication with the master and archiving systems, etc.) requires knowledge of the format of the data transmitted, their availability, communication network protocols, operating system, etc. Hence, the environment for which the algorithm will be developed should be specified, roughly at least. The following topics are addressed: Description of technical means of Czech nuclear power plants (Dukovany, Temelin, Mochovce), and Proposal for technical means to implement the monitoring algorithm (Requirements related to the monitoring systems, Identification of the reference system, Parameters of the selected system). Since no domestic manufacturer of HW for monitoring and diagnostic systems exists, a novel system of the Brueel and Kjaer company for on-line diagnosis and monitoring, COMPASS, was selected as a model model system for the implementation of the supervisory algorithms. (P.A.)

  20. Solving Differential Equations in R: Package deSolve

    Science.gov (United States)

    In this paper we present the R package deSolve to solve initial value problems (IVP) written as ordinary differential equations (ODE), differential algebraic equations (DAE) of index 0 or 1 and partial differential equations (PDE), the latter solved using the method of lines appr...

  1. Solving Differential Equations in R: Package deSolve

    NARCIS (Netherlands)

    Soetaert, K.E.R.; Petzoldt, T.; Setzer, R.W.

    2010-01-01

    In this paper we present the R package deSolve to solve initial value problems (IVP) written as ordinary differential equations (ODE), differential algebraic equations (DAE) of index 0 or 1 and partial differential equations (PDE), the latter solved using the method of lines approach. The

  2. 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.

  3. Solved problems in electromagnetics

    CERN Document Server

    Salazar Bloise, Félix; Bayón Rojo, Ana; Gascón Latasa, Francisco

    2017-01-01

    This book presents the fundamental concepts of electromagnetism through problems with a brief theoretical introduction at the beginning of each chapter. The present book has a strong  didactic character. It explains all the mathematical steps and the theoretical concepts connected with the development of the problem. It guides the reader to understand the employed procedures to learn to solve the exercises independently. The exercises are structured in a similar way: The chapters begin with easy problems increasing progressively in the level of difficulty. This book is written for students of physics and engineering in the framework of the new European Plans of Study for Bachelor and Master and also for tutors and lecturers. .

  4. Solved problems in electrochemistry

    International Nuclear Information System (INIS)

    Piron, D.L.

    2004-01-01

    This book presents calculated solutions to problems in fundamental and applied electrochemistry. It uses industrial data to illustrate scientific concepts and scientific knowledge to solve practical problems. It is subdivided into three parts. The first uses modern basic concepts, the second studies the scientific basis for electrode and electrolyte thermodynamics (including E-pH diagrams and the minimum energy involved in transformations) and the kinetics of rate processes (including the energy lost in heat and in parasite reactions). The third part treats larger problems in electrolysis and power generation, as well as in corrosion and its prevention. Each chapter includes three sections: the presentation of useful principles; some twenty problems with their solutions; and, a set of unsolved problems

  5. Lesion mapping of social problem solving.

    Science.gov (United States)

    Barbey, Aron K; Colom, Roberto; Paul, Erick J; Chau, Aileen; Solomon, Jeffrey; Grafman, Jordan H

    2014-10-01

    Accumulating neuroscience evidence indicates that human intelligence is supported by a distributed network of frontal and parietal regions that enable complex, goal-directed behaviour. However, the contributions of this network to social aspects of intellectual function remain to be well characterized. Here, we report a human lesion study (n = 144) that investigates the neural bases of social problem solving (measured by the Everyday Problem Solving Inventory) and examine the degree to which individual differences in performance are predicted by a broad spectrum of psychological variables, including psychometric intelligence (measured by the Wechsler Adult Intelligence Scale), emotional intelligence (measured by the Mayer, Salovey, Caruso Emotional Intelligence Test), and personality traits (measured by the Neuroticism-Extraversion-Openness Personality Inventory). Scores for each variable were obtained, followed by voxel-based lesion-symptom mapping. Stepwise regression analyses revealed that working memory, processing speed, and emotional intelligence predict individual differences in everyday problem solving. A targeted analysis of specific everyday problem solving domains (involving friends, home management, consumerism, work, information management, and family) revealed psychological variables that selectively contribute to each. Lesion mapping results indicated that social problem solving, psychometric intelligence, and emotional intelligence are supported by a shared network of frontal, temporal, and parietal regions, including white matter association tracts that bind these areas into a coordinated system. The results support an integrative framework for understanding social intelligence and make specific recommendations for the application of the Everyday Problem Solving Inventory to the study of social problem solving in health and disease. © The Author (2014). Published by Oxford University Press on behalf of the Guarantors of Brain. All rights reserved

  6. Technical specifications, Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423). Appendix ''A'' to License No. NPF-49

    International Nuclear Information System (INIS)

    1986-01-01

    Information is presented concerning specifications on the following aspects of the Millstone Nuclear Power Station, Unit No. 3: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  7. Technical specifications: Callaway Plant, Unit No. 1 (Docket No. STN 50-483). Appendix A to License No. NPF-30. Revision 1

    International Nuclear Information System (INIS)

    1984-10-01

    Revised specifications are presented concerning limiting safety system settings for control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical systems, refueling operations, radioactive effluents, and radiation environmental monitoring

  8. Technical Specifications, Shearon Harris Nuclear Power Plant, Unit No. 1 (Docket No. 50-400). Appendix ''A'' to License No. NPF-53

    International Nuclear Information System (INIS)

    1986-10-01

    This report presents specifications for the Shearon Harris Nuclear Power Plant Unit No. 1 concerning: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  9. L'impact des développements scientifiques sur la résolution des problèmes techniques posés par la nouvelle conjoncture dans l'exploration et la production du pétrole Impact of Scientific Developments on the Solving of Technical Problems Raised by the New Economic Situation in Oil Exploration and Production

    Directory of Open Access Journals (Sweden)

    Tissot B.

    2006-11-01

    Full Text Available Dans les circonstances difficiles que traverse l'exploration et la production du pétrole, le savoir-faire technologique, associé à la maîtrise des coûts, seront pour l'industrie pétrolière et parapétrolière des atouts essentiels. On envisage ici l'impact prévisible des développements scientifiques sur la résolution des problèmes techniques dans l'exploration et la production. Les principales disciplines scientifiques concernées (géologie, géophysique, géochimie, mécanique des roches et des sols, mécanique des fluides, physicochimie des interfaces ainsi que trois techniques de base (modélisation, systèmes experts, matériaux nouveaux sont examinées dans ce sens. En particulier,la modélisation numérique voit son importance croître de manière spectaculaire : elle couvre désormais des domaines nouveaux, comme les Sciences de la Terre, et continue à s'enrichir de développements importants, même dans les secteurs où on l'utilise depuis 20 ans comme la production. Ces évolutions s'accompagneront nécessairement d'ajustements dans la formation des hommes et le fonctionnement des organisations; en particulier un espace nouveau pourrait se dégager pour de petites entreprises de conseil et de service plus riches en matière grise qu'en investissements lourds. In the difficult circumstances now confronting oil exploration and production, technical know-how combined with cost control will be essential assets for the petroleum and petroleum equipment and service industries. This article considers the foreseeable impact of scientific developments on the solving of technical problems in exploration and production. The principal scientific disciplines involved (geology, geophysics, geochemistry, rock and soil mechanics, fluid mechanics, interface physicochemistry as well as three basic techniques (modeling, expert systems, new materials are examined within this context. In particular, numerical modeling is increasing in

  10. 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

  11. 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

  12. 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

  13. Creative and Participative Problem Solving - The Art and the Science

    DEFF Research Database (Denmark)

    Vidal, Rene Victor Valqui

    This book collects my experiences as a facilitator for many different communities and organizations and as a teacher at the Technical University of Denmark for the courses Creativity and Problem Solving and Systemic Operational Research. Several of the chapters has been used in my lecturing activ...

  14. Technical specifications, La Salle County Station, Unit No. 1. Appendix A to License No. NPF-11, Docket No. 50-373

    International Nuclear Information System (INIS)

    1982-04-01

    Specifications are presented concerning safety limits; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling system; containment systems; plant systems; electrical power systems; refueling operations; special test exceptions; radioactive effluents; radiological environmental monitoring; reactor site; fuel storage; and plant operations

  15. How to develop and write a case for technical writing

    Science.gov (United States)

    Couture, B.; Goldstein, J.

    1981-01-01

    Case of different sizes and shapes for teaching technical writing to engineers at Wayne State University have been developed. The case approach was adopted for some assignments because sophomores and juniors lacked technical expertise and professional knowledge of the engineering world. Cases were found to be good exercises, providing realistic practice in specific writing tasks or isolating particular skills in the composing process. A special kind of case which narrates the experiences of one technical person engaged in the problem-solving process in a professional rhetorical situation was developed. This type of long, realistic fiction is called a an "holistic" case. Rather than asking students to role-play a character, an holistic case realistically encompasses the whole of the technical writing process. It allows students to experience the total communication act in which the technical task and data are fully integrated into the rhetorical situation and gives an opportunity to perform in a realistic context, using skills and knowledge required in communication on the job. It is believed that the holistic case most fully exploits the advantages of the case method for students of professional communication.

  16. Technical specifications for waste packages conditioned in a durable confining shell, with an hydraulic binder basis, intended to a ground disposal site

    International Nuclear Information System (INIS)

    1995-06-01

    The aim of this document is to precise the general and particular conditions for the acceptance on a ground disposal site of a low- and middle-level radioactive waste package conditioned in a durable confining shell. This specification concerns the wastes that contain beta and gamma decay radionuclides and/or long life alpha decay radionuclides in higher quantities than accepted for the protective coatings. Physico-chemical and mechanical specifications are given for the wastes, the fixing material, the confining shell and the container. Accepted limits for degassing and dose rates, surface contamination, dimensions and weight are given. The agreement is delivered by the ANDRA after the package has satisfied the different mechanical, chemical, fire, moisture and radiation resistance tests. (J.S.). 1 fig., 3 tabs., 1 glossary

  17. 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

  18. 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

  19. 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

  20. Problem Solving and the Development of Expertise in Management.

    Science.gov (United States)

    Lash, Fredrick B.

    This study investigated novice and expert problem solving behavior in management to examine the role of domain specific knowledge on problem solving processes. Forty-one middle level marketing managers in a large petrochemical organization provided think aloud protocols in response to two hypothetical management scenarios. Protocol analysis…

  1. Glogs as Non-Routine Problem Solving Tools in Mathematics

    Science.gov (United States)

    Devine, Matthew T.

    2013-01-01

    In mathematical problem solving, American students are falling behind their global peers because of a lack of foundational and reasoning skills. A specific area of difficulty with problem solving is working non-routine, heuristic-based problems. Many students are not provided with effective instruction and often grow frustrated and dislike math.…

  2. Is Word-Problem Solving a Form of Text Comprehension?

    Science.gov (United States)

    Fuchs, Lynn S.; Fuchs, Douglas; Compton, Donald L.; Hamlett, Carol L.; Wang, Amber Y.

    2015-01-01

    This study's hypotheses were that (a) word-problem (WP) solving is a form of text comprehension that involves language comprehension processes, working memory, and reasoning, but (b) WP solving differs from other forms of text comprehension by requiring WP-specific language comprehension as well as general language comprehension. At the start of…

  3. Technical Note

    African Journals Online (AJOL)

    Administratör

    In this report on four patients, we did not use any of these techniques. The existence and the site of the fistulas was clearly demonstrated using basic but important preoperative detailed assessment and two intraoperative findings. The preoperative referral note that indicated the site of technical difficulty during the previous ...

  4. 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...

  5. 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...

  6. 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

  7. Designing Teaching Materials for Learning Problem Solving in Technology Education

    NARCIS (Netherlands)

    Doornekamp, B.G.

    In the process of designing teaching materials for learning problem solving in technology education, domain-specific design specifications are considered important elements to raise learning outcomes with these materials. Two domain-specific design specifications were drawn up using a four-step

  8. Difficulties in Genetics Problem Solving.

    Science.gov (United States)

    Tolman, Richard R.

    1982-01-01

    Examined problem-solving strategies of 30 high school students as they solved genetics problems. Proposes a new sequence of teaching genetics based on results: meiosis, sex chromosomes, sex determination, sex-linked traits, monohybrid and dihybrid crosses (humans), codominance (humans), and Mendel's pea experiments. (JN)

  9. Problem Solving, Scaffolding and Learning

    Science.gov (United States)

    Lin, Shih-Yin

    2012-01-01

    Helping students to construct robust understanding of physics concepts and develop good solving skills is a central goal in many physics classrooms. This thesis examine students' problem solving abilities from different perspectives and explores strategies to scaffold students' learning. In studies involving analogical problem solving…

  10. Problem Solving on a Monorail.

    Science.gov (United States)

    Barrow, Lloyd H.; And Others

    1994-01-01

    This activity was created to address a lack of problem-solving activities for elementary children. A "monorail" activity from the Evening Science Program for K-3 Students and Parents program is presented to illustrate the problem-solving format. Designed for performance at stations by groups of two students. (LZ)

  11. Solving complex fisheries management problems

    DEFF Research Database (Denmark)

    Petter Johnsen, Jahn; Eliasen, Søren Qvist

    2011-01-01

    A crucial issue for the new EU common fisheries policy is how to solve the discard problem. Through a study of the institutional set up and the arrangements for solving the discard problem in Denmark, the Faroe Islands, Iceland and Norway, the article identifies the discard problem as related...

  12. 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...

  13. Community-powered problem solving.

    Science.gov (United States)

    Gouillart, Francis; Billings, Douglas

    2013-04-01

    Traditionally, companies have managed their constituencies with specific processes: marketing to customers, procuring from vendors, developing HR policies for employees, and so on. The problem is, such processes focus on repeatability and compliance, so they can lead to stagnation. Inviting your constituencies to collectively help you solve problems and exploit opportunities--"co-creation"--is a better approach. It allows you to continually tap the skills and insights of huge numbers of stakeholders and develop new ways to produce value for all. The idea is to provide stakeholders with platforms (physical and digital forums) on which they can interact, get them to start exploring new experiences and connections, and let the system grow organically. A co-creation initiative by a unit of Becton, Dickinson and Company demonstrates how this works. A global leader in syringes, BD set out to deepen its ties with hospital customers and help them reduce the incidence of infections from unsafe injection and syringe disposal practices. The effort began with a cross-functional internal team, brought in the hospital procurement and supply managers BD had relationships with, and then reached out to hospitals' infection-prevention and occupational health leaders. Eventually product designers, nurses, sustainability staffers, and even hospital CFOs were using the platform, contributing data that generated new best practices and reduced infections.

  14. Technical vocational education in India

    OpenAIRE

    溝上, 智恵子

    1999-01-01

    In India, several efforts have been made for the development of skilled manpower during the last twenty years since the launch of formal technical vocational education at school. A huge education infrastructure has developed in India. However, 45~50 percent of the population of India is still illiterate. To solve the mismatch between education and employment, a revolution in education is really needed. Additionally, there is a need for a system of National Vocational Qualifications in India a...

  15. Problem solving therapy - use and effectiveness in general practice.

    Science.gov (United States)

    Pierce, David

    2012-09-01

    Problem solving therapy (PST) is one of the focused psychological strategies supported by Medicare for use by appropriately trained general practitioners. This article reviews the evidence base for PST and its use in the general practice setting. Problem solving therapy involves patients learning or reactivating problem solving skills. These skills can then be applied to specific life problems associated with psychological and somatic symptoms. Problem solving therapy is suitable for use in general practice for patients experiencing common mental health conditions and has been shown to be as effective in the treatment of depression as antidepressants. Problem solving therapy involves a series of sequential stages. The clinician assists the patient to develop new empowering skills, and then supports them to work through the stages of therapy to determine and implement the solution selected by the patient. Many experienced GPs will identify their own existing problem solving skills. Learning about PST may involve refining and focusing these skills.

  16. Teachers' ICT and Problem-Solving Skills: Competencies and Needs. Education Indicators in Focus. No. 40

    Science.gov (United States)

    OECD Publishing, 2016

    2016-01-01

    The education sector performs well for information and communication technology (ICT) and problem-solving skills, although it still lags behind the professional, scientific and technical activities sector. Primary and secondary teachers have better ICT and problem-solving skills than the general population, and similar skills to other…

  17. 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 ...

  18. 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 ...

  19. 48 CFR 227.7102-2 - Rights in technical data.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Rights in technical data... Technical Data 227.7102-2 Rights in technical data. (a) The clause at 252.227-7015, Technical Data—Commercial Items, provides the Government specific license rights in technical data pertaining to commercial...

  20. Can Pollution Problems Be Effectively Solved by Environmental Science and Technology? An Analysis of Critical Limitations

    Energy Technology Data Exchange (ETDEWEB)

    Huesemann, Michael H.(BATTELLE (PACIFIC NW LAB))

    2000-12-01

    It is currently believed that science and technology can provide effective solutions to most, if not all, environmental problems facing western industrial societies. The validity of this optimistic assumption is highly questionable for at least three reasons: First, current mechanistic, reductionist science is inherently incapable of providing the complete and accurate information which is required to successfully address environmental problems. Second, both the conservation of mass principle and the second law of thermodynamics dictate that most remediation technologies - while successful in solving specific pollution problems - cause unavoidable negative environmental impacts elsewhere or in the future. Third, it is intrinsically impossible to design industrial processes that have no negative environmental impacts. This follows not only from the entropy law but also from the fact that any generation of energy is impossible without negative environmental consequences. It can therefore be concluded that science and technology have only very limited potential in solving current and future environmental problems. Consequently, it will be necessary to address the root cause of environmental deterioration, namely the prevailing materialistic values that are the main driving force for both overpopulation and overconsumption. The long-term protection of the environment is therefore not primarily a technical problem but rather a social and moral problem that can only be solved by drastically reducing the strong influence of materialistic values.

  1. Problem Solving with General Semantics.

    Science.gov (United States)

    Hewson, David

    1996-01-01

    Discusses how to use general semantics formulations to improve problem solving at home or at work--methods come from the areas of artificial intelligence/computer science, engineering, operations research, and psychology. (PA)

  2. How to solve mathematical problems

    CERN Document Server

    Wickelgren, Wayne A

    1995-01-01

    Seven problem-solving techniques include inference, classification of action sequences, subgoals, contradiction, working backward, relations between problems, and mathematical representation. Also, problems from mathematics, science, and engineering with complete solutions.

  3. Interactive Problem-Solving Interventions

    African Journals Online (AJOL)

    Frew Demeke Alemu

    concerted efforts of unofficial actors to establish unofficial communication ... Frew Demeke Alemu (LLB, LLM in International Human Rights Law from Lund ..... 24 Tamra Pearson d'Estrée (2009), “Problem-Solving Approaches”, (in The SAGE ...

  4. Technical Leadership Development Program-Year 3

    Science.gov (United States)

    2012-08-30

    be subject to a penalty for failing to comply with a collection of information if it does not display a currently valid OMB control number. 1. REPORT...NASA6, Nokia , BAE Systems, the DoD, and the Australian government to develop our initial competency model. These models were discussed in deliverable...UNCLASSIFIED 17 solutions to pursue and why they should be built. 2. Help teams solve technical problems holistically, overcoming technical and non

  5. 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...

  6. 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...

  7. Using a general problem-solving strategy to promote transfer.

    Science.gov (United States)

    Youssef-Shalala, Amina; Ayres, Paul; Schubert, Carina; Sweller, John

    2014-09-01

    Cognitive load theory was used to hypothesize that a general problem-solving strategy based on a make-as-many-moves-as-possible heuristic could facilitate problem solutions for transfer problems. In four experiments, school students were required to learn about a topic through practice with a general problem-solving strategy, through a conventional problem solving strategy or by studying worked examples. In Experiments 1 and 2 using junior high school students learning geometry, low knowledge students in the general problem-solving group scored significantly higher on near or far transfer tests than the conventional problem-solving group. In Experiment 3, an advantage for a general problem-solving group over a group presented worked examples was obtained on far transfer tests using the same curriculum materials, again presented to junior high school students. No differences between conditions were found in Experiments 1, 2, or 3 using test problems similar to the acquisition problems. Experiment 4 used senior high school students studying economics and found the general problem-solving group scored significantly higher than the conventional problem-solving group on both similar and transfer tests. It was concluded that the general problem-solving strategy was helpful for novices, but not for students that had access to domain-specific knowledge. PsycINFO Database Record (c) 2014 APA, all rights reserved.

  8. Pre-Service Mathematics Teachers’ Problem Solving Processes with Geometer’s Sketchpad: Mirror Problem

    OpenAIRE

    ÖÇAL, Mehmet Fatih; ŞİMŞEK, Mertkan

    2016-01-01

    Problem solving skill is the core of mathematics education and its importance cannot be denied. This study specifically examined 56 freshmen pre-service mathematics teachers’ problem solving processes on a specific problem with the help of Geometer’s Sketchpad (GSP). They were grouped into two-person teams to solve a problem called "the mirror problem". They were expected to solve it by means of GSP. According to their works on GSP and related reflections, there appeared two differe...

  9. Social problem-solving among adolescents treated for depression.

    Science.gov (United States)

    Becker-Weidman, Emily G; Jacobs, Rachel H; Reinecke, Mark A; Silva, Susan G; March, John S

    2010-01-01

    Studies suggest that deficits in social problem-solving may be associated with increased risk of depression and suicidality in children and adolescents. It is unclear, however, which specific dimensions of social problem-solving are related to depression and suicidality among youth. Moreover, rational problem-solving strategies and problem-solving motivation may moderate or predict change in depression and suicidality among children and adolescents receiving treatment. The effect of social problem-solving on acute treatment outcomes were explored in a randomized controlled trial of 439 clinically depressed adolescents enrolled in the Treatment for Adolescents with Depression Study (TADS). Measures included the Children's Depression Rating Scale-Revised (CDRS-R), the Suicidal Ideation Questionnaire--Grades 7-9 (SIQ-Jr), and the Social Problem-Solving Inventory-Revised (SPSI-R). A random coefficients regression model was conducted to examine main and interaction effects of treatment and SPSI-R subscale scores on outcomes during the 12-week acute treatment stage. Negative problem orientation, positive problem orientation, and avoidant problem-solving style were non-specific predictors of depression severity. In terms of suicidality, avoidant problem-solving style and impulsiveness/carelessness style were predictors, whereas negative problem orientation and positive problem orientation were moderators of treatment outcome. Implications of these findings, limitations, and directions for future research are discussed. Copyright 2009 Elsevier Ltd. All rights reserved.

  10. Technical specification of HANARO fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y

    1998-03-01

    The design and installation of the irradiation test facility for verification test of the fuel performance are very important in connection with maximization of the utilization of HANARO. HANARO fuel test loop was designed in accordance with the same code and standards of nuclear power plant because HANARO FTL will be operated the high pressure and temperature same as nuclear power plant operation conditions. The objective of this study is to confirm the operation limit, safety limit, operation condition and checking points of HANARO fuel test loop. This results will become guidances for the planning of irradiation testing and operation of HANARO fuel test loop. (author). 13 refs., 13 tabs., 8 figs.

  11. High Flux Isotope Reactor technical specifications

    International Nuclear Information System (INIS)

    1977-03-01

    Included are sections covering safety limits and limiting safety system settings, limiting conditions for operation, surveillance requirements, design features, and administrative controls. An appendix deals with accidents and anticipated transients

  12. 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.

  13. Knowledge based management of technical specifications

    International Nuclear Information System (INIS)

    Fiedler, U.; Schalm, S.; Pranckeviciute, K.

    1992-01-01

    TechSPEX is a knowledge based advisory system for checking the status of a nuclear plant on compliance with the safety limits and the limiting conditions of operation. These prescripts for safe reactor operation exist as textual information. For the purpose of its operational use an explicit representation formalism is introduced. On this basis, various approaches of text retrieval are realized, condition based surveillance and control is supported too. Knowledge editing and verification modules ease the adaption to changing requirements. TechSPEX has been implemented in PROLOG. (author). 6 refs, 3 figs

  14. 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, ...

  15. Tangram solved? Prefrontal cortex activation analysis during geometric problem solving.

    Science.gov (United States)

    Ayaz, Hasan; Shewokis, Patricia A; Izzetoğlu, Meltem; Çakır, Murat P; Onaral, Banu

    2012-01-01

    Recent neuroimaging studies have implicated prefrontal and parietal cortices for mathematical problem solving. Mental arithmetic tasks have been used extensively to study neural correlates of mathematical reasoning. In the present study we used geometric problem sets (tangram tasks) that require executive planning and visuospatial reasoning without any linguistic representation interference. We used portable optical brain imaging (functional near infrared spectroscopy--fNIR) to monitor hemodynamic changes within anterior prefrontal cortex during tangram tasks. Twelve healthy subjects were asked to solve a series of computerized tangram puzzles and control tasks that required same geometric shape manipulation without problem solving. Total hemoglobin (HbT) concentration changes indicated a significant increase during tangram problem solving in the right hemisphere. Moreover, HbT changes during failed trials (when no solution found) were significantly higher compared to successful trials. These preliminary results suggest that fNIR can be used to assess cortical activation changes induced by geometric problem solving. Since fNIR is safe, wearable and can be used in ecologically valid environments such as classrooms, this neuroimaging tool may help to improve and optimize learning in educational settings.

  16. Using qualitative problem-solving strategies to highlight the role of conceptual knowledge in solving problems

    Science.gov (United States)

    Leonard, William J.; Dufresne, Robert J.; Mestre, Jose P.

    1996-12-01

    We report on the use of qualitative problem-solving strategies in teaching an introductory, calculus-based physics course as a means of highlighting the role played by conceptual knowledge in solving problems. We found that presenting strategies during lectures and in homework solutions provides an excellent opportunity to model for students the type of concept-based, qualitative reasoning that is valued in our profession, and that student-generated strategies serve a diagnostic function by providing instructors with insights on students' conceptual understanding and reasoning. Finally, we found strategies to be effective pedagogical tools for helping students both to identify principles that could be applied to solve specific problems, as well as to recall the major principles covered in the course months after it was over.

  17. 48 CFR 12.211 - Technical data.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Technical data. 12.211... ACQUISITION OF COMMERCIAL ITEMS Special Requirements for the Acquisition of Commercial Items 12.211 Technical data. Except as provided by agency-specific statutes, the Government shall acquire only the technical...

  18. Solving ptychography with a convex relaxation

    Science.gov (United States)

    Horstmeyer, Roarke; Chen, Richard Y.; Ou, Xiaoze; Ames, Brendan; Tropp, Joel A.; Yang, Changhuei

    2015-05-01

    Ptychography is a powerful computational imaging technique that transforms a collection of low-resolution images into a high-resolution sample reconstruction. Unfortunately, algorithms that currently solve this reconstruction problem lack stability, robustness, and theoretical guarantees. Recently, convex optimization algorithms have improved the accuracy and reliability of several related reconstruction efforts. This paper proposes a convex formulation of the ptychography problem. This formulation has no local minima, it can be solved using a wide range of algorithms, it can incorporate appropriate noise models, and it can include multiple a priori constraints. The paper considers a specific algorithm, based on low-rank factorization, whose runtime and memory usage are near-linear in the size of the output image. Experiments demonstrate that this approach offers a 25% lower background variance on average than alternating projections, the ptychographic reconstruction algorithm that is currently in widespread use.

  19. Direction of technical and tactical skill in athletes playing team sports, playing with light position

    Directory of Open Access Journals (Sweden)

    Doroshenko Eduard Iur'evich

    2011-10-01

    Full Text Available A new method for evaluating the effectiveness of technical and tactical activities in basketball. A distinctive feature of the technique is presented key components of the accounting games, length of stay in the athletes play and the specific features of the game line. Established the specific means of correction of the training process taking into account the magnitude and direction of the load. Identified ways of solving the problem of optimal evaluation of gaming activities, taking into account the length of stay player on the court and its role. Refine management training process in team sports.

  20. Environmental Aspects of the Engineering Training at Technical University

    Directory of Open Access Journals (Sweden)

    V. V. Bushueva

    2015-01-01

    Full Text Available Problem relevance. The article gives a justification for a need to train professionally competent, ecologically oriented engineers capable to create new equipment taking into account the ecological characteristics. Such approach expresses a requirement coherence to develop technical systems and technologies taking into account, both technical reliability and human and environmental safety. Today, in conditions of modern industrial production it is an important point in engineer’s activity. So to train future engineers who meet these requirements new forms and methods are to be found.Objectives. To prove that involvement of creative student’s teams in training the future ecologically oriented engineers is of importance. The organisational structure and methods of activities along with the principles of revitalizing search for engineering ideas and solutions to develop environmentally safe technical systems and technologies allow us to solve more complicated problems. This is the important characteristic in activities of creative groups. The article considers a significance of the future engineer’s responsibility in terms of environment safety. It gives "Methodical advices to analyse the operational impacts of technical systems on the human and environment" to show that there is a need in development of reliable and environment-safe technical systems.Novelty of this work is a technique for the organization and forms of student creative team’s activities. It represents a revised and updated option of a technique of the creative teams working at the industrial enterprises in France. The revised technique takes into consideration both the specifics of student's audience at technical university and the environment-oriented tasks to be solved. Efficiency of search and solution of environment-oriented engineering tasks is enhanced owing to use of revitalizing methods for the creative team’s activities, which are widely used today in student

  1. TECHNICAL COORDINATION

    CERN Document Server

    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...

  2. 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 ...

  3. 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...

  4. Technical mechanics in constructional reactor safety

    International Nuclear Information System (INIS)

    Matthees, W.

    1979-01-01

    Reactor safety is based on close cooperation between a number of technical and scientific disciplines; most problems of reactor technology can be solved with the aid of technical mechanics. At the 5th International Conference on Structural Mechanics in Reactor Technology (5th SMIRT), one of the biggest conferences in the field of applied technical mechanics, about 800 papers were read giving the latest state of knowledge in the field of constructional reactor safety. The main subject of the conference was the analysis of material behaviour under high loads; the information and methods of these analysis go far beyond what is required in the conventional field. (orig./UA) [de

  5. Psychosocial dimensions of solving an indoor air problem.

    Science.gov (United States)

    Lahtinen, Marjaana; Huuhtanen, Pekka; Kähkönen, Erkki; Reijula, Kari

    2002-03-01

    This investigation focuses on the psychological and social dimensions of managing and solving indoor air problems. The data were collected in nine workplaces by interviews (n = 85) and questionnaires (n = 375). Indoor air problems in office environments have traditionally utilized industrial hygiene or technical expertise. However, indoor air problems at workplaces are often more complex issues to solve. Technical questions are inter-related with the dynamics of the work community, and the cooperation and interaction skills of the parties involved in the solving process are also put to the test. In the present study, the interviewees were very critical of the process of solving the indoor air problem. The responsibility for coordinating the problem-managing process was generally considered vague, as were the roles and functions of the various parties. Communication problems occurred and rumors about the indoor air problem circulated widely. Conflicts were common, complicating the process in several ways. The research focused on examining different ways of managing and resolving an indoor air problem. In addition, reference material on the causal factors of the indoor air problem was also acquired. The study supported the hypothesis that psychosocial factors play a significant role in indoor air problems.

  6. Technical presentation

    CERN Document Server

    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

  7. 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...

  8. Technical presentation

    CERN Document Server

    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...

  9. 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

  10. 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 -...

  11. Customer-centered problem solving.

    Science.gov (United States)

    Samelson, Q B

    1999-11-01

    If there is no single best way to attract new customers and retain current customers, there is surely an easy way to lose them: fail to solve the problems that arise in nearly every buyer-supplier relationship, or solve them in an unsatisfactory manner. Yet, all too frequently, companies do just that. Either we deny that a problem exists, we exert all our efforts to pin the blame elsewhere, or we "Band-Aid" the problem instead of fixing it, almost guaranteeing that we will face it again and again.

  12. Inference rule and problem solving

    Energy Technology Data Exchange (ETDEWEB)

    Goto, S

    1982-04-01

    Intelligent information processing signifies an opportunity of having man's intellectual activity executed on the computer, in which inference, in place of ordinary calculation, is used as the basic operational mechanism for such an information processing. Many inference rules are derived from syllogisms in formal logic. The problem of programming this inference function is referred to as a problem solving. Although logically inference and problem-solving are in close relation, the calculation ability of current computers is on a low level for inferring. For clarifying the relation between inference and computers, nonmonotonic logic has been considered. The paper deals with the above topics. 16 references.

  13. Crew Transportation Technical Standards and Design Evaluation Criteria

    Science.gov (United States)

    Lueders, Kathryn L.; Thomas, Rayelle E. (Compiler)

    2015-01-01

    Crew Transportation Technical Standards and Design Evaluation Criteria contains descriptions of technical, safety, and crew health medical processes and specifications, and the criteria which will be used to evaluate the acceptability of the Commercial Providers' proposed processes and specifications.

  14. Capacity Building Imperatives for Developing Science, Technical ...

    African Journals Online (AJOL)

    ... of white-collar jobs, and lack of productive skills for self-employment among graduates. The educational system at that time could not solve the mounting national problem. This was the major purpose why the National Policy on Education was launched in 1977 with great emphasis on Vocational and Technical education ...

  15. Solving black box computation problems using expert knowledge theory and methods

    International Nuclear Information System (INIS)

    Booker, Jane M.; McNamara, Laura A.

    2004-01-01

    The challenge problems for the Epistemic Uncertainty Workshop at Sandia National Laboratories provide common ground for comparing different mathematical theories of uncertainty, referred to as General Information Theories (GITs). These problems also present the opportunity to discuss the use of expert knowledge as an important constituent of uncertainty quantification. More specifically, how do the principles and methods of eliciting and analyzing expert knowledge apply to these problems and similar ones encountered in complex technical problem solving and decision making? We will address this question, demonstrating how the elicitation issues and the knowledge that experts provide can be used to assess the uncertainty in outputs that emerge from a black box model or computational code represented by the challenge problems. In our experience, the rich collection of GITs provides an opportunity to capture the experts' knowledge and associated uncertainties consistent with their thinking, problem solving, and problem representation. The elicitation process is rightly treated as part of an overall analytical approach, and the information elicited is not simply a source of data. In this paper, we detail how the elicitation process itself impacts the analyst's ability to represent, aggregate, and propagate uncertainty, as well as how to interpret uncertainties in outputs. While this approach does not advocate a specific GIT, answers under uncertainty do result from the elicitation

  16. New approaches to solving the management problem of long-lived radionuclides

    International Nuclear Information System (INIS)

    Egorov, N.N.; Zakharov, M.A.; Lazarev, L.N.; Lyubtsev, R.I.; Nikiforov, A.S.; Strakhov, M.V.; Filippov, E.A.

    1991-01-01

    During spent fuel reprocessing the most dangerous long-lived radionuclides are present both in off-gases on the stage of cutting and dissolution and mainly in highly radioactive raffinates arising from the first extraction cycle. In the last years the investigators of the Soviet Union are more and more led to the conclusion that the more reasonable combination of routine methods for waste management and new technical approaches could contribute to the profound solution of this problem. Estimations and specific development are focused on the followings; partitioning of long-lived radionuclides; improvement of solidification methods; substantiation of possibilities for transmutation of long-lived radionuclides; evaluation of potentialities for disposal of radioactive wastes into outer space. Many sided elaborations are needed for the realization of such concept; the most necessary developments have been already performed in some research programs. International cooperation in this field is likely to approach solving the settled problem. (M.N.)

  17. Working memory dysfunctions predict social problem solving skills in schizophrenia.

    Science.gov (United States)

    Huang, Jia; Tan, Shu-ping; Walsh, Sarah C; Spriggens, Lauren K; Neumann, David L; Shum, David H K; Chan, Raymond C K

    2014-12-15

    The current study aimed to examine the contribution of neurocognition and social cognition to components of social problem solving. Sixty-seven inpatients with schizophrenia and 31 healthy controls were administrated batteries of neurocognitive tests, emotion perception tests, and the Chinese Assessment of Interpersonal Problem Solving Skills (CAIPSS). MANOVAs were conducted to investigate the domains in which patients with schizophrenia showed impairments. Correlations were used to determine which impaired domains were associated with social problem solving, and multiple regression analyses were conducted to compare the relative contribution of neurocognitive and social cognitive functioning to components of social problem solving. Compared with healthy controls, patients with schizophrenia performed significantly worse in sustained attention, working memory, negative emotion, intention identification and all components of the CAIPSS. Specifically, sustained attention, working memory and negative emotion identification were found to correlate with social problem solving and 1-back accuracy significantly predicted the poor performance in social problem solving. Among the dysfunctions in schizophrenia, working memory contributed most to deficits in social problem solving in patients with schizophrenia. This finding provides support for targeting working memory in the development of future social problem solving rehabilitation interventions. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  18. 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.

  19. Optimization and improvement of the technical specifications for Santa Maria de Garona and Cofrentes nuclear power plants; Optimizacion y mejora de las especificaciones tecnicas de funcionamiento para las centrales de Santa Maria de Garona y Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Norte Gomez, M D [Empresarios Agrupados, A.I.E., Madrid (Spain); Alcantud, F [Iberdrola C.N., Cofrentes, (Spain); Hoyo, C del [Nuclenor C.N., Santa Maria de Garona (Spain)

    1993-12-15

    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)

  20. Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    ,; ,; ,

    2012-02-01

    The 2011 World Materials Summit, held on 10/9-12/2011 in Washington DC, provided a forum for top decision makers and energy experts from aropund the world to focus on the materials research needs for the growing energy economy. Organized jointly by the Materials Research Society (MRS), the European MRS (E-MRS), and the Chinese MRS (C-MRS), the goal of the Summit was to explore how the different regions of the world can work together on the critical issue of clean energy, including its relation to environmental sustainability and water. The participants considered the area of materials research as well as advocacy, economics, outreach, and education. Realizing that the concerns are long-term and that young players will ultimately be the ones who are going to need to solve the energy challenges, the chairs of the Summit inaugurated a Student Congress, a program for graduate students and postdoctoral scholars in fields directly related to energy and environmental science, engineering, and/or policy. The top 45 candidates coming from 18 countries were selected on a competititve basis to participate in the Student Congress. The four-day effort culminated in a 2011 Worlds Materials Summit Declaration delineating materials directions related to global access to clean energy and water in a sustainable way.

  1. Threshold Concepts in the Development of Problem-solving Skills

    Directory of Open Access Journals (Sweden)

    Shelly Wismath

    2015-03-01

    Full Text Available Problem-solving skills are often identified as a key component of 21st century education. This study collected data from students enrolled in a university-level Liberal Education science course called Problems and Puzzles, which introduced students to the theory and practice of problem solving via puzzles. Based on classroom observation and other qualitative data collected over three semesters, we have identified three significant changes in student behaviour at specific points in the course. These changes can be posited to reveal three underlying threshold concepts in the evolution and establishment of students’ problem-solving skills.

  2. Human Problem Solving in 2012

    Science.gov (United States)

    Funke, Joachim

    2013-01-01

    This paper presents a bibliography of 263 references related to human problem solving, arranged by subject matter. The references were taken from PsycInfo and Academic Premier data-base. Journal papers, book chapters, and dissertations are included. The topics include human development, education, neuroscience, and research in applied settings. It…

  3. Solved problems in classical electromagnetism

    CERN Document Server

    Franklin, Jerrold

    2018-01-01

    This original Dover publication is the companion to a new edition of the author's Classical Electromagnetism: Second Edition. The latter volume will feature only basic answers; this book will contain some problems from the reissue as well as many other new ones. All feature complete, worked-out solutions and form a valuable source of problem-solving material for students.

  4. Error Patterns in Problem Solving.

    Science.gov (United States)

    Babbitt, Beatrice C.

    Although many common problem-solving errors within the realm of school mathematics have been previously identified, a compilation of such errors is not readily available within learning disabilities textbooks, mathematics education texts, or teacher's manuals for school mathematics texts. Using data on error frequencies drawn from both the Fourth…

  5. Quantitative Reasoning in Problem Solving

    Science.gov (United States)

    Ramful, Ajay; Ho, Siew Yin

    2015-01-01

    In this article, Ajay Ramful and Siew Yin Ho explain the meaning of quantitative reasoning, describing how it is used in the to solve mathematical problems. They also describe a diagrammatic approach to represent relationships among quantities and provide examples of problems and their solutions.

  6. Students' Problem Solving and Justification

    Science.gov (United States)

    Glass, Barbara; Maher, Carolyn A.

    2004-01-01

    This paper reports on methods of students' justifications of their solution to a problem in the area of combinatorics. From the analysis of the problem solving of 150 students in a variety of settings from high-school to graduate study, four major forms of reasoning evolved: (1) Justification by Cases, (2) Inductive Argument, (3) Elimination…

  7. Solving Differential Equations in R: Package deSolve

    Directory of Open Access Journals (Sweden)

    Karline Soetaert

    2010-02-01

    Full Text Available In this paper we present the R package deSolve to solve initial value problems (IVP written as ordinary differential equations (ODE, differential algebraic equations (DAE of index 0 or 1 and partial differential equations (PDE, the latter solved using the method of lines approach. The differential equations can be represented in R code or as compiled code. In the latter case, R is used as a tool to trigger the integration and post-process the results, which facilitates model development and application, whilst the compiled code significantly increases simulation speed. The methods implemented are efficient, robust, and well documented public-domain Fortran routines. They include four integrators from the ODEPACK package (LSODE, LSODES, LSODA, LSODAR, DVODE and DASPK2.0. In addition, a suite of Runge-Kutta integrators and special-purpose solvers to efficiently integrate 1-, 2- and 3-dimensional partial differential equations are available. The routines solve both stiff and non-stiff systems, and include many options, e.g., to deal in an efficient way with the sparsity of the Jacobian matrix, or finding the root of equations. In this article, our objectives are threefold: (1 to demonstrate the potential of using R for dynamic modeling, (2 to highlight typical uses of the different methods implemented and (3 to compare the performance of models specified in R code and in compiled code for a number of test cases. These comparisons demonstrate that, if the use of loops is avoided, R code can efficiently integrate problems comprising several thousands of state variables. Nevertheless, the same problem may be solved from 2 to more than 50 times faster by using compiled code compared to an implementation using only R code. Still, amongst the benefits of R are a more flexible and interactive implementation, better readability of the code, and access to R’s high-level procedures. deSolve is the successor of package odesolve which will be deprecated in

  8. Using a genetic algorithm to solve fluid-flow problems

    International Nuclear Information System (INIS)

    Pryor, R.J.

    1990-01-01

    Genetic algorithms are based on the mechanics of the natural selection and natural genetics processes. These algorithms are finding increasing application to a wide variety of engineering optimization and machine learning problems. In this paper, the authors demonstrate the use of a genetic algorithm to solve fluid flow problems. Specifically, the authors use the algorithm to solve the one-dimensional flow equations for a pipe

  9. Threshold Concepts in the Development of Problem-solving Skills

    OpenAIRE

    Shelly Wismath; Doug Orr; Bruce MacKay

    2015-01-01

    Problem-solving skills are often identified as a key component of 21st century education. This study collected data from students enrolled in a university-level Liberal Education science course called Problems and Puzzles, which introduced students to the theory and practice of problem solving via puzzles. Based on classroom observation and other qualitative data collected over three semesters, we have identified three significant changes in student behaviour at specific points in the course....

  10. Genetics problem solving and worldview

    Science.gov (United States)

    Dale, Esther

    The research goal was to determine whether worldview relates to traditional and real-world genetics problem solving. Traditionally, scientific literacy emphasized content knowledge alone because it was sufficient to solve traditional problems. The contemporary definition of scientific literacy is, "The knowledge and understanding of scientific concepts and processes required for personal decision-making, participation in civic and cultural affairs and economic productivity" (NRC, 1996). An expanded definition of scientific literacy is needed to solve socioscientific issues (SSI), complex social issues with conceptual, procedural, or technological associations with science. Teaching content knowledge alone assumes that students will find the scientific explanation of a phenomenon to be superior to a non-science explanation. Formal science and everyday ways of thinking about science are two different cultures (Palmer, 1999). Students address this rift with cognitive apartheid, the boxing away of science knowledge from other types of knowledge (Jedege & Aikenhead, 1999). By addressing worldview, cognitive apartheid may decrease and scientific literacy may increase. Introductory biology students at the University of Minnesota during fall semester 2005 completed a written questionnaire-including a genetics content-knowledge test, four genetic dilemmas, the Worldview Assessment Instrument (WAI) and some items about demographics and religiosity. Six students responded to the interview protocol. Based on statistical analysis and interview data, this study concluded the following: (1) Worldview, in the form of metaphysics, relates to solving traditional genetic dilemmas. (2) Worldview, in the form of agency, relates to solving traditional genetics problems. (3) Thus, worldview must be addressed in curriculum, instruction, and assessment.

  11. 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...

  12. 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...

  13. Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Jonathan D. Istok

    2008-06-01

    ‘Bioimmobilization’ of redox-sensitive metals and radionuclides is being investigated as a way to remediate contaminated groundwater and sediments. In this approach, growth-limiting substrates are added to stimulate the activity of targeted groups of indigenous microorganisms and create conditions favorable for the microbially-mediated precipitation (‘bioimmobilization’) of targeted contaminants. This project investigated a fundamentally new approach for modeling this process that couples thermodynamic descriptions for microbial growth with associated geochemical reactions. In this approach, a synthetic microbial community is defined as a collection of defined microbial groups; each with a growth equation derived from bioenergetic principles. The growth equations and standard-state free energy yields are appended to a thermodynamic database for geochemical reactions and the combined equations are solved simultaneously to predict the effect of added substrates on microbial biomass, community composition, and system geochemistry. This approach, with a single set of thermodynamic parameters (one for each growth equation), was used to predict the results of laboratory and field bioimmobilization experiments at two geochemically diverse research sites. Predicted effects of ethanol or acetate addition on uranium and technetium solubility, major ion geochemistry, mineralogy, microbial biomass and community composition were in general agreement with experimental observations although the available experimental data precluded rigorous model testing. Model simulations provide insight into the long-standing difficulty in transferring experimental results from the laboratory to the field and from one field site to the next, especially if the form, concentration, or delivery of growth substrate is varied from one experiment to the next. Although originally developed for use in better understanding bioimmobilization of uranium and technetium via reductive precipitation

  14. Republic Scientific-practical Conference 'The Youth Role in solving the most important issues of globalization process' Proceedings

    International Nuclear Information System (INIS)

    2015-01-01

    Present collection comprises of materials of Republic Scientific-practical Conference 'The Youth Role in solving the most important issues of globalization process'. Present collection is intended for scientific and technical staff, postgraduates, and students of institutes of higher education.

  15. Distance Measurement Solves Astrophysical Mysteries

    Science.gov (United States)

    2003-08-01

    distance. "Our measurements showed that the pulsar is about 950 light-years from Earth, essentially the same distance as the supernova remnant," said Steve Thorsett, of the University of California, Santa Cruz. "That means that the two almost certainly were created by the same supernova blast," he added. With that problem solved. the astronomers then turned to studying the pulsar's neutron star itself. Using a variety of data from different telescopes and armed with the new distance measurement, they determined that the neutron star is between 16 and 25 miles in diameter. In such a small size, it packs a mass roughly equal to that of the Sun. The next result of learning the pulsar's actual distance was to provide a possible answer to a longstanding question about cosmic rays. Cosmic rays are subatomic particles or atomic nuclei accelerated to nearly the speed of light. Shock waves in supernova remnants are thought to be responsible for accelerating many of these particles. Scientists can measure the energy of cosmic rays, and had noted an excess of such rays in a specific energy range. Some researchers had suggested that the excess could come from a single supernova remnant about 1000 light-years away whose supernova explosion was about 100,000 years ago. The principal difficulty with this suggestion was that there was no accepted candidate for such a source. "Our measurement now puts PSR B0656+14 and the Monogem Ring at exactly the right place and at exactly the right age to be the source of this excess of cosmic rays," Brisken said. With the ability of the VLBA, one of the telescopes of the NRAO, to make extremely precise position measurements, the astronomers expect to improve the accuracy of their distance determination even more. "This pulsar is becoming a fascinating laboratory for studying astrophysics and nuclear physics," Thorsett said. In addition to Brisken and Thorsett, the team of astronomers includes Aaron Golden of the National University of Ireland, Robert

  16. Technical innovation and management

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Yang Cheol

    1982-08-15

    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. 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.

  18. SHA-1, SAT-solving, and CNF

    CSIR Research Space (South Africa)

    Motara, YM

    2017-09-01

    Full Text Available the intersection between the SHA-1 preimage problem, the encoding of that problem for SAT-solving, and SAT-solving. The results demonstrate that SAT-solving is not yet a viable approach to take to solve the preimage problem, and also indicate that some...

  19. Assessing Algebraic Solving Ability: A Theoretical Framework

    Science.gov (United States)

    Lian, Lim Hooi; Yew, Wun Thiam

    2012-01-01

    Algebraic solving ability had been discussed by many educators and researchers. There exists no definite definition for algebraic solving ability as it can be viewed from different perspectives. In this paper, the nature of algebraic solving ability in terms of algebraic processes that demonstrate the ability in solving algebraic problem is…

  20. Comprehension and computation in Bayesian problem solving

    Directory of Open Access Journals (Sweden)

    Eric D. Johnson

    2015-07-01

    Full Text Available Humans have long been characterized as poor probabilistic reasoners when presented with explicit numerical information. Bayesian word problems provide a well-known example of this, where even highly educated and cognitively skilled individuals fail to adhere to mathematical norms. It is widely agreed that natural frequencies can facilitate Bayesian reasoning relative to normalized formats (e.g. probabilities, percentages, both by clarifying logical set-subset relations and by simplifying numerical calculations. Nevertheless, between-study performance on transparent Bayesian problems varies widely, and generally remains rather unimpressive. We suggest there has been an over-focus on this representational facilitator (i.e. transparent problem structures at the expense of the specific logical and numerical processing requirements and the corresponding individual abilities and skills necessary for providing Bayesian-like output given specific verbal and numerical input. We further suggest that understanding this task-individual pair could benefit from considerations from the literature on mathematical cognition, which emphasizes text comprehension and problem solving, along with contributions of online executive working memory, metacognitive regulation, and relevant stored knowledge and skills. We conclude by offering avenues for future research aimed at identifying the stages in problem solving at which correct versus incorrect reasoners depart, and how individual difference might influence this time point.

  1. 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

  2. TECHNICAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    ADAMS, RICHARD D., PhD.

    2011-04-06

    Cadmium selenide nanoparticles and nanoclusters were prepared and added to polymer solar cells to improve their photon capture ability. These nanoparticles did exhibit some beneficial effects on the photon conversion efficiencies of selected polymer solar cells. Ternary bulk heterojunction systems based on composites of methyl viologen-doped, CdSe nanoparticles blended with poly (3-hexothiopene) (P3HT) and 6, 6-phenyl C{sub 61}-butyric acid methyl ester (PCBM) were also tested. It was found that the devices with methyl viologen-doped CdSe nanoparticles do produce more photocurrent in a region surrounding the absorption peak of the particles (560 to 660nm) when compared to pristine P3HT:PCBM devices. Gold nanorods were also prepared and tested in some solar cells. These nanorods did produce a very small enhancement in photon absorbance, but the observed increase the photon conversion efficiency was not sufficient to make the effort worthwhile. Our goals were (1) to prepare cadmium sulfide and cadmium selenide clusters and nanoparticles to be tested as photon absorbers to enhance the photon conversion efficiency of polymer solar polymer solar cells and (2) to prepare gold and silver nanorods to be added to polymer solar cells to enhance their photon capture capability. The cadmium sulfide and cadmium selenide nanoparticles and some new nanoclusters were prepared. The cadmium selenide nanoparticles were also tested in solar cells and did exhibit some positive effects when they were combined with certain co-absorbing polymers. Due to solubility problems that were not solved in the available time, the new nanoclusters were not tested in solar cells. Ternary bulk heterojunction systems based on composites of methyl viologen doped, CdSe nanoparticles blended with poly (3-hexothiopene) (P3HT) and 6, 6-phenyl C61-butyric acid methyl ester (PCBM) have been examined in detail. The methyl viologen was added to promote charge separation of the initially formed excitons. It was

  3. Methods of solving nonstandard problems

    CERN Document Server

    Grigorieva, Ellina

    2015-01-01

    This book, written by an accomplished female mathematician, is the second to explore nonstandard mathematical problems – those that are not directly solved by standard mathematical methods but instead rely on insight and the synthesis of a variety of mathematical ideas.   It promotes mental activity as well as greater mathematical skills, and is an ideal resource for successful preparation for the mathematics Olympiad. Numerous strategies and techniques are presented that can be used to solve intriguing and challenging problems of the type often found in competitions.  The author uses a friendly, non-intimidating approach to emphasize connections between different fields of mathematics and often proposes several different ways to attack the same problem.  Topics covered include functions and their properties, polynomials, trigonometric and transcendental equations and inequalities, optimization, differential equations, nonlinear systems, and word problems.   Over 360 problems are included with hints, ...

  4. Pillars of peace: The evolution of nuclear technical cooperation

    International Nuclear Information System (INIS)

    Cetto, A.M.

    2003-01-01

    The twentieth century witnessed unprecedented scientific and technological progress, unfortunately paralleled by the development of weapons of mass destruction. And with this progress came an incredible amount of responsibility for scientists and governments. The creation of the IAEA and its technical cooperation programme brought together scientists and governments to use nuclear technology for the 'peaceful pursuits of mankind'. The programme supports application of nuclear techniques to solve socio-economic and human development problems in areas as diverse as agriculture, health, natural resource management, and radiation protection. Fifty years after President Eisenhower's famous 'Atoms for Peace' speech, the IAEA technical cooperation programme provides more than $70 million worth of experts, training, and procurement services each year to approximately 75% of its 137 Member States. But as development budgets shrink, the programme is seeking to make more meaningful use of resources at hand (national capacities, regional resources, development partners and the voluntary Technical Cooperation Fund), targeting specific problems of Member States and partnering with other sustainable development organizations. At the same time, efforts continue to overcome the past legacy that necessitated the 'Atoms for Peace' proposal in the first place. Even as development challenges are addressed, the IAEA, its partners and governments face other challenges along the way, including public opinion for a technology that had a devastating global introduction

  5. Confluent-Functional solving systems

    Directory of Open Access Journals (Sweden)

    V.N. Koval

    2001-08-01

    Full Text Available The paper proposes a statistical knowledge-acquision approach. The solving systems are considered, which are able to find unknown structural dependences between situational and transforming variables on the basis of statistically analyzed input information. Situational variables describe features, states and relations between environment objects. Transforming variables describe transforming influences, exerted by a goal-oriented system onto an environment. Unknown environment rules are simulated by a structural equations system, associating situational and transforming variables.

  6. Understanding catastrophizing from a misdirected problem-solving perspective.

    Science.gov (United States)

    Flink, Ida K; Boersma, Katja; MacDonald, Shane; Linton, Steven J

    2012-05-01

    The aim is to explore pain catastrophizing from a problem-solving perspective. The links between catastrophizing, problem framing, and problem-solving behaviour are examined through two possible models of mediation as inferred by two contemporary and complementary theoretical models, the misdirected problem solving model (Eccleston & Crombez, 2007) and the fear-anxiety-avoidance model (Asmundson, Norton, & Vlaeyen, 2004). In this prospective study, a general population sample (n= 173) with perceived problems with spinal pain filled out questionnaires twice; catastrophizing and problem framing were assessed on the first occasion and health care seeking (as a proxy for medically oriented problem solving) was assessed 7 months later. Two different approaches were used to explore whether the data supported any of the proposed models of mediation. First, multiple regressions were used according to traditional recommendations for mediation analyses. Second, a bootstrapping method (n= 1000 bootstrap resamples) was used to explore the significance of the indirect effects in both possible models of mediation. The results verified the concepts included in the misdirected problem solving model. However, the direction of the relations was more in line with the fear-anxiety-avoidance model. More specifically, the mediation analyses provided support for viewing catastrophizing as a mediator of the relation between biomedical problem framing and medically oriented problem-solving behaviour. These findings provide support for viewing catastrophizing from a problem-solving perspective and imply a need to examine and address problem framing and catastrophizing in back pain patients. ©2011 The British Psychological Society.

  7. Generating and Solving Symbolic Parity Games

    Directory of Open Access Journals (Sweden)

    Gijs Kant

    2014-07-01

    Full Text Available We present a new tool for verification of modal mu-calculus formulae for process specifications, based on symbolic parity games. It enhances an existing method, that first encodes the problem to a Parameterised Boolean Equation System (PBES and then instantiates the PBES to a parity game. We improved the translation from specification to PBES to preserve the structure of the specification in the PBES, we extended LTSmin to instantiate PBESs to symbolic parity games, and implemented the recursive parity game solving algorithm by Zielonka for symbolic parity games. We use Multi-valued Decision Diagrams (MDDs to represent sets and relations, thus enabling the tools to deal with very large systems. The transition relation is partitioned based on the structure of the specification, which allows for efficient manipulation of the MDDs. We performed two case studies on modular specifications, that demonstrate that the new method has better time and memory performance than existing PBES based tools and can be faster (but slightly less memory efficient than the symbolic model checker NuSMV.

  8. Technical note

    International Nuclear Information System (INIS)

    Moshier, W.C.; Tack, W.T.; Phull, B.

    1992-01-01

    Lithium is a potent addition to Al alloys for increasing their specific strength and stiffness, which makes Li-containing Al alloys attractive materials for typical aerospace applications in which reduced weight and increased strength and stiffness can improve system performance. Weldalite 049 (AA X2094) [Al-(4.0-6.3) Cu-1.3 Li-0.4 Ag-0.4 Mg-0.14 Zr] was recently developed as an ultra-high strength, weldable alloy designed for use in launch vehicle structures. Standard SCC testing contains the inherent difficulty of test duration and unclear interpretation of results. Use of slow strain rate tests (SSRTs) on aluminum alloys has met with mixed results, and the purpose of this paper is to evaluate the feasibility of using SSRT to evaluate the SCC susceptibility of two Weldalite 049 variants

  9. Towards a Framework of Using Knowledge Tools for Teaching by Solving Problems in Technology-Enhanced Learning Environment

    Science.gov (United States)

    Kostousov, Sergei; Kudryavtsev, Dmitry

    2017-01-01

    Problem solving is a critical competency for modern world and also an effective way of learning. Education should not only transfer domain-specific knowledge to students, but also prepare them to solve real-life problems--to apply knowledge from one or several domains within specific situation. Problem solving as teaching tool is known for a long…

  10. Problem solving through recreational mathematics

    CERN Document Server

    Averbach, Bonnie

    1999-01-01

    Historically, many of the most important mathematical concepts arose from problems that were recreational in origin. This book takes advantage of that fact, using recreational mathematics - problems, puzzles and games - to teach students how to think critically. Encouraging active participation rather than just observation, the book focuses less on mathematical results than on how these results can be applied to thinking about problems and solving them. Each chapter contains a diverse array of problems in such areas as logic, number and graph theory, two-player games of strategy, solitaire ga

  11. Problem solving and inference mechanisms

    Energy Technology Data Exchange (ETDEWEB)

    Furukawa, K; Nakajima, R; Yonezawa, A; Goto, S; Aoyama, A

    1982-01-01

    The heart of the fifth generation computer will be powerful mechanisms for problem solving and inference. A deduction-oriented language is to be designed, which will form the core of the whole computing system. The language is based on predicate logic with the extended features of structuring facilities, meta structures and relational data base interfaces. Parallel computation mechanisms and specialized hardware architectures are being investigated to make possible efficient realization of the language features. The project includes research into an intelligent programming system, a knowledge representation language and system, and a meta inference system to be built on the core. 30 references.

  12. Back to Basics: Solving Games with SAT

    Directory of Open Access Journals (Sweden)

    QUER, S.

    2016-08-01

    Full Text Available Games became popular, within the formal verification community, after their application to automatic synthesis of circuits from specifications, and they have been receiving more and more attention since then. This paper focuses on coding the "Sokoban" puzzle, i.e., a very complex single-player strategy game. We show how its solution can be encoded and represented as a Bounded Model Checking problem, and then solved with a SAT solver. After that, to cope with very complex instances of the game, we propose two different ad-hoc divide-and-conquer strategies. Those strategies, somehow similar to state-of-the-art abstraction-and-refinement schemes, are able to decompose deep Bounded Model Checking instances into easier subtasks, trading-off between efficiency and completeness. We analyze a vast set of difficult hard-to-solve benchmark games, trying to push forward the applicability of state-of-the-art SAT solvers in the field. Those results show that games may provide one of the next frontier for the SAT community.

  13. Guidance for modeling causes and effects in environmental problem solving

    Science.gov (United States)

    Armour, Carl L.; Williamson, Samuel C.

    1988-01-01

    Environmental problems are difficult to solve because their causes and effects are not easily understood. When attempts are made to analyze causes and effects, the principal challenge is organization of information into a framework that is logical, technically defensible, and easy to understand and communicate. When decisionmakers attempt to solve complex problems before an adequate cause and effect analysis is performed there are serious risks. These risks include: greater reliance on subjective reasoning, lessened chance for scoping an effective problem solving approach, impaired recognition of the need for supplemental information to attain understanding, increased chance for making unsound decisions, and lessened chance for gaining approval and financial support for a program/ Cause and effect relationships can be modeled. This type of modeling has been applied to various environmental problems, including cumulative impact assessment (Dames and Moore 1981; Meehan and Weber 1985; Williamson et al. 1987; Raley et al. 1988) and evaluation of effects of quarrying (Sheate 1986). This guidance for field users was written because of the current interest in documenting cause-effect logic as a part of ecological problem solving. Principal literature sources relating to the modeling approach are: Riggs and Inouye (1975a, b), Erickson (1981), and United States Office of Personnel Management (1986).

  14. The Strength of the Strongest Ties in Collaborative Problem Solving

    DEFF Research Database (Denmark)

    de Montjoye, Yves-Alexandre; Stopczynski, Arkadiusz; Shmueli, Erez

    2014-01-01

    Complex problem solving in science, engineering, and business has become a highly collaborative endeavor. Teams of scientists or engineers collaborate on projects using their social networks to gather new ideas and feedback. Here we bridge the literature on team performance and information networks...... by studying teams' problem solving abilities as a function of both their within-team networks and their members' extended networks. We show that, while an assigned team's performance is strongly correlated with its networks of expressive and instrumental ties, only the strongest ties in both networks have...... an effect on performance. Both networks of strong ties explain more of the variance than other factors, such as measured or self-evaluated technical competencies, or the personalities of the team members. In fact, the inclusion of the network of strong ties renders these factors non...

  15. Solving the geologic issues in nuclear waste disposal

    International Nuclear Information System (INIS)

    Towse, D.

    1979-01-01

    Technical problems with nuclear waste disposal are largely geological. If these are not solved, curtailment of nuclear power development may follow, resulting in loss of an important element in the national energy supply. Present knowledge and credible advances are capable of solving these problems provided a systems view is preserved and a national development plan is followed. This requires identification of the critical controllable elements and a systematic underground test program to prove those critical elements. Waste migration can be understood and controlled by considering the key elements in the system: the system geometry, the hydrology, and the waste-rock-water chemistry. The waste program should: (1) identify and attack the critical problems first; (2) provide tests and demonstration at real disposal sites; and (3) schedule elements with long lead-times for early start and timely completion

  16. 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

    Industry has a great need for highly skilled technicians that graduate from Technical Vocational Education and Training (TVET). In a study started at Aalborg University (AAU) the purpose is to evaluate the effectiveness of the (PBL) approach on students’ skills, in particular on programming course...... 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...

  17. Solving fault diagnosis problems linear synthesis techniques

    CERN Document Server

    Varga, Andreas

    2017-01-01

    This book addresses fault detection and isolation topics from a computational perspective. Unlike most existing literature, it bridges the gap between the existing well-developed theoretical results and the realm of reliable computational synthesis procedures. The model-based approach to fault detection and diagnosis has been the subject of ongoing research for the past few decades. While the theoretical aspects of fault diagnosis on the basis of linear models are well understood, most of the computational methods proposed for the synthesis of fault detection and isolation filters are not satisfactory from a numerical standpoint. Several features make this book unique in the fault detection literature: Solution of standard synthesis problems in the most general setting, for both continuous- and discrete-time systems, regardless of whether they are proper or not; consequently, the proposed synthesis procedures can solve a specific problem whenever a solution exists Emphasis on the best numerical algorithms to ...

  18. Solving rational expectations models using Excel

    DEFF Research Database (Denmark)

    Strulik, Holger

    2004-01-01

    Problems of discrete time optimal control can be solved using backward iteration and Microsoft Excel. The author explains the method in general and shows how the basic models of neoclassical growth and real business cycles are solved......Problems of discrete time optimal control can be solved using backward iteration and Microsoft Excel. The author explains the method in general and shows how the basic models of neoclassical growth and real business cycles are solved...

  19. 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.

  20. CONTRIBUTING FACTORS TOWARDS DIFFICULTIES IN GENERATING IDEAS AMONG TECHNICAL STUDENTS

    OpenAIRE

    Yee Mei Heong

    2013-01-01

    Idea is a thought or collection of thoughts that are important to decision making and problem solving.  The purpose of this research was to analysis the factors contributing to difficulty in generating ideas among technical students.  A total of 375 technical students from four technical universities in Malaysia were randomly selected as samples.  A set of questionnaires was developed and used as research instrument.  The findings indicated that a total of 319 (85.1%) technical students faced...

  1. LEGO Robotics: An Authentic Problem Solving Tool?

    Science.gov (United States)

    Castledine, Alanah-Rei; Chalmers, Chris

    2011-01-01

    With the current curriculum focus on correlating classroom problem solving lessons to real-world contexts, are LEGO robotics an effective problem solving tool? This present study was designed to investigate this question and to ascertain what problem solving strategies primary students engaged with when working with LEGO robotics and whether the…

  2. Perspectives on Problem Solving and Instruction

    Science.gov (United States)

    van Merrienboer, Jeroen J. G.

    2013-01-01

    Most educators claim that problem solving is important, but they take very different perspective on it and there is little agreement on how it should be taught. This article aims to sort out the different perspectives and discusses problem solving as a goal, a method, and a skill. As a goal, problem solving should not be limited to well-structured…

  3. Scaffolding for solving problem in static fluid: A case study

    Science.gov (United States)

    Koes-H, Supriyono; Muhardjito, Wijaya, Charisma P.

    2018-01-01

    Problem solving is one of the basic abilities that should be developed from learning physics. However, students still face difficulties in the process of non-routine problem-solving. Efforts are necessary to be taken in order to identify such difficulties and the solutions to solve them. An effort in the form of a diagnosis of students' performance in problem solving can be taken to identify their difficulties, and various instructional scaffolding supports can be utilized to eliminate the difficulties. This case study aimed to describe the students' difficulties in solving static fluid problems and the effort to overcome such difficulties through different scaffolding supports. The research subjects consisted of four 10-grade students of (Public Senior High School) SMAN 4 Malang selected by purposive sampling technique. The data of students' difficulties were collected via think-aloud protocol implemented on students' performance in solving non-routine static fluid problems. Subsequently, combined scaffolding supports were given to the students based on their particular difficulties. The research findings pointed out that there were several conceptual difficulties discovered from the students when solving static fluid problems, i.e. the use of buoyancy force formula, determination of all forces acting on a plane in a fluid, the resultant force on a plane in a fluid, and determination of a plane depth in a fluid. An effort that can be taken to overcome such conceptual difficulties is providing a combination of some appropriate scaffolding supports, namely question prompts with specific domains, simulation, and parallel modeling. The combination can solve students' lack of knowledge and improve their conceptual understanding, as well as help them to find solutions by linking the problems with their prior knowledge. According to the findings, teachers are suggested to diagnose the students' difficulties so that they can provide an appropriate combination of

  4. Situated, Embodied and Social Problem-Solving in Virtual Worlds

    Science.gov (United States)

    Cram, Andrew; Hedberg, John G.; Gosper, Maree; Dick, Geoff

    2011-01-01

    Contemporary theories of problem-solving highlight that expertise is domain specific, contingent on the social context and available resources, and involves knowledge, skills, attitudes, emotions and values. Developing educational activities that incorporate all of these elements is a challenge. Through case studies, this paper outlines how…

  5. Cognitive load and the acquisition of a problem solving skill

    NARCIS (Netherlands)

    Hoe, van R.R.G.; Brouwer-Janse, M.D.; Harrington, T.L.

    1994-01-01

    Current theories of leaming consider the restructuring of the components of a weak problem solving sequence into a domain-specific procedure to be the fundamental leaming mechanism in complex knowledge domains. Within the context of cognitive load theory, there is growing evidence that applying weak

  6. Restricted dynamic programming: a flexible framework for solving realistic VRPs

    NARCIS (Netherlands)

    Gromicho, J.; van Hoorn, J.J.; Kok, A.L.; Schutten, Johannes M.J.

    2009-01-01

    Most solution methods for solving large vehicle routing and schedu- ling problems are based on local search. A drawback of these ap- proaches is that they are designed and optimized for specific types of vehicle routing problems (VRPs). As a consequence, it is hard to adapt these solution methods to

  7. Gender Differences in the Measurement of Creative Problem-Solving

    Science.gov (United States)

    Hardy, Jay H., III; Gibson, Carter

    2017-01-01

    Despite significant scholarly attention, the literature on the existence and direction of gender differences in creativity has produced inconsistent findings. In the present paper, we argue that this lack of consensus may be attributable, at least in part, to gender-specific inconsistencies in the measurement of creative problem-solving. To…

  8. Students applying their knowledge of material science in problem-solving: implications for competence based-learning at the University of Zimbabwe

    Directory of Open Access Journals (Sweden)

    Peter Kwaira

    2017-05-01

    Full Text Available This study involved a class of serving teachers in their second year of a Bachelor of Education degree programme, in which one of the pre-requisite courses covered during first year was ‘Principles of Material Science (PMS. At the time of study, they were studying ‘Machine-shop Practice’ (MsP; a course based on the Design and Technology (D&T approach, in terms of teaching and learning. They were required to solve practical-technical problems through hands-on practical activities, supported by relevant ancillary theory. In practice, during such activities, students are expected to demonstrate the ability to apply their knowledge of Material Science (MS in various ways; for example, in the choice of materials for given projects aimed at solving specific problems and in the methods of working such materials. Now given this background, the problem was therefore to determine the extent to which students applied their knowledge of MS in solving selected problems under MsP. Data were gathered through interviews, discussions, observations and document analysis. Findings showed students being able to apply their knowledge of MS effectively during problem-solving under MsP; thereby, qualifying their learning as having been outcome-based in nature.

  9. 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...

  10. Fabrication of fuel elements interplay between typical SNR Mark Ia specifications and the fuel element fabrication

    International Nuclear Information System (INIS)

    Biermann, W.K.; Heuvel, H.J.; Pilate, S.; Vanderborck, Y.; Pelckmans, E.; Vanhellemont, G.; Roepenack, H.; Stoll, W.

    1987-01-01

    The core and fuel were designed for the SNR-300 first core by Interatom GmbH and Belgonucleaire. The fuel was fabricated by Alkem/RBU and Belgonucleaire. Based on the preparation of drawings and specifications and on the results of the prerun fabrication, an extensive interplay took place between design requirements, specifications, and fabrication processes at both fuel plants. During start-up of pellet and pin fabrication, this solved such technical questions as /sup 239/Pu equivalent linear weight, pellet density, stoichiometry of the pellets, and impurity content. Close cooperation of designers and manufacturers has allowed manufacture of 205 fuel assemblies without major problems

  11. Problem-Based Learning: Student Engagement, Learning and Contextualized Problem-Solving. Occasional Paper

    Science.gov (United States)

    Mossuto, Mark

    2009-01-01

    The adoption of problem-based learning as a teaching method in the advertising and public relations programs offered by the Business TAFE (Technical and Further Education) School at RMIT University is explored in this paper. The effect of problem-based learning on student engagement, student learning and contextualised problem-solving was…

  12. TECHNICAL TRAINING PROGRAMME

    CERN Multimedia

    Davide Vitè

    2002-01-01

    CLEAN-2002: Working in a Cleanroom A new, free of charge, half-day seminar is offered in the context of Technical Training for the LHC, for personnel working or managing activities in a 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 problems put forward beforehand by attendees will also be addressed, if possible. More information and registration is available HERE The next session, in English, will be on 24.4 (afternoon). Other sessions, in French and English, will be offered following demand. Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch

  13. ITER technical basis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    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.

  14. 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

  15. 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

  16. FORMATION OF RESEARCH COMPETENCE IN TECHNICAL COLLEGE POSTGRADUATES

    Directory of Open Access Journals (Sweden)

    Dmitry Vladimirovich Katchalov

    2015-05-01

    Full Text Available The modern model of professional education is geared to meet the challenges of innovation development of economy and society and is an important element in the training of specialists who are ready to the transformation of the world and reality.Until recently, the goals of higher education formulated by studying a set of knowledge and skills. But today’s situation is that now the order of the society is fixed on reclaiming the gra-duates who are ready to actively participate in the production process, showing the ability to solve practical problems that they faced with.In order to solve the existing contradictions between society’s need for qualified professionals and the existing system of training modern higher professional education is focused on achieving the goal of quality of education, the result of which is the formation of a strong knowledge and skills, the ability to operate in a rapidly changing environment, readiness to implement continuing education. This leads to the fact that amplifies an urgent need in the formation at university students general and professional competencies.Despite the large number of studies devoted to the problems of formation of general and professional competences, the question of determining the specificity of the content, conditions, ways and means of forming research competence of postgraduates remains open. There is a need for scientific substantiation and development of pedagogical bases of formation of research competence in technical college postgraduates.

  17. Students’ difficulties in probabilistic problem-solving

    Science.gov (United States)

    Arum, D. P.; Kusmayadi, T. A.; Pramudya, I.

    2018-03-01

    There are many errors can be identified when students solving mathematics problems, particularly in solving the probabilistic problem. This present study aims to investigate students’ difficulties in solving the probabilistic problem. It focuses on analyzing and describing students errors during solving the problem. This research used the qualitative method with case study strategy. The subjects in this research involve ten students of 9th grade that were selected by purposive sampling. Data in this research involve students’ probabilistic problem-solving result and recorded interview regarding students’ difficulties in solving the problem. Those data were analyzed descriptively using Miles and Huberman steps. The results show that students have difficulties in solving the probabilistic problem and can be divided into three categories. First difficulties relate to students’ difficulties in understanding the probabilistic problem. Second, students’ difficulties in choosing and using appropriate strategies for solving the problem. Third, students’ difficulties with the computational process in solving the problem. Based on the result seems that students still have difficulties in solving the probabilistic problem. It means that students have not able to use their knowledge and ability for responding probabilistic problem yet. Therefore, it is important for mathematics teachers to plan probabilistic learning which could optimize students probabilistic thinking ability.

  18. IDEAL Problem Solving dalam Pembelajaran Matematika

    Directory of Open Access Journals (Sweden)

    Eny Susiana

    2012-01-01

    Full Text Available Most educators agree that problem solving is among the most meaningful and importantkinds of learning and thingking. That is, the central focus of learning and instructionshould be learning to solve problems. There are several warrants supporting that claims.They are authenticity, relevance, problem solving engages deeper learning angtherefore enhances meaning making, and constructed to represent problems (problemsolving is more meaningful. It is the reason why we must provide teaching and learningto make student’s problem solving skill in progress. There are many informationprocessingmodels of problem solving, such as simplified model of the problem-solvingprocess by Gicks, Polya’s problem solving process etc. One of them is IDEAL problemsolving. Each letter of IDEAL is stand for an aspect of thinking that is important forproblem solving. IDEAL is identify problem, Define Goal, Explore possible strategies,Anticipate outcme and Act, and Look back and learn. Using peer interaction andquestion prompt in small group in IDEAL problem solving teaching and Learning canimprove problem solving skill.Kata kunci: IDEAL Problem Solving, Interaksi Sebaya, Pertanyaan Penuntun, KelompokKecil.

  19. Analytical derivation: An epistemic game for solving mathematically based physics problems

    Science.gov (United States)

    Bajracharya, Rabindra R.; Thompson, John R.

    2016-06-01

    Problem solving, which often involves multiple steps, is an integral part of physics learning and teaching. Using the perspective of the epistemic game, we documented a specific game that is commonly pursued by students while solving mathematically based physics problems: the analytical derivation game. This game involves deriving an equation through symbolic manipulations and routine mathematical operations, usually without any physical interpretation of the processes. This game often creates cognitive obstacles in students, preventing them from using alternative resources or better approaches during problem solving. We conducted hour-long, semi-structured, individual interviews with fourteen introductory physics students. Students were asked to solve four "pseudophysics" problems containing algebraic and graphical representations. The problems required the application of the fundamental theorem of calculus (FTC), which is one of the most frequently used mathematical concepts in physics problem solving. We show that the analytical derivation game is necessary, but not sufficient, to solve mathematically based physics problems, specifically those involving graphical representations.

  20. 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.