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Sample records for plant works technical

  1. Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

  2. Savannah River Plant, Works Technical Department monthly progress report for March 1956

    International Nuclear Information System (INIS)

    1956-01-01

    This document details activities of the Works Technical Department during the month of March 1956. It covers reactor technology, separations technology, engineering assistance and heavy water technology

  3. Savannah River Plant Works Technical Department monthly progress report for May 1958: Deleted Version

    Energy Technology Data Exchange (ETDEWEB)

    1958-06-17

    This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory Work. (JT)

  4. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1998-01-01

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force

  5. Diagnostic systems in nuclear power plants. Proceedings of a technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    Nuclear power industry has a quite long tradition in on-line diagnostic of mechanical components and a considerable effort was put in developing diagnostic systems which are able to detect arising mechanical problems at an early stage. Computers are increasingly exploited to provide higher level information on process behaviour such as: early indication of the process deviation from normal conditions; rapid identification of the cause of any disturbance; prediction of the evolution of a disturbance; operator aid through computerized help. Following the recommendation of Several Member States to strengthen the activity in this field two divisions of IAEA established in 1995 the International Task Force on Nuclear Power Plant Diagnostics. The scope of the task force cover both technological developments and safety/licensing aspects of diagnostics. This report contains papers presented at the last in the series of Technical Committee Meetings on the Diagnostic Systems in Nuclear Power Plants organized in the framework of International Task Force Refs, figs, tabs

  6. Determination of technical and economic parameters of an ionic transport membrane air separation unit working in a supercritical power plant

    Directory of Open Access Journals (Sweden)

    Kotowicz Janusz

    2016-09-01

    Full Text Available In this paper an air separation unit was analyzed. The unit consisted of: an ionic transport membrane contained in a four-end type module, an air compressor, an expander fed by gas that remains after oxygen separation and heat exchangers which heat the air and recirculated flue gas to the membrane operating temperature (850 °C. The air separation unit works in a power plant with electrical power equal to 600 MW. This power plant additionally consists of: an oxy-type pulverized-fuel boiler, a steam turbine unit and a carbon dioxide capture unit. Life steam parameters are 30 MPa/650 °C and reheated steam parameters are 6 MPa/670 °C. The listed units were analyzed. For constant electrical power of the power plant technical parameters of the air separation unit for two oxygen recovery rate (65% and 95% were determined. One of such parameters is ionic membrane surface area. In this paper the formulated equation is presented. The remaining technical parameters of the air separation unit are, among others: heat exchange surface area, power of the air compressor, power of the expander and auxiliary power. Using the listed quantities, the economic parameters, such as costs of air separation unit and of individual components were determined. These quantities allowed to determine investment costs of construction of the air separation unit. In addition, they were compared with investment costs for the entire oxy-type power plant.

  7. Technical assessment of compliance with work place air sampling requirements at T Plant. Revision No. 1

    International Nuclear Information System (INIS)

    Hackworth, M.F.

    1995-01-01

    The US DOE requires its contractors to conduct air sampling to detect and evaluate airborne radioactive material in the workplace. Hanford Reservation T Plant compliance with workplace air sampling requirements has been assessed. Requirements, basis for determining compliance and recommendations are included

  8. NWMO transportation technical work program

    International Nuclear Information System (INIS)

    Hatton, C.

    2015-01-01

    This paper describes technical work program for the transportation nuclear waste by the Nuclear Waste Management Organization (NWMO). Transportation work program involves risk assessment which under normal conditions involves dose assessment to the worker and the public as well as consideration of transportation system routing and operations. It also involves possible accident scenarios using forensic modelling and probability analysis.

  9. NWMO transportation technical work program

    Energy Technology Data Exchange (ETDEWEB)

    Hatton, C. [Nuclear Waste Management Organization, Toronto, ON (Canada)

    2015-07-01

    This paper describes technical work program for the transportation nuclear waste by the Nuclear Waste Management Organization (NWMO). Transportation work program involves risk assessment which under normal conditions involves dose assessment to the worker and the public as well as consideration of transportation system routing and operations. It also involves possible accident scenarios using forensic modelling and probability analysis.

  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. 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

  11. 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

  12. 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

  13. [Ageing and work: technical standards].

    Science.gov (United States)

    De Vito, G; Riva, M A; Meroni, R; Cesana, G C

    2010-01-01

    Over the last few years, studies on the relationship between ageing and work have attracted growing interest due to the increased probability among workers of developing major health problems as a consequence of ageing of the working population. Negative outcomes for health are possible when an age-related imbalance appears between physical workload and physical work capacity. Interventions based on workload reductions should help to keep workers on the job for as long as allowed by law. Reference masses by age and sex are suggested by the technical standards of the ISO 11228 series, which are also quoted by Italian law D.Lgs. 81/2008, and EN 1005 series, which recommend limits valid also for manual material handling, and pushing and pulling. Decreasing low back pain prevalence or recurrence, in an ageing population with high prevalence of back disorders, could be more effective than many other approaches to enhance workers' quality of life and consequently maintain and improve workers' performance.

  14. Seismic evaluation of existing nuclear power plants and other facilities V. 1. Proceedings of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of this Tcm are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. Today the nuclear industry relies much more on existing facilities than on the design of new ones. Nevertheless it appears that safety evaluation against external hazards is not a decreasing activity. The reason being that maintaining an acceptable level of nuclear safety requires periodic re-assessments of facilities, either because of modifications of the environment due to human activity or because of new data or new approaches in the assessment of natural hazards. In this regard, seismic re-evaluation has increasingly become a key issue for several existing nuclear facilities, including not only nuclear power plants but also other plants of the fuel cycle, as well as research reactors or laboratories. The IAEA has already supported development of engineering practices in this field by managing a Co-ordinated Research Programme, launched in 1992, on a Benchmark Study for the seismic analysis and testing of WWER 1000 type NPPs. It is now proposed to investigate other aspects of this issue. Many of these facilities were built according to older standards which did not take into account seismic hazard. Consequently, the seismic re-evaluation of existing facilities is a real challenge for earthquake engineers. In most of the cases, it is impossible to re-evaluate according to the up to date standards because entering these standards implies that some design rules are met, what is generally not the case for older facilities. In the best cases some rules exist for non nuclear buildings. In order to achieve a consensus on this matter, the IAEA intends to edit a Safety Report on 'Seismic Evaluation of existing NPPs'. The TCM will offer the opportunity to review the draft of

  15. Achievements of the IAEA technical working group on life management of nuclear power plants (TWG-LMNPP) under the chairmanship of Acad. Myrddin Davies

    International Nuclear Information System (INIS)

    Kang, K.-S.; Tipping, Philip

    2004-01-01

    This meeting, organised by CRISM-PROMETEY in St Petersburg, Russia, is held to honour the memory of Academician Myrddin Davies, who passed away due to a tragic road accident on 11 March 2003 in Stretton, England. Academician Myrddin Davies started technical collaboration with the IAEA in the early 1980s, and in 1985 became chairman of the International Working Group on Reliability of Reactor Pressure Components (IWG-RRPC). Under his chairmanship this grew to become the Technical Working Group on Life Management of Nuclear Power Plants (TWG-LMNPP) covering broader issues and with world wide collaboration. An insight to the creation, working methods and achievements of the TWG-LMNPP is given in this paper. Acad. Myrddin Davies was a competent chairman at many specialist meetings, major conferences hosted by IAEA, other European organizations and Nuclear Engineering International activities. The direction given to the TWG-LMNPP by Acad. Myrddin Davies is shown to have made a significant contribution to the safe use of nuclear energy. Major contributions to nuclear technology of the TWG-LMNPP, during the Chairmanship of Myrddin Davies, are thus cited

  16. Seismic evaluation of existing nuclear power plants and other facilities V. 2. Proceedings of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of this TCM are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. This volume includes presentations of the member states describing the practical approach to evaluation of seismic equipment of the existing NPPs, validation of innovative systems for earthquake protection; seismic re-evaluation of the NPPs, seismic regulations and safety standards; and other activities related to seismic safety in Member States

  17. Seismic evaluation of existing nuclear power plants and other facilities V. 2. Proceedings of the technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-01-01

    The objectives of this TCM are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. This volume includes presentations of the member states describing the practical approach to evaluation of seismic equipment of the existing NPPs, validation of innovative systems for earthquake protection; seismic re-evaluation of the NPPs, seismic regulations and safety standards; and other activities related to seismic safety in Member States.

  18. Works Technical Department progress report, March 1961

    Energy Technology Data Exchange (ETDEWEB)

    None

    1961-04-19

    This document details the activities of the Savannah River Works Technical Department during the month of March 1961. Topics discussed are: Reactor Technology, Separations Technology, Engineering Assistance, Health Physics, Laboratories Overview, and Technical Papers Issued.

  19. Data base on operator support systems (OSSDB) in nuclear power plants: Status evaluation. Technical report. Working material

    International Nuclear Information System (INIS)

    1996-01-01

    In 1991 the IAEA Committee for Contractual Scientific Services approved the Co-ordinated Research Programme on Operator Support Systems in Nuclear Power Plants in the framework of the Project ''Man-Machine Interface Studies''. The major goal of the co-ordinated research programmes was to supply guidance and technology transfer in the development and implementation of computerized support systems. Several sub-gals were identified to accomplish the first steps necessary to achieve this overall goal. Among others, creation of a databased containing the most pertinent characteristics of the OSSs operating in NPPs was recommended. The database is assumed to be of use to several groups of organizations. It therefore contains a large set of data on each specific OSS record. In this report an attempt was made to analyse the available data from the point of view of different user groups in order to guide the use as directly as possible into a practical use of the database. It is assumed that the reader on beforehand has made himself familiar with the main features of the database by reading the Users Guide, which is included in the Appendix 2 of the report. Figs, tabs

  20. Information integration in control rooms and technical offices in nuclear power plants. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2001-11-01

    The majority of the nuclear power plants in the world were designed 25 to 45 years ago. The information, instrumentation, safety, and control systems in these plant designs were based on analog, relay, and primitive digital technology. Computers that were available when most of the nuclear power plants were built were unsophisticated compared with those currently available. These less powerful machines with limited computational capabilities and memory were used to collect and store information. The main means for obtaining information from the plant were analog meters and strip chart recorders. In many cases these pieces of data had to be integrated and correlated with other data manually, in order to be usable. Procedures and plant information resided on paper only and were frequently hard to find and access in a timely manner. This report provides guidance to help with the integration of information in order to enhance the usability and usefulness of the information. It can also be used to help avoid the pitfalls that can occur when implementing new systems with respect to the information they need and produce. This reports philosophy is based on three important issues that allow the convenient structuring of the problem and to keep all of its important features. The first issue is the process of information systems integration and use. This is achieved by long term planning and the creation of the plant infrastructure plan. The second is to take care of the end users' needs in relation to their abilities. This is realized through analyses of user needs. Third is the design of the human-system interface (HSI), for example to distinguish between types of information for use in the plant control room and in technical offices. The development of this report was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is a logical follow-up to IAEA-TECDOC-1016, Modernization of Instrumentation and Control

  1. Management of life cycle and ageing at nuclear power plants: Improved I and C maintenance. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2004-08-01

    The topic of this TECDOC was originally suggested in the May 2001 meeting of the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG NPPCI). It was then approved by the IAEA for work to begin in 2002. It originated from the remarks of the TWG members that it is now time to address the instrumentation and control (I and C) ageing issues in terms of plant life management and licence renewal. Furthermore, the nuclear industry is believed to be able to survive only if plant economy is favourable in addition to plant safety. Therefore, in dealing with I and C ageing and obsolescence, one has to consider how to proceed in addressing this question, not only from a plant operational and safety standpoint, but also in the context of plant economy in terms of the cost of electricity production, and including initial and recurring capital costs. For this important reason, consideration of new technologies, such as on-line monitoring and in situ testing methods is recommended. These can be used not only to predict the consequences of ageing, and guard against it, but also to verify equipment performance throughout the lifetime of the plant, and help establish replacement schedules for I and C equipment, and predict residual life. The basic ageing and obsolescence management process involves: Understanding the ageing and obsolescence phenomena and identifying the (potential) effects on I and C; Addressing the specific impact of these effects on the plant taking into account operational profiles and analyzing the risks; Carrying out necessary mitigating actions to counteract the effects of ageing and obsolescence. Based on the above listed activities the ageing and obsolescence management programme needs to be an iterative process. The goal of this TECDOC is to provide the latest information on ageing, obsolescence, and performance monitoring of those I and C equipment that are classified as safety equipment and/or safety-related equipment, are

  2. Working conditions in nuclear reprocessing plants

    International Nuclear Information System (INIS)

    1986-12-01

    In the context of the project, the working conditions of workers in reprocessing plants and associated plant of the fuel circuit were thoroughly examined. The project design and course of the project are a good example of a precautionary technical assessment necessary for social policy reasons, which is in the public interest and is required by the Trade Unions. By working conditions, one means the whole set of scientific/technical, medical, legal, economic and political conditions for the permanent employment of workers in reprocessing plants including the associated parts of the fuel circuit. (orig./HP) [de

  3. 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

  4. Hanford Engineer Works technical manual

    Energy Technology Data Exchange (ETDEWEB)

    1944-05-01

    The uranium metal, as discharged from the piles in the 100 Areas, contains the alpha emitting product, plutonium, in concentration in the neighborhood of 150--250 grams per metric ton, along with similar amounts of beta and gamma fission elements. It is the purpose of the Separations Plant to effect the separation of this product from the uranium metal and fission elements, and to prepare a concentrated, relatively pure solution of plutonium nitrate as the final product of the Hanford Plant. This section of the manual discusses the chemistry of the separations process, describes the buildings and equipment provided for carrying out the various steps in the operation, and presents the detailed operating procedures used. There are included, in many instances, references to other documents presenting a more detailed view of a specific point in the process.

  5. 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

  6. Nuclear Power Plant Temelin Technical Support Centre

    International Nuclear Information System (INIS)

    Krizek, K.

    2000-01-01

    The erection of the Technical Support Centre for the Nuclear Power Plant Temelin has been a relatively sophisticated and costly issue. It was by proper use of the existing systems, as e.g. I and C, ISE and other systems, that a robust system has been created that is able to meet any requirements laid on the performance of the Technical Support Centre. The decision of the utility CEZ, a.s. that made it possible to establish the Technical Support Centre at the Nuclear Power Plant Temelin has been a right step which shows the level of safety culture within the utility. (author)

  7. 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

  8. Independent technical review of the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This report documents an Independent Technical Review (ITR) of the facilities, organizations, plans, and activities required to transition particular elements of the Mound Plant from Defense Program (DP) funded operation as appropriate either to community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Dr. Willis Bixby, Deputy Assistant Secretary, U.S. Department of Energy EM-60, Office of Facility Transition and Management and is a consensus of the nine member ITR Team. Information for the review was drawn from documents provided to the ITR Team by the Miamisburg Area Office (MB) of the DOE, EG&G, the City of Miamisburg, and others; and from presentations, discussions, interviews, and facility inspections at the Mound Plant during the weeks of March 14 and March 28, 1994. During the week of April 25, 1994, the ITR Team met at Los Alamos, New Mexico to develop consensus recommendations. A presentation of the core recommendations was made at the Mound Plant on May 5, 1994. This is an independent assessment of information available to, and used by, the Mound Plant personnel. Repetition of the information is not meant to imply discovery by the ITR Team. Team members, however, acting as independent reviewers, frequently assess the information from a perspective that differs significantly from that of the Mound Plant personnel. The report is based on information obtained and conditions observed during the March 1994 review interval. The ITR process and normal site work often initiate rapid, beneficial changes in understanding and organization immediately following the review. These changes frequently alter conditions observed during the review, but the report does not address changes subsequent to the review interval.

  9. Discussion on enterprise technical standard management work

    International Nuclear Information System (INIS)

    Li Xinyou

    2010-01-01

    The technical standard management is an important part of enterprise information work, also the basis of enterprise standardization work. Only by rational and orderly management, can it exert maximum effectiveness, provide reliable support for the production and business of enterprise. (author)

  10. INMM Physical Protection Technical Working Group Workshops

    International Nuclear Information System (INIS)

    Williams, J.D.

    1982-01-01

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

  11. Harmonization of the licensing process for digital instrumentation and control systems in nuclear power plants. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2002-12-01

    This report was prepared in response to the recommendation of the Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). This recommendation was based on the recognition of the present diversity in national practices in licensing digital Instrumentation and control (I and C). The goal of this report is to promote harmonization of I and C licensing requirements in the Member States. It applies to I and C modernization, retrofits, upgrades, replacement, new installation, and other aspects of digital I and C in both existing and new nuclear power plants. It should be pointed out that a single publication, like this report, can only take the first step towards initiating a process leading to licensing requirements, which are more harmonized. It is therefore hoped that that this report will get a broad readership among those who can influence requirements that are set on digital I and C. This report provides general and high level recommendations to assist senior officials at utilities, vendor organizations, regulatory bodies, and their support organizations who are involved in the licensing of digital I and C. It is also intended to be read by persons participating in technical committees which are writing standards. The authors of this report believe that harmonization can be achieved through a consideration of the technical and scientific basis of high integrity digital I and C systems. It is also believed that many benefits can be reached in resolving various issues of a technical and engineering nature, which presently are creating controversies in the licensing of digital I and C in NPP safety applications. This publication is based on a consideration of the licensing process of I and C in a top down fashion to discuss generic principles to be applied when assessing digital I and C in NPP safety applications. This report gives an overview of the confidence building process in which evidence is created that digital I and C fulfils

  12. Solutions for cost effective assessment of software based instrumentation and control systems in nuclear power plants. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Implementation

    International Nuclear Information System (INIS)

    2002-12-01

    The introduction of software based instrumentation and control (I and C) systems for use in nuclear power plants, mainly due to I and C modernization activities, has raised many issues of safety and economics. Many of these issues have been raised in the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) meetings and by other organizations, such as the OECD and the European Commission. One increasingly important issue is the need for engineering solutions to justify them for the cost effective assessment and deployment of software based I and C systems. To address this important issue, the IAEA put together the Co-ordinated Research Project (CRP) on Solutions for Cost Effective Assessments of Software based I and C Systems. The overall objective of the project is to facilitate the cost effective assessment of software based I and C systems in nuclear power plants. This is necessary to address obsolescence issues, to introduce new beneficial functionality, and to improve overall performance. The engineering solutions developed in this CRP will contribute to this overall objective. The objective of the CRP was reached through co-ordinated research and collected experience in the areas of project management; requirements specifications; use of software explicitly designed for nuclear applications, use of commercial off the shelf (COTS) products, generic pre-qualification of systems and components; safety and reliability enhancements; verification and validation; and licensing impact. This TECDOC is the result of the research and collected experience put together under this CRP. The CRP participants gave presentations on their work performed as part of this CRP at the various meetings of the group. The first meeting of the CRP was held in Vienna on 8-12 November 1999 in which the participants developed the objectives, scope, and outline of this report. The second meeting was held in Halden, Norway on 4-8 December 2000 and the

  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. Hanford Waste Vitrification Plant technical manual

    Energy Technology Data Exchange (ETDEWEB)

    Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

  17. Hanford Waste Vitrification Plant technical manual

    International Nuclear Information System (INIS)

    Larson, D.E.; Watrous, R.A.; Kruger, O.L.

    1996-03-01

    A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

  18. VGB-requirements regarding technical data for power plants

    International Nuclear Information System (INIS)

    Richnow, Joerg

    2009-01-01

    Much of the technical plant data resulting from the planning, construction and start-up of power plants is needed for subsequent management and maintenance. Because of this, VGB has taken the initiative and has defined standard minimum requirements from power plant operators for technical plant data. They relate to the details and structure of this data, the definition of material classes and characteristics for the main power plant components and IT implementation for delivery of the technical plant data. (orig.)

  19. Independent technical review of the Pinellas Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This report documents an Independent Technical Review (ITR) of facilities, organizations, plans, activities and various other elements required to successfully transition the Pinellas Plant from Defense Program (DP) funded operation to either community developed reuse or safe deactivation leading to decontamination and decommissioning (D&D). The review was conducted at the request of the Department of Energy (DOE) Deputy Assistant Secretary for Facility Transition and Management (EM-60) and is a consensus of the nine member ITR Team.

  20. Technical diagnosis of industrial plants with radioisotopes

    International Nuclear Information System (INIS)

    Hartmann, G.

    1984-01-01

    A survey is given of the application of radioisotopes in technical diagnosis of industrial plants. Proceeding from the economic importance and the state of the art of radioisotope applications, the principles of tracer techniques are outlined including topical examples of application such as passage of coal through a steam generator, wear in impact crashing of coal, wear and corrosion in pipelines, testing the effective cross section of pipes, and investigations of microstructures. Limits and restrictions of applications are briefly discussed

  1. Optimal maintenance work organization and technical education

    International Nuclear Information System (INIS)

    Toshiro Kitamura

    2005-01-01

    Under Japanese multi-layered maintenance routines, almost 100% of work is delegated to outside contractors. For taking such form, there are several reasons unique to Japan. U.S. maintenance work organization makes a contrast, reducing the volume of subcontract in these past ten years. On the other hand, France has a trend of increasing the volume of subcontract for cost reduction that is expected in liberalization and privatization. In Japan, since the subcontract went too far, there is a trend that the multi-layered subcontract structure will be relieved. The Japan Atomic Power, Inc., has organized a team that performs a part of maintenance work by employees themselves since three years before. Direct work is effective to greatly supporting the employees' technical ability. It is expected that the quality of subcontract management will be markedly improved from now on. (author)

  2. Plant Operation: Work Week, Administration

    Science.gov (United States)

    Nation's Schools and Colleges, 1975

    1975-01-01

    A four-day work week for maintenance workers in the Jefferson County Public Schools in Lakewood, Colorado, reduces absenteeism and increases productivity; a basic manual for physical plant directors is reviewed. (Author/MLF)

  3. Nuclear power plant life management processes: Guidelines and practices for heavy water reactors. Report prepared within the framework of the Technical Working Groups on Advanced Technologies for Heavy Water Reactors and on Life Management of Nuclear Power Plants

    International Nuclear Information System (INIS)

    2006-06-01

    The time is right to address nuclear power plant life management and ageing management issues in terms of processes and refurbishments for long term operation and license renewal aspects of heavy water reactors (HWRs) because some HWRs are close to the design life. In general, HWR nuclear power plant (NPP) owners would like to keep their NPPs in service as long as they can be operated safely and economically. This involves the consideration of a number of factors, such as the material condition of the plant, comparison with current safety standards, the socio-political climate and asset management/ business planning considerations. This TECDOC deals with organizational and managerial means to implement effective plan life management (PLiM) into existing plant in operating HWR NPPs. This TECDOC discusses the current trend of PLiM observed in NPPs to date and an overview of PLiM programmes and considerations. This includes key objectives of such programs, regulatory considerations, an overall integrated approach, organizational and technology infrastructure considerations, importance of effective plant data management and finally, human issues related to ageing and finally integration of PLiM with economic planning. Also general approach to HWR PLiM, including the key PLiM processes, life assessment for critical structures and components, conditions assessment of structures and components and obsolescence is mentioned. Technical aspects are described on component specific technology considerations for condition assessment, example of a proactive ageing management programme, and Ontario power generation experiences in appendices. Also country reports from Argentina, Canada, India, the Republic of Korea and Romania are attached in the annex to share practices and experiences to PLiM programme. This TECDOC is primarily addressed to both the management (decision makers) and technical staff (engineers and scientists) of NPP owners/operators and technical support

  4. Clean Energy Works Oregon Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Jacob, Andria [City of Portland; Cyr, Shirley [Clean Energy Works

    2013-12-31

    In April 2010, the City of Portland received a $20 million award from the U.S. Department of Energy, as part of the Energy Efficiency and Conservation Block Grant program. This award was appropriated under the American Recovery and Reinvestment Act (ARRA), passed by President Obama in 2009. DOE’s program became known as the Better Buildings Neighborhood Program (BBNP). The BBNP grant objectives directed the City of Portland Bureau of Planning and Sustainability (BPS) as the primary grantee to expand the BPS-led pilot program, Clean Energy Works Portland, into Clean Energy Works Oregon (CEWO), with the mission to deliver thousands of home energy retrofits, create jobs, save energy and reduce carbon dioxide emissions.The Final Technical Report explores the successes and lessons learned from the first 3 years of program implementation.

  5. Technical Safety Appraisal of the Pinellas Plant

    International Nuclear Information System (INIS)

    1991-01-01

    This report presents the Technical Safety Appraisal (TSA) of the Pinellas Plant in Pinellas County, Florida. The plant is owned and controlled by the US Department of Energy and operated by General Electric Neutron Devices (GEND). The TSA was performed during the period January 15--31, 1989, in support of a Tiger Team Assessment which occurred during the period January 15 to February 2, 1989. The TSA provided the Safety and Health Subteam input to the Tiger Team Assessment. The completion of the assessment process includes: (1) submission of the Team's preliminary findings and concerns, in a Draft Report, to the Manager, Albuquerque Operations Office and to the site contractors at the conclusion of the onsite assessment; (2) review of the Draft Report for technical and factual accuracy; incorporation of the appropriate review comments, suggested changes, and modifications, as well as input from all interested Program Secretarial Offices; preparation of a draft Action Plan by the Albuquerque Operations Office to address the Concerns, and submittal of that Action Plan through the Program Office to ES ampersand H for their review and comment. The Secretary approved the final Action Plan on December 16, 1990, and directed its implementation. The comments and suggestions of the Program Secretarial Offices, the Operations Office, and the site contractor have been incorporated, as appropriate, in this report prior to its publication

  6. Crowdsourcing for Challenging Technical Problems - It Works!

    Science.gov (United States)

    Davis, Jeffrey R.

    2011-01-01

    problems or challenges were posted through three different vendors: InnoCentive, yet2.com and TopCoder. The 20 internal challenges were conducted using the InnoCentive crowdsourcing platform designed for use internal to an organization and customized for NASA use, and promoted as NASA@Work. The results were significant. Of the seven InnoCentive external challenges, two full and five partial awards were made in complex technical areas such as predicting solar flares and long-duration food packaging.

  7. Work in a virtual plant

    International Nuclear Information System (INIS)

    Thibault, G.; Smadja, S.

    1996-01-01

    An EDF graphic simulator is based on a three dimensional image built by an optical radar in an EDF PWR power plant. The resulting virtual plant has improved accuracy thanks to radar millimeter range spatial resolution. These performances allow realistic and reliable training of reactor operators, in particular for work in virtual reality. The simulation gives accurate data on the possibility of introducing a tool in a particular place. EDF work resulted in COMPROMIS computer code which optimizes their maintenance. (D.L.). 7 refs., 6 figs

  8. Decommissioning and back working of Greifswald nuclear power plant

    International Nuclear Information System (INIS)

    Rittscher, D.; Leushacke, D.F.; Meyer, R.

    1998-01-01

    At Nuclear Power Plant Greifswald, the Energiewerke Nord are carrying out the presently world's largest decommissioning project. This requires the gathering up of experience from the operation of the nuclear power plants at Greifswald, the decommissioning of other nuclear power plants, waste management, project management and licensing procedures for the decommissioning of nuclear power plants. That confirmed that the back working of nuclear plants is not a technical problem but a challenge for project management and logistics. It shows that the dismantling and disposal of nuclear plants is an ordinary process in our economic life. (orig.) [de

  9. Reduced waste generation technical work plan

    International Nuclear Information System (INIS)

    1987-05-01

    The United States Department of Energy has established policies for avoiding plutonium losses to the waste streams and minimizing the generation of wastes produced at its nuclear facilities. This policy is evidenced in DOE Order 5820.2, which states ''Technical and administrative controls shall be directed towards reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste.'' To comply with the DOE directive, the Defense Transuranic Waste Program (DTWP) supports and provides funding for specific research and development tasks at the various DOE sites to reduce the generation of waste. This document has been prepared to give an overview of current and past Reduced Waste Generation task activities which are to be based on technical and cost/benefit factors. The document is updated annually, or as needed, to reflect the status of program direction. Reduced Waste Generation (RWG) tasks encompass a wide range of goals which are basically oriented toward (1) avoiding the generation of waste, (2) changing processes or operations to reduce waste, (3) converting TRU waste into LLW by sorting or decontamination, and (4) reducing volumes through operations such as incineration or compaction

  10. Guidelines for the technical evaluation of replacement items in nuclear power plants (NCIG-11)

    International Nuclear Information System (INIS)

    Craig, W.E.; Fakhar, A.A.; Shulman, M.N.

    1989-12-01

    This document presents guidelines and supporting information for the technical evaluation of replacement items in nuclear power plants. These guidelines contain six major sections which provide the practical knowledge and a programmatic approach to determine the technical and quality requirements necessary to generate purchase documents to procure the proper replacement items. The technical evaluation methodology includes the following steps. (1) Identification of the need for a technical evaluation. (2) Component/part functional classification procedures. (3) Performance of a Failure Modes and Effects Analysis. (4) Selection of Critical Characteristics for Design Determination. (5) Performance of a ''Like-For-Like'' or ''Alternate'' item Evaluation. (6) Preparation of the Technical and Quality Requirements Specification. Work on this document was initiated in response to the increased emphasis by the utilities owning nuclear power plants and nuclear industry on procurement of replacement items for use in safety related applications at nuclear power plants. 20 refs., 9 figs., 14 tabs

  11. PETRA - Technical implementation. PETRA working no. 9

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report describes the technical implementation of PETRA. The report is intended for specialist users and refers to the series of reports describing the project. The PETRA system consists of a number of econometric models, representing the national travel demand in Denmark. Application of these models requires the definition of a scenario, a number of runs with the individual models and extensive data transfer between the models and a database containing base data and results. The system contains three basic scenarios to which changes in various assumptions can be applied. It is possible to construct more basic scenarios but this is outside the scope of using the model as it presently stands. The focus of this report is thus on the specification of changes to basic scenario, on running the model - including description of the data flows, and on the possibilities for analysis of the results. (au) EFP-94. 11 refs.

  12. Examining work structure in nuclear power plants

    International Nuclear Information System (INIS)

    Bauman, M.B.; Boulette, M.D.; Van Cott, H.P.

    1985-01-01

    This paper describes the assessment of the work structure of ten nuclear power plants. Work structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Questionnaires given to a cross-section of personnel at the plants were the primary source of data collection. Structured ''critical incident'' interviews were conducted to verify the questionnaire results. The study revealed that a variety of work structure factor problem areas do exist in nuclear power plants. The paper highlights a prioritized set of candidate research themes to be considered in EPRI's Work Structure and Performance Research Program

  13. Technical strategy map to employing nuclear power plant aging management

    International Nuclear Information System (INIS)

    Sekimura, Naoto; Kanno, Masanori

    2008-01-01

    Stated in this report are back ground of technical strategy map for nuclear power plant aging management, result of the first road map, significance of technical strategy map, introduction scenario, technology map, road map, upgrade in every year, three groups of academia, industry and government, plan of technical strategy map, upgrade system, comprehensive introduction scenario, measures of nuclear power plant aging management in Japan and the world, new inspection system, outline of 'technical strategy map 2008', preparation of technical information bases in industry, academia and government, collaboration of them, safety researches of neutron radiation damage, stress corrosion crack, fatigue, piping thinning, insulation degradation, concrete degradation, thermal aging, evaluation technologies of earthquake resistance, preparation of rules and standards, ideal maintenance, and training talent. (S.Y.)

  14. Tele-maintenance 'intelligent' system for technical plants result management

    International Nuclear Information System (INIS)

    Concetti, Massimo; Cuccioletta, Roberto; Fedele, Lorenzo; Mercuri, Giampiero

    2009-01-01

    The management of technical plant for productivity and safety is generally a complex activity, particularly when many plants distributed in the territory are considered (i.e. the more and more frequent case of outsourced plants maintenance by specialized companies), granted quality and cost results are required (i.e. the case of some rather innovative contract solutions) and the technology involved is heterogeneous and innovative (i.e. electro-mechanical plants). In order to efficiently achieve the above aims an 'intelligent' maintenance-management system for the distant monitoring and controlling by a remote control center has been developed. The so-called GrAMS (granted availability management system) system is conceived to give to organizations involved in technical-industrial plants management the possibility to tend to a 'well-known availability' and 'zero-failures' management. In particular, this study deals with the diagnostic aspects and safety level of technical plants (such as elevators, thermo-technical plants, etc.), and with the involvement of ad hoc designed software analysis tools based on neural networks and reliability indicators. Part of the research dealing with the tele-maintenance intelligent system has been financed by the Italian High Institute for Safety (ISPESL) and led to the development of a pre-industrial prototype whose realization and testing is here described

  15. Technical Training: CLEAN-2002: Working in a Cleanroom

    CERN Multimedia

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an "application for training" form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt. TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch CERN Technical Training Programme: Learning for the LHC! CLEAN-2002 is a free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific ...

  16. Report on all ARRA Funded Technical Work

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2013-10-05

    The main focus of this American Recovery and Reinvestment Act of 2009 (ARRA) funded project was to design an energy efficient carbon capture and storage (CCS) process using the Recipients membrane system for H{sub 2} separation and CO{sub 2} capture. In the ARRA-funded project, the Recipient accelerated development and scale-up of ongoing hydrogen membrane technology research and development (R&D). Specifically, this project focused on accelerating the current R&D work scope of the base program-funded project, involving lab scale tests, detail design of a 250 lb/day H{sub 2} process development unit (PDU), and scale-up of membrane tube and coating manufacturing. This project scope included the site selection and a Front End Engineering Design (FEED) study of a nominally 4 to 10 ton-per-day (TPD) Pre-Commercial Module (PCM) hydrogen separation membrane system. Process models and techno-economic analysis were updated to include studies on integration of this technology into an Integrated Gasification Combined Cycle (IGCC) power generation system with CCS.

  17. International Technical Working Group Round Robin Tests

    Energy Technology Data Exchange (ETDEWEB)

    Dudder, Gordon B.; Hanlen, Richard C.; Herbillion, Georges M.

    2003-02-01

    The goal of nuclear forensics is to develop a preferred approach to support illicit trafficking investigations. This approach must be widely understood and accepted as credible. The principal objectives of the Round Robin Tests are to prioritize forensic techniques and methods, evaluate attribution capabilities, and examine the utility of database. The HEU (Highly Enriched Uranium) Round Robin, and previous Plutonium Round Robin, have made tremendous contributions to fulfilling these goals through a collaborative learning experience that resulted from the outstanding efforts of the nine participating internal laboratories. A prioritized list of techniques and methods has been developed based on this exercise. Current work is focused on the extent to which the techniques and methods can be generalized. The HEU Round Robin demonstrated a rather high level of capability to determine the important characteristics of the materials and processes using analytical methods. When this capability is combined with the appropriate knowledge/database, it results in a significant capability to attribute the source of the materials to a specific process or facility. A number of shortfalls were also identified in the current capabilities including procedures for non-nuclear forensics and the lack of a comprehensive network of data/knowledge bases. The results of the Round Robin will be used to develop guidelines or a ''recommended protocol'' to be made available to the interested authorities and countries to use in real cases.

  18. International Technical Working Group Round Robin Tests

    International Nuclear Information System (INIS)

    Dudder, Gordon B.; Hanlen, Richard C.; Herbillion, Georges M.

    2003-01-01

    The goal of nuclear forensics is to develop a preferred approach to support illicit trafficking investigations. This approach must be widely understood and accepted as credible. The principal objectives of the Round Robin Tests are to prioritize forensic techniques and methods, evaluate attribution capabilities, and examine the utility of database. The HEU (Highly Enriched Uranium) Round Robin, and previous Plutonium Round Robin, have made tremendous contributions to fulfilling these goals through a collaborative learning experience that resulted from the outstanding efforts of the nine participating internal laboratories. A prioritized list of techniques and methods has been developed based on this exercise. Current work is focused on the extent to which the techniques and methods can be generalized. The HEU Round Robin demonstrated a rather high level of capability to determine the important characteristics of the materials and processes using analytical methods. When this capability is combined with the appropriate knowledge/database, it results in a significant capability to attribute the source of the materials to a specific process or facility. A number of shortfalls were also identified in the current capabilities including procedures for non-nuclear forensics and the lack of a comprehensive network of data/knowledge bases. The results of the Round Robin will be used to develop guidelines or a ''recommended protocol'' to be made available to the interested authorities and countries to use in real cases

  19. 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

  20. 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

  1. Canadian CANDU plant data systems for technical surveillance and analysis

    International Nuclear Information System (INIS)

    Deverno, M.; Pothier, H.; Xian, C.; Grosbois, J. De; Bosnich, M.

    1996-01-01

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs

  2. Canadian CANDU plant data systems for technical surveillance and analysis

    Energy Technology Data Exchange (ETDEWEB)

    Deverno, M; Pothier, H; Xian, C [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Fredericton, NB (Canada); Grosbois, J De; Bosnich, M [Atomic Energy of Canada Ltd., Control Centre Technology Branch, Chalk River, ON (Canada). Chalk River Labs.

    1997-12-31

    Plant data systems are emerging as a critical plant support system technology. In particular, plant-wide Historical Data Systems (HDS) are pivotal to the successful implementation of technical surveillance and analysis programs supporting plant operations, maintenance, safety, and licensing activities. In partnership with Canadian CANDU utility and design organizations, AECL has conducted a review of current Canadian CANDU HDS approaches with emphasis on understanding the existing functionality and uses of plant historical data systems, their future needs and benefits. The results is a vision of a plant-wide HDS providing seamless access to both near real-time and historical data, user tool-kits for data visualization and analysis, and data management of the large volume of data acquired during the life of a plant. The successful implementation of the HDS vision will lead to higher capability and capacity factors while minimizing Operations, Maintenance, and Administration (OM and A) costs. (author). 5 refs, 3 figs.

  3. Technical Integration of SMART Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Park, P. H.; Noh, P. C. (and others)

    2006-12-15

    Preliminary experimental tests were carried out using the thermal-hydraulic integral test facility, VISTA (Experimental Verification by Integral Simulation of Transients and Accidents), which has been constructed to simulate the SMART-P. The VISTA facility is an integral test facility including the primary and secondary systems as well as safety-related Passive Residual heat removal (PRHR) systems. The integrated SMART desalination plant consists of Multi Effect Distillation Process combined with Thermal-Vapor Compressor(MED-TVC) and coupled with the extracted steam from turbine through the steam transformer. Steam transformer produces the main pressure steam and supplies to the MED-TVC unit. MED-TVC was selected as a desalination process coupled with SMART, since the thermal vapor compression is very effective where the steam is available at high temperature and pressure conditions than required in the evaporator. The standard design of the SMART desalination plant is under development as a part of the SMART project. This report describes design concept of these systems and their requirements.

  4. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  5. Technical Report Cellulosic Based Black Liquor Gasification and Fuels Plant Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Fornetti, Micheal [Escanaba Paper Company, MI (United States); Freeman, Douglas [Escanaba Paper Company, MI (United States)

    2012-10-31

    produce transportation fuels and produce pulp at the same time. This has the added advantage of reducing or eliminating the need for a recovery boiler. The recovery boiler is an extremely expensive unit operation in the Kraft process and is key to the chemical recovery system that makes the Kraft process successful. Going to a gasification process with potentially higher energy efficiency, improve the pulping process and be more efficient with the use of wood. At the same time a renewable fuel product can be made. Cellulosic Based Black Liquor Gasification and Fuels Plant progressed with the design of the mill as Chemrec continued to work on their pilot plant data gathering. The design information helped to guide the pilot plant and vice versa. In the end, the design details showed that the process was technically feasible. However, at the relatively small size of this plant the specific capital cost was very high and could only be considered if the pulp operation needed to replace the recovery boiler. Some of the reasons for the costs being high are attributed to the many constraints that needed to be addressed in the pulping process. Additionally, the Methanol product did not have a vehicle fuel supply chain to enter into. A different product selection could have eliminated this issue. However, with the selected design, the installation at Escanaba Paper Mill was not economically feasible and the project was not pursued further.

  6. Waste Isolation Pilot Plant Technical Assessment Team Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-17

    This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

  7. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    2017-01-01

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum…

  8. Technical and institutional safety features of nuclear power plants in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.)

  9. Technical and regulatory challenges for digital instrumentation and control and control room systems in nuclear plants

    International Nuclear Information System (INIS)

    Torok, R.; Naser, J.; Harris, T.; Keithline, K.

    2006-01-01

    There are several unsettled technical and licensing issues in the areas of instrumentation and control (I and C), human factors, and updated control room designs that need coordinated, proactive industry attention. Some of these issues are already causing protracted regulatory reviews for existing plants, and left untreated, may cause substantial delays and increased costs for new plant combined construction and operating license approvals. Both industry and the NRC will have roles in resolving the key issues and addressing them in future design efforts and regulatory reviews. Where action is needed, the industry will want to minimize costs and risks by defining industry consensus solutions with corresponding technical bases. NEI has formed a working group to coordinate industry efforts and communications with NRC staff. The working group will also help determine priorities and coordinate both new and existing plant resources. EPRI will provide technical input and guidance for the working group. In order to be able to conduct reviews in a timely fashion, the NRC will likely need to enhance and expand staff resources as existing plants are upgraded and new plant reviews become more active. The industry initiative began with a workshop sponsored by EPRI and NEI on March 28-29, 2006, which led to the creation of the NEI working group. The working group has now identified and prioritized important generic issues, established resolution paths and schedules, and identified the roles of various stakeholders including utility companies, EPRI, NEI, vendors and the NRC. Through the course of this initiative I and C issues for both existing and new plants are being addressed. This paper describes the key I and C related technical and regulatory issues and their implications for new and operating plants, and provides a status report on the efforts to resolve them. (authors)

  10. The Paluel power plant workings

    International Nuclear Information System (INIS)

    Weber, Pierre

    1982-01-01

    The Paluel work site is described, the first power station of the new power level, of which the four 1300 MW units will be operating in 1985. As from 1982 Paluel 1 will start is commissioning trials that are to spread out over 12 months [fr

  11. Technical evaluation of bids for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    In continuation of its efforts to provide comprehensive and impartial guidance to Member States facing the need to introduce nuclear power, the International Atomic Energy Agency is issuing this guidebook as part of a series of guidebooks and codes of practice and, in particular, as a necessary supplement to 'Economic Evaluation of Bids for Nuclear Power Plants: A Guidebook', published by the IAEA in 1976 as Technical Reports Series No.175. The present publication is intended for project managers and senior engineers of electric utilities who are concerned with the evaluation of bids for a nuclear power project. It assumes that the reader has a good knowledge of the technical characteristics of nuclear power plants and of nuclear power project implementation. Its purpose is to provide the information necessary to organize, guide and supervise the technical evaluation of bids for a nuclear power project. It goes without saying that the technical staff carrying out the evaluation must have prior technical experience which cannot be provided by a guidebook

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

    International Nuclear Information System (INIS)

    1992-09-01

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

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

    International Nuclear Information System (INIS)

    1992-09-01

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

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

    International Nuclear Information System (INIS)

    1992-09-01

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

  15. 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

  16. 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

  17. Socio-technicality, Human Work Interaction Design (HWID), and Work Engagement

    DEFF Research Database (Denmark)

    Clemmensen, Torkil; Campos, Pedro; Abdelnour-Nocera, José

    the sociotechnical tradition, however, tells us that looking at work engagement only or mainly from a technical design side is the wrong way to go; instead the social and the technical need to be considered on an equal footing. We give the theoretical motivation and background in sociotechnical thinking for our...

  18. Technical aspects of coupling a 6300 m3/day MSF-RO desalination plant to a PHWR nuclear power plant

    International Nuclear Information System (INIS)

    Verma, R.K.

    1998-01-01

    Presently, eight pressurised Heavy Water Reactors (PHWRs) each of 235 MWe capacity are operational in India. Four more units of similar capacity are expected to be commissioned soon. Work on two units each of 500 MWe capacity is also initiated. Extensive engineering development work has also been carried out in India, both on the MSF process and the membrane process. Based on the experience obtained from the presently operating 425 m 3 /d MSF plant and from the R and D work on the RO process, a 6300 m 3 /d MSF-RO plant (4500 m 3 /d MSF and 1800 m 3 /d RO) has been designed and the work for setting up this plant is undertaken. The steam for the heating duty in the brine heater as well as the steam for the evacuation purpose for the MSF plant is proposed to be obtained from the nuclear plant steam cycle. Sea water feed for the MSF plant as well as for the RO plant will be derived from the sea water discharge system of the nuclear power plant. Provision is made for supply of electrical power also from the power plant. The details of the heating steam supply circuit starting from the steam tapping point on the nuclear plant side to the MSF plant brine heater inlet and the arrangement for the return of condensate to the nuclear plant has been described with component requirement and various technical considerations. All the liquid streams and the steam supplied from the nuclear plant to the desalination plant as well as the product water will be monitored to ensure that there is no radioactive contamination. (author)

  19. Working in a virtual power plant

    International Nuclear Information System (INIS)

    Thibault, G.; Smadja, S.

    1999-01-01

    Graphical simulations on computer providing a virtual and reversible experience can now be used for maintenance in nuclear power plants allowing operations to be tested and tools to be optimised. Eventually, operatives will be trained to work in virtual nuclear power plants in complete safety. (authors)

  20. 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

  1. Technical Work Plan for: Fracture and Lithophysal Studies

    Energy Technology Data Exchange (ETDEWEB)

    n

    2006-09-11

    The primary objective of the work scope described in this technical work plan (TWP) is to enhance the descriptions of fracture and lithophysal parameters for the repository host horizon (RHH) over the repository footprint utilizing a predictive model. This work is planned to address U.S. Nuclear Regulatory Commission (NRC) additional information needs (AINs) associated with the Structural Deformation and Seismicity (SDS) Key Technical Issues (KTI) agreement SDS 3.03 (Schlueter 2000 [DIRS 166615]). The results of the planned work are expected to enhance the technical basis and confirm the results of the fracture analyses presented in ''Drift Degradation Analysis'' (BSC 2004 [DIRS 166107], Section 6.1.6). This model is not intended to provide an alternative for the unsaturated zone and saturated zone flow and transport models currently used by the Yucca Mountain Project (YMP). Nor are the outputs of this model intended to address the SDS 3.03 AINs related to the unsaturated zone and saturated zone flow and transport models.

  2. Technical Work Plan for: Fracture and Lithophysal Studies

    International Nuclear Information System (INIS)

    2006-01-01

    The primary objective of the work scope described in this technical work plan (TWP) is to enhance the descriptions of fracture and lithophysal parameters for the repository host horizon (RHH) over the repository footprint utilizing a predictive model. This work is planned to address U.S. Nuclear Regulatory Commission (NRC) additional information needs (AINs) associated with the Structural Deformation and Seismicity (SDS) Key Technical Issues (KTI) agreement SDS 3.03 (Schlueter 2000 [DIRS 166615]). The results of the planned work are expected to enhance the technical basis and confirm the results of the fracture analyses presented in ''Drift Degradation Analysis'' (BSC 2004 [DIRS 166107], Section 6.1.6). This model is not intended to provide an alternative for the unsaturated zone and saturated zone flow and transport models currently used by the Yucca Mountain Project (YMP). Nor are the outputs of this model intended to address the SDS 3.03 AINs related to the unsaturated zone and saturated zone flow and transport models

  3. Floating natural gas processing plants. Technical ideal or feasible technology

    Energy Technology Data Exchange (ETDEWEB)

    Backhaus, H

    1977-04-01

    Realizability of floating natural gas processing plants is decisively influenced by the economy of the system. Illustrated by the example of the natural gas product LPG (liquefied petroleum gas), a model cost calculation is carried out. It is demonstrated that the increase in the price level during the 1973/1974 energy crisis is an important factor for the realiability in terms of economy of such complicated technical systems. Another aspect which the model calculation revealed is that the economy of floating natural gas processing plants and storage systems can only be estimated in connection with other system components.

  4. U Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of an Aggregate Area Management Study of U Plant. It provides a technical baseline of the aggregate area and results from an environmental investigation that was undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC), which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. U Plant refers to the 221-U Process Canyon Building, a chemical separation facility constructed during World War II. It also includes the Uranium Oxide (UO 3 ) Plant constructed at the same time as 221-U as an adjunct to the original plutonium separation process but which, like 221-U, was converted for other missions. Waste sites are associated primarily with U Plant's 1952 through 1958 Uranium Metal Recovery Program mission and the U0 3 Plant's ongoing U0 3 mission. Waste sites include cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, a waste vault, and the lines and encasements that connect them. It also includes the U Pond and its feed ditches and an underground tank farm designed for high-level liquid wastes

  5. Technical concepts of further improvement of nuclear power plant safety

    International Nuclear Information System (INIS)

    Sochor, R.

    1983-01-01

    The following technical concepts are described which secure the integrity of the containment in case of an accident whose scale exceeds the so-called design basis accident: siting nuclear power plants underground which raises construction costs by 20 - 25%; completing the containment with equipment preventing the outflow of molten corium; completing the containment with emergency pressure space for discharging overpressure - this emergency space is filled with gravel which will trap approximately 50% of fission waste. (Ha)

  6. Technical Support Section annual work plan for FY 1998

    Energy Technology Data Exchange (ETDEWEB)

    Adkisson, B.P.; Allison, K.L.; Effler, R.P.; Hess, R.A.; Keeble, T.A.; Odom, S.M.; Smelcer, D.R.

    1997-12-01

    The Technical Support Section (TSS) of the Instrumentation and Controls (I and C) Division of Oak Ridge National Laboratory (ORNL) provides technical services such as fabrication, modification, installation, calibration, operation, repair, and preventive maintenance of instruments and other related equipment. Because the activities and priorities of TSS must be adapted to the technical support needs of ORNL, the TSS Annual Work Plan is derived from, and is driven directly by, current trends in the budgets and activities of each ORNL division for which TSS provides support. Trends that will affect TSS planning during this period are reductions in the staffing levels of some R and D programs because of attrition or budget cuts. TSS does not have an annual budget to cover operating expenses incurred in providing instrument maintenance support to ORNL. Each year, TSS collects information concerning the projected funding levels of programs and facilities it supports. TSS workforce and resource projections are based on the information obtained and are weighted depending on the percentage of support provided to that division or program. Each year, TSS sets the standard hourly charge rate for the following fiscal year. The Long-Range Work Plan is based on estimates of the affects of the long-range priorities and directions of the Laboratory. Proposed new facilities and programs provide additional bases for long-range planning. After identifying long-range initiatives, TSS planning includes future training requirements, reevaluation of qualifications for new hires, and identification of essential test equipment that will be needed for new work.

  7. 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)

  8. 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

  9. 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

  10. International Technical Working Group Cooperation to Counter Illicit Nuclear Trafficking

    International Nuclear Information System (INIS)

    Smith, D K; Niemeyer, S

    2004-01-01

    The Nuclear Smuggling International Technical Working Group (ITWG) is an international body of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective data analysis to interpret the history of seized nuclear materials. This approach has been adopted by many nations as they respond to incidents of illicit nuclear trafficking

  11. Technical Work Plan For: Meteorological Monitoring and Data Analysis

    International Nuclear Information System (INIS)

    C.T. Bastian

    2003-01-01

    The meteorological monitoring and analysis program has three overall objectives. First, the program will acquire qualified meteorological data from monitoring activities in the Environmental Safety and Health (ES and H) network, including appropriate controls on measuring and test equipment. All work will be completed in accordance with U.S. Department of Energy (DOE) Office of Repository Development (ORD) administrative procedures and Bechtel SAIC Co., LLC (BSC) line procedures. The continuously operating monitoring program includes measuring and test equipment calibrations, operational checks, preventive and corrective maintenance, and data collection. Second, the program will process the raw monitoring data collected in the field and submit technically reviewed, traceable data to the Technical Data Management System (TDMS) and the Records Processing Center. Third, reports containing analyses or calculations could be created to provide information to data requesters

  12. Education, training and work experience among nuclear power plant workers

    International Nuclear Information System (INIS)

    Blair, L.M.; Doggette, J.

    1980-01-01

    This paper uses a unique data set to examine the prior work experience, training, and education of skilled and technical workers in United States nuclear power plants. The data were collected in the latter half of 1977 by the International Brotherhood of Electrical Workers (IBEW) in a survey of union locals in nuclear power plants. The survey results provided substantial evidence that workers in United States nuclear power plants have a relatively high level of education, training, and skill development. Analysis of average education by age did not reveal any significant differences in years of schooling between younger and older workers. Very high rates of participation in formal training programmes were reported by all types of workers. The most common type of training programme was held on-site at the power plant and was provided by utility personnel. The majority of workers reported previous work experience related to nuclear power plant activities. Almost one-third of the workers had been directly involved in nuclear energy in a previous job, the majority of these through the United States Navy nuclear programme. However, the newer plants are hiring relatively fewer persons with previous nuclear experience. (author)

  13. Technical Safety Appraisal of the Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Blake P.

    1989-01-01

    This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.

  14. Control of heavy loads at nuclear power plants: Resolution of Generic Technical Activity A-36. Technical report

    International Nuclear Information System (INIS)

    George, H.J.

    1980-07-01

    This report summarizes work performed by the NRC staff in the resolution of Generic Technical Activity A-36, Control of Heavy Loads Near Spent Fuel. Generic Technical Activity A-36 is one of the generic technical subjects designated as unresolved safety issues pursuant to Section 210 of the Energy Reorganization Act of 1974. The report describes the technical studies and evaluations performed by the NRC staff, the staff's guidelines based on these studies, and the staff's plans for implementaton of its technical guidelines

  15. S Plant Aggregate Area Management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document is prepared in support of an Aggregate Area Management Study of S Plant, 200 West Area, at the US Department of Energy's (DOE) Hanford Site near Richland, Washington. It provides a technical baseline of the aggregate area and the results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC). This document is based on review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. This report describes the REDOX facility and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them

  16. Z plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    This document was prepared in support of the development of a Aggregate Area Management Study of Z Plant, 200 West Area, at the US Department of Energy (DOE) Hanford Site near Richland, Washington. It provides a technical description and operational history of the aggregate area and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (WHC) which is currently the Waste Site and Facility Research Office, Natural Resources, Bechtel Hanford, Inc. (BHI). It is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted in support of this report

  17. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Groom, S.H.

    1994-01-01

    The workshop which was intended to present operating experiences from utilities with a wide range of numbers of operating nuclear units. The speaker, S.H. Groom, presented N.B. Power's experience with a single nuclear unit, and intended to: Present the objectives, organization, and scope of work of the central and site Technical Service groups within N.B. Power which support the operation of the Point Lepreau NGS; Define responsibilities of, and interfaces between the on-site and the central technical service staff; Recommend methods for the establishment and maintenance of an efficient technical support group for the operation of any nuclear power plant

  18. Technical knowledge/skill transfer in nuclear power plant manufacturer

    International Nuclear Information System (INIS)

    Arima, Hiroshi; Sagawa, Wataru; Ogawa, Yukio

    2009-01-01

    Due to environmental concerns such as global warming, needs for nuclear power is increasing. However, many expert engineers and technicians are now entering a period of retirement. And due to weak demands of new plant construction for long years, opportunity for technology learning/experience had been lost. Therefore, to secure human resource and to develop their ability are urgent issues for nuclear industries. Hitachi nuclear division continues efforts for technology transfer and human resource training. This paper describes the following two activities. (1) Improvement of common technical basis, and implementation of PDCA cycle, (2) Development of supporting tools to accelerate technology transfer through OJT (On the Job Training). (author)

  19. Technical guidelines for aseismic design of nuclear power plants

    International Nuclear Information System (INIS)

    Park, Y.J.; Hofmayer, C.H.

    1994-06-01

    This document is a translation, in its entirety, of the Japan Electric Association (JEA) publication entitled open-quotes Technical Guidelines for Aseismic Design of Nuclear Power Plants - JEAG 4601-1987.close quotes This guideline describes in detail the aseismic design techniques used in Japan for nuclear power plants. It contains chapters dealing with: (a)the selection of earthquake ground motions for a site, (b) the investigation of foundation and bedrock conditions, (c) the evaluation of ground stability and the effects of ground movement on buried piping and structures, (d) the analysis and design of structures, and (e) the analysis and design of equipment and distribution systems (piping, electrical raceways, instrumentation, tubing and HVAC duct). The guideline also includes appendices which summarize data, information and references related to aseismic design technology

  20. Presentation of the G-24 technical working group on training

    International Nuclear Information System (INIS)

    Haber, S.

    1993-01-01

    The Technical Working Group on Training (TWG-T) was created during the Plenary Session of September 1992 in order to inform the Members on ongoing activities in the Nuclear Training field, define redundancies and gaps of the ''Assistance Programs'', and propose efficient ways to progress. Training was recognized as one major activity through which operational safety can be very effectively and quite quickly improved and therefore the Plenary Session unanimously decided to launch a TWG on the subject. The present report is issued one year after the creation of the TWG. It summarizes the major steps of the activities and presents the relevant results. It also contains copies of documents on training infrastructures and requirements, provided by the recipient countries during the course of the work

  1. International technical working group cooperation to counter illicit nuclear trafficking

    International Nuclear Information System (INIS)

    Smith, D.K.; Niemeyer, S.

    2004-01-01

    The Nuclear Smuggling International Technical Working Group (ITWG) is an international group of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective data analysis to interpret the history of seized nuclear materials. This approach has been adopted by many nations as they respond to incidents of illicit nuclear trafficking. ITWG members include policy and decision makers, law enforcement personnel, and scientists with expertise in, and responsibility for, nuclear forensics. (author)

  2. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

  3. [Carbon isotope fractionation in plants]: Annual technical progress report

    International Nuclear Information System (INIS)

    O'Leary, M.H.

    1988-01-01

    Plants fractionate carbon isotopes during photosynthesis in ways which reflect photosynthetic pathway and environment. The fractionation is product of contributions from diffusion, carboxylation and other factors which can be understood using models which have been developed in our work. The object of our work is to use this fractionation to learn about the factors which control the efficiency of photosynthesis. Unlike previous studies, we do not rely principally on combustion methods, but instead develop more specific methods with substantially higher resolving power. We have recently developed a new short-term method for studying carbon isotope fractionation which promises to provide a level of detail about temperature, species, and light intensity effects on photosynthesis which has not been available until now. We are studying the isotopic compositions of metabolites (particularly aspartic acid) in C 3 plants in order to determine the role of phosphoenolpyruvate carboxylase in C 3 photosynthesis. We are studying the relative roles of diffusion and carboxylation in nocturnal CO 2 fixation in CAM plants. We are studying the use of isotopic content as an index of water-use efficiency in C 3 plants. We are developing new methods for studying carbon metabolism in plants. 3 refs

  4. Technical Work Plan for: Thermodynamic Databases for Chemical Modeling

    International Nuclear Information System (INIS)

    C.F. Jovecolon

    2006-01-01

    The objective of the work scope covered by this Technical Work Plan (TWP) is to correct and improve the Yucca Mountain Project (YMP) thermodynamic databases, to update their documentation, and to ensure reasonable consistency among them. In addition, the work scope will continue to generate database revisions, which are organized and named so as to be transparent to internal and external users and reviewers. Regarding consistency among databases, it is noted that aqueous speciation and mineral solubility data for a given system may differ according to how solubility was determined, and the method used for subsequent retrieval of thermodynamic parameter values from measured data. Of particular concern are the details of the determination of ''infinite dilution'' constants, which involve the use of specific methods for activity coefficient corrections. That is, equilibrium constants developed for a given system for one set of conditions may not be consistent with constants developed for other conditions, depending on the species considered in the chemical reactions and the methods used in the reported studies. Hence, there will be some differences (for example in log K values) between the Pitzer and ''B-dot'' database parameters for the same reactions or species

  5. Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

    International Nuclear Information System (INIS)

    Sturm, A.; Foerster, R.

    1977-01-01

    Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

  6. PUREX Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The PUREX aggregate area is made up of six operable units; 200-PO-1 through 200-PO-6 and consists of liquid and solid waste disposal sites in the vicinity of, and related to, PUREX Plant operations. This report describes PUREX and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  7. Cycling of conventional power plants: Technical limits and actual costs

    International Nuclear Information System (INIS)

    Van den Bergh, Kenneth; Delarue, Erik

    2015-01-01

    Highlights: • Literature reports a wide range of cycling parameters (technical and cost-related). • The impact of different cycling parameters is assessed. • The German 2013 system is studied as a case study. • Even for stringent parameters, the dynamic limit of the portfolio is not reached. • Cycling costs can be reduced with 40% when taken into account in the scheduling. - Abstract: Cycling of conventional generation units is an important source of operational flexibility in the electricity generation system. Cycling is changing the power output of conventional units by means of ramping and switching (starting up and shutting down). In the literature, a wide range of technical and cost-related cycling parameters can be found. Different studies allocate different cycling parameters to similar generation units. This paper assesses the impact of different cycling parameters allocated to a conventional generation portfolio. Both the technical limitations of power plants and all costs related to cycling are considered. The results presented in this paper follow from a unit commitment model, used for a case study based on the German 2013 system. The conventional generation portfolio has to deliver different residual load time series, corresponding to different levels of renewables penetration. The study shows, under the assumptions made, that although the dynamic limits of some units are reached, the limits of the conventional generation portfolio as a whole are not reached, even if stringent dynamic parameters are assigned to the generation portfolio and a highly variable residual load is imposed to the system. The study shows also the importance of including full cycling costs in the unit commitment scheduling. The cycling cost can be reduced by up to 40% when fully taken into account

  8. International technical working group cooperation to counter illicit nuclear trafficking

    International Nuclear Information System (INIS)

    Smith, D.K.

    2004-01-01

    Full text: The Nuclear Smuggling International Technical Working Group (ITWG) is an international group of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective data analysis to interpret the history of seized nuclear materials. This approach has been adopted by many nations as they respond to incidents of illicit nuclear trafficking. ITWG members include policy and decision makers, law enforcement personnel, and scientists with expertise in, and responsibility for, nuclear forensics. It remains an association of active practitioners of nuclear forensics underwritten by funding from sponsoring countries and organizations. While the primary mission of the ITWG continues to be advancing the science and techniques of nuclear forensics and sharing technical and information resources to combat nuclear trafficking, recently the ITWG has focused on improvements to its organization and outreach. Central is the establishment of guidelines for best practices in nuclear forensics, conducting international exercises, promoting research and development, communicating with external organizations, providing a point-of-contact for nuclear forensics assistance, and providing mutual assistance in nuclear forensics investigations. By its very nature nuclear trafficking is a transboundary problem; nuclear materials

  9. Year-end technical stop: train to work safely

    CERN Multimedia

    Rosaria Marraffino

    2016-01-01

    As mentioned in the previous issue of the Bulletin (see here), the accelerators are currently undergoing maintenance as part of the year-end technical stop (YETS). Hundreds of people are working simultaneously on different machines, and many of them need to be trained in order to work safely underground. From a Safety Training point of view, this has resulted in a significant increase in training requests, most of them at the last minute, which are now being handled – but not without difficulties.     In the LHC mock-up, a helium leak is simulated. In this stressful situation, the trainees learn how to put their mask on in less than 40 seconds.   "The most requested course is the Self-Rescue Mask classroom training,” explains Christoph Balle, Safety Training Section Leader. “In this course, people are trained to face the oxygen deficiency hazards that may occur in CERN's underground areas, learning...

  10. FY 1992 work plan and technical progress reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-11-01

    The Desert Research Institute (DRI) is a division of the University of Nevada System devoted to multidisciplinary scientific research. For more than 25 years, DRI has conducted research for the US Department of Energy`s Nevada Field Office (DOE/NV) in support of operations at the Nevada Test Site (NTS). During that time, the research program has grown from an early focus on hydrologic studies to include the areas of geology, archaeology, environmental compliance and monitoring, statistics, database management, public education, and community relations. The range of DRI`s activities has also expanded to include a considerable amount of management and administrative support in addition to scientific investigations. DRI`s work plan for FY 1992 reflects a changing emphasis in DOE/NV activities from nuclear weapons testing to environmental restoration and monitoring. Most of the environmental projects from FY 1991 are continuing, and several new projects have been added to the Environmental Compliance Program. The Office of Technology Development Program, created during FY 1991, also includes a number of environmental projects. This document contains the FY 1992 work plan and quarterly technical progress reports for each DRI project.

  11. B Plant aggregate area management study technical baseline report

    International Nuclear Information System (INIS)

    DeFord, D.H.; Carpenter, R.W.

    1995-05-01

    The B aggregate area is made up of 13 operable units; 200-BP 1 through 200-BP 1 1, 200-IU-6, and 200-SS-1 that consist of liquid and solid waste disposal sites in the vicinity of, and related to, B Plant operations. This report describes B Plant and its waste sites, including cribs, french drains, septic tanks and drain fields, trenches and ditches, ponds, catch tanks, settling tanks, diversion boxes, underground tank farms designed for high-level liquid wastes, and the lines and encasements that connect them. Each waste site in the aggregate area is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. This document provides a technical baseline of the aggregate area and results from an environmental investigation. This document is based upon review and evaluation of numerous Hanford Site current and historical reports, drawings and photographs, supplemented with site inspections and employee interviews. No intrusive field investigations or sampling were conducted

  12. Evaluation of the feasibility, economic impact, and effectiveness of underground nuclear power plants. Final technical report

    International Nuclear Information System (INIS)

    1978-05-01

    Information on underground nuclear power plants is presented concerning underground nuclear power plant concepts; public health impacts; technical feasibility of underground concepts; economic impacts of underground construction; and evaluation of related issues

  13. Nuclear power plant control and instrumentation 1993. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    The regular meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of nuclear power plant control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The meeting was held at the Merlin-Gerin Headquarters in Paris and was attended by twenty one national delegates and observers from 17 countries. The present volume contains: (1) report on the meeting of the IWG-NPPCI, Paris, 21-22 October 1993, (2) report by the scientific secretary on the major activities of IAEA during 1991-1993 in the NPPCI area, and (3) reports of the national representatives to the International Working Group on NPPCI. The papers and discussions with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economic aspects of the introduction of modern control systems and on the improvement of plant availability and safety. Refs, figs and tabs

  14. Nuclear heat generating plants - technical concepts and market potentials. Chapter 11

    International Nuclear Information System (INIS)

    Hasenkopf, O.; Erhard, W.D.; Nonnenmacher, A.; Hanselmann, M.

    1988-01-01

    Within the framework of a case study under the Federal Ministry of Research and Technology project 'Nuclear heat generating plants - technological concepts and market potentials', the possible applications of such plants were studied giving the district heat supply network of the Technische Werke der Stadt Stuttgart AG (Technical Works of the City of Stuttgart, Inc.) as an example. The use of district heating systems concentrated specifically on areas identified for economical supply because of their topographical position, existing heat density, distance from power plants, and a reasonable delimination from the available gas network. Based on the results of optimization calculations made by the Stuttgart Institute for Nuclear Technology and Energy Conversion, the required investment capital can be estimated as a function of the amount of fuel savings under the Stuttgart case study. (orig./UA) [de

  15. An analysis of factors that influence the technical efficiency of Malaysian thermal power plants

    International Nuclear Information System (INIS)

    See, Kok Fong; Coelli, Tim

    2012-01-01

    The main objectives of this paper are to measure the technical efficiency levels of Malaysian thermal power plants and to investigate the degree to which various factors influence efficiency levels in these plants. Stochastic frontier analysis (SFA) methods are applied to plant-level data over an eight year period from 1998 to 2005. This is the first comprehensive analysis (to our knowledge) of technical efficiency in the Malaysian electricity generation industry using parametric method. Our empirical results indicate that ownership, plant size and fuel type have a significant influence on technical efficiency levels. We find that publicly-owned power plants obtain average technical efficiencies of 0.68, which is lower than privately-owned power plants, which achieve average technical efficiencies of 0.88. We also observe that larger power plants with more capacity and gas-fired power plants tend to be more technically efficient than other power plants. Finally, we find that plant age and peaking plant type have no statistically significant influence on the technical efficiencies of Malaysian thermal power plants. - Highlights: ► We examine the technical efficiency (TE) levels of Malaysian thermal power plants. ► We also investigate the degree to which various factors influence efficiency levels in these plants. ► Stochastic frontier analysis methods are used. ► Average plant would have to increase their TE level by 21% to reach the efficient frontier. ► Ownership, plant size and fuel type have a significant influence on the TE levels.

  16. State of work on Main Task 3.1.3 of Complex Programme of Scientific and Technical Progress and precondition for ensuring Czechoslovak automatic control system instrumentation and electrical parts for new-generation power plant project

    International Nuclear Information System (INIS)

    Hrebik, V.

    1990-01-01

    A brief account is given of the state of negotiations with the Soviet partner concerning the preparation, creation and implementation of prospective automated technological equipment control systems at WWER type nuclear power plants. The organization is very clumsy in some fields and their conceptions are not clear. (Z.S.)

  17. Technical basis for the internal dosimetry program at the Y-12 Plant

    International Nuclear Information System (INIS)

    Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

    1992-01-01

    Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

  18. Technical safety appraisal of the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    1992-05-01

    On June 27, 1989, Secretary of Energy, Admiral James D. Watkins, US Navy (Retired), announced a 10-point initiative to strengthen environment, safety, and health (ES ampersand H) programs and waste management operations in the Department of Energy (DOE). One of the initiatives involved conducting independent Tiger Team Assessments (TTA) at DOE operating facilities. A TTA of the Idaho National Engineering Laboratory (INEL) was performed during June and July 1991. Technical Safety Appraisals (TSA) were conducted in conjunction with the TTA as its Safety and Health portion. However, because of operational constraints the the Idaho Chemical Processing Plant (ICPP), operated for the DOE by Westinghouse Idaho Nuclear Company, Inc. (WINCO), was not included in the Safety and Health Subteam assessment at that time. This TSA, conducted April 12 - May 8, 1992, was performed by the DOE Office of Performance Assessment to complete the normal scope of the Safety and Health portion of the Tiger Team Assessment of the Idaho National Engineering Laboratory. The purpose of TSAs is to evaluate and strengthen DOE operations by verifying contractor compliance with DOE Orders, to assure that lessons learned from commercial operations are incorporated into facility operations, and to stimulate and encourage pursuit of excellence; thus, the appraisal addresses more issues than would be addressed in a strictly compliance-oriented appraisal. A total of 139 Performance Objectives have been addressed by this appraisal in 19 subject areas. These 19 areas are: organization and administration, quality verification, operations, maintenance, training and certification, auxiliary systems, emergency preparedness, technical support, packaging and transportation, nuclear criticality safety, safety/security interface, experimental activities, site/facility safety review, radiological protection, worker safety and health compliance, personnel protection, fire protection, medical services and natural

  19. Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

    International Nuclear Information System (INIS)

    1999-09-01

    This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

  20. 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

  1. [Health & safety in a steel plant: technical and managerial action].

    Science.gov (United States)

    Fusato, M

    2012-01-01

    The report presents the experience in a steel company to improve the management of issues relating to health and safety of workers. The first part of the work focuses on the description of the interventions made by the company in recent years, which can be divided into technical interventions on production facilities, training and information, organizational activities and specific projects in collaboration with the health service. The second part presents the certification project according to OHSAS 18001, with particular focus on the efforts for a lean management of the documentation required by the management systems and for the automation of internal processes. The last part finally describes in detail the manner in which it was decided to address some issues that significantly affect the factory doctor: the recording and analysis of accidents and medications, management of hazardous substances and personal protective equipment.

  2. Remote repair and inspection technics in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

    1986-01-01

    Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

  3. Technical basis for staffing levels at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Shurberg, D.A.; Haber, S.B. [Brookhaven National Lab., Upton, NY (United States); Morisseau, D. [Nuclear Regulatory Commission, Washington, DC (United States)] [and others

    1995-04-01

    The objective of this project is to provide a technical basis for the establishment of criteria for minimum staffing levels of licensed and non-licensed NPP shift personnel. Minimum staffing levels for the purpose of this study, are defined as those necessary for successful accomplishment of all safety and additional functions that must be performed in order for the licensee to meet applicable regulatory requirements. This project involves a multi-faceted approach to the investigation of the issue. Relevant NRC documentation was identified and reviewed. Using the information obtained from this documentation review, a test plan was developed to aid in the collection of further information regarding the adequacy of current shift staffing levels. The test plan addresses three different activities to be conducted to provide information to the NRC for use in the assessment of current minimum staffing levels. The first activity is collection of data related to industry shift staffing practices through site visits to seven nuclear power plants. The second activity is a simulator study, which will use licensed operator crews responding to a simulated event, under two different staffing levels. Finally, workload models will be constructed for both licensed and non-licensed personnel, using a priori knowledge of the simulator scenarios with data resulting from one of the staffing levels studied in the simulator, and the data collected from the site visits. The model will then be validated against the data obtained from the second staffing level studied in the simulator. The validated model can then be used to study the impact of changing staffing-related variables on the plant shift crew`s ability to effectively mitigate an event.

  4. [Characteristics of working conditions at metallurgy-related plants].

    Science.gov (United States)

    Egorova, A M

    2008-01-01

    Working conditions at more versus less advanced technology steel plants of the Volgograd Region are analyzed. The working conditions at the less advanced technology plants are referred to as a very high occupational risk. It is necessary to work out measures to lower the poor impact of microclimate, dust, noise, to improve illumination, and to regulate labor at steel plants.

  5. Have U.S. power plants become less technically efficient? The impact of carbon emission regulation

    International Nuclear Information System (INIS)

    Zhou, Yishu; Huang, Ling

    2016-01-01

    We estimate directional distance functions to measure the impact of carbon emission regulation, the Regional Greenhouse Gas Initiative (RGGI) in particular, on U.S. power plants' technical efficiency. The model shows that the average technical efficiency scores for coal and natural gas plants are 88.70% and 83.14% respectively, indicating a very technically efficient industry. We find no evidence of technical efficiency changes due to the RGGI regime in the RGGI area. In the same area, relatively less efficient coal plants exited the market and slightly more efficient natural gas plants entered, compared to the incumbent plants. In addition, some evidence of a spillover effect is found. Using a counterfactual analysis, the RGGI regulation leads to a 1.48% decline in the average technical efficiency for coal plants within neighboring states of RGGI during 2009–2013. - Highlights: • RGGI does not lead to a change in the technical efficiency of RGGI power plants. • Less efficient coal plants exit. • Entering natural gas plants are more efficient. • RGGI has a spillover effect on neighboring coal plants.

  6. 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

  7. 48 CFR 2452.237-73 - Conduct of Work and Technical Guidance.

    Science.gov (United States)

    2010-10-01

    ... conditions of the contract. (c) The GTR will issue technical guidance in writing or, if issued orally, he/she... Technical Guidance. 2452.237-73 Section 2452.237-73 Federal Acquisition Regulations System DEPARTMENT OF... Provisions and Clauses 2452.237-73 Conduct of Work and Technical Guidance. As prescribed in 2437.110(d...

  8. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, John

    2011-07-15

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  9. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    International Nuclear Information System (INIS)

    Saurwein, J.

    2011-01-01

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  10. Annotated bibliography of structural equation modelling: technical work.

    Science.gov (United States)

    Austin, J T; Wolfle, L M

    1991-05-01

    Researchers must be familiar with a variety of source literature to facilitate the informed use of structural equation modelling. Knowledge can be acquired through the study of an expanding literature found in a diverse set of publishing forums. We propose that structural equation modelling publications can be roughly classified into two groups: (a) technical and (b) substantive applications. Technical materials focus on the procedures rather than substantive conclusions derived from applications. The focus of this article is the former category; included are foundational/major contributions, minor contributions, critical and evaluative reviews, integrations, simulations and computer applications, precursor and historical material, and pedagogical textbooks. After a brief introduction, we annotate 294 articles in the technical category dating back to Sewall Wright (1921).

  11. Design and Assessment of an Associate Degree-Level Plant Operations Technical Education Program

    Science.gov (United States)

    Selwitz, Jason Lawrence

    Research was undertaken to develop and evaluate an associate degree-level technical education program in Plant Operations oriented towards training students in applied science, technology, engineering, and mathematics (STEM) skills and knowledge relevant to a spectrum of processing industries. This work focuses on four aspects of the curriculum and course development and evaluation research. First, the context of, and impetus for, what was formerly called vocational education, now referred to as technical or workforce education, is provided. Second, the research that was undertaken to design and evaluate an associate degree-level STEM workforce education program is described. Third, the adaptation of a student self-assessment of learning gains instrument is reviewed, and an analysis of the resulting data using an adapted logic model is provided, to evaluate the extent to which instructional approaches, in two process control/improvement-focused courses, were effective in meeting course-level intended learning outcomes. Finally, eight integrative multiscale exercises were designed from two example process systems, wastewater treatment and fast pyrolysis. The integrative exercises are intended for use as tools to accelerate the formation of an operator-technician's multiscale vision of systems, unit operations, underlying processes, and fundamental reactions relevant to multiple industries. Community and technical colleges serve a vital function in STEM education by training workers for medium- and high-skilled technical careers and providing employers the labor necessary to operate and maintain thriving business ventures. Through development of the curricular, course, and assessment-related instruments and tools, this research helps ensure associate degree-level technical education programs can engage in a continual process of program evaluation and improvement.

  12. New experience on construction and installation work in Qinshan PHWR nuclear power plant

    International Nuclear Information System (INIS)

    Lu Huaxiang

    2004-01-01

    The article provides a summary of the new experience on construction management and construction technology in the field of civil construction and installation work in Qinshan PHWR nuclear power plant, with focus on innovation in project management mode, new technology application and computerized management of construction and installation work. Management innovation, technical innovation and information technology are the key contributors to overall success of Qinshan PHWR nuclear power plant in construction and installation work. The new experience derived in these fields will be of great significance to promote independent construction of the new-round nuclear power projects in China. (author)

  13. Technical Working Group on Career and Technical Education Meeting. Meeting Summary (Washington, DC, September 22, 2017)

    Science.gov (United States)

    Ahn, Judie

    2017-01-01

    On September 22, 2017, the National Center for Special Education Research (NCSER) and the National Center for Education Research (NCER) at the Institute of Education Sciences (IES) convened a group of experts in policy, practice, and research related to Career and Technical Education (CTE). The goal of the meeting was to seek input from…

  14. Catalogue and classification of technical safety rules for light-water reactors and reprocessing plants

    International Nuclear Information System (INIS)

    Bloser, M.; Fichtner, N.; Neider, R.

    1975-08-01

    This report on the cataloguing and classification of technical rules for land-based light-water reactors and reprocessing plants contains a list of classified rules. The reasons for the classification system used are given and discussed

  15. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    John Collins

    2009-01-01

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  16. Automatic scheduling of maintenance work in nuclear power plants

    International Nuclear Information System (INIS)

    Kasahara, T.; Nishizawa, Y.; Kato, K.; Kiguchi, T.

    1987-01-01

    An automatic scheduling method for maintenance work in nuclear power plants has been developed using an AI technique. The purpose of this method is to help plant operators by adjusting the time schedule of various kinds of maintenance work so that incorrect ordering or timing of plant manipulations does not cause undersirable results, such as a plant trip. The functions of the method were tested by off-line simulations. The results show that the method can produce a satisfactory schedule of plant component manipulations without interference between the tasks and plant conditions

  17. Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  18. 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

  19. XML: Solution for the integration of nuclear power plant data and technical documents

    International Nuclear Information System (INIS)

    Gordillo, F.

    2000-01-01

    Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

  20. KWL Lingen nuclear plant. Technical annual report 2016; KWL Kernkraftwerk Lingen. Technischer Jahresbericht 2016

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-07-01

    The technical annual report 2016 for KWL (Lingen nuclear plant) covers the following sections: dismantling project management and operation, monitoring and clearance; waste management, technical qualification, security and safety, central tasks; licensing and supervision procedures, operational data, radiation monitoring, radioactive materials, in-service inspections.

  1. Technical Description Lillgrund Wind Power Plant. Lillgrund Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Jeppsson, Joakim; Larsen, Poul Erik; Larsson, Aake [Vattenfall Vindkraft AB, Stockholm (Sweden)

    2008-09-15

    Lillgrund offshore wind power plant comprises 48 wind turbines, each rated at 2.3 MW, bringing the total wind farm capacity to 110 MW. The Lillgrund offshore wind power plant is located in a shallow area of Oeresund, 7 km off the coast of Sweden and 7 km south from the Oeresund Bridge connecting Sweden and Denmark. An average wind speed of around 8,5 m/s at hub height, combined with a relatively low water depth of 4 to 8 meters makes it economically feasible to build here. Vattenfall Vindkraft AB is the owner and operator of Lillgrund offshore wind power plant. Lillgrund is a Swedish pilot project supported by the Swedish Energy Agency. The bidding process was completed during 2005 and the offshore power plant was constructed in the period 2006 to 2007. The wind farm was constructed on time and has now been successfully operational since December 2007. There is, however, always potential for improvement and the aim of this report has been to determine and highlight these areas. It is worth noting out that only the electrical system and the foundations are tailor made at offshore wind power plants. The wind turbines are more or less standard products with none or very limited possibilities for project specific design changes. Geotechnical investigations are expensive and it can be difficult to balance the risks as well as the benefits of this expense in the early phases of a large infrastructure project. As a whole, the geotechnical surveys at Lillgrund proved to be useful. They identified potential issues, such as the fact that extra excavation was required for two of the foundations. It also revealed the location of a small number of boulders that would have to be removed. Vattenfall requested a complete study of the electrical system for Lillgrund to be delivered with the bids. That request was not met. Instead Siemens Wind Power began a complete electrical system study after being awarded the Contract. The electrical system study was completed during the

  2. Statements of work handbook. [technical writing for NASA programs

    Science.gov (United States)

    1975-01-01

    Guidelines are presented for preparing statements of work (SOW) to assure a consistent approach throughout NASA. Statements of work for study and preliminary definition contracts, for definition and development of major systems, for support services, and for small research and development contracts are discussed.

  3. Central Heating Plant Coal Use Handbook. Volume 1: Technical Reference.

    Science.gov (United States)

    1996-11-01

    CHUTES LIFT TRUCKS MONORAILS , TRAMWAYS J p WEIGHING, 0 MEASURING SCALES COAL METERS HOPPERS SAMPLERS 9 FIRING EQUIPMENT (Source: Power, February...Defense (DOD) installations employ coal- fired central energy plants, the U.S. Army Construction Engineering Research Laboratories (USACERL) was... fired central heat plant operations cost by improving coal quality specifications. The Handbook is tailored for military installation industrial

  4. PUTTING PLANT BIOTECHNOLOGY TO WORK FOR FOOD ...

    African Journals Online (AJOL)

    Plant biotechnology is safely bringing valuable new benefits to farmers around the world, including those in developing countries where the needs for food, nutrition and overall development may be greatest. >From the current base of experience, it is reasonable to expect even greater benefits in the future, provided that ...

  5. Technical Note: Methionine, a precursor of methane in living plants

    Science.gov (United States)

    Lenhart, K.; Althoff, F.; Greule, M.; Keppler, F.

    2015-03-01

    When terrestrial plants were identified as producers of the greenhouse gas methane, much discussion and debate ensued not only about their contribution to the global methane budget but also with regard to the validity of the observation itself. Although the phenomenon has now become more accepted for both living and dead plants, the mechanism of methane formation in living plants remains to be elucidated and its precursor compounds to be identified. We made use of stable isotope techniques to verify the in vivo formation of methane, and, in order to identify the carbon precursor, 13C positionally labeled organic compounds were employed. Here we show that the amino acid L-methionine acts as a methane precursor in living plants. Employing 13C-labeled methionine clearly identified the sulfur-bound methyl group of methionine as a carbon precursor of methane released from lavender (Lavandula angustifolia). Furthermore, when lavender plants were stressed physically, methane release rates and the stable carbon isotope values of the emitted methane greatly increased. Our results provide additional support that plants possess a mechanism for methane production and suggest that methionine might play an important role in the formation of methane in living plants, particularly under stress conditions.

  6. Technical Working Group on Fast Reactors: German Report

    International Nuclear Information System (INIS)

    Maschek, W.

    2012-01-01

    General German situation: • After Fukushima decision to phase out definitely until 2022; • Currently only 9 reactors left (2 BWRs and 7 PWRs); • Start of new search for final repository all over Germany (salt, clay); • Discussion on retrievable repository; • Search for methods to reduce risk from waste repositories. Future prospects: • Continuation of work within EU programs; • Continuation of work within international organizations (IAEA, NEA-OECD); • New CRP‘s are of interest; • Education and training; • Focus on safety: prevention and mitigation; • Embedded in work on transmutation and waste treatment; • Cycle studies to demonstrate both sustainability potential and waste burning capability (reduced loads for final repositories) of FR

  7. Innovation and the organisation of technical expertise and work

    DEFF Research Database (Denmark)

    Howells, John

    This paper reviews a selection of the comparative research on the organisation of skills and work in different countries. It argues that despite differences in institutional means, such as keiretsu and structured apprenticeship, the ends, in terms of a capacity to organise skills, is similar. It ...... of what makes an effective technology manager. The conclusion is that in the most effective cases, whatever the institutional means that allows training, the object is the integration of formal academic knowledge with a structured and broad base of work experience...

  8. Technical data for concentrated solar power plants in operation, under construction and in project

    Directory of Open Access Journals (Sweden)

    Ugo Pelay

    2017-08-01

    Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

  9. "Good Work Awards:" Effects on Children's Families. Technical Report #12.

    Science.gov (United States)

    Chun, Sherlyn; Mays, Violet

    This brief report describes parental reaction to a reinforcement strategy used with children in the Kamehameha Early Education Program (KEEP). Staff members report that "Good Work Awards" (GWAs) are viewed favorably by mothers of students. GWAs are dittoed notes sent home with children when they have met a minimum criterion for daily…

  10. The Current Working Conditions in Ugandan Apparel Assembly Plants

    Directory of Open Access Journals (Sweden)

    Mike Tebyetekerwa

    2017-12-01

    Full Text Available Background: The present rapid shift of industrialization from developed to developing countries requires developing countries to understand issues related to work organization, management, and working conditions. There are many factors slackening production, of which working conditions is part. A complete inquiry into the workers' working conditions can enable managements to reduce risks in the workplaces and improve productivity. Understanding and awareness of the benefits of workplace research and a probe into the working conditions in the Ugandan apparel assembly plants are urgently required. Methods: A total of 103 (70 women and 33 men workers from five different plants were interviewed. Together with the top management of various plants, questionnaires about the workers' opinions of their physical working conditions were prepared. Data was collected using two methods: (1 questionnaire; and (2 observation of the workers during their work. Results: The results indicated that poor plant working conditions were mainly contributed by the workers' social factors and the management policies. Conclusion: The government, together with the management, should work to improve the working conditions in the apparel assembly plants, as it greatly affects both. Keywords: apparel assembly plants, ergonomics, musculoskeletal disorders, Uganda, working conditions

  11. Experience with drilling and blasting work during construction of Mochovce nuclear power plant

    International Nuclear Information System (INIS)

    Mraz, M.; Vojta, A.; Podel, R.

    1986-01-01

    The results are discussed of four years of investigating the technical and economic parameters of drilling and blasting equipment employed on the building site of the Mochovce nuclear power plant. The technical and operating characteristics are given of tested breaking and drilling sets manufactured by various foreign companies. The final choice was based on output, hard currency prices, power demand, operating reliability and number of personnel required for operation. The optimal set consists of two Hausherr HBM 70 drilling systems (holes with a diameter of 130 to 150 mm) and two ROC 601-02 Atlas Copco machines (auxiliary work, breaking foundation holes for nuclear reactors). (J.C.)

  12. Report of results on the research and development work 1979 of the Institute for Technical Chemistry

    International Nuclear Information System (INIS)

    1980-02-01

    The results report on the research and development work in 1979 carried out at the Institute for Technical Physics of the Nuclear Research Centre, Karlsruhe is concerned here. The main field of this development work is the research into superconducting magnets for fusion reactors. Studies are published on the material, processing and shape of these magnets. Furthermore, a report is given on fusion magnet technology, superconducting fundamentals and technical superconductors, as well as an cryonergy technique and cryotechnique. (KBI) [de

  13. CSNI technical opinion papers no.10. The role of human and organisational factors in nuclear power plant modifications

    International Nuclear Information System (INIS)

    2009-01-01

    Nuclear power plant modifications may be needed for a number of different reasons. These include physical ageing of plant systems, structures and components; obsolescence in hardware and software; feedback from operating experience; and opportunities for improved plant safety, reliability or capability. However, experience has also shown that weaknesses in the design and/or implementation of modifications can present significant challenges to plant safety. They can also have a considerable impact on the commercial performance of the plant. It is therefore important that the plant modification process reflect a recognition of the potential impact of human errors and that it incorporate suitable measures to minimise the potential for such errors. In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Working Group on Human and Organisational Factors organised an international workshop in 2003 to discuss the role of human and organisational performance in the nuclear plant modification process. This technical opinion paper represents the consensus of specialists in human and organisational factors (HOF) in the NEA member countries on commendable practices and approaches to dealing with nuclear plant modifications. It considers factors that should be taken into account when developing a modification process and identifies some lessons learnt from application of the process. The paper should be of particular interest of nuclear safety regulators and nuclear power plant operators. (author)

  14. Technical report on dc power supplies in nuclear power plants

    International Nuclear Information System (INIS)

    1977-06-01

    Emergency electrical power supplies, both a.c. and d.c. for nuclear power plants are important to safety. For this reason, the electric power systems for operating nuclear plants and those plants under licensing review have been required to provide a high degree of reliability. It is this high reliability that provides confidence that sufficient safety margin exists against loss of all d.c. power for extended periods of time to allow an orderly examination of safety issues, such as this. However, because of the importance of the a.c. and d.c. power systems, the staff has been expending effort to review the reliability of these systems and shall continue to do so in the future

  15. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire range of software life-cycle activities; the assessment of the technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary, includes an overview of the framework and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; Volume 2 is the main report

  16. IMPROVEMENT OF SYSTEMS OF TECHNICAL WATER SUPPLY WITH COOLING TOWERS FOR HEAT POWER PLANTS TECHNICAL AND ECONOMIC INDICATORS PERFECTION. Part 2

    Directory of Open Access Journals (Sweden)

    Yu. A. Zenovich-Leshkevich-Olpinskiy

    2016-01-01

    Full Text Available The method of calculation of economic efficiency that can be universal and is suitable for feasibility study of modernization of irrigation and water distribution system of cooling towers has been developed. The method takes into account the effect of lower pressure exhaust steam in the condenser by lowering the temperature of the cooling water outlet of a cooling tower that aims at improvement of technical and economic indicators of heat power plants. The practical results of the modernization of irrigation and water distribution system of a cooling tower are presented. As a result, the application of new irrigation and water distribution systems of cooling towers will make it possible to increase the cooling efficiency by more than 4 оС and, therefore, to obtain the fuel savings by improving the vacuum in the turbine condensers. In addition, the available capacity of CHP in the summer period is increased. The results of the work, the experience of modernization of irrigation and water distribution systems of the Gomel CHP-2 cooling towers system, as well as the and methods of calculating of its efficiency can be disseminated for upgrading similar facilities at the power plants of the Belarusian energy system. Some measures are prosed to improve recycling systems, cooling towers and their structures; such measures might significantly improve the reliability and efficiency of technical water supply systems of heat power plants.

  17. Biking to work in Miami. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Kerr, O.

    1982-08-01

    The objective of the project was to produce and distribute a guide to commuting by bicycle in the Miami metropolitan area. The area is uniquely suited to bicycling because of its pleasant year-round climate and relatively flat topography. Persuading even a small percentage of automobile commuters to try biking to work could result in substantial energy savings in Miami as in most other major metropolitan areas. Seven of the largest employment centers in the area were selected as major commuter destinations suitable for bicycle commuters. Safe and scenic ways of commuting to these areas by bicycle were mapped and described in a series of short narratives. Additional material on safe riding techniques and the choice of equipment was developed. The resulting 40 page booklet, Biking to Work in Miami, was printed and distributed by the author to local cycling groups, bicycle interests, and others. Copies were also sent to interested parties outside the Miami area. The initial reception has been very encouraging and a number of favorable reply cards have been received with useful comments and suggestions. A revised version aimed at stimulating bikers to avail of the soon-to-be-opened rapid transit system is being considered. A writer for the Miami Herald is interested in using parts of the Guide for a series in the newspaper.

  18. Control of subcontractors by civil works contractor for a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Xinguo, Jiang [Huaxing Construction Company, Yizheng, JS (China)

    1995-10-01

    The civil works (CW) contractor is responsible for managing its subcontractors according to the requirements of quality assurance programme including the establishment of organization, quality assurance management, document control, material control, construction schedule control, inspection and test control, non-conformance control, corrective actions and executive technical files. The responsibilities of the plant owner, the CW contractor and its subcontractors in relation to performing their functions in the above-mentioned activities are described in detail.

  19. Control of subcontractors by civil works contractor for a nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Xinguo

    1995-10-01

    The civil works (CW) contractor is responsible for managing its subcontractors according to the requirements of quality assurance programme including the establishment of organization, quality assurance management, document control, material control, construction schedule control, inspection and test control, non-conformance control, corrective actions and executive technical files. The responsibilities of the plant owner, the CW contractor and its subcontractors in relation to performing their functions in the above-mentioned activities are described in detail

  20. 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)

  1. Studies of safety and critical work situations in nuclear power plants: A human factors perspective

    International Nuclear Information System (INIS)

    Jacobsson Kecklund, L.

    1998-05-01

    The purpose of this thesis was to develop and apply different approaches for analyzing safety in critical work situations in real work settings in nuclear power plants, and also to identify safety enhancing measures by using the framework of interaction between human, organizational and technical subsystems. A Cognitive Psychology as well as a Stress Psychology framework was used. All studies were related to the annual outage operational state where the need for coping with many infrequent tasks, often carried out under high time pressure, puts great strain on the staff and organisation of the plant. In three studies the natural variations in the plant state, normal operation and annual outage operation, were used to explore human performance, work-related factors as well as coping and the operators' own resources and the relationship between them. In the annual outage condition high work demands, decreased sleepiness at night shift, more errors and less satisfaction with work performance quality was reported by maintenance as well as by control room operators. A relationship between high work demands and more organizational problems and reports of more frequent human errors and lower satisfactions with work performance quality was also identified in the annual outage condition. Moreover, a relationship between increased sleepiness during night shift, more frequent use of coping strategies and a higher frequency of human errors was reported. In two studies the Event and Barrier Function Model was applied to analyze the safety of barrier function systems inserted into work process sequences to protect the systems from the negative consequences of failures and errors. The model was also used to assess safety in relation to a technical and organizational change. The last study addressed changes in work performance and work-related factors in relation to a technical and organizational change of a safety significant work process involving increased automation and new

  2. Nuclear design and technical development required for ISER plant

    International Nuclear Information System (INIS)

    Yokoyama, Takashi; Yamano, Naoki.

    1987-01-01

    The report outlines some results of a study carried out by the ISER (intrinsically safe and economical reactor) Investigation Group. In particular, nuclear design concepts are examined in relation to the fuel cycle. Discussion is also made on technical development efforts to be made for realizing an ISER. Calculation of some basic nuclear design parameters is performed and results are used to examine the reactor core and fuel for ISER. As a result, it is indicated that a high-burnup type reactor core should be used on a 4.5-batch replacement, 15 EFPM (effective full power month) scheme to optimize an ISER. For technical development, consideration is made on various tests to be performed with an experimental reactor, called ISER-E, as well as other tests to provide basic data required for demonstrating the inherent safety of ISER. The study also deals with the possibility of the application of currently available light water reactor techniques to experiments with a critical assembly, non-nuclear test loop, and the experimental reactor ISER-E. It is revealed that many of the required experiments can be carried out by using test facilities and light water reactor techniques which are currently, or will be readily, available. It is stressed that international cooperation is necessary to accomplish these tests. (Nogami, K.)

  3. SAT-based personnel training for nuclear power plants. Proceedings of a seminar jointly organized under the technical cooperation programme (UKR/4/003) by the International Atomic Energy Agency, Goskomatom of Ukraine, South-Ukrainian NPP and held in Yuzhnoukrainsk, Ukraine, 10-14 April 1995. Working material

    International Nuclear Information System (INIS)

    1995-01-01

    In 1995 the IAEA technical co-operation project ''Training for Safe Operation and Management of Nuclear Power Plants'' (UKR/4/003) has been started with the main goal to improve training systems and training infrastructures to ensure safe and reliable operation of nuclear power plants. As the first step of the project implementation, a seminar on introducing the Systematic Approach to Training for NPP personnel was recommended by the IAEA and G-24 mission on training as one of the primary training needs and priorities of Ukraine. The Seminar was held at the South-Ukrainian Nuclear Power Plant (SUNPP), Yuzhnoukrainsk, Ukraine from 10 to 13 April 1995 and was attended by 35 representatives from GOSKOMATOM, Ministry for Environment Protection and Nuclear Safety, OGPU, and all NPPs of Ukraine

  4. Technical and economical analysis of concepts for using the heat of biogas plants in rural areas

    International Nuclear Information System (INIS)

    Kaths, Friederike Annette

    2012-08-01

    Since the implementation of the EEG in Germany the biogas production becomes an independent branch of industry in the agriculture. At this time more than 90 percent of the biogas plants work with co-generation plant for heat and power with a thermal engine efficiencies of more than 50 percent. Because of the location in the rural area heat costumers with a continuous demand of heat over the whole year are rare. This research had a closer look how to use the heat of biogas production efficiently and also generating profit. The aim of the study was to use heat over the whole year, a profitable heat concept without counting the KWK-bonus and an added value on the farm. During the study the following concepts were analyzed: asparagus production using soil heating, drying equipment for different products, the production of fish in aquaculture, the poultry production and the heated production of tomatoes. The results showed different concepts using heat of biogas plants as efficient for farmers. However with only one concept the aims - to use the heat over the whole year, generating a profitable heat concept without counting the KWK-bonus, add an value on the farm - mostly can not be achieved. The combination of different heat concepts is necessary. In this analysis the poultry production in combination with the dryer can be considered as the most efficient concept. Bearing in mind the benefit which can be generated with a heat concept as well as the higher income and the higher technical efficiency of biogas plants operators should implement an individual concept for their heat.

  5. A Study on Establishment of Nuclear Power Plant Technical Support System and Activation Plan

    International Nuclear Information System (INIS)

    Wi, M. H.; Park, W. S.; Lee, H. S.; Kim, J. H.; Won, B. C.; Kim, Y. H.; Goo, D. S.; Choi, H. B.

    2009-11-01

    This report includes activities related to establishment of 'BaroBaro nuclear plant technical support center', 'selection of nuclear plant applicable technology', and 'various information interchange between KAERI and nuclear power plant'. 'BaraBaro center was newly organized to support on resolving the technical difficulties in operation of nuclear power plant'. The center consists of 10 technical parts and a leading expert is assigned to each part to support more efficiently. This center is always served for 24 hour. The plant operators can register their problem to the center by a call, e-mail, or internet and they can receive the answer about what they issued from KAERI experts. To make a brochure, we selected 32 technologies which are applicable in nuclear plant without additional R and D activity. The brochure was distributed to the officer in charge of nuclear plant operations. Various meetings were held to increase interchange of experience and technology between KAERI and nuclear power plant and we discussed many different issues at that meeting

  6. Resolution of digital instrumentation and control and human factors technical and regulatory issues for new plants and for modernization of operating plants

    International Nuclear Information System (INIS)

    Naser, J.A.; Torok, R.C.; Canavan, K.T.

    2008-01-01

    There are several technical and regulatory issues in the areas of digital I and C, human factors, and control rooms needing generic resolution. If they are not generically resolved, they can contribute to protracted regulatory reviews for operating plant license amendments and substantial delays and increased costs for new plant COL approvals. Therefore; a coordinated, proactive program has been established to resolve key issues. Both Industry and NRC have roles in resolving these key issues and addressing them in future design efforts and regulatory reviews. The Industry initiative is led by the NEI Digital I and C and Human Factors Working Group. NRC has established Task Working Groups under the NRC Digital I and C Steering Committee to address the issues and interact with Industry. EPRI is providing technical input and resolution leadership for some of the issues being addressed in three of the task working groups. For the Highly Integrated Control Room - Human Factors Task area, EPRI has taken the lead in developing draft industry position technical reports for the following three issues: 1) Minimum inventory of human system interfaces, 2) Computerized procedures and associated topics of automation and soft controls, and 3) Methodology to determine the acceptability of manual operator actions response times for a BTP 7-19 software common cause failure. For the Diversity and Defense-in-Depth area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Integrating defensive measures and diversity attributes to protect against digital common cause failures and 2) Susceptibility of digital devices and components to common cause failures. For the Risk Informing area, EPRI has taken the lead in developing two draft industry position technical papers on the following topics: 1) Clarifying how to use current methods to model digital systems in a PRA and 2) Application of PRA to specific digital I and C issues

  7. The Current Working Conditions in Ugandan Apparel Assembly Plants.

    Science.gov (United States)

    Tebyetekerwa, Mike; Akankwasa, Nicholus Tayari; Marriam, Ifra

    2017-12-01

    The present rapid shift of industrialization from developed to developing countries requires developing countries to understand issues related to work organization, management, and working conditions. There are many factors slackening production, of which working conditions is part. A complete inquiry into the workers' working conditions can enable managements to reduce risks in the workplaces and improve productivity. Understanding and awareness of the benefits of workplace research and a probe into the working conditions in the Ugandan apparel assembly plants are urgently required. A total of 103 (70 women and 33 men) workers from five different plants were interviewed. Together with the top management of various plants, questionnaires about the workers' opinions of their physical working conditions were prepared. Data was collected using two methods: (1) questionnaire; and (2) observation of the workers during their work. The results indicated that poor plant working conditions were mainly contributed by the workers' social factors and the management policies. The government, together with the management, should work to improve the working conditions in the apparel assembly plants, as it greatly affects both.

  8. Technical Work Plan for: Additional Multiscale Thermohydrologic Modeling

    International Nuclear Information System (INIS)

    B. Kirstein

    2006-01-01

    will be evaluated and justified. Some of this evaluation will be conducted in conjunction with the post-model development validation activity involving comparisons of predicted TH conditions with measured TH conditions in the DST. The expected result is that, consistent with what was found in Revision 03 of Multiscale Thermohydrologic Model (BSC 2005 [DIRS 173944], Section 6.3.9), near-field/in-drift TH behavior is insensitive to a wide range of host-rock hydrologic property values. It is the intention of the work described in this TWP to propagate the new infiltration fluxes from the replacement infiltration model, by using the percolation fluxes from the revised site-scale unsaturated zone (UZ) flow model that has applied those new infiltration fluxes. The percolation flux distributions will be obtained from the updated site-scale UZ flow model, which has applied updated infiltration flux maps. Another objective of the work scope is to develop, implement, and validate a revised TH submodel-construction approach. This revised approach utilizes interpolation among a set of generic LDTH submodels that are run for a range of percolation flux histories that cover a sufficiently broad range of infiltration flux uncertainty, as well as for four host-rock units (two lithophysal units and two nonlithophysal units), and for three thermal property sets (low, mean, and high). A key motivation for this revised LDTH submodel-construction approach is to enable the MSTHM to be more flexible in addressing a broad range of infiltration flux cases. This approach allows the generic LDTH submodel simulations to be conducted prior to receiving percolation flux maps

  9. Technical considerations for flexible piping design in nuclear power plants

    International Nuclear Information System (INIS)

    Lu, S.C.; Chou, C.K.

    1985-01-01

    The overall objective of this research project is to develop a technical basis for flexible piping designs which will improve piping reliability and minimize the use of pipe supports, snubbers, and pipe whip restraints. The current study was conducted to establish the necessary groundwork based on the piping reliability analysis. A confirmatory piping reliability assessment indicated that removing rigid supports and snubbers tends to either improve or affect very little the piping reliability. A couple of changes to be implemented in Regulatory Guide (RG) 1.61 and RG 1.122 aimed at more flexible piping design were investigated. It was concluded that these changes substantially reduce calculated piping responses and allows piping redesigns with significant reduction in number of supports and snubbers without violating ASME code requirements

  10. International working group on life management of nuclear power plants (IWG-LMNPP). Regular meeting. 30 August - 1 September 1995. Working material. V. 2

    International Nuclear Information System (INIS)

    1995-01-01

    This meeting of the International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP) was organized to review the national programmes of the countries and to advise the IAEA on its technical meetings and activities in the subject areas taking into consideration current progress, problems and operating experience. Refs, figs and tabs

  11. International working group on life management of nuclear power plants (IWG-LMNPP). Regular meeting. 30 August - 1 September 1995. Working material. V. 1

    International Nuclear Information System (INIS)

    1995-01-01

    This meeting of the International Working Group on Life Management of Nuclear Power Plants (IWG-LMNPP) was organized to review the national programmes of the countries and to advise the IAEA on its technical meetings and activities in the subject areas taking into consideration current progress, problems and operating experience. Refs, figs and tabs

  12. 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

  13. 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

  14. 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

  15. A technical system to improve the operational monitoring of the Zaporozh'ye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Schumann, P.; Seidel, A.; Weiss, F.-P.; Zschau, J.; Nowak, K.

    1997-01-01

    As part of a programme of cooperation with Central and Eastern European states, a technical system has been established for the Zaporozhe nuclear power plant, which complements existing operational checking and monitoring facilities with modern means of information technology. It makes it possible to continuously monitor the state of the units in normal operation and in cases of anomalies or incidents. The parameters selected for monitoring are listed, and the system of automatic evaluation at the power plant site is described in detail. Test operation of the technical system started in late 1995 and the industrial testing phase in mid-1996. (A.K.)

  16. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  17. 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)

  18. 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)

  19. Groundwater Interim Measures Work Plan for the Former Chemical Plant

    Science.gov (United States)

    May 2012 Groundwater IMWP, revised per EPA's approval, focuses on the installation of a groundwater containment system to mitigate groundwater migration from the former plant. A prior 2002 work plan is included in its entirety in Appendix B.

  20. School-to-Work Transition of Career and Technical Education Graduates

    Science.gov (United States)

    Packard, Becky Wai-Ling; Leach, Miki; Ruiz, Yedalis; Nelson, Consuelo; DiCocco, Hannah

    2012-01-01

    This study analyzed the career development of career and technical education (CTE) high school graduates during their school-to-work transition, specifically their adaptability in the face of barriers. Forty graduates (22 men, 18 women) from working-class backgrounds participated in baseline surveys at graduation and phenomenological interviews 1…

  1. technical guidelines for the design and construction of the next generation of nuclear power plants with pressurized water reactors

    International Nuclear Information System (INIS)

    2009-01-01

    These technical guidelines present the opinion of the French 'Groupe Permanent charge des Reacteurs nucleaires' (GPR) concerning the safety philosophy and approach as well as the general safety requirements to be applied for the design and construction of the next generation of nuclear power plants of the PWR (pressurized water reactor) type, assuming the construction of the first units of this generation would start at the beginning of the 21. century. These technical guidelines are based on common work of the French Institut de Protection et de Surete Nucleaire (IPSN) and of the German Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). Moreover, these technical guidelines were extensively discussed with members of the German Reaktor Sicherheitskommission (RSK) until the end of 1998 and further with German experts. The context of these technical guidelines must be clearly understood. Faced with the current situation of nuclear energy in the world, the various nuclear steam supply system designers are developing new products, all of them claiming their intention of obtaining a higher safety level, by various ways. GPR believes that, for the operation of a new series of nuclear power plants at the beginning of the next century, the adequate way is to derive the design of these plants in an 'evolutionary' way from the design of existing plants, taking into account the operating experience and the in-depth studies conducted for such plants. Nevertheless, introduction of innovative features must also be considered in the frame of the design of the new generation of plants, especially in preventing and mitigating severe accidents. GPR underlines here that a significant improvement of the safety of the next generation of nuclear power plants at the design stage is necessary, compared to existing plants. If the search for improvement is a permanent concern in the field of safety, the necessity of a significant step at the design stage clearly derives from better

  2. On the technical superiority of domestic power plant equipment and its development

    International Nuclear Information System (INIS)

    Zhao Zhiyi

    1993-01-01

    Under the Presumption of affirmed superiority of domestic power plant equipment, some existing deficiencies are pointed out. The scientific and technical development of domestic power equipment can be impelled through catching up with advanced technologies. The necessity of optimal matching of plant equipment from the engineering point of view is emphasized by the authors in association with a prospective outlook of key power equipment and development suggestions

  3. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    Energy Technology Data Exchange (ETDEWEB)

    Field, H C

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted.

  4. Next Generation Nuclear Plant Methods Technical Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-12-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  5. Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498

    Energy Technology Data Exchange (ETDEWEB)

    Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

    2010-09-01

    One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

  6. Technical safety appraisal: Buildings 776/777 Rocky Flats Plant

    International Nuclear Information System (INIS)

    Field, H.C.

    1988-03-01

    Buildings 776/777 at the Rocky Flats Plant are major components of the production complex at the plant site. They have been in operation since 1957. The operations taking place in the buildings are nuclear weapons production support, processing of weapons assemblies returned from Pantex, waste processing, research and development in support of production, special projects, and those generated by support groups, such as maintenance. The appraisal team identified nine deficiencies that it believed required prompt attention. DOE management for EH, the program office (Defense Programs), and the field office analyzed the information provided by the appraisal team and instituted compensatory measures for closer monitoring of contractor activities by knowledgeable DOE staff and staff from other sites. Concurrently, the contractor was requested to address both short-term and long-term remedial measures to correct the identified issues as well as the underlying problems. The contractor has provided his action plan, which is included. This plan was under evaluation by EH and the DOE program office at the time this report was prepared. In addressing the major areas of concern identified above, a well as the specific deficiencies identified by the appraisal team, the contractor and the field office are cautioned to search for the root causes for the problems and to direct corrective actions to those root causes rather than solely to the symptoms to assure the sustainability of the improvements being made. The results of prior TSAs led DOE to conclude that previous corrective actions were not sufficient in that a large number of the individual findings are recurrent. Pending completion of remedial actions over the next few months, enhanced DOE oversight of the contractor is warranted

  7. Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1984-01-01

    The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

  8. ``Recycling'' Nuclear Power Plant Waste: Technical Difficulties and Proliferation Concerns

    Science.gov (United States)

    Lyman, Edwin

    2007-04-01

    One of the most vexing problems associated with nuclear energy is the inability to find a technically and politically viable solution for the disposal of long-lived radioactive waste. The U.S. plan to develop a geologic repository for spent nuclear fuel at Yucca Mountain in Nevada is in jeopardy, as a result of managerial incompetence, political opposition and regulatory standards that may be impossible to meet. As a result, there is growing interest in technologies that are claimed to have the potential to drastically reduce the amount of waste that would require geologic burial and the length of time that the waste would require containment. A scenario for such a vision was presented in the December 2005 Scientific American. While details differ, these technologies share a common approach: they require chemical processing of spent fuel to extract plutonium and other long-lived actinide elements, which would then be ``recycled'' into fresh fuel for advanced reactors and ``transmuted'' into shorter-lived fission products. Such a scheme is the basis for the ``Global Nuclear Energy Partnership,'' a major program unveiled by the Department of Energy (DOE) in early 2006. This concept is not new, but has been studied for decades. Major obstacles include fundamental safety issues, engineering feasibility and cost. Perhaps the most important consideration in the post-9/11 era is that these technologies involve the separation of plutonium and other nuclear weapon-usable materials from highly radioactive fission products, providing opportunities for terrorists seeking to obtain nuclear weapons. While DOE claims that it will only utilize processes that do not produce ``separated plutonium,'' it has offered no evidence that such technologies would effectively deter theft. It is doubtful that DOE's scheme can be implemented without an unacceptable increase in the risk of nuclear terrorism.

  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. 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

  13. Working toward integrated models of alpine plant distribution.

    Science.gov (United States)

    Carlson, Bradley Z; Randin, Christophe F; Boulangeat, Isabelle; Lavergne, Sébastien; Thuiller, Wilfried; Choler, Philippe

    2013-10-01

    Species distribution models (SDMs) have been frequently employed to forecast the response of alpine plants to global changes. Efforts to model alpine plant distribution have thus far been primarily based on a correlative approach, in which ecological processes are implicitly addressed through a statistical relationship between observed species occurrences and environmental predictors. Recent evidence, however, highlights the shortcomings of correlative SDMs, especially in alpine landscapes where plant species tend to be decoupled from atmospheric conditions in micro-topographic habitats and are particularly exposed to geomorphic disturbances. While alpine plants respond to the same limiting factors as plants found at lower elevations, alpine environments impose a particular set of scale-dependent and hierarchical drivers that shape the realized niche of species and that require explicit consideration in a modelling context. Several recent studies in the European Alps have successfully integrated both correlative and process-based elements into distribution models of alpine plants, but for the time being a single integrative modelling framework that includes all key drivers remains elusive. As a first step in working toward a comprehensive integrated model applicable to alpine plant communities, we propose a conceptual framework that structures the primary mechanisms affecting alpine plant distributions. We group processes into four categories, including multi-scalar abiotic drivers, gradient dependent species interactions, dispersal and spatial-temporal plant responses to disturbance. Finally, we propose a methodological framework aimed at developing an integrated model to better predict alpine plant distribution.

  14. Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors

    Directory of Open Access Journals (Sweden)

    Sylva Brabencová

    2017-12-01

    Full Text Available Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0 and Wassilewskija (Ws homogenized by two techniques (grinding in a cryomill or with a mortar and pestle. We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants. Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

  15. Variations of Histone Modification Patterns: Contributions of Inter-plant Variability and Technical Factors.

    Science.gov (United States)

    Brabencová, Sylva; Ihnatová, Ivana; Potěšil, David; Fojtová, Miloslava; Fajkus, Jiří; Zdráhal, Zbyněk; Lochmanová, Gabriela

    2017-01-01

    Inter-individual variability of conspecific plants is governed by differences in their genetically determined growth and development traits, environmental conditions, and adaptive responses under epigenetic control involving histone post-translational modifications. The apparent variability in histone modifications among plants might be increased by technical variation introduced in sample processing during epigenetic analyses. Thus, to detect true variations in epigenetic histone patterns associated with given factors, the basal variability among samples that is not associated with them must be estimated. To improve knowledge of relative contribution of biological and technical variation, mass spectrometry was used to examine histone modification patterns (acetylation and methylation) among Arabidopsis thaliana plants of ecotypes Columbia 0 (Col-0) and Wassilewskija (Ws) homogenized by two techniques (grinding in a cryomill or with a mortar and pestle). We found little difference in histone modification profiles between the ecotypes. However, in comparison of the biological and technical components of variability, we found consistently higher inter-individual variability in histone mark levels among Ws plants than among Col-0 plants (grown from seeds collected either from single plants or sets of plants). Thus, more replicates of Ws would be needed for rigorous analysis of epigenetic marks. Regarding technical variability, the cryomill introduced detectably more heterogeneity in the data than the mortar and pestle treatment, but mass spectrometric analyses had minor apparent effects. Our study shows that it is essential to consider inter-sample variance and estimate suitable numbers of biological replicates for statistical analysis for each studied organism when investigating changes in epigenetic histone profiles.

  16. Technical and institutional safety features of nuclear power plants in Brazil. Aspectos tecnicos e institucionais da seguranca dos reatores nucleares no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Rosa, L P [Sociedade Brasileira de Fisica, Rio de Janeiro, RJ (Brazil)

    1986-01-01

    This work reports technical, political and institutional safety features of nuclear power plants in Brazil. It is mainly concerned with reactor accidents and personnel safety. The three mile Island and Chernobyl accidents are also discussed and taken as examples. (A.C.A.S.).

  17. The atmospheric corrosion: an important technical-economic and nuclear safety factor during storage in the construction of nuclear power plants

    International Nuclear Information System (INIS)

    Rodriguez, R.; Rodriguez, J.; Diaz, J.; Gomez, J.; Galeano, N.

    1993-01-01

    The purpose of this work is to show the results of the research performed to determine the atmospheric corrosion in the region of Juragua nuclear power plant and to offer some practical recommendations to increase the efficiency during the storage of materials, considering technical-economic and nuclear safety aspects

  18. Investigative study on the technical code requirements of natural events hazards for nuclear power plants

    International Nuclear Information System (INIS)

    Ito, Kunio; Aoki, Takayuki

    2012-01-01

    Technical codes and standards on natural phenomena, in particular, earthquake and tsunami for nuclear power plants in the other developed countries including IAEA safety standards were investigated. Then, the results were compared with the corresponding Japanese technical codes and standards. As a results, it was found that: (1) technical codes and standards on natural phenomena, especially those for earthquakes and tsunami/flooding in those foreign countries and their requirements are all included in the Japanese technical codes and standards. (2) Nevertheless, the actual measures against tsunami/flooding in those foreign countries are more advanced than those in Japan which had been taken before Fukushima accident. Therefore, further investigation is needed to clarify the reason why there are such differences by investigating the details of the basic ideas and evaluation methods for the protection of tsunami/flooding. (author)

  19. [Analysis of work-related fatigue characteristics and its influencing factors in scientific and technical personnel].

    Science.gov (United States)

    Yang, Ting; Zhou, Dinglun; Song, Mingying; Lan, Yajia

    2015-02-01

    To investigate the current status and characteristics of work-related fatigue among scientific and technical personnel and its associated factors, and to provide a scientific basis for further interventions. A cross-sectional survey was conducted in the staff from a single scientific institution, using a self-administered questionnaire. Basic information of participants, Fatigue Scale-14, and Job Content Questionnaire were collected. The prevalence of work-related fatigue among the scientific and technical personnel was 54.6%; work-related fatigue was positively correlated with occupational stress (rs = 0.384, P work-related fatigue included occupational stress profiles, social support, and educational status. A higher risk of work-related fatigue was found in the staff under high stress, compared with those under low stress (OR = 8.5, 95%CI = 3.9∼18.7). Social support served as a protective factor for work-related fatigue, while a higher level of education was correlated with more severe work-related fatigue. Work-related fatigue is common and serious among scientific and technical personnel, especially in those under high stress. Effective interventions according to occupational stress are of great importance to reduce work-related fatigue.

  20. Development of management system for plant repairing work

    International Nuclear Information System (INIS)

    Terauchi, Makoto

    1999-01-01

    In the fast breeder reactor, ''Monju'', in order to conduct nuclear plant repairing works securely and effectively, development of a computer system to assist management business on plant repairing work was begun on 1993. The system has been applied to about 5,000 times of operational management through past four times of plant inspection and to daily inspections and maintenance, and is daily used at working places of ''Monju'' such as issue/management of about 110,000 times of operational prohibition tag in isolated management. And, by automation of issue/management on working sheets and operational prohibition tag and others conducted hitherto by hand, the management business has been largely rationalized. (G.K.)

  1. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods - mothballing, entombing, or dismantling, or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which requires surveillance and maintenance for a significant period to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for an 1100-MW(e) light-water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as US $200,000. Although some tooling development will be needed for removing highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g. the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund, or annual depreciation type operating allowance, will have little effect on construction or on operating costs. (author)

  2. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods, namely, mothballing, entombing, or dismantling or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which require surveillance and maintenance for a significant period of time to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for a 1100 MW(e) light water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as $200,000. Although some tooling development will be needed for the removal of the highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g., the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund or annual depreciation type operating allowance will have little impact on either construction or operating costs

  3. Environmental Impact Report from Santa Rita Hydroelectric Power Plant (Minas Gerais State - Brazil): technical strategic for its elaboration

    International Nuclear Information System (INIS)

    Souza, J.A. de; Marques Neto, F.P.

    1989-01-01

    The steps for developing the technical strategies used on the elaboration of Environmental Impact Report from Santa Rita Hydroelectric Power Plant, Minas Gerais State, are described, including the influence area, technical requirements, impact identification, technical selection of mitigative measures, impact meaning and strategy for evaluating the identified impacts. (C.G.C.)

  4. Technical skills requirement of Indonesian construction labors to work in Malaysia

    Science.gov (United States)

    Adi, Henny Pratiwi

    2017-03-01

    Labors skills is an important part of construction projects implementation. Suitability between the skills possessed by labors with the skills needed by user is required to increase employment opportunities. Malaysia is a country that using construction labors from Indonesia. This study aims to get the kind of technical skills required by users of Indonesian constructian labors in Malaysia and also the importance level of technical skills. Data collecting in this research was conducted through interviews and questionnaires on contractors in Malaysia. The next stage was determine the importance level of technical skills in work field of carpenter, bricklayer, plumber and painters. The importance level of technical skills analyzed using the Relative Importance Index (RII). The results showed that mastering the operation of both instruments either manually or electrically is the most importance in the technical skills. Therefore, an understanding of the types of equipment for work field and the manner of operation is need to had by Indonesian construction labors who will work in Malaysia.

  5. [Fortieth Annual] Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 39th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2007, 2008 and 2009; - Review the Agency’s ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations; - Discuss future joint activities in view of the Agency’s Programme and Budget Cycle 2008–2009 (and beyond)

  6. Approaches to the safety of future nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-09-01

    The Technical Committee Meeting on Approaches to Safety of Future Nuclear Power Plants in Different Countries, held from 29 May to 2 June 1995, contributed to this process. Experts from 14 different countries and two international organizations participated in the meeting, which provided the opportunity to exchange information and to review the answers developed to date to these issues (primarily form the IAEA's technical document ''Development of Safety Principles for the Design of Future Nuclear Power Plants'' IAEA-TECDOC-801) and the report of the International Nuclear Safety Advisory Group ''Basic Safety Principles for Nuclear Power Plants'' (INSAG-3). These references were then used as a starting point for answering the question ''to what degree does general agreement (or harmonization) exist on these desired safety approaches for future reactors, and what opportunities remain for further harmonization? 11 refs, 1 tab

  7. Cycle water chemistry based on film forming amines at power plants: evaluation of technical guidance documents

    Science.gov (United States)

    Dyachenko, F. V.; Petrova, T. I.

    2017-11-01

    Efficiency and reliability of the equipment in fossil power plants as well as in combined cycle power plants depend on the corrosion processes and deposit formation in steam/water circuit. In order to decrease these processes different water chemistries are used. Today the great attention is being attracted to the application of film forming amines and film forming amine products. The International Association for the Properties of Water and Steam (IAPWS) consolidated the information from all over the World, and based on the research studies and operating experience of researchers and engineers from 21 countries, developed and authorized the Technical Guidance Document: “Application of Film Forming Amines in Fossil, Combined Cycle, and Biomass Power Plants” in 2016. This article describe Russian and International technical guidance documents for the cycle water chemistries based on film forming amines at fossil and combined cycle power plants.

  8. Study on optimization of normal plant outage work plan for nuclear power plants

    International Nuclear Information System (INIS)

    Aoki, Takayuki; Kodama, Noriko; Takase, Kentaro; Miya, Kenzo

    2011-01-01

    This paper discusses maintenance optimization in maintenance implementation stage following maintenance planning stage in nuclear power plants and proposes a methodology to get an optimum maintenance work plan. As a result of consideration, the followings were obtained. (1) The quantitative evaluation methodology for optimizing maintenance work plan in nuclear power plants was developed. (2) Utilizing the above methodology, a simulation analysis of maintenance work planning for BWR's PLR and RHR systems in a normal plant outage was performed. Maintenance cost calculation in several cases was carried out on the condition of smoothening man loading over the plant outage schedule as much as possible. (3) As a result of the simulation, the economical work plans having a flat man loading over the plant outage schedule were obtained. (author)

  9. Report of working group for technical standard of cutting and melting works in Glovebox dismantling

    International Nuclear Information System (INIS)

    Asazuma, Shinichiroh; Takeda, Shinsoh; Tajima, Shoichi

    2004-11-01

    In order to prevent spread of contamination, glovebox dismantling activity is usually performed in a confined enclosure with personal radioactive protective equipment. Since large potion of these materials is made of vinyl acetate, there exist potential risks of fire, damage and injury to the environment and workers during the dismantling (cutting or melting) operation. It is therefore important to establish standard for proper use of equipment and hazard controls in such a specific environment. Working Group composed of Tokai Works and Oarai Works has examined and developed the operational standard for cutting work in glovebox dismantlement. The result is reflected to the Tokai Works Safety Operational Standard. (author)

  10. Nuclear plant engineering work and integrated management system

    International Nuclear Information System (INIS)

    Ohkubo, Y.; Obata, T.; Tanaka, K.

    1992-01-01

    The Application of computers to the design, engineering, manufacturing and construction works of nuclear power plants has greatly contributed to improvement of productivity and reliability in the nuclear power plants constructed by Mitsubishi Nuclear Group for more than ten years. However, in most cases, those systems have been developed separately and utilized independently in different computer software and hardware environments and have not been fully utilized to achieve high efficiency and reliability. In order to drastically increase the productivity and efficiency, development of NUclear power plant engineering Work and INtegrated manaGement System (NUWINGS) started in 1987 to unify and integrate various conventional and developing systems using the state-of-the-art computer technology. The NUWINGS is almost completed and is now applied to actual plant construction. (author)

  11. A socio-technical analysis of work with ideas in NPD: an industrial case study

    DEFF Research Database (Denmark)

    Gish, Liv; Hansen, Claus Thorp

    2013-01-01

    on piecing together a number of ideas that were developed and disseminated in a large industrial company. We do this through an in-depth case study of the development of the energy-labeled circulation pump Alpha Pro, developed by one of the world’s leading pump manufacturers, Grundfos. Using a socio-technical...... approach, we focus especially on the actors involved and the contextual factors, and less on the detailed development of technical ideas. In our study, we observe that (1) ideas are pieced together from previous ideas and results; (2) ideas are implemented through continuous mobilization of support...... and development of legitimate arguments; and (3) idea work is also a socio-technical process, because contextual factors matter. We observe that idea work is an ongoing process undertaken across different projects, actors, departments, strategies, and visions within Grundfos, while also involving external actors...

  12. Choice of optimal working fluid for binary power plants at extremely low temperature brine

    Science.gov (United States)

    Tomarov, G. V.; Shipkov, A. A.; Sorokina, E. V.

    2016-12-01

    The geothermal energy development problems based on using binary power plants utilizing lowpotential geothermal resources are considered. It is shown that one of the possible ways of increasing the efficiency of heat utilization of geothermal brine in a wide temperature range is the use of multistage power systems with series-connected binary power plants based on incremental primary energy conversion. Some practically significant results of design-analytical investigations of physicochemical properties of various organic substances and their influence on the main parameters of the flowsheet and the technical and operational characteristics of heat-mechanical and heat-exchange equipment for binary power plant operating on extremely-low temperature geothermal brine (70°C) are presented. The calculation results of geothermal brine specific flow rate, capacity (net), and other operation characteristics of binary power plants with the capacity of 2.5 MW at using various organic substances are a practical interest. It is shown that the working fluid selection significantly influences on the parameters of the flowsheet and the operational characteristics of the binary power plant, and the problem of selection of working fluid is in the search for compromise based on the priorities in the field of efficiency, safety, and ecology criteria of a binary power plant. It is proposed in the investigations on the working fluid selection of the binary plant to use the plotting method of multiaxis complex diagrams of relative parameters and characteristic of binary power plants. Some examples of plotting and analyzing these diagrams intended to choose the working fluid provided that the efficiency of geothermal brine is taken as main priority.

  13. Optimisation of maintenance and inspection work in nuclear power plants

    International Nuclear Information System (INIS)

    Meyer, V.

    1996-01-01

    The long-term planning and comparative evaluation of inspection and maintenance intervals as well as results of electric components and machinery have to be intensified in order to shorten maintenance shut-down periods, e.g. of the Grohnde reactor station, thus improving the availability of the plant and the specific electricity generation cost. Economically efficient maintenance has to be based on an efficient organisational structure. Outsourcing of less plant-specific work and tasks offers the possibility for in-house personnel to concentrate on their core competences. All the measures discussed contribute to improving the economic efficiency of the nuclear power plants. (orig./DG) [de

  14. Report of results and of research and development work at the Institute of Technical Physics 1991

    International Nuclear Information System (INIS)

    1992-03-01

    The central areas of work are superconductivity and its applications, cryo-technology and microwave technology. The main point of technical development is the construction of magnets for the nuclear fusion project NET/ITER. Basic investigations concern low temperature and superconductor materials such as YBa 2 Cu 3 O 7-x single crystals. (DG) [de

  15. 76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

    Science.gov (United States)

    2011-04-14

    ... mandatory deposit requirements of the copyright law. The objective is to identify file submission, packaging... mandatory deposit provisions of the copyright law. Under the interim regulation, certain works available... LIBRARY OF CONGRESS Copyright Office [Docket No. 2011-3] Notice of Public Meeting: Technical...

  16. Academic & Technical Skills + Life/Work Skills + Career Information & Guidance = Success in Career Building.

    Science.gov (United States)

    Jarvis, Phillip S.

    There has been a renaissance in the thinking about career development. It is becoming accepted that information is not enough; in addition to academic and technical skills, youth and adults need to learn life/work designing and building skills to become healthy, productive, and self-reliant citizens. Despite the fact that Canadian students have…

  17. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nakajima, J.; Suezono, N.; Higuchi, T. [Toshiba Corp., Isogo Nuclear Engineering Center, Isogo-ku, Yokohama (Japan); Katayama, H. [Toshiba Corp., Power and Industrial Systems Research and Development Center, Isogo-ku, Yokohama (Japan)

    2014-07-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (author)

  18. Establishment of the technical basis to apply the viscous damper in nuclear power plant

    International Nuclear Information System (INIS)

    Nakajima, J.; Suezono, N.; Higuchi, T.; Katayama, H.

    2014-01-01

    In recent years, the technical development of the damper using viscous fluid (hereinafter called 'the viscous damper') for the structures, bridges and components in the general industrial field is remarkable, and the experiences of the application to mitigate influence in an earthquake is being gathered now. In this paper, purpose of the whole activity, schedule, the research and test results carried out so far, and future plan to establish the technical basis to apply the viscous damper in nuclear power plant are reported. (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 requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

  1. THE TECHNICAL AND ETHNICAL DIVISION OF WORK, THE INDIGEOUS GROUPS AND THE FAMILY BUSINESSES

    OpenAIRE

    Gloria A. Miranda-Zambrano; Ricardo Contreras-Soto; Alejandra López-Salazar

    2013-01-01

    The work exposes some forms of indigenous groups participation on entrepreneurial family businesses, mainly in the region of Laja - Bajío where the family plays an important role in these organizations. The work point out the approach on technical ethnic division of labour to locate such actors in labour circuits, in economic activities or guilds that have been built in various social processes. To analyze the ways in which they operate, the role of the family, their knowledge (cultural capit...

  2. Study on the improvement of working environment at night in maintenance works at nuclear power plants

    International Nuclear Information System (INIS)

    Hiramoto, Mitsuru; Kotani, Fumio

    2000-01-01

    At the maintenance work site in nuclear power plants, due to the shortening (reduction of a regular inspection period) of the regular inspection period, the tendency toward working on around-the-clock basis has increased; thus, nighttime work is on the rise. Based upon research both locally and internationally, as well as examples of measures against such a tendency and the results of on-site surveys of the environment surrounding maintenance works at nuclear power plants, the author comprehensively studied the effects of nighttime work on workers, the measures to cope with the situation, and how a working environment for nighttime work should be. Based on the results, the authors made a guidebook for nighttime maintenance work at nuclear power plants. This guidebook, which deals with the subject of nighttime maintenance work at nuclear power plants, is quite unique in the world. It is expected that by using this guidebook, the quality of nighttime maintenance work and the levels of techniques/skills would be enhanced and maintained, and the safety of workers would be ensured, promoting considerably thus the establishment of a comfortable workplace. (author)

  3. Study on the improvement of working environment at night in maintenance works at nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hiramoto, Mitsuru; Kotani, Fumio [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

    2000-09-01

    At the maintenance work site in nuclear power plants, due to the shortening (reduction of a regular inspection period) of the regular inspection period, the tendency toward working on around-the-clock basis has increased; thus, nighttime work is on the rise. Based upon research both locally and internationally, as well as examples of measures against such a tendency and the results of on-site surveys of the environment surrounding maintenance works at nuclear power plants, the author comprehensively studied the effects of nighttime work on workers, the measures to cope with the situation, and how a working environment for nighttime work should be. Based on the results, the authors made a guidebook for nighttime maintenance work at nuclear power plants. This guidebook, which deals with the subject of nighttime maintenance work at nuclear power plants, is quite unique in the world. It is expected that by using this guidebook, the quality of nighttime maintenance work and the levels of techniques/skills would be enhanced and maintained, and the safety of workers would be ensured, promoting considerably thus the establishment of a comfortable workplace. (author)

  4. Technical Feasibility Study of Thermal Energy Storage Integration into the Conventional Power Plant Cycle

    Directory of Open Access Journals (Sweden)

    Jacek D. Wojcik

    2017-02-01

    Full Text Available The current load balance in the grid is managed mainly through peaking fossil-fuelled power plants that respond passively to the load changes. Intermittency, which comes from renewable energy sources, imposes additional requirements for even more flexible and faster responses from conventional power plants. A major challenge is to keep conventional generation running closest to the design condition with higher load factors and to avoid switching off periods if possible. Thermal energy storage (TES integration into the power plant process cycle is considered as a possible solution for this issue. In this article, a technical feasibility study of TES integration into a 375-MW subcritical oil-fired conventional power plant is presented. Retrofitting is considered in order to avoid major changes in the power plant process cycle. The concept is tested based on the complete power plant model implemented in the ProTRAX software environment. Steam and water parameters are assessed for different TES integration scenarios as a function of the plant load level. The best candidate points for heat extraction in the TES charging and discharging processes are evaluated. The results demonstrate that the integration of TES with power plant cycle is feasible and provide a provisional guidance for the design of the TES system that will result in the minimal influence on the power plant cycle.

  5. Some considerations on the development of individual work plan for teachers of Technical and Vocational Education

    Directory of Open Access Journals (Sweden)

    Carlos Alberto Gato Armas

    2010-03-01

    Full Text Available This article analyzes, from the optics of upgrading Technical and Professional Education chief staff in the province and professors in the Technical Sciences Faculty in the University of Pedagogical Sciencies “Rafael María of Mendive” in Pinar del Río, which can facilitate the elaboration of the plan for teachers’ individual work, so that it facilitates the assessment and performance of the planned activities, and at the same time, propitiating the professional development of the teachers, in each school term.

  6. New handling systems as technical support for the working process. Part 6. Feeding devices

    Energy Technology Data Exchange (ETDEWEB)

    Becher, H; Burkhardt, R; Drexel, P; Graf, B; Krreis, W

    1982-03-01

    Social, technical and economic reasons require an enhanced application of handling systems such as industrial robots. Quality and efficiency of an industrial robot depends greatly on feeding devices, and the ARGE-HHS within its project new handling systems as a technical aid in the working process intends to analyze all feeding devices that are likely to be most suitable for advanced applications. Forty one feeding devices were developed, known devices were modified, adapted to different applications, and tested. A variety of feeding devices for most applications in the field of material handling is reported.

  7. AVLIS Production Plant work breakdown structure and Dictionary

    International Nuclear Information System (INIS)

    1984-01-01

    The work breakdown structure has been prepared for the AVLIS Production Plant to define, organize, and identify the work efforts and is summarized in Fig. 1-1 for the top three project levels. The work breakdown structure itself is intended to be the primary organizational tool of the AVLIS Production Plant and is consistent with the overall AVLIS Program Work Breakdown Structure. It is designed to provide a framework for definition and accounting of all of the elements that are required for the eventual design, procurement, and construction of the AVLIS Production Plant. During the present phase of the AVLIS Project, the conceptual engineering phase, the work breakdown structure is intended to be the master structure and project organizer of documents, designs, and cost estimates. As the master project organizer, the key role of the work breakdown structure is to provide the mechanism for developing completeness in AVLIS cost estimates and design development of all hardware and systems. The work breakdown structure provides the framework for tracking, on a one-to-one basis, the component design criteria, systems requirements, design concepts, design drawings, performance projections, and conceptual cost estimates. It also serves as a vehicle for contract reporting. 12 figures, 2 tables

  8. CERN Technical Training 2002: Learning for the LHC! CLEAN-2002: WORKING IN A CLEAN ROOM

    CERN Multimedia

    Davide Vitè

    2002-01-01

    CLEAN-2002 is a new, free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific problems put forward beforehand by attendees will also be addressed. If you are interested in CLEAN-2002, please discuss with your supervisor or your DTO. More information and online registration by EDH are available from the Technical Training pages. The next session, in English, will be on 10 October (afternoon). Other sessions, in French and English, will be offered following demand: the first session in French will be organised in November. Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch

  9. Safety technical considerations on the 2012 periodic safety verification of the Beznau nuclear power plant

    International Nuclear Information System (INIS)

    2016-12-01

    of the examination of the defects discovered during the revision shutdown in 2015 concerning the material of the reactor pressure vessel of block 1. As far as the NOK’s request for an unlimited operational license is concerned, NOK has to prove in time, before the 40-year license limit is up, that the design boundaries of safety-relevant components will not be reached during the duration of extended operation. Otherwise, the necessary refit works have to be performed in time. KKB has produced the requested proof for the long-term operation of both blocks. The results of the supervisory work carried out by the Swiss Federal Nuclear Safety Inspectorate (ENSI) were published in the safety technical review for KKB1 and KKB2. ENSI concludes that there are no safety technical objections against the operation of both blocks beyond the limit of 40 years. On the basis of the state of knowledge when the considerations were made, the criteria for shutting down will not be reached in the 10 following operational years, neither by KKB1 nor by KKB2

  10. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  11. 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

  12. Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-07-01

    At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989

  13. Gas-cooled reactor technology safety and siting. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1990-01-01

    At the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGRs to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: the diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors; the Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan (The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period.); disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany (These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Juelich, Germany, was also shutdown at the end of 1988.); the continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750 deg. C to 950 deg. C; the continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power; the combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989

  14. Application and development of probabilistic safety assessment for nuclear power plant operations. Report of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The Technical Committee Meeting on Procedures for Use of PSA for Optimizing Operational Limits and Conditions for Nuclear Power Plants was held in Barcelona from 20 to 23 September 1993 to serve as a forum for discussion of the development of methods and approaches for PSA applications. The meeting was co-sponsored by the IAEA and the Asco and Vandellos nuclear power plants in Spain and was attended by more than 85 participants from 23 countries. The 35 papers and presentations reflected the extent of activities in this area worldwide. Most of the papers discuss PSA application programmes and/or specific methods and approaches used. This TECDOC, which was prepared by the participants of the Technical Committee meeting, summarizes the insights gained from the papers and plenary discussions. It also presents the conclusions of the work of three working groups which discussed the advantages and limitations of specific aspects of PSA. It provides an up-to-date description of computerized tools for risk monitoring in used or under development in Member States. It is hoped that this report will be a useful source of information on PSA applications. Refs, figs, tabs.

  15. A technical learning on the Pressurized Water Nuclear Power Plants using animation

    International Nuclear Information System (INIS)

    Ito, Hajime; Tomohara, Yasutaka; Kubo, Setsuo; Ninomiya, Toshiaki

    2002-01-01

    The pressurized water nuclear power generation plants tends to reduce construction of its new plant from viewpoints of recent stabilization in power demand/supply balance, development of new siting points, and so on. And, together with reducing any opportunity to experience at site, generation alternation to younger engineers without such experiences is progressing. In order to carry out technical tradition with high quality , as it is important to understand experiences of troubles and so on as valuable inheritance to apply them to actual use, it can be thought, in doubt, to be one of solving measures to prepare some learning tools applying the newest technology. The Kansai Electric Co., Ltd. Developed a CAD software using animation and 3D pictures using a personal computer which is edited some processes of technical transition on nuclear energy as a reference on a shape of CD ROM as an object from initial period of nuclear power station to present APWR. (G.K.)

  16. Technical dictionary power plant engineering. Vol. 1. 4. rev. and enlarged ed.

    International Nuclear Information System (INIS)

    1987-01-01

    This dictionary is a compilation of German and English technical terms of power plant engineering as far as power plants, turbine-generators and assembly engineering are concerned. It is the result of a joint effort by the Kraftwerk Union AG (KWU) and Utility Power Corp. (UPC). The entire content has been revised and approx. 6000 new terms have been added. The dictionary is meant to form a basis for uniform terminology on technical documents as well as correspondence between KWU, UPC and licensees. This computer aided dictionary is printed in capital/low case letters. Only nouns, terms with an article and proper names are capitalized in German. Some terms are written differently in American and British English and are marked with (US) or (GB). (orig./HP) [de

  17. Nuclear power plant shift technical advisor. Recommendations for position description, qualifications, education and training

    International Nuclear Information System (INIS)

    1981-01-01

    The purpose of this document is to describe the position and identify specific areas of formal education, plant-specific training and experience necessary to assure an advanced level of analytical ability on shift. These recommendations will provide a level of technical ability that is essential to improved operational safety and are consistent with regulatory requirements. This position was developed in conjunction with representatives of utilities, equipment vendors and engineering educators, giving consideration to specific contributions the function must make to shift operations

  18. Application of data-processing to the technical and economical management of the plants of Simo

    International Nuclear Information System (INIS)

    Chastagner, F.

    1988-01-01

    The firm Simo is entrusted with the processing of the uranium ores extracted from the mines of Cogema in France, in its three plants. The paper describes the conception and the functioning of the information system. Among the advantages contributed by the system, the coherence between the technical follow-up and the economical follow-up constitutes one of the principal progressive features [fr

  19. 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

  20. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, M; Carl, H; Nowak, K [Technischer Ueberwachungsverein Rheinland, Koeln (Germany). Inst. for Nuclear Engineering and Radiation Protection; Schumann, P; Seidel, A; Weiss, F P; Zschau, J

    1998-10-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  1. A technical system to improve the operational monitoring of the Zaporozhye nuclear power plant

    International Nuclear Information System (INIS)

    Beyer, M.; Carl, H.; Nowak, K.; Schumann, P.; Seidel, A.; Weiss, F.P.; Zschau, J.

    1998-01-01

    As part of the programme implemented by the German Ministry of Environment, Nature Conservation and Reactor Safety to cooperate with the Central and Eastern European States (CEES) and the Commonwealth of Independent States (CIS) in the area of nuclear safety, a technical system to improve operational monitoring has been designed, specified and established since 1992 as a pilot project in the Zaporozhye/Ukraine nuclear power plant by Forschungszentrum Rossendorf and Technischer Ueberwachungsverein Rheinland with a significant contribution from the State Scientific and Technical Centre of the Ukrainian supervisory authority. The technical system complements existing operational checking and monitoring facilities by including modern means of information technology. It enables a continuous monitoring of the state of unit 5 in normal operation and in cases of anomalies or incidents so that when recognisable deviations from the regular plant operation occur, the Ukrainian supervisory authority can immediately inquire and if necessary impose conditions on the operator. The radiological and meteorological parameters at the nuclear power plant location are monitored to the extent necessary to assess the current radiation situation and to implement efficient emergency management measures. (orig.)

  2. The working lifetime of nuclear power plants and new types of power reactors

    International Nuclear Information System (INIS)

    Bataille, Ch.; Birraux, C.

    2003-01-01

    The report on the working lifetime of nuclear power plants and new reactor types, by Mr Christian Bataille, deputy for the Nord, and Mr Claude Birraux, deputy for Haute-Savoie as well as President of the Office, supplements the studies carried out by the Parliamentary Office on the Safety of Nuclear Installations and Radioactive Wastes: it examines the remaining working life of the EDF nuclear power plants and the current status of projects that might, if circumstances were right, replace the reactors at present in service. The report investigates the different physical and other factors that influence the ageing of nuclear power plants and tackles the question of whether the design life of 40 years could be exceeded in practice. The whole issue of French nuclear power plant is put in perspective and compared with the situation of nuclear plants in Finland, Sweden, Germany and the United States, from the technical and regulatory standpoints. Believing that any attempt to optimise the working lifetime of the power plants currently in service must be accompanied by simultaneous moves aimed at their replacement, Messrs. Christian Bataille and Claude Birraux go on to review in detail the various light water reactor projects being proposed around the world for completion by 2015, as developments of existing models, in particular the EPR reactor of Framatome ANP, characterised by its competitiveness. They suggest that a first such reactor should be built as quickly as possible. Describing the other nuclear systems being investigated by research organisations not only in France but also in the United States and Sweden, Mrs. Christian Bataille and Claude Birraux review the objectives of these and the circumstances in which they might be developed, which would be unlikely to be before 2035 in view of the technological problems to be overcome and the industrial demonstration plants that would be needed

  3. The Nuclear Smuggling International Technical Working Group: Making a difference in combating illicit trafficking

    International Nuclear Information System (INIS)

    Niemeyer, S.; Koch, L.

    2002-01-01

    Full text: The ITWG was first formed in 1995 for the purpose of fostering international cooperation for combating illicit trafficking of nuclear materials. The initial focus for the ITWG was on the development of nuclear forensics to help answer attribution questions regarding nuclear materials of unknown origin. More recently, the ITWG has also expanded its focus to include detection of nuclear materials during transit. This paper presents some of the key developments by this group and their potential impact for combating nuclear smuggling. The initial focus of the ITWG was to write a status report on international cooperation on nuclear smuggling forensic analysis. This 26-page report summarized previous work on nuclear forensics and gave an initial analysis on prioritizing techniques and methods for forensic analysis regarding source and route attribution. This report was submitted to the G-8 countries, and shortly thereafter, nuclear forensics was endorsed at the Moscow Summit in April, 1996, as part of an illicit trafficking program. The work of the ITWG has also been noted at subsequent summit declarations, e.g. Cologne. The ITWG's primary goal is to develop a preferred approach to nuclear forensic investigations that is widely understood and accepted as credible. The technical elements include: 1) development of protocols for a) collection and preservation of evidence and b) for laboratory investigation, 2) prioritizing of techniques for forensic analysis, 3) development of forensic databanks to assist in interpretation, 4) executing inter-laboratory exercises, and 5) facilitating technical assistance to countries upon request. The development of protocols has been conducted jointly by law enforcement officials and laboratory scientists. A major focus during much of the past six years has been the development of a model action plan for nuclear forensics. This action plan lays out the elements that are needed in the instance that illicit nuclear material is

  4. Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Rubiolo, Pablo R. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Conway, Lawarence E. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Oriani, Luca [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Lahoda, Edward J. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; DeSilva, Greg [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Science and Technology Dept.; Hu, Min H. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Hartz, Josh [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Bachrach, Uriel [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Smith, Larry [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Dudek, Daniel F. [Westinghouse Electric Company LLC, Pittsburgh, PA (United States). Nuclear Services Division; Toman, Gary J. [Electric Power Research Inst. (EPRI), Palo Alto, CA (United States); Feng, Dandong [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Hejzlar, Pavel [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Kazimi, Mujid S. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

    2006-03-31

    This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a standard 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (~600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output.

  5. Advanced Power Ultra-Uprates of Existing Plants (APPU) Final Scientific/Technical Report

    International Nuclear Information System (INIS)

    Rubiolo, Pablo R.; Conway, Lawarence E.; Oriani, Luca; Lahoda, Edward J.; DeSilva, Greg; Hu, Min H.; Hartz, Josh; Bachrach, Uriel; Smith, Larry; Dudek, Daniel F.; Toman, Gary J.; Feng, Dandong; Hejzlar, Pavel; Kazimi, Mujid S.

    2006-01-01

    This project assessed the feasibility of a Power Ultra-Uprate on an existing nuclear plant. The study determined the technical and design limitations of the current components, both inside and outside the containment. Based on the identified plant bottlenecks, the design changes for major pieces of equipment required to meet the Power Ultra-Uprate throughput were determined. Costs for modified pieces of equipment and for change-out and disposal of the replaced equipment were evaluated. These costs were then used to develop capital, fuel and operating and maintenance cost estimates for the Power Ultra-Uprate plant. The cost evaluation indicates that the largest cost components are the replacement of power (during the outage required for the uprate) and the new fuel loading. Based on these results, the study concluded that, for a ''standard'' 4-loop plant, the proposed Power Ultra-Uprate is technically feasible. However, the power uprate is likely to be more expensive than the cost (per Kw electric installed) of a new plant when large capacity uprates are considered (>25%). Nevertheless, the concept of the Power Ultra-Uprate may be an attractive option for specific nuclear power plants where a large margin exists in the steam and power conversion system or where medium power increases (∼600 MWe) are needed. The results of the study suggest that development efforts on fuel technologies for current nuclear power plants should be oriented towards improving the fuel performance (fretting-wear, corrosion, uranium load, manufacturing, safety) required to achieve higher burnup rather focusing on potential increases in the fuel thermal output

  6. Conceptual design of small-sized HTGR system (4). Plant design and technical feasibility

    International Nuclear Information System (INIS)

    Ohashi, Hirofumi; Sato, Hiroyuki; Yan, Xing L.; Sumita, Junya; Nomoto, Yasunobu; Tazawa, Yujiro; Noguchi, Hiroki; Imai, Yoshiyuki; Tachibana, Yukio

    2013-09-01

    Japan Atomic Energy Agency (JAEA) has started a conceptual design of a 50MWt small-sized high temperature gas cooled reactor (HTGR) for steam supply and electricity generation (HTR50S), which is a first-of-kind of the commercial plant or a demonstration plant of a small-sized HTGR system for steam supply to the industries and district heating and electricity generation by a steam turbine, to deploy in developing countries in the 2020s. HTR50S was designed for steam supply and electricity generation by the steam turbine with the reactor outlet temperature of 750degC as a reference plant configuration. On the other hand, the intermediate heat exchanger (IHX) will be installed in the primary loop to demonstrate the electricity generation by the helium gas turbine and hydrogen production by thermochemical water splitting by utilizing the secondary helium loop with the reactor outlet temperature of 900degC as a future plant configuration. The plant design of HTR50S for the steam supply and electricity generation was performed based on the plant specification and the requirements for each system taking into account for the increase of the reactor outlet coolant temperature from 750degC to 900degC and the installation of IHX. The technical feasibility of HTR50S was confirmed because the designed systems (i.e., reactor internal components, reactor pressure vessel, vessel cooling system, shutdown cooling system, steam generator (SG), gas circulator, SG isolation and drainage system, reactor containment vessel, steam turbine and heat supply system) satisfies the design requirements. The conceptual plant layout was also determined. This paper provides the summary of the plan design and technical feasibility of HTR50S. (author)

  7. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Bouget, Y.H.

    1994-01-01

    The seminar discussed the objectives, organization and scope of work of the Central and Site Technical Service Department in support of operating NPP; transfer of capability to establish and maintain an efficient operation support; defined the responsibilities and interface between on site and Central Technical Staff

  8. Facilitating computer supported cooperative work with socio-technical self-descriptions

    OpenAIRE

    Kunau, Gabriele

    2006-01-01

    How can the concept of self-description from newer systems theory be used for improving the co-evolvement of software engineering and organizational change in CSCW-projects? This thesis suggests transferring the concept of self-description into a concept of socio-technical self-description allowing an organization to describe its own computer supported work processes. The presentation of results is organized in four steps: First, a theoretical foundation is elaborated; second, an initial meth...

  9. International Economic Association on organization of co-operative production and development of equipment and providing technical assistance in construction of nuclear power plants - ''INTERATOMENERGO''

    International Nuclear Information System (INIS)

    Mal'tsev, N.D.

    1979-01-01

    History is stated of foundation of the International Economic Association ''Interatomenergo''. Structure is given of the Association and the list of main problems to be solved by it. Project is given of the programm of co-operation in the field of scientific and technical works as well as of design and projecting works in creation of new types of equipment for nuclear power plants, in particular, creation of serial power units with improved WWER-1000 reactor. Directions are stated of activity of the Association in the field of providing assistance in construction and exploitation of nuclear power plants as well as in training of operational personnel [ru

  10. Technical analysis of advanced wastewater-treatment systems for coal-gasification plants

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-31

    This analysis of advanced wastewater treatment systems for coal gasification plants highlights the three coal gasification demonstration plants proposed by the US Department of Energy: The Memphis Light, Gas and Water Division Industrial Fuel Gas Demonstration Plant, the Illinois Coal Gasification Group Pipeline Gas Demonstration Plant, and the CONOCO Pipeline Gas Demonstration Plant. Technical risks exist for coal gasification wastewater treatment systems, in general, and for the three DOE demonstration plants (as designed), in particular, because of key data gaps. The quantities and compositions of coal gasification wastewaters are not well known; the treatability of coal gasification wastewaters by various technologies has not been adequately studied; the dynamic interactions of sequential wastewater treatment processes and upstream wastewater sources has not been tested at demonstration scale. This report identifies key data gaps and recommends that demonstration-size and commercial-size plants be used for coal gasification wastewater treatment data base development. While certain advanced treatment technologies can benefit from additional bench-scale studies, bench-scale and pilot plant scale operations are not representative of commercial-size facility operation. It is recommended that coal gasification demonstration plants, and other commercial-size facilities that generate similar wastewaters, be used to test advanced wastewater treatment technologies during operation by using sidestreams or collected wastewater samples in addition to the plant's own primary treatment system. Advanced wastewater treatment processes are needed to degrade refractory organics and to concentrate and remove dissolved solids to allow for wastewater reuse. Further study of reverse osmosis, evaporation, electrodialysis, ozonation, activated carbon, and ultrafiltration should take place at bench-scale.

  11. 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)

  12. Restructuring of technical standards for regulation of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takehiko Nakamura; Masahiro Aoki; Kiyoshi Takasaka; Yukio Hirano; Eiji Hiraoka; Mikio Kurihara; Junichi Morita; Zenichi Ogiso; Yoshihiko Nishiwaki

    2005-01-01

    Regulatory requirements for nuclear power plants (NPPs) have been reviewed and restructured in Japan, in order to accommodate recent technical progress in a timely manner. In this new regulatory process, the governmental technical requirements are modified to performance specifications and the consensus codes and standards established by academic and public societies are being used as prescriptive specifications to realize the performance. As a first step, a fitness-rule to evaluate structural integrity of the components having cracks was introduced into the Japanese regulatory rules in Oct. 2003. 'Rules on Fitness-for-Service for Nuclear Power Plants' by the Japan Society of Mechanical Engineers (JSME) was utilized as a prescriptive specification for in-service-inspections and for the integrity evaluation of the components with stress corrosion cracks and fatigue cracks. The process is being extended to other requirements for structural design and construction of mechanical components and concrete containments, as well as requirements for welding. Prescriptive specifications for the requirements by the JSME and other consensus codes have been technically reviewed by a regulatory body, the Nuclear and Industrial Safety Agency, and specified as regulatory standards for the licensing procedure. In the course of the review, consistency and coverage of the requirements were examined against the Safety Design Guidelines by the Nuclear Safety Commission and the safety requirements for design of nuclear power plant by the International Atomic Energy Agency, NS-R-1. Additional requirements against the stress corrosion cracking, hydrogen accumulation, high-cycle thermal fatigue, etc. are being specified in the requirements to prevent troubles experienced in NPPs in Japan and overseas. This paper describes outlines of the on-going activities restructuring the technical standards for regulation of NPPs in Japan. (authors)

  13. Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Working Material

    International Nuclear Information System (INIS)

    2012-01-01

    The overall purpose of the Technical Meeting was to recognize and analyse the implications of the accident occurred at the Fukushima Dai-ichi Nuclear Power Station on current and future fast neutron systems design and operation. The aim was to provide a global forum for discussing the principal lessons learned from this event, and thus to review safety principles and characteristics of existing and future fast neutron concepts, especially in relation with extreme natural events which potentially may lead to severe accident scenarios. The participants also presented and discussed innovative technical solutions, design features and countermeasures for design extension conditions - including earthquakes, tsunami and other extreme natural hazards - which can enhance the safety level of existing and future fast neutron systems. Furthermore, the meeting gave the opportunity to present advanced methods for the evaluation of the robustness of plants against design extension conditions. Another important goal of this TM was to discuss how to harmonize safety approaches and goals for next generation’s fast reactors. Finally, the meeting was intended to identify areas where further research and development in nuclear safety, technology and engineering in the light of the Fukushima accident are needed. In the frame of the implementation of its Nuclear Safety Action Plan endorsed by all Member States, the IAEA will consider these areas as potential technical topics for new Coordinated Research Projects, to be launched in the near future

  14. Technical Meeting on Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    2015-01-01

    A major focus of the design of modern fast reactor systems is on inherent and passive safety. Specific systems to improve reactor safety performance during accidental transients have been developed in nearly all fast reactor programs, and a large number of proposed systems have reached various stages of maturity. This Technical Meeting on Passive Shutdown Systems for Fast Reactors, which was recommended by the Technical Working Group on Fast Reactors (TWG-FR), addressed Member States’ expressed need for information exchange on projects and programs in the field, as well as for the identification of priorities based on the analysis of technology gaps to be covered through R&D activities. This meeting was limited to shutdown systems only, and did not include other passive features such as natural circulation decay heat removal systems etc.; however the meeting catered to passive shutdown safety devices applicable to all types of fast neutron systems. It was agreed to initiate a new study and produce a Nuclear Energy Series (NES) Technical Report to collect information about the existing operational systems as well as innovative concepts under development. This will be a useful source for member states interested in gaining technical expertise to develop passive shutdown systems as well as to highlight the importance and development in this area

  15. Public service electric and gas company technical supervisory skills programs for nuclear power plant personnel

    International Nuclear Information System (INIS)

    Meredith, J.B.

    1985-01-01

    A series of training programs entitled Technical Supervisory Skills Programs for management personnel are described. The first level of this program, TSSP-1, is a seven week program designed for first-line supervisors and other selected management personnel responsible for directing the work forces in the stations. TSSP-1 includes training in PWR/BWR Technology, Supervision, Aberrant Behavior Identification, Labor Relations and Ethics, Technical Administration, Quality Assurance Program, On-the-job Training, and Specific Departmental Training. TSSP-2, TSSP-3, and TSSP-4 courses are described in this paper

  16. Method for assessment of the technical potential of the plant agricultural waste suitable for energy purposes in Bulgaria

    International Nuclear Information System (INIS)

    Georgiev, V.

    2004-01-01

    A method for assessment of technical potential of quantitatively important plant agriculture waste; straw from wheat and barley; corn stalks; sunflower stalks and heads; tobacco stalks; orchard prunings and vineyard prunings suitable for energy purposes for Bulgarian conditions is developed. Data for assessment of the technical potential for 2002 using this method are presented. A comparison between technical potential of mentioned wastes, final energy consumption in agriculture and all branches of Bulgarian economy for 2002 is made. (author)

  17. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, Garth M. [Bechtel National Inc., 2435 Stevens Center Place, Richland, Washington, 99352 (United States); Saunders, Scott A. [Washington River Protection Solutions, P.O. Box 850, Richland, Washington, 99352 (United States)

    2013-07-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  18. Improved Management of the Technical Interfaces Between the Hanford Tank Farm Operator and the Hanford Waste Treatment Plant - 13383

    International Nuclear Information System (INIS)

    Duncan, Garth M.; Saunders, Scott A.

    2013-01-01

    The Department of Energy (DOE) is constructing the Waste Treatment and Immobilization Plant (WTP) at the Hanford site in Washington to treat and immobilize approximately 114 million gallons of high level radioactive waste (after all retrievals are accomplished). In order for the WTP to be designed and operated successfully, close coordination between the WTP engineering, procurement, and construction contractor, Bechtel National, Inc. and the tank farms operating contractor (TOC), Washington River Protection Solutions, LLC, is necessary. To develop optimal solutions for DOE and for the treatment of the waste, it is important to deal with the fact that two different prime contractors, with somewhat differing contracts, are tasked with retrieving and delivering the waste and for treating and immobilizing that waste. The WTP and the TOC have over the years cooperated to manage the technical interface. To manage what is becoming a much more complicated interface as the WTP design progresses and new technical issues have been identified, an organizational change was made by WTP and TOC in November of 2011. This organizational change created a co-located integrated project team (IPT) to deal with mutual and interface issues. The Technical Organization within the One System IPT includes employees from both TOC and WTP. This team has worked on a variety of technical issues of mutual interest and concern. Technical issues currently being addressed include: - The waste acceptance criteria; - Waste feed delivery and the associated data quality objectives (DQO); - Evaluation of the effects of performing a riser cut on a single shell tank on WTP operations; - The disposition of secondary waste from both TOC and WTP; - The close coordination of the TOC double shell tank mixing and sampling program and the Large Scale Integrated Test (LSIT) program for pulse jet mixers at WTP along with the associated responses to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation

  19. Direction of the methodological work in the Technical and Professional Education: the department bosses' preparation

    Directory of Open Access Journals (Sweden)

    Rolando Rodríguez Delgado

    2017-09-01

    Full Text Available The present work deals with the process of preparation of the heads of teaching departments for the direction of methodological work in Technical and Professional Education with the purpose of improving their professional performance with the collective of teachers and specialists in the continuous training of the worker. The results of the diagnosis made on this process revealed shortcomings because it is unsystematic and poorly contextualized, which does not allow to achieve a positive impact on the training of subordinates and students to join the world of work. For the development of the work we used the structural systemic methods, analysis and synthesis, induction and deduction, survey, interview, observation and statistical techniques such as percentage calculation, tables of frequencies and contingencies, which allowed to deepen the object of study and to elaborate a strategy of preparation for the heads of department like main result that is presented in this work. In order to verify the practical effectiveness of the proposed strategy, 12 heads of teaching departments of the polytechnic centers of the municipality of La Palma for the academic year 2014-2015 were studied and 5 managers, 69 teachers and 18 specialists of production and services. The evaluation of the results evidences advances in the preparation of the heads of departments and in their professional performance with teachers and specialist, according to the current requirements of the technical and professional continuing education of the worker in formation.

  20. Results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal

    International Nuclear Information System (INIS)

    Galkin, A.V.; Baldov, A.N.

    2001-01-01

    In the paper the results of technical and economical examinations for substantiation of special plant design for reprocessing and radioactive wastes disposal are presented. Ground for the examination conducting was Health of Nation Programme ratified by the President and a number of Governmental decisions. The special plant is planned in the Mangystau Region. In the framework of feasibility study the data base by the worldwide known technologies was implemented, on reprocessing and experience of radioactive waste disposal. The technical requirements for the special plant construction are determined. The alternative options by structure content and site location of the special plant and radioactive waste disposal are cited

  1. Technical evaluation of RETS-required reports for the Edwin I. Hatch Nuclear Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Young, T.E.; Magleby, E.H.

    1985-01-01

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Edwin I. Hatch Nuclear Plant were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 7 refs

  2. Radiation protection aspects of the repair work at Paks Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bujtas, T.; Nenyei, A.

    2006-01-01

    On the Unit 2 at Paks Nuclear Power Plant accident occurred on 10th April 2003. Thirty fuel assemblies damaged in the cleaning tank installed in the Pit No. 1. Due to the accident casing of the fuel elements and uranium-dioxide pellets inside them damaged. The scratched fuel assemblies and nuclear fuel fragments should be removed and safely deposited. In order to restore the operational condition of the Pit No. 1 a lot of complicated activities with radiation hazard should be implemented. These tasks bring up both technical difficulties and serious radiation protection problems, and it is essential to resolve them in order to reduce radiation exposure of the working personnel and to minimize the amount of off-site radioactive releases.There was a serious incident (An INES level 3 event) at Paks Nuclear Power plant in april 10, 2003. (TRA)

  3. THE CONCEPTION OF NURSING WORK BY STUDENTES AND TEACHERS FROM A TECHNICAL COURSE

    Directory of Open Access Journals (Sweden)

    Amailson Sandro Barros

    2016-12-01

    Full Text Available This article aims at presenting the conception of work envisioned by students and teachers from a technical course on nursing. For that end, we interviewed 12 students and 03 teachers from the course. The data was collected through structured interviews. The data obtained pointed to a concept of work relied on pleasure and satisfaction for caring, as well as source of remuneration, which is related to the ideological background perpetuated that associates nursing to dedication, obedience and material detachment. The speech of the participants disregards the shock between capital and labor and the social construction and historical exploitation of the workforce, keeping strongly the dogma of charity in the field of nursing. The reports pointed to the dual character of the work which comprises the abstract and concrete conceptions, leading to a division between intellectual labor versus manual work and precarization of labor in nursing and teaching.

  4. New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR plants

    International Nuclear Information System (INIS)

    Hirai, Junya; Nakamura, Takao; Amano, Yoichi

    2013-01-01

    Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

  5. Manpower development for safe operation of nuclear power plant. China. Seminar on the technical support functions. Activity: 6.1.1-Task-03. Technical report

    International Nuclear Information System (INIS)

    Kofron, K.L.

    1994-01-01

    The seminar was held in Wuhan PRC from 01.10/94 - 01/14/94. It revolved about the role of the Technical Support Groups, both onsite and offsite, of the Nuclear Power Plant. This was to assist the Chinese in deciding their best course of action for the establishment and operation of this group

  6. Status of project design work for a German reprocessing plant

    International Nuclear Information System (INIS)

    Lang, K.; Zuehlke, P.

    1976-01-01

    A reprocessing plant will be built within the framework of a comprehensive waste management center planned by the Federal Government to treat the fuel elements unloaded from German nuclear power stations. On the basis of an annual throughput of 1,400 te of uranium averaged over the life of the plant, the center will be able to serve between 45,000 and 50,000 MWe of installed nuclear generating capacity. A comprehensive conceptual design study of the reprocessing plant to be built has been completed on the basis of the operating experience accumulated at the Karlsruhe reprocessing plant and the development work carried out by the Karlsruhe Nuclear Research Center and in the light also of an intensive exchange of experience with British and French reprocessing companies within the framework of United Reprocessors GmbH. This conceptual design study is the foundation for the preliminary project to be carried out on a collaborative basis by KEWA and PWK. (orig.) [de

  7. Technical considerations in repowering a nuclear plant for fossil fueled operation

    International Nuclear Information System (INIS)

    Patti, F.J.

    1996-01-01

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today's world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal

  8. Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (39th annual meeting). Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The 39th Annual Meeting of the Technical Working Group on Fast Reactors (TWG FR) was held from 15-19 May 2006 in Beijing, China, at the invitation of the China Institute of Atomic Energy (CIAEA). The meeting was attended by TWG-FR Members and Advisers from the following Member States (MS): Belgium (observer), Brazil, China, France, Germany, India, Italy, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, Sweden (observer), the United Kingdom, and the United States. Belarus, Switzerland, the European Commission, and OECD/NEA were unable to participate. Moreover, Prof. Carlo Rubbia, CERN director general emeritus, participated, upon IAEA invitation, in the meeting as distinguished scientist and IAEA expert. Mr. S.C. Chetal, from India (Indira Gandhi Centre for Atomic Research, IGCAR), was appointed chairman. The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 38th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2006 and 2007; - Reviewed the Agency's ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as co-ordination of the TWG-FR's activities with other organizations; - Discuss future joint activities in view of the Agency's Programme and Budget Cycle 2008-2009 (and beyond)

  9. Technical Training Programme: Learning for the LHC ! CLEAN-2002: WORKING IN A CLEANROOM

    CERN Multimedia

    Davide Vitè

    2002-01-01

    CLEAN-2002 is a new, free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific problems put forward beforehand by attendees will also be addressed. More information and registration through EDH is available HERE The next session, in English, will be on 24 April (afternoon). Other sessions, in French and English, will be offered following demand: the first session in French will be organised in May or June. Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch

  10. CERN Technical Training Programme: Learning for the LHC ! CLEAN-2002: Working in a Cleanroom

    CERN Multimedia

    Davide Vitè

    2002-01-01

    Exceptional session in Italian on June 13, 2002 (am). CLEAN-2002 is a new, free of charge, half-day seminar in the context of Technical Training for the LHC. The course is designed for personnel working or managing activities in an assembly cleanroom, for example physicists, engineers and technicians working at or visiting the laboratory. CLEAN-2002 is aimed at raising awareness about good working practices in a cleanroom, and at providing practical examples, analysis tools, and documentation. Specific problems put forward beforehand by attendees will also be addressed. More information and registration through EDH is available here. The next session will be held in Italian, on 13 June (morning), following a specific request. Other sessions, in French and English, will be offered following demand: the first session in French will be organised in July 2002. Organiser: Davide Vitè / HR-TD / 75141 Davide.Vite@cern.ch

  11. THE TECHNICAL AND ETHNICAL DIVISION OF WORK, THE INDIGEOUS GROUPS AND THE FAMILY BUSINESSES

    Directory of Open Access Journals (Sweden)

    Gloria A. Miranda-Zambrano

    2013-04-01

    Full Text Available The work exposes some forms of indigenous groups participation on entrepreneurial family businesses, mainly in the region of Laja - Bajío where the family plays an important role in these organizations. The work point out the approach on technical ethnic division of labour to locate such actors in labour circuits, in economic activities or guilds that have been built in various social processes. To analyze the ways in which they operate, the role of the family, their knowledge (cultural capital, its forms of linkage with the community of origin and with the Group (social capital, as well as the existence of certain differences with business in common. This research is part of a larger work on family businesses.

  12. Technical and economic proposal for the extension of the Laguna Verde Nuclear Power plant with an additional nuclear reactor

    International Nuclear Information System (INIS)

    Leal C, C.D.; Francois L, J.L.

    2006-01-01

    The increment of the human activities in the industrial environments and of generation of electric power, through it burns it of fossil fuels, has brought as consequence an increase in the atmospheric concentrations of the calls greenhouse effect gases and, these in turn, serious repercussions about the environment and the quality of the alive beings life. The recent concern for the environment has provoked that industrialized countries and not industrialized carry out international agreements to mitigate the emission from these gases to the atmosphere. Our country, like part of the international community, not is exempt of this problem for what is necessary that programs begin guided toward the preservation of the environment. As for the electric power generation, it is indispensable to diversify the sources of primary energy; first, to knock down the dependence of the hydrocarbons and, second, to reduce the emission of polluting gases to the atmosphere. In this item, the nucleo electric energy not only has proven to be safe and competitive technical and economically, able to generate big quantities of electric power with a high plant factor and a considerable cost, but rather also, it is one of the energy sources that less pollutants it emits to the atmosphere. The main object of this work is to carry out a technical and economic proposal of the extension of the Laguna Verde Nuclear power plant (CNLV) with a new nuclear reactor of type A BWR (Advanced Boiling Water Reactor), evolutionary design of the BWR technology to which belong the two reactors installed at the moment in the plant, with the purpose of increasing the installed capacity of generation of the CNLV and of the Federal Commission of Electricity (CFE) with foundation in the sustainable development and guaranteeing the protection of the environment by means of the exploitation of a clean and sure technology that counts at the moment with around 12,000 year-reactor of operational experience in more of

  13. Organization of work with training mathematical text for technical university students under conditions of informatization of education

    Directory of Open Access Journals (Sweden)

    Михаил Владимирович Поспелов

    2013-12-01

    Full Text Available This article describes the model of the organization of working with training mathematical text for technical university students. Need for development of training text works competencies of first-year students is proved. The impact of learning materials transition into hypertext format on training text works organizing theory is cleared. Training text works organizing stages are described.

  14. Fundamental Aeronautics Program: Overview of Propulsion Work in the Supersonic Cruise Efficiency Technical Challenge

    Science.gov (United States)

    Castner, Ray

    2012-01-01

    The Supersonics Project, part of NASA's Fundamental Aeronautics Program, contains a number of technical challenge areas which include sonic boom community response, airport noise, high altitude emissions, cruise efficiency, light weight durable engines/airframes, and integrated multi-discipline system design. This presentation provides an overview of the current (2012) activities in the supersonic cruise efficiency technical challenge, and is focused specifically on propulsion technologies. The intent is to develop and validate high-performance supersonic inlet and nozzle technologies. Additional work is planned for design and analysis tools for highly-integrated low-noise, low-boom applications. If successful, the payoffs include improved technologies and tools for optimized propulsion systems, propulsion technologies for a minimized sonic boom signature, and a balanced approach to meeting efficiency and community noise goals. In this propulsion area, the work is divided into advanced supersonic inlet concepts, advanced supersonic nozzle concepts, low fidelity computational tool development, high fidelity computational tools, and improved sensors and measurement capability. The current work in each area is summarized.

  15. Frontex Working Arrangements: Legitimacy and Human Rights Concerns Regarding ‘Technical Relationships’

    Directory of Open Access Journals (Sweden)

    Melanie Fink

    2012-06-01

    Full Text Available Practices of extraterritorialisation have become cornerstones of the European Union member states' border control. Most of them are highly dependent on the willingness of third countries to cooperate. An increasingly important phenomenon is that cooperation is secured through relationships established by administrative authorities. This article deals with the challenges arising from the active engagement of Frontex in setting up cooperation structures.It is argued that the so-called working arrangements concluded between Frontex and the respective authorities of third countries, in their current form, show considerable deficiencies from the perspectives of the rule of law, democracy and human rights protection. They are not open to judicial review, the Parliament is not involved in their conclusion and they are not disclosed to the public. Furthermore, the human rights record of cooperating authorities is not considered. Concerns in this respect are frequently attempted to be dispelled by recourse to the 'technical' as opposed to 'political' nature of working arrangements. Likewise, it is assumed that merely 'technical relationships' cannot affect individuals. These arguments are not convincing. Quite the contrary, the political implications of working arrangements and their operation in a highly human rights sensitive field demand conformity with the fundamental values the European Union is based on.

  16. IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors. Working Material

    International Nuclear Information System (INIS)

    2011-01-01

    The IAEA, within the framework of its Nuclear Energy Department’s Technical Working Group on Fast Reactors (TWG-FR), assists Member States activities in fast reactors technology development areas by providing an umbrella for information exchange [topical Technical Meetings (TMs), Workshops and large Conferences] and collaborative R&D [Coordinated Research Projects (CRPs)]. The Technical meeting on “Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors” was held from 21 – 22 December 2011 in Vienna, addressing Member States’ expressed needs of information exchange in the field of advanced fast reactor design features, with particular attention to innovative heat exchangers and steam generators. The Objective of the TM is to provide a global forum for in-depth information exchange and discussion on the most advanced concepts of heat exchangers and steam generators for fast reactors. More specifically, the objectives are: · Review of the status of advanced fast reactor development activities with special emphasis on design and performance of heat exchangers and steam generators; · Discuss requirements for innovative heat exchangers and steam generators; · Present results of studies and conceptual designs for innovative heat exchangers and steam generators; · Provide recommendations for international collaboration under the IAEA aegis. The meeting agenda of the meeting is in Annex I

  17. Occupational exposure to ambient electromagnetic fields of technical operational personnel working for a mobile telephone operator

    International Nuclear Information System (INIS)

    Chauvin, S.; Gibergues, M. L.; Wuethrich, G.; Picard, D.; Desreumaux, J. P.; Bouillet, J. C.

    2009-01-01

    In order to investigate the exposure of operational personnel to radiofrequency electromagnetic fields when working for a mobile telephone operator, exposimeters were used to make individual records on 23 Technical Operations personnel (mobile telephone maintenance staff) and also on 22 Other Workers. The exposure densities, to which each of the 45 subjects was subjected, were quantified using 229 exposure indicators. Cluster analysis techniques were applied to the data, in an attempt to show that they would re-emerge as belonging to one of the two groups, i.e. the Technical Operational Personnel group or the Other Workers group. This exploratory investigation has shown that the cluster analysis does not reveal a sufficiently reliable emergence of the two groups, even though certain exposure indicators were significantly different for the two groups. In addition, the use of a Learning Group method does not lead to the discovery of a predictive law that could identify the Technical Operational Personnel as a sub-group within the overall group. (authors)

  18. Operation of a semi-technical pilot plant for nuclear aided steam gasification of coal

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Heek, K.H. van; Juentgen, H.; Peters, W.

    1984-01-01

    After intensive investigations on a small scale, the principle of the process has been tested in a semi-technical pilot plant. In its gasifier a fluidized bed of approx. 1 m 2 cross-section and of up to 4 m height is operated at 40 bar. Heat is supplied to the bed from an immersed heat exchanger with helium flowing through it, which is heated electrically. The plant was commissioned in 1976 and has been in hot operation for approx. 23000 h, over 13000 h whereof account for coal gasification. Roughly 1600 t of coal have been put through. During recent years the processing of German caking long-flame gas coal and the marked improvement of the process by the use of catalysts have been demonstrated successfully. (orig.)

  19. Floating nuclear energy plants for seawater desalination. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    Floating nuclear desalination facilities are one of the alternatives being considered. They may offer a particularly suitable choice for remote locations and small island or coastal communities where the necessary manpower and infrastructure to support desalination plants are not available. In the interest of focusing specific attention on the technology of floating nuclear desalination, the IAEA sponsored a Technical Committee Meeting on Floating Nuclear Plants for Seawater Desalination from 29 to 31 May 1995 in Obninsk, Russian Federation. This publication documents the papers and presentations given by experts from several countries at that meeting. It is hoped that the information contained in this report will be a valuable resource for those interested in nuclear desalination, and that it will stimulate further interest in the potential for floating nuclear desalination facilities. Refs, figs, tabs

  20. Guideline for the seismic technical evaluation of replacement items for nuclear power plants

    International Nuclear Information System (INIS)

    Harris, S.P.; Cushing, R.W.; Johnson, H.W.; Abeles, J.M.

    1993-02-01

    Seismic qualification for equipment originally installed in nuclear power plants was typically performed by the original equipment suppliers or manufactures (OES/OEM). Many of the OES/OEM no longer maintain quality assurance programs with adequate controls for supplying nuclear equipment. Utilities themselves must provide reasonable assurance in the continued seismic adequacy of such replacement items. This guideline provides practical, cost-effective techniques which can be used to provide reasonable assurance that replacement items will meet seismic performance requirements necessary to maintain the seismic design basis of commercial nuclear power plants. It also provides a method for determining when a seismic technical evaluation of replacement items (STERI) is required as part of the procurement process for spare and replacement items. Guidance on supplier program requirements necessary to maintain continued seismic adequacy and on documentation of maintaining required seismic adequacy is also included

  1. Technical improvement of ATE system of Ling'ao Nuclear Power Plant Phase II

    International Nuclear Information System (INIS)

    Zhu Xingbao; Xiong Jingchuan; Liang Qiaohong

    2009-01-01

    In order to solve the problem that the content of SO 4 2- in Steam Generator significantly increased beyond the criteria after the use of the condensate treatment (ATE) system in Daya Bay Nuclear Power Plant and Ling'ao Nuclear Power Plant Phase I, technical improvement have been conducted on the sizes of the fore cation bed and the mixed bed, water distributing devices, ion exchange resins and separation facility. The effectiveness for the ion exchange of the mixed bed is improved, the resolved substance of cation resin is decreased; it is more impossible for fragments and powder which would lead high SO 4 2- content in Steam Generator. Finally, the quality of the steam-water could be improved and ensured. (authors)

  2. Fourth Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group

    International Nuclear Information System (INIS)

    Schwantes, J.M.; Reilly, D.; Marsden, O.

    2018-01-01

    The Nuclear Forensics International Technical Working Group is a community of nuclear forensic practitioners who respond to incidents involving nuclear and other radioactive material out of regulatory control. The Group is dedicated to advancing nuclear forensic science in part through periodic participation in materials exercises. The Group completed its fourth Collaborative Materials Exercise in 2015 in which laboratories from 15 countries and one multinational organization analyzed three samples of special nuclear material in support of a mock nuclear forensic investigation. This special section of the Journal for Radioanalytical and Nuclear Chemistry is devoted to summarizing highlights from this exercise. (author)

  3. Involvement of stakeholders in the work of Technical Support Organisation: a strategy to learn together a new way of working

    International Nuclear Information System (INIS)

    Rollinger, Francois; Petitfrere, Michael

    2008-01-01

    Full text: Society's concerns have led to changes in the legal framework towards a greater requirement for public information and participation in decision-making processes. International organisations such as the OECD/NEA and the IAEA have also made similar changes. Moving towards expertise sharing is a development that demands a real change of culture on the part of all players, putting technical issues as part of a broader process of evaluation and decision-making. Which evolutions are necessary to the way Technical Support Organisations work to introduce a fourth player the population representatives in controlling radiological and nuclear risk? Developing experimental expert assessment processes involving parts of civil society that both sides can learn from one another is the core of IRSN's strategy for opening its expertise to civil society. In this perspective a dedicated team is responsible for carrying out actions in consultation with stakeholders from civil society. Two pluralistic assessment groups have been set up on radiological protection issues, and their innovative method of operation is worth highlighting. Another participative action is the development jointly with the Local Committees in the Loire Valley of methods of collecting environmental monitoring data. An internal network dedicated to stakeholder involvement has also been set up to accompany and promote this new approach internally. IRSN is currently elaborating a charter which will make public its commitments to the society related to stakeholder's involvement. Finally IRSN also intends to take advantage of existing experiences elsewhere and has been working for three years with four other assessments agencies in France in the frame of health and environmental risks about this new challenge: involving civil society in the assessments preceding the decision-making. (author)

  4. CO2 capture from power plants: Part I. A parametric study of the technical performance based on monoethanolamine

    NARCIS (Netherlands)

    Abu-Zahra, Mohammad R.M.; Schneiders, Léon H.J.; Niederer, John; Feron, Paul H.M.; Versteeg, Geert

    2007-01-01

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  5. CO2 capture from power plants. Part I : A parametric study of the technical performance based on monoethanolamine

    NARCIS (Netherlands)

    Abu-Zahra, M. R. M.; Schneiders, L. H. J.; Niederer, J. P. M.; Feron, P. H. M.; Versteeg, G. F.

    Capture and storage of CO2 from fossil fuel fired power plants is drawing increasing interest as a potential method for the control of greenhouse gas emissions. An optimization and technical parameter study for a CO2 capture process from flue gas of a 600 MWe bituminous coal fired power plant, based

  6. 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

  7. 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

  8. Compliance with technical codes becomes obligatory for receipt of feed-in tariff and ancillary services bonus for wind power plants in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Boemer, Jens. C. [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Delft Univ. of Technology (Netherlands). Electrical Power Systems Group; Burges, Karsten [Ecofys Germany GmbH, Berlin (Germany). Power Systems and Markets Group; Kumm, Thomas [VDE, Network Technology and Operation Forum (FNN), Berlin (Germany); Poeller, Markus [DIgSILENT GmbH, Gomaringen (Germany)

    2009-07-01

    The German government aims at a share of electricity generation based on renewable sources (RES-E) of more than 30% by 2020. A major part of this share will be reached by the use of wind power plants (WPP). Therefore, when amending the Renewable Energy Sources Act (EEG) in June 2008, the German government acknowledged the importance of enhanced technical requirements for WPP and announced the development of a respective technical ordinance. For all WPP that go into operation after June 2010, full grid code-compliance becomes a precondition for privileged network access, receipt of feed-in tariff, and extra payments (''ancillary services bonus''). The basis for the technical requirements in the EEG has been laid down by Medium-Voltage (MV)-Directive 2008 and the TransmissionCode 2007. However, the work of the authors - consulting the German government during the development of the technical ordinance - showed that the TransmissionCode 2007 needed careful review and some clarifying specifications were proposed. Eventually, the so called ''Ancillary Services Ordinance'' for wind power plants went into power in July 2009. The interrelation between all three grid codes as well as their specifications and implications for renewable energy sources generators, with special regard to wind power plants, are presented in this paper. (orig.)

  9. Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant - 59211

    International Nuclear Information System (INIS)

    Gilli, Ludivine

    2012-01-01

    In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator's decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with 'outsiders' during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders' involvement. (authors)

  10. Technical and economical prerequisites of special district-heating nuclear power plant development

    International Nuclear Information System (INIS)

    Baturov, B.B.; Boldyrev, V.M.; Losev, V.L.; Sigal, M.V.

    1983-01-01

    Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine

  11. Technical and economic assessment of the integrated solar combined cycle power plants in Iran

    International Nuclear Information System (INIS)

    Soltani Hosseini, M.; Hosseini, R.; Valizadeh, G.H.

    2002-01-01

    Thermal efficiency, capacity factor, environmental considerations, investment cost, fuel and O and M costs are the main parameters for technical and economic assessment of solar power plants. This analysis has shown that the Integrated Solar Combined Cycle System with 67 MW e solar field(ISCCS-67) is the most suitable plan for the first solar power plant in Iran. The Levelized Energy Costs of combined cycle and ISCCS-67 power plants would be equal if 49 million dollars of ISCCS-67 capital cost supplied by the international environmental organizations such as Global Environmental Facilities and World Bank. This study shows that an ISCCS-67 saves 59 million dollars in fuel consumption and reduces about 2.4 million ton in CO 2 emission during 30 years operating period. Increasing of steam turbine capacity by 50%, and 4% improvement in overall efficiency are other advantages of iSCCS-67 power plant. The LEC of ISCCS-67 is 10% and so 33% lower than the combined cycle and gas turbine, respectively, at the same capacity factor with consideration of environmental costs

  12. Organizational factors influencing human performance in nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-05-01

    In 1991 a Safety Series report on Safety Culture of the International Nuclear Safety Advisory Group (INSAG) was published as 75-INSAG-4 by the IAEA. This report deals with the concept of Safety Culture as it relates to organizations and individuals involved in the operations of nuclear power plants (NPPs). Generally, the role of management and organization in assuring the safe operation of NPPs has been widely recognized and its importance accepted. However, the understanding of what constitutes effective management and organization the area of safety is less developed than the understanding of most of the technical issues which plant operators and regulatory bodies are confronted with. The Technical Committee meeting provided a forum for a broad exchange of information on practices and experiences in the area of organization and management to accomplish operational safety in NPPs and thus enhance Safety Culture. This report and the papers presented at the meeting discuss those factors which influence and improve human performance covering both aspects, i.e. the basic requirements imposed on the operator and the ways of managerial support which enhance the reliable and safety oriented performance of operators. Refs, figs, tabs

  13. Work ability and associated factors of Brazilian technical-administrative workers in education.

    Science.gov (United States)

    Godinho, Marluce Rodrigues; Greco, Rosangela Maria; Teixeira, Maria Teresa Bustamante; Teixeira, Liliane Reis; Guerra, Maximiliano Ribeiro; Chaoubah, Alfredo

    2016-01-02

    Studies about work ability have grown in importance owing to the worldwide aging of active populations. Research has shown that measuring work ability has a predictive value in cases of long-term sickness absence and early retirement. Our goal was to analyze the work ability and associated factors of civil servants from a higher education institution in Brazil. The participants in this cross-sectional study were 600 technical-administrative workers at a public university. Work ability was measured using the work ability index. The participants were as follows: 51.8% male; mean age of 45 years (SD = ±11); married or in a stable union (61.5%); holding a graduate degree (56.7%); having only one job (83.3%), working 40 h a week or less (78.6%); not working evenings (79.8%); and having direct contact with the public (58.3%). The prevalence of reduced work ability was 13.9%. The following factors were found to be associated with reduced work ability: age 50 years old or above (PR = 2.58; 95% CI 1.25-5.09); female (PR = 2.77; 95% CI 1.25-3.60); education up to secondary school (PR = 2.37; 95% CI 1.13-3.59); overall poor self-assessed health (PR = 2.96; 95% CI 1.32-3.93); signs and symptoms of depression (PR = 4.86; 95% CI 2.23-6.55); sedentariness (PR = 3.00; 95% CI 1.38-4.68) and poor social support at work (PR = 4.01; 95% CI 1.66-4.37). Most of the participants showed good work ability, but some subjects had reduced work ability. This study makes a contribution to expanding the discussion about the factors associated with work ability toward proposing actions for maintaining that ability or helping recovery in the case of diminished ability. Such actions can help reduce work absenteeism and early retirement, both of which have a social and economic impact in Brazil. Studying the determinants of work ability and recommendations to address those determinants will help efforts to improve the quality of life of individuals, both at work and personally, and promote healthy

  14. The Waste Treatment Plant, a Work in Progress

    International Nuclear Information System (INIS)

    Hamel, W. F. Jr.; Duncan, G. M.

    2006-01-01

    There are many challenges in the design and construction of Department of Energy's (DOE) Waste Treatment and Immobilization Plant (WTP) at the Hanford site. The plant is being built to process some 55 million gallons of radioactive waste from 177 underground tanks. Engineering and construction are progressing on this largest project in the DOE complex. This paper describes some of WTP's principal recent challenges and opportunities and how they are being addressed to minimize impact on the project, enhance the capabilities of the facilities, and reduce risk. A significant new development in 2005 was the need to account for higher seismic accelerations than originally specified for the facility structures and equipment. Efforts have centered on continuing design and construction with minimal risk, while the final seismic design spectra was developed. Other challenges include development of an alternative cesium ion exchange resin to minimize the risk from reliance on a single product, implementing advanced analytical techniques to improve laboratory performance, adopting a thinner walled high level waste (HLW) canister to reduce waste volume and mission duration, and commissioning a comprehensive external flowsheet review of the design, along with its underpinning technologies, and projected plant operability. These challenges make it clear that WTP is a work in progress, but the challenges are being successfully resolved as the design and construction move on to completion. (authors)

  15. Technical and economic analysis of integrating low-medium temperature solar energy into power plant

    International Nuclear Information System (INIS)

    Wang, Fu; Li, Hailong; Zhao, Jun; Deng, Shuai; Yan, Jinyue

    2016-01-01

    Highlights: • Seven configurations were studied regarding the integration of solar thermal energy. • Economic analysis was conducted on new built plants and retrofitted power plants. • Using solar thermal energy to preheat high pressure feedwater shows the best performance. - Abstract: In order to mitigate CO_2 emission and improve the efficiency of the utilization of solar thermal energy (STE), solar thermal energy is proposed to be integrated into a power plant. In this paper, seven configurations were studied regarding the integration of STE. A 300 MWe subcritical coal-fired plant was selected as the reference, chemical absorption using monoethanolamine solvent was employed for CO_2 ​capture, and parabolic trough collectors and evacuated tube collectors were used for STE collection. Both technical analysis and economic evaluation were conducted. Results show that integrating solar energy with post-combustion CO_2​ capture can effectively increase power generation and reduce the electrical efficiency penalty caused by CO_2 capture. Among the different configurations, Config-2 and Config-6, which use medium temperature STE to replace high pressure feedwater without and with CO_2 capture, show the highest net incremental solar efficiency. When building new plants, integrating solar energy can effectively reduce the levelized cost of electricity (LCOE). The lowest LCOE, 99.28 USD/MWh, results from Config-6, with a parabolic trough collector price of 185 USD/m"2. When retrofitting existing power plants, Config-6 also shows the highest net present value (NPV), while Config-2 has the shortest payback time at a carbon tax of 50 USD/ton CO_2. In addition, both LCOE and NPV/payback time are clearly affected by the relative solar load fraction, the price of solar thermal collectors and the carbon tax. Comparatively, the carbon tax can affect the configurations with CO_2 capture more clearly than those without CO_2 capture.

  16. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1986-11-15

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident.

  17. The Chernobyl accident and the Spanish nuclear power plants. Technical report

    International Nuclear Information System (INIS)

    1986-11-01

    On the morning of April 26, 1986, Unit 4 of the Chernobyl Nuclear Power Plant (Ukraine, USSR) suffered an accident of the greatest magnitude among those which have taken place in nuclear energy installations employed for peaceful uses. The accident reached a degree of severity unknown up to now in nuclear energy generating plants, both with respect to the loss of human lives and the effects caused to the neighboring population (as well as to other nations within a wide radius of radioactivity dispersal), and also with respect to the damage caused in the nuclear plant itself. In the light of the anxiety created internationally, the USSR State Committee for the Utilization of Atomic Energy prepared a report (1), based on the conclusions of the Governmental Commission entrusted to study the causes of the accident, which was presented at the international meeting of experts held at the International Atomic Energy Agency (IAEA) headquarters in Vienna from August 25 to 29, 1986. The present technical report has been prepared by the Spanish nuclear power plants within the framework of UNIDAD ELECTRICA, S.A. (UNESA) - the Association of Spanish electric utilities - in collaboration with EMPRESARIOS AGRUPADOS, S.A. The report reflects the utilities' analyses of the causes and consequences of the accident and, based on similarities and differences with Spanish plants under construction and in operation, intends to: a. Evaluate the possibility of an accident with similar consequences occurring in a Spanish plant b. Identify possible design and operation modifications indicated by the lessons learned from this accident

  18. Technical feasibility and carbon footprint of biochar co-production with tomato plant residue.

    Science.gov (United States)

    Llorach-Massana, Pere; Lopez-Capel, Elisa; Peña, Javier; Rieradevall, Joan; Montero, Juan Ignacio; Puy, Neus

    2017-09-01

    World tomato production is in the increase, generating large amounts of organic agricultural waste, which are currently incinerated or composted, releasing CO 2 into the atmosphere. Organic waste is not only produced from conventional but also urban agricultural practices due recently gained popularity. An alternative to current waste management practices and carbon sequestration opportunity is the production of biochar (thermally converted biomass) from tomato plant residues and use as a soil amendment. To address the real contribution of biochar for greenhouse gas mitigation, it is necessary to assess the whole life cycle from the production of the tomato biomass feedstock to the actual distribution and utilisation of the biochar produced in a regional context. This study is the first step to determine the technical and environmental potential of producing biochar from tomato plant (Solanum lycopersicum arawak variety) waste biomass and utilisation as a soil amendment. The study includes the characterisation of tomato plant residue as biochar feedstock (cellulose, hemicellulose, lignin and metal content); feedstock thermal stability; and the carbon footprint of biochar production under urban agriculture at pilot and small-scale plant, and conventional agriculture at large-scale plant. Tomato plant residue is a potentially suitable biochar feedstock under current European Certification based on its lignin content (19.7%) and low metal concentration. Biomass conversion yields of over 40%, 50% carbon stabilization and low pyrolysis temperature conditions (350-400°C) would be required for biochar production to sequester carbon under urban pilot scale conditions; while large-scale biochar production from conventional agricultural practices have not the potential to sequestrate carbon because its logistics, which could be improved. Therefore, the diversion of tomato biomass waste residue from incineration or composting to biochar production for use as a soil amendment

  19. Yemen watched from cement plant construction work. Cement plant koji wo toshite mita Yemen

    Energy Technology Data Exchange (ETDEWEB)

    Furuta, M [Kajima Corp., Tokyo (Japan)

    1993-06-25

    Construction of a cement plant was planned at southern part of Yemen. This is a cement plant with annual production 500,000 tons. The term of work was from January, 1990 to February, 1993. The present paper describes an outline the construction of this Cement Plant, the nationality and living environment in Yemen, and construction equipment which was used. The construction work consisted of 113,000m[sup 3] of digging, 82,000m[sup 3] of backfilling, 66,100m[sup 3] of concreting, and 29,285m[sup 3] of asphalt pavement. Reinforcing steel weighing 6,400 tons and steel frame weighing 3,600 tons were totally used. Equipment weighing 7,912 tons and electric devices weighing 1,299 tons were totally installed. For this construction work, two crawler cranes, six hydraulic cranes, aggregate plant, concrete mixers, and construction equipment, such as bulldozers, shovels, and dumpers, were brought from Japan. 5 figs.

  20. Concrete works for Hamaoka No. 1 nuclear power plant

    International Nuclear Information System (INIS)

    Horiuchi, Minoru; Sugihara, Kazuo; Iwasawa, Jiro.

    1975-01-01

    Various aspects of concrete works performed for the reactor building of Hamaoka No.1 plant are reviewed. Control building and waste disposal building were all together combined with the reactor building in order to improve safety against earthquakes. Special consideration was given for the quality control of concrete works by establishing quality control committee, making quality control manual and by performing daily examination and monthly report. The quality and various materials of concrete used are described. The composition of concrete used for various parts of the building is also listed. Detailed description is made regarding the concrete placing for foundation mat, under a containment vessel, and the construction of air gaps and the placing of shielding concrete around the containment vessel. Curves representing the temperature history of concrete at various points are presented. As for testing, the items of test, methods of measurement, and the results of these test and measurement are presented in detail. (Aoki, K.)

  1. Advanced Outage and Control Center: Strategies for Nuclear Plant Outage Work Status Capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Gregory Weatherby

    2012-05-01

    The research effort is a part of the Light Water Reactor Sustainability (LWRS) Program. LWRS is a research and development program sponsored by the Department of Energy, performed in close collaboration with industry to provide the technical foundations for licensing and managing the long-term, safe and economical operation of current nuclear power plants. The LWRS Program serves to help the US nuclear industry adopt new technologies and engineering solutions that facilitate the continued safe operation of the plants and extension of the current operating licenses. The Outage Control Center (OCC) Pilot Project was directed at carrying out the applied research for development and pilot of technology designed to enhance safe outage and maintenance operations, improve human performance and reliability, increase overall operational efficiency, and improve plant status control. Plant outage management is a high priority concern for the nuclear industry from cost and safety perspectives. Unfortunately, many of the underlying technologies supporting outage control are the same as those used in the 1980’s. They depend heavily upon large teams of staff, multiple work and coordination locations, and manual administrative actions that require large amounts of paper. Previous work in human reliability analysis suggests that many repetitive tasks, including paper work tasks, may have a failure rate of 1.0E-3 or higher (Gertman, 1996). With between 10,000 and 45,000 subtasks being performed during an outage (Gomes, 1996), the opportunity for human error of some consequence is a realistic concern. Although a number of factors exist that can make these errors recoverable, reducing and effectively coordinating the sheer number of tasks to be performed, particularly those that are error prone, has the potential to enhance outage efficiency and safety. Additionally, outage management requires precise coordination of work groups that do not always share similar objectives. Outage

  2. Current status and technical description of Chinese 2 x 250 MWth HTR-PM demonstration plant

    International Nuclear Information System (INIS)

    Zhang Zuoyi; Wu Zongxin; Wang Dazhong; Xu Yuanhui; Sun Yuliang; Li Fu; Dong Yujie

    2009-01-01

    After the nuclear accidents of Three Mile Island and Chernobyl the world nuclear community made great efforts to increase research on nuclear reactors and to develop advanced nuclear power plants with much improved safety features. Following the successful construction and a most gratifying operation of the 10 MW th high-temperature gas-cooled test reactor (HTR-10), the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University has developed and designed an HTR demonstration plant, called the HTR-PM (high-temperature-reactor pebble-bed module). The design, having jointly been carried out with industry partners from China and in collaboration of experts worldwide, closely follows the design principles of the HTR-10. Due to intensive engineering and R and D efforts since 2001, the basic design of the HTR-PM has been finished while all main technical features have been fixed. A Preliminary Safety Analysis Report (PSAR) has been compiled. The HTR-PM plant will consist of two nuclear steam supply system (NSSS), so called modules, each one comprising of a single zone 250 MW th pebble-bed modular reactor and a steam generator. The two NSSS modules feed one steam turbine and generate an electric power of 210 MW. A pilot fuel production line will be built to fabricate 300,000 pebble fuel elements per year. This line is closely based on the technology of the HTR-10 fuel production line. The main goals of the project are two-fold. Firstly, the economic competitiveness of commercial HTR-PM plants shall be demonstrated. Secondly, it shall be shown that HTR-PM plants do not need accident management procedures and will not require any need for offsite emergency measures. According to the current schedule of the project the completion date of the demonstration plant will be around 2013. The reactor site has been evaluated and approved; the procurement of long-lead components has already been started. After the successful operation of the demonstration plant

  3. Tenth meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation, Vienna, 3-5 March 1986

    International Nuclear Information System (INIS)

    1986-07-01

    The meeting of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) was organized in order to summarize operating experience of NPP control systems, gain a general overview of activities in development of modern control systems and receive recommendations on the further directions and particular measures within the Agency's programme. The papers and discussions mostly dealt with practical experience and described actual problems encountered. Emphasis was placed on the technical, industrial and economic aspects of the introduction of modern, highly automated control systems and on the improvement of plant availability and safety. A separate abstract was prepared for each of the 20 presentations of the meeting

  4. Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

    International Nuclear Information System (INIS)

    Korsah, K.

    2001-01-01

    This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I and C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I and C system upgrades of present-day nuclear power plants, as well as I and C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I and C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in

  5. Technical Work Plan for: Near Field Environment: Engineered Barrier System: Radionuclide Transport Abstraction Model Report

    International Nuclear Information System (INIS)

    J.D. Schreiber

    2006-01-01

    This technical work plan (TWP) describes work activities to be performed by the Near-Field Environment Team. The objective of the work scope covered by this TWP is to generate Revision 03 of EBS Radionuclide Transport Abstraction, referred to herein as the radionuclide transport abstraction (RTA) report. The RTA report is being revised primarily to address condition reports (CRs), to address issues identified by the Independent Validation Review Team (IVRT), to address the potential impact of transport, aging, and disposal (TAD) canister design on transport models, and to ensure integration with other models that are closely associated with the RTA report and being developed or revised in other analysis/model reports in response to IVRT comments. The RTA report will be developed in accordance with the most current version of LP-SIII.10Q-BSC and will reflect current administrative procedures (LP-3.15Q-BSC, ''Managing Technical Product Inputs''; LP-SIII.2Q-BSC, ''Qualification of Unqualified Data''; etc.), and will develop related Document Input Reference System (DIRS) reports and data qualifications as applicable in accordance with prevailing procedures. The RTA report consists of three models: the engineered barrier system (EBS) flow model, the EBS transport model, and the EBS-unsaturated zone (UZ) interface model. The flux-splitting submodel in the EBS flow model will change, so the EBS flow model will be validated again. The EBS transport model and validation of the model will be substantially revised in Revision 03 of the RTA report, which is the main subject of this TWP. The EBS-UZ interface model may be changed in Revision 03 of the RTA report due to changes in the conceptualization of the UZ transport abstraction model (a particle tracker transport model based on the discrete fracture transfer function will be used instead of the dual-continuum transport model previously used). Validation of the EBS-UZ interface model will be revised to be consistent with

  6. Technical comparison between Integrated Gasification Combined Cycle (IGCC) and Natural Gas Combined Cycle (NGCC) power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz, Pablo Andres Silva; Venturini, Osvaldo Jose; Lora, Electo Eduardo Silva [Federal University of Itajuba - UNIFEI, MG (Brazil). Excellence Group in Thermal Power and Distributed Generation - NEST], e-mails: osvaldo@unifei.edu.br, electo@unifei.edu.br

    2010-07-01

    Among the emerging clean coal technologies for power generation, Integrated Gasification Combined Cycle (IGCC) and Natural Gas Combined Cycle (NGCC) systems are receiving considerable attention as a potentially attractive option to reduce the emissions of greenhouse gases (GHG). The main reason is because these systems has high efficiency and low emissions in comparison with traditional power generation plants. Currently in IGCC and NGCC systems at demonstration stage is been considered to implement CCS technology. CO{sub 2} emissions can be avoided in a gasification-based power plant because by transferring almost all carbon compounds to CO{sub 2} through the water gas shift (WGS) reaction, then removing the CO{sub 2} before it is diluted in the combustion stage. The aim of this study is to compare the technical performance of an IGCC system that uses Brazilian coal and petroleum coke as fuel with a NGCC system, with the same fixed output power of 450 MW. The first section of this paper presents the plant configurations of IGCC systems. The following section presents an analysis of NGCC technology. (author)

  7. 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.)

  8. ENSI's technical view on the periodic safety review 2008 of the nuclear power plant Goesgen

    International Nuclear Information System (INIS)

    2012-08-01

    The owner of a license for a nuclear power plant operation in Switzerland has to undergo every 10 years a comprehensive safety check called 'periodic safety review' (PSR). The regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI), reviews the documents supplied by the licensee. The Goesgen power plant (KKG) obtained its operation license and started operation in 1978. A first PSR was performed in the years 1996 to 1998 (PSR 1998) and reported. KKG delivered an analysis of the safety status, an evaluation of subsystems as well as test reports. The new PSR covers the period 1998 to 2007. The basis of the evaluation by ENSI is the new nuclear energy law in force since 1 February 2005. In comparison to PSR 1998, new aspects have to be considered like the description of the safety concept, including the technical safety classification of buildings, systems and components, or consideration of the protection objective 'limitation of the radiation exposure'. The PSR 2008 is focussed on the estimate of the nuclear safety of KKG. Basically, for the operation of a nuclear power plant, a sufficient protection has to be guaranteed against the release of radioactive materials to the environment as well as the irradiation of persons, during normal operation as well as in the case of accidents. The licensee of a nuclear power plant in operation must retrofit his plant according to the experience already gained and the state-of-the-art. The purpose of the PSR is to check the quality of the plant in the domain of safety. A probabilistic safety assessment (PSA) study must prove that the probability of damages to the reactor core is smaller than 10 -5 /year. In Switzerland the life time of a nuclear power plant is not limited by a fixed maximum time of operation. On the contrary, the limitation proceeds from safety criteria. Insufficiencies in the plant design are often recognized only through the evolution of the technique or some unexpected events. Ageing

  9. Systems scenarios: a tool for facilitating the socio-technical design of work systems.

    Science.gov (United States)

    Hughes, Helen P N; Clegg, Chris W; Bolton, Lucy E; Machon, Lauren C

    2017-10-01

    The socio-technical systems approach to design is well documented. Recognising the benefits of this approach, organisations are increasingly trying to work with systems, rather than their component parts. However, few tools attempt to analyse the complexity inherent in such systems, in ways that generate useful, practical outputs. In this paper, we outline the 'System Scenarios Tool' (SST), which is a novel, applied methodology that can be used by designers, end-users, consultants or researchers to help design or re-design work systems. The paper introduces the SST using examples of its application, and describes the potential benefits of its use, before reflecting on its limitations. Finally, we discuss potential opportunities for the tool, and describe sets of circumstances in which it might be used. Practitioner Summary: The paper presents a novel, applied methodological tool, named the 'Systems Scenarios Tool'. We believe this tool can be used as a point of reference by designers, end-users, consultants or researchers, to help design or re-design work systems. Included in the paper are two worked examples, demonstrating the tool's application.

  10. Views of plant operators - work done at Eurelectric

    International Nuclear Information System (INIS)

    Ibanez, M.

    2004-01-01

    The Union of the Electricity Industry - EURELECTRIC, formed as a result of a merger in December 1999 of the twin Electricity Industry Associations, UNIPEDE and EURELECTRIC, is the sector association representing the common interests of the European Electricity Industry and its world wide affiliates and associates. Its mission is to contribute to the development and competitiveness of the Electricity Industry and to promote the role of electricity in the advancement of society. As a centre of strategic expertise, the Union of the Electricity Industry - EURELECTRIC will identify and represent the common interests of its members and assist them in formulating common solutions to be implemented and in coordinating and carrying out the necessary actions. To that end it will also act in liaison with other international associations and organisations, respecting the specific missions and responsibilities of these organisations. The Union of the Electricity Industry - EURELECTRIC is also the association of the Electricity Industry within the European Union representing it in public affairs, in particular in relation to the institutions of the EU and other international organisations, in order to promote the interest of its members at a political level and to create awareness of its policies. The EURELECTRIC's work agenda and main policies and strategies of the association are determine by the five committees of its organisational structure: Energy Policy and Generation, Networks, Markets, Environment and Sustainable Development, Management. Each committee has its own specific working group structure of expertise and adopts positions or undertakes studies on all issues falling within its competence. One of the working groups of the Energy Policy and Generation Committee is the Working Group Nuclear. Its terms of Reference include as main items of the working agenda the radioactive waste management and plant decommissioning. (author)

  11. Safe Operation of Nuclear Power Plants. Code of Practice and Technical Appendices

    International Nuclear Information System (INIS)

    1969-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Nuclear Power Plants and the second part is a compilation of technical appendices. Its object is to give information and illustrative examples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. Safe operation of a nuclear power plant postulates suitable siting and proper design, construction and management of the plant. Under the present Code of Practice for the Safe Operation of Nuclear Power Plants, those intending to operate the plant are recommended to prepare documentation which would deal with its operation and include safety analyses. The documentation in question would be reviewed by a regulatory body independent of the operating organization; operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code may be subject to revision in the light of experience. The Appendices provide additional information together with some examples relating to certain topics dealt with in the Code; it must be emphasized that they are included as examples for information only and are not part of any recommendation. Purpose and scope: The recommendations in the Code are designed to protect the general public and the operating personnel from radiation hazards, and the Code forms part of the Agency's Safety Standards. The Code, which should be used in conjunction with the Agency's other Safety Standards, provides guidance and information to persons and authorities responsible for the operation of stationary nuclear power plants whose main function is the generation of thermal, mechanical or electrical power; it is not intended to apply to reactors used solely for experimental or research purposes. It sets forth minimum requirements which, it is believed, in the light of experience, must be met in order to achieve safe operation of a

  12. 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

  13. 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

  14. 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

  15. 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

  16. Using plant status data for off-site emergency management: Technical and political aspects

    International Nuclear Information System (INIS)

    Govaerts, P.

    2004-01-01

    Subsequent to the TMI and Chernobyl accidents, emergency management is investigating the possibility of taking balanced decisions on interventions as early as possible. This process relies more and more on in-plant data to assess the term of releases. The paper discusses the regulatory aspects of the communication related to the source term between the utility and the national authorities, and the authorities of a host country and neighbouring countries that may be affected. The technical aspects of the assessment process are summarised, with the emphasis on the handling of uncertainties. Notwithstanding the technical progress, the main dilemma for the decision makers remains the same. Risk management and prevention measures become more familiar to authorities. Utilities and national authorities have to get rid of complexes with respect to accidents covered by the accepted residual risk. International emergency management has to look for an organisation type ensuring the continuity of countermeasures independent of the presence of administrative borders, and with respect to national autonomies. (authors)

  17. WORK EXPERIENCE INTERNSHIP THROUGH THE EYES OF TECHNICAL UNIVERSITY STUDENTS (ON THE MATERIALS OF SOCIOLOGICAL RESEARCH

    Directory of Open Access Journals (Sweden)

    Alexandr Yu. Myagkov

    2015-01-01

    Full Text Available The aim of the investigation is to study the problem of efficiency of work experience internship in a technical university and its role in the education of future professionals (problem has been investigated in the framework of the research project «Monitoring of social well-being and problems of professional adaptation of ISPEU students».Methods. While carrying out of sociological research, selection of respondents was occurred on the multistage combined (serially-nested model of sample among students I, III and V courses of six faculties of full-time course of ISPEU. The complex of questions (its answers show features of professional identity of the future experts on initial (I course, intermediate (III course and finishing (V course stages of their professional formation has been developed to find out the dynamics of process of professional adaptation of students from the first to the fifth year. The information was processed with application of program and analytical complex SPSS. The comparative analysis to a gender sign of degree of satisfaction/dissatisfaction has been undertaken by the work experience internship organization on the side of high school and the accepting enterprises.Results. The level of graduates’ satisfaction with the work experience internship is revealed that works on an estimation by students of quality of preparation in high school, the relation to a received speciality and success in the future profession. The data on a self-estimation of readiness of students to work experience internship is cited. Criteria of successful work experience internship are formulated.Scientific novelty. The given researches carried out by the authors, prove that work experience internship positively influences professional consciousness of students and promote formation of steady positive installations for professional job. However, work experience internship in its institutional forms is functional and appears to be the effective

  18. A technical and financial analysis of two recuperated, reciprocating engine driven power plants. Part 1: Thermodynamic analysis

    International Nuclear Information System (INIS)

    Orbaiz, Pedro Jose; Brear, Michael J.

    2014-01-01

    Highlights: • A thermodynamic analysis of two recuperated ICE plants is undertaken. • The overall plant efficiency and CO 2 emissions are analysed. • Chemical recuperation without a secondary heat source is unlikely. • Using a renewable secondary heat source reduces the CO 2 emission of the plant. - Abstract: This paper is the first of a two part study that analyses the technical and financial performance of particular, recuperated engine systems. This first paper presents a thermodynamic study of two systems. The first system involves the chemical recuperation of a reciprocating, spark ignited, internal combustion engine using only the waste heat of the engine to power a steam–methane reformer. The performance of this system is evaluated for different coolant loads and steam–methane ratios. The second system is a so-called ’hybrid’ in which not only the waste heat of the engine is used, but also a secondary heat source – the combustion of biomass. The effects of the reformer’s temperature and the steam–methane ratio on the system performance are analysed. These analyses show that the potential efficiency improvement obtained when using only the engine waste heat to power the recuperation is marginal. However, results for the hybrid show that although the overall efficiency of the plant, defined in terms of the energy from both the methane and biomass, is similar to that of the conventional, methane fuelled engine, the efficiency of the conversion of the biomass fuel energy to work output appears to be higher than for other biomass fuelled technologies currently in use. Further, in the ideal limit of a fully renewable biomass fuel, the burning of biomass does not contribute to the net CO 2 emissions, and the CO 2 emission reduction for this second plant can be considerable. Indeed, its implementation on larger internal combustion engine power plants, which have efficiencies of around 45–50%, could result in CO 2 emissions that are as much as

  19. Forty-Fifth Annual Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2012-01-01

    The objectives of the meeting were to: • Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); • Review the progress since the 44 th TWG-FR Annual Meeting, including the status of the actions; • Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Programme & Budget (P&B) biennium 2012-2013; • Review the IAEA’s concluded, on-going and planned coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.). The 45th Meeting of the TWG-FR reached the following conclusions/recommendations: • The participants expressed satisfaction and appreciation for the large amount of new information on on-going activities carried out by the Member States in the field of FR and ADS exchanged during the meeting; • Also the organizations which have participated to the TWG-FR meeting for the first time expressed their appreciation for the lively discussion and the results and thanked the IAEA for inviting them at the meeting; • The meeting was very useful in particular for collecting inputs and advice in view of the preparation of the IAEA Programme & Budget 2014-2015 (and then 2016-2017) in the area of FR and ADS technology development; • The TWG-FR remains an unique international forum for information exchange in the field of fast neutron systems and for promoting RT&D activities in this area; • Due to the increasing interest in FR and in view of the forthcoming realizations, it would be advisable to increase the involvement of industries, regulators and other R&D organizations; • The annual TWG-FR meeting should focused on exchange of information on national and international programmes, avoiding duplications or overlapping’s with other IAEA initiatives in the field;

  20. Important functions and development ideas of the library and information work in scientific and technical research institutes

    International Nuclear Information System (INIS)

    Ye Qingsen

    2010-01-01

    The library and information branch is an important constituent part of a scientific and technic research institute, and is a technically assistant department which is set for scientific and technic research and production. The investigations show that the achievements by the library and information departments are marked in scientific and technic research institutes, and the library and information works play important roles for the existence, development and innovation of the institute in past years. But, the present conditions and statuses are dropped behind, and more problems existed in the library and information departments as a whole. The development ideas are proposed for the library and information work by analyzing the characteristics of nowadays knowledge service, knowledge economy and network information time. (authors)

  1. C. Rubbia's hybrid plant concept: a preliminary technical and economic analysis

    International Nuclear Information System (INIS)

    Bacher, P.

    1999-01-01

    The long term development of nuclear energy depends, inter alia, on the ability to use the abundant fertile materials (238U and/or thorium) and on an accepted management of the long-lived radioactive wastes. In order to meet both these objectives, C. Rubbia has presented a new version of an old concept: the hybrid reactor where a subcritical reactor is fed with neutrons produced by spallation. In his concept, the reactor is a molten lead cooled fast reactor, which can use either the uranium or the thorium cycle, and burn the minor actinides and some fission products. The present work is a preliminary and partial technical and economic analysis of the reactor part of C. Rubbia's proposal as they were set forth in a French Parliamentary audition in November 1996. The technical conclusions are that many of the design options proposed are not optimum and the uncertainties important, which is not particularly surprising at this stage of the concept. The economic 'guesstimate' yields a cost per kWh anywhere between one and two times that of a modern light water reactor, which is in contradiction with C. Rubbia's claims (half the cost.), but in a range which warrants more conceptual work before drawing any conclusions. Alternative design concepts are suggested. (orig.)

  2. Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  3. Regulatory surveillance of safety related maintenance at nuclear power plants. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-08-01

    The operational safety and reliability of a nuclear power plant as well as its availability for electricity generation depend on, among other things, its maintenance programme. Regulatory bodies therefore have considerable interest in maintenance activities. There are several approaches to maintenance, i.e. reliability centered maintenance or risk focused maintenance, aimed at optimizing maintenance by focusing on important components or systems. These approaches may result in significant changes to maintenance activities and therefore have to be considered for regulatory acceptance. In order to review and discuss the status of maintenance regulation in participating countries, the IAEA convened a Technical Committee Meeting on Regulatory Oversight of Maintenance Activities at Nuclear Power Plants in Vienna from 9 to 13 October 1995. The meeting was attended by 16 experts from 11 countries. In addition to the consideration of papers that were presented and which are reproduced here, extensive group and panel discussions took place during the meeting. These covered three main topics: general features and basic characteristics of maintenance regulation, regulatory acceptance of maintenance optimization and use of PSA for maintenance optimization. The discussion are summarized in Section 2. Section 3 discusses the following three additional topics: regulatory involvement in the maintenance programme, modifications to the maintenance programme and personnel related aspects of maintenance. The conclusions are presented in Section 4. Figs, tabs

  4. 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

  5. Technical safety appraisal of buildings 9206 and 9212, Oak Ridge Y-12 plant

    International Nuclear Information System (INIS)

    1989-03-01

    This report covers the results of a Safety Performance Review of the Y-12 Plant conducted during the period July 25 through August 3, 1988. A Safety Performance Review is a followup to assess changes in performance since the 1986 Technical Safety Appraisal (TSA). This review is patterned after a TSA and covered the overall safety performance at Y-12, evaluating progress to date against standards of accepted practice. The review included coverage of actions taken in response to recommendations in the TSA conducted in July--August 1986. Remaining issues were identified through an assessment of safety program deficiencies and their root causes. For each of the 14 safety-related functional areas at the Y-12 Plant, results of this review are listed in Section V. These results include a discussion, conclusions, and any new safety concerns for each program. Appendix A contains a description of the system for categorizing concerns, and the concerns are summarily tabulated in Appendix B for all programs. Appendix C describes the contractor's response and current status of each of the 59 recommendations contained in the 1986 TSA

  6. Instrumentation and process control for fossil demonstration plants. Quarterly technical progress report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    LeSage, L.G.

    1977-07-01

    Work has been performed on updating the study of the state-of-the-art of instrumentation for Fossil Demonstration Plants (FDP), development of mass-flow and other on-line instruments for FDP, process control analysis for FDP, and organization of a symposium on instrumentation and control for FDP. A Solids/Gas Flow Test Facility (S/GFTF) under construction for instrument development, testing, evaluation, and calibration is described. The development work for several mass-flow and other on-line instruments is described: acoustic flowmeter, capacitive density flowmeter, neutron activation flowmeter and composition analysis system, gamma ray correlation flowmeter, optical flowmeter, and capacitive liquid interface level meter.

  7. Work Practice, Safety and Heedfulness. Studies of Organizational Reliability in Hospitals and Nuclear Power Plants

    International Nuclear Information System (INIS)

    Gauthereau, Vincent

    2003-01-01

    The study of safety in complex systems has focused on different issues over the past decades. This focus was often linked to the conclusions of previous accidents'/incidents' analyses. When accidents were attributed to technical causes, safety research focused on technical developments. When they were later attributed to 'human errors', safety research focused on this 'component'. And when, since the mid-eighties accidents have been attributed to 'organizational factors', safety research has focused on these very same 'organizational factors'. The present thesis argues for a 'practice view' over safety to be taken. This view is mainly drawn from the field of research on High Reliability Organizations (HRO). HRO theorists' point of view on safety is that we can operate complex systems safely despite the fact that we have made them so complex that they are prone to 'normal accidents'. Humans involved in the operation of our systems actually create safety. Safety is formed through the adaptation of work practice to local conditions, and this adaptation is part of safe operation. Safety is not only a substantial quality of our socio-technical systems: the discursive dimension of safety actually seems to be a central component of safety creation. However, the adaptive ability of HRO can sometimes become their downfall. Adaptation, which is the backbone of safety, can sometimes be a drawback as well. Consequently, the practice view of safety, proposed in the present work, argues that we need to further comprehend how work practice evolves over time, and more specifically what are the inherent characteristics of work practice that create this evolution. Empirical studies from health-care and nuclear power generation highlight different details about organizational reliability. For instance, one study of planning at a nuclear power plant draws our attention to the different roles of planning in the organization. Another study, within heath-care, underlines the evolution of

  8. Annual meeting on nuclear technology '85. Technical session on nuclear power plant simulators. Jahrestagung Kerntechnik '85. Fachsitzung Simulatoren bei Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    The ten lectures read at this Technical Session deal with nuclear power plant simulators and their functions for the training of control room personnel, with test facilities for analysis and simulation of incidents and the relevant plant behaviour, and with the computer codes for fast simulation of reactor processes. The papers explain in particular the HAMMLAB project, the COSIMA fast core simulator, and the OPAL simulator for the KWU convoy process information system named PRINS.

  9. Technical Work Plan for: Near Field Environment: Engineered System: Radionuclide Transport Abstraction Model Report

    Energy Technology Data Exchange (ETDEWEB)

    J.D. Schreiber

    2006-12-08

    This technical work plan (TWP) describes work activities to be performed by the Near-Field Environment Team. The objective of the work scope covered by this TWP is to generate Revision 03 of EBS Radionuclide Transport Abstraction, referred to herein as the radionuclide transport abstraction (RTA) report. The RTA report is being revised primarily to address condition reports (CRs), to address issues identified by the Independent Validation Review Team (IVRT), to address the potential impact of transport, aging, and disposal (TAD) canister design on transport models, and to ensure integration with other models that are closely associated with the RTA report and being developed or revised in other analysis/model reports in response to IVRT comments. The RTA report will be developed in accordance with the most current version of LP-SIII.10Q-BSC and will reflect current administrative procedures (LP-3.15Q-BSC, ''Managing Technical Product Inputs''; LP-SIII.2Q-BSC, ''Qualification of Unqualified Data''; etc.), and will develop related Document Input Reference System (DIRS) reports and data qualifications as applicable in accordance with prevailing procedures. The RTA report consists of three models: the engineered barrier system (EBS) flow model, the EBS transport model, and the EBS-unsaturated zone (UZ) interface model. The flux-splitting submodel in the EBS flow model will change, so the EBS flow model will be validated again. The EBS transport model and validation of the model will be substantially revised in Revision 03 of the RTA report, which is the main subject of this TWP. The EBS-UZ interface model may be changed in Revision 03 of the RTA report due to changes in the conceptualization of the UZ transport abstraction model (a particle tracker transport model based on the discrete fracture transfer function will be used instead of the dual-continuum transport model previously used). Validation of the EBS-UZ interface model

  10. The nuclear smuggling international technical working group: Making a difference in combating illicit trafficking

    International Nuclear Information System (INIS)

    Niemeyer, S.; Koch, L.

    2001-01-01

    The ITWG was first formed in 1995 for the purpose of fostering international cooperation for combating illicit trafficking of nuclear materials. The initial focus for the ITWG was on the development of nuclear forensics to help answer attribution questions regarding nuclear materials of unknown origin. More recently, the ITWG has also expanded its focus to include detection of nuclear materials during transit. This paper presents some of the key developments by this group and their potential impact for combating nuclear smuggling. The initial focus of the ITWG was to write a status report on international cooperation on nuclear smuggling forensic analysis. This report was submitted to the G-8 countries, and shortly thereafter, nuclear forensics was endorsed at the Moscow Summit in April, 1996, as part of an illicit trafficking program. The ITWG's primary goal is to develop a preferred approach to nuclear forensic investigations that is widely understood and accepted as credible. The technical elements include: 1) development of protocols for a) collection and preservation of evidence and b) for laboratory investigation; 2) prioritizing of techniques for forensic analysis; 3) development of forensic databanks to assist in interpretation; 4) executing inter-laboratory exercises; and 5) facilitating technical assistance to countries upon request. The development of protocols has been conducted jointly by law enforcement officials and laboratory scientists. A major focus during much of the past five years has been the development of a model action plan for nuclear forensics of seized nuclear materials. This action plan lays out the elements that are needed in the instance that illicit nuclear material is uncovered, e.g. incident response, crime scene analysis, collection of evidence (both radioactive and 'traditional' forensics, transportation to a nuclear facility, subsequent laboratory analysis, and then development of the case. At the most recent meeting (ITWG-6

  11. 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

  12. Technical development to remove radionuclides from agricultural soils by plants (Joint research)

    International Nuclear Information System (INIS)

    Yamada, Satoshi; Sakoda, Akihiro; Ishimori, Yu

    2012-07-01

    Tottori University and Japan Atomic Energy Agency started a joint study to develop an environmental remediation technique for agricultural soil. Nine plants were water-cultured and examined for screening. A few were selected as candidates for demonstrations in fields. Preselected plants were mainly halophytes that can specifically absorb more Na than K, and others like sunflower demonstrated for domestic large-scale tests. Easily cultivated and harvested plants without harmful effect on new agriculture were also considered. Seedings prepared were first grown for a certain term. Additive-free, 133 Cs and 88 Sr groups, which are both stable isotopes, were then made. Cs (CsCl) and Sr (SrCl 2 ·6H 2 O) contents in cultures were 1.6836 mg/L (0.01 mM) and 266.62 mg/L (1 mM), respectively. Stems, leaves and roots were harvested, in principle, two weeks after the addition, to measure K, Ca, Mg, Sr and Cs concentrations in them. Considering the examination period, a content rate (i.e. element amount per dry sample weight) was regarded as an index. It was concluded that New Zealand spinach and ice plant were most adequate for removing contaminants from surface soil. The two accumulate Cs and Sr mostly in the shoots, are prostrate, and spread the roots shallowly. For valid application, growth-phase dependences of absorption and distribution, growth property and root distribution should be elucidated. Plants that meet the present purpose are ones that specifically absorb object substances, or that show normal absorption but high removal rate per area due to the large bulk size. The latter view also needs to be evaluated when the field test is conducted, since developing stages of the plants used in the present work were not correspondent. Finally, the application study plan was developed based on the screening test results. (author)

  13. Evaluation of systems interactions in nuclear power plants: Technical findings related to Unresolved Safety Issue A-17

    International Nuclear Information System (INIS)

    Thatcher, D.

    1989-05-01

    This report presents a summary of the activities related to Unresolved Safety Issue (USI)A-17, ''Systems Interactions in Nuclear Power Plants,'' and also includes the NRC staff's conclusions based on those activities. The staff's technical findings provide the framework for the final resolution of this unresolved safety issue. The final resolution will be published later as NUREG-1229. 52 refs., 4 tabs

  14. The working of RVNRL pilot plant of Rubber Board and it's safety devices

    International Nuclear Information System (INIS)

    Britto, I.J.; Thomas, E.V.

    1996-01-01

    A pilot plant for producing radiation vulcanized natural rubber latex (RVNRL) was established at Rubber Board, India in 1992. Irradiation is done by a batch process in the plant. The plant has a versatile safety system for safety of operators and people working in and around the plant

  15. Technical and economical studies on the modernization of small-scale hydroelectric power plants: difficulties and proposals; Estudo tecnico-economicos de mordernizacao de PCH`s: Dificuldades e propostas

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Antonio Tadeu Lyrio de; Beltrame, Eduardo; Santos, Afonso Henriques Moreira; Souza, Zulcy [Escola Federal de Engenharia de Itajuba, MG (Brazil)

    1989-12-31

    This work describes and analyses some technical alternatives to be used in re-designing or reforming small-scale hydroelectric power plants. In addition, some criteria are also presented in order to proceed a comparative evaluation based on economic feasibility 7 refs. 5 figs. 1 tab.

  16. Technical and economical studies on the modernization of small-scale hydroelectric power plants: difficulties and proposals; Estudo tecnico-economicos de mordernizacao de PCH`s: Dificuldades e propostas

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Antonio Tadeu Lyrio de; Beltrame, Eduardo; Santos, Afonso Henriques Moreira; Souza, Zulcy [Escola Federal de Engenharia de Itajuba, MG (Brazil)

    1990-12-31

    This work describes and analyses some technical alternatives to be used in re-designing or reforming small-scale hydroelectric power plants. In addition, some criteria are also presented in order to proceed a comparative evaluation based on economic feasibility 7 refs. 5 figs. 1 tab.

  17. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    1998-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include ''engineering tools'' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire PRA analyses are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (author)

  18. Technical methods for a risk-informed, performance-based fire protection program at nuclear power plants

    International Nuclear Information System (INIS)

    Dey, M.K.

    2000-01-01

    This paper presents a technical review and examination of technical methods that are available for developing a risk-informed, performance-based fire protection program at a nuclear plant. The technical methods include 'engineering tools' for examining the fire dynamics of fire protection problems, reliability techniques for establishing an optimal fire protection surveillance program, fire computer codes for analyzing important fire protection safety parameters, and risk-informed approaches that can range from drawing qualitative insights from risk information to quantifying the risk impact of alternative fire protection approaches. Based on this technical review and examination, it is concluded that methods for modeling fires, and reliability and fire probabilistic risk analyses (PRA) are currently available to support the initial implementation of simple risk-informed, performance-based approaches in fire protection programs. (orig.) [de

  19. A technical pilot plant assessment of flue gas desulfurisation in a circulating fluidised bed

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez, F.J.; Ollero, P. [Universidad de Sevilla (Spain). Dept. de Ingenieria Quimica y Ambiental; Cabanillas, A.; Otero, J. [Centro de Investigaciones Energeticas y Medioambientales, (CIEMAT), Madrid (Spain)

    2002-11-01

    Flue gas desulfurisation in a circulating fluidised bed absorber (CFBA) is quite a novel dry desulfurisation technology [6th International Conference on Circulating Fluidised Beds (1999) 601] that shows significant advantages in comparison with other dry technologies and that could also be competitive with the widely-used wet FGD technology. This experimental study analyses the performance of a flue gas treatment plant comprising a CFBA and an electrostatic precipitator (ESP). The most significant aspects considered in this study are: the effect of precollecting the fly ash, the effect of the SO{sub 2} inlet concentration, the effect of power plant load changes, the contribution of the final particulate control equipment to the overall SO{sub 2} removal efficiency and the impact of the desulfurisation unit on the ESP behaviour and its final dust emissions. In addition, the behaviour of the integrated CFBA-ESP system with respect to the main operating parameters was studied by means of a fractional factorial design of experiments. All this experimental work was carried out in a 3-MWe equivalent pilot plant that processes real gases withdrawn from the Los Barrios Power Plant. Processing a flue gas with up to 2000 ppm SO{sub 2} concentration, a sulfur removal of 95-97% with a lime utilisation of 75% was achieved. A simple regression model to evaluate the efficiency of the whole system is also proposed.(author)

  20. Analysis and evaluation of the ASTEC model basis on plant simulations. 2. Technical report

    International Nuclear Information System (INIS)

    Koppers, Vera; Braehler, Thimo; Koch, Marco K.

    2015-06-01

    The present report is the 2 nd Technical Report of the research project ''Analysis and Evaluation of the ASTEC model basis'' funded by the Federal Ministry for Economic Affairs and Energy (BMWi 1501433) and conducted at the Reactor Simulation and Safety Group, Chair of Energy Systems and Energy Economics (LEE) at Ruhr-Universitaet Bochum. Within this report, the quality of a nuclear power plant simulation with ASTEC is investigated. Different parameters are varied to analyze the simulation stability within the dataset, which describes a generic German Konvoi power plant and is deposit in the program set of ASTEC. Firstly, plant specifications in the data set are checked for plausibility. In addition, the compliance of the data set with the nodalization rules is verified. After that, the stationary phase, in which no accident is calculated, is analyzed and parametric studies are performed in the transient phase, focusing on the primary and secondary circuit as well as on the containment behavior. The performed calculations focusing the primary and secondary circuit indicate a high dependency of the simulation results on the user's input in the data set. There are significant deviations between each simulations results, for example in the different calculated point of time of the reactor pressure vessel failure. Already changes in the stationary phase cause a significantly earlier reactor pressure vessel failure compared to the simulation with the original data. Beyond that, the location of the leakage of the reactor pressure vessel lower head varied and therefore cannot be clearly determined, although there have been no changes by the user on the accident course. A reliable indication of the plant behavior under severe accident conditions is therefore difficult using ASTEC. The results of the parametric studies within the Containment show the same significant influence of certain parameter changes on the simulation results. By using the

  1. Technical solutions for mitigating adverse impacts on the environment implemented at Deva Thermal Power Plant

    International Nuclear Information System (INIS)

    Vaida, Victor; Egyed, Francisc; Manea, Laurean

    2004-01-01

    harmony with current and prospective environmental protection demands, especially for air protection. The facts herein presented clearly show the financial efforts so far made in operation as well as for prospective investments in further modernisation of the electrostatic precipitators and implementation of desulfurization plants, as top priorities. Another concern is the landscape and agricultural reinstatement of the ash disposal dumps that have been filled thus mitigating to the greatest extent possible the adverse effects that the existence of Deva Power Plant creates in its environment. A parallel ash recycling process has been initiated by marketing the dry ash to be used in the cement industry; the Power Plant collaborate with an important neighbouring cement producer for this purpose. The impact that the ash disposal dump has on the environment will be thus alleviated. The ash disposal area will also be reduced with the increase in the need of ash to be utilised on other commercial activities. The action plan for desulfurization, and gas emission mitigation in general, elaborated by Deva Power Plant has been integrated in a national average term programme involving all power industry polluting bodies. The flue gas desulfurization programme requires further modernisation of main power generation systems, primarily of burners to reduce NOx emission level below 500 mg/Nm 3 , and of electrostatic precipitators to reduce the powder emissions below 50 mg/Nm 3 . By adopting the wet limestone desulfurization method, SO 2 emissions into the air will be decreased from 50,000 tons annually to 4,500 tons and the desulfurization by-products will be marketed for the cement industry or infrastructure works

  2. International Working Group on Life Management of Nuclear Power Plants. (IWG-LMNPP). Regular meeting. Working material. V. 2

    International Nuclear Information System (INIS)

    1998-01-01

    National programs of Hungary, Japan, Korea, Russian Federation, Bulgaria, Slovenia, Sweden, Switzerland, Ukraine, United Kingdom and USA, related to nuclear power plants life management presented at the Technical Committee Meeting are published in this volume. The main features of the reports are oriented towards extension of NPP lifetime and conditions indispensable to achieve in order to fulfil the safety requirements including testing the mechanical properties of relevant reactor components

  3. International Working Group on Life Management of Nuclear Power Plants. (IWG-LMNPP). Regular meeting. Working material. V. 1

    International Nuclear Information System (INIS)

    1998-01-01

    National programs of Argentina, Brazil, Belgium, Czech Republic, Canada, France and Germany related to nuclear power plants life management presented at the Technical Committee Meeting are published in this volume. Finnish report VTT-TIED-1843 included in this volume was already included separately in the INIS Database. The main features of the reports are oriented towards extension of NPP lifetime and conditions indispensable to achieve in order to fulfil the safety requirements including testing the mechanical properties of relevant reactor components

  4. Technical assessment of TRUSAF for compliance with work place air sampling. Revision 1

    International Nuclear Information System (INIS)

    Butler, J.D.

    1995-01-01

    The purpose of this Technical Work Document is to satisfy WHC-CM-1-6, the ''WHC Radiological Control Manual.'' This first revision of the original Supporting Document covers the period from January 1, 1994 to December 31, 1994. WHC-CM-1-6 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. In addition to WHC-CM-1-6, there is HSRCM-1, the ''Hanford Site Radiological Control Manual'' and several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. this document also provides an evaluation of the compliance of the TRUSAF workplace air sampling program to the criteria, standards, and requirements and documents. Where necessary, it also indicates changes needed to bring specific locations into compliance

  5. Forty-Second Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2009-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 41st TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meetings meeting arrangements for 2009, 2010, 2011 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2010-2011

  6. COMPUTER-BASED SYSTEMS OF PHYSICAL EXPERIMENT IN INDEPENDENT WORK OF STUDENTS OF TECHNICAL UNIVERSITY

    Directory of Open Access Journals (Sweden)

    Iryna Slipukhina

    2016-11-01

    Full Text Available Purpose: The self-study activity of students is an important form of educational process under the conditions of rapid changes of technologies. Ability and readiness of future engineers for independent education is one of their key competences. Investigation of modern methods of planning, organization and control of independent cognitive activity of students while studying physics as effective means of complex forming of their professional qualities is the object of the research. Methods: We analyse the curricula of some engineering specialities in leading technical universities, existent methods and forms of organization of students’ self-study, and own pedagogical experience. Results: Based on the theoretical analysis of existing methods of students’ self-study, it was found that a systematizing factor of appropriate educational technology is the problem focused cognitive tasks. They have to be implemented by application of the modern technological devices integrated with a computer-based experiment. We define the aim of individual or group laboratory works; the necessary theoretical and practical knowledge and skills of students are rationalized; timing and form of presentation of the results are clarified after individual and group consulting. The details of preparatory, searching-organizational, operational, and control stages in organization of students’ self-study with the use of computer oriented physical experiment are specified, these details differ depending on the didactic purpose, form of organization and students’ individuality. Discussion: The research theoretical aspect confirms the determining role of subject-subject cooperation in forming of competences of independent learning of the future engineers. Basic practical achievements of the research consist of improving methods of using of digital learning systems, creation of textbooks that promote consultative and guiding role for the educational process, working-out of

  7. Technical and economical feasibility study of a sewage sludge disinfection plants by irradiation process

    International Nuclear Information System (INIS)

    Rojas Bustos, Gustavo

    1999-01-01

    This report presents a technical and economical evaluation for a disinfection plant of sewage sludge based on irradiation. The process starts after sludge stabilization which is achieved by anaerobic digestion. It includes two stages, plus an optional: the first corresponds to dewatering of sewage sludge up to a solids content between 20 and 25 %, the second stage corresponds to disinfection by gamma or electron beam irradiation, and the third, which is optional, corresponds to the drying of sewage sludge up to a water content of 50%, which allows to diminish significantly the volumes of solids to be transported. If this stage is not accomplished the final product corresponds to a sewage sludge with 25 % of dry solids, which can also be disposed in agricultural land. Process was designed to treat 60 tons per day of sewage sludge (dry matter basis). The report presents the design of process equipment, principal and auxiliary, the investment and operational cost estimations as well as the total cost of treatment per ton of sewage sludge. A sensitivity analysis is also included to determine the influence of operational process parameters in operational and investment costs. The results showed that a sewage sludge plant including dewatering and disinfection process through gamma irradiation, achieves a capital investment of about US$ 12.000.000 with a treatment cost per ton of dry sludge of US$140. Including the optional air-drying stage, the total cost of treatment is about US$148 per ton of dry matter. In the case of electron beam irradiation the capital investment achieves a value of US$ 11 millions with a total treatment cost of US$ 136 per ton of dry matter. These values resulted quite similar to the cost of alternative treatment, i.e., disposal in a dedicated landfill. (L.V.)

  8. How a submarine returns to periscope depth: analysing complex socio-technical systems using Cognitive Work Analysis.

    Science.gov (United States)

    Stanton, Neville A; Bessell, Kevin

    2014-01-01

    This paper presents the application of Cognitive Work Analysis to the description of the functions, situations, activities, decisions, strategies, and competencies of a Trafalgar class submarine when performing the function of returning to periscope depth. All five phases of Cognitive Work Analysis are presented, namely: Work Domain Analysis, Control Task Analysis, Strategies Analysis, Social Organisation and Cooperation Analysis, and Worker Competencies Analysis. Complex socio-technical systems are difficult to analyse but Cognitive Work Analysis offers an integrated way of analysing complex systems with the core of functional means-ends analysis underlying all of the other representations. The joined-up analysis offers a coherent framework for understanding how socio-technical systems work. Data were collected through observation and interviews at different sites across the UK. The resultant representations present a statement of how the work domain and current activities are configured in this complex socio-technical system. This is intended to provide a baseline, from which all future conceptions of the domain may be compared. The strength of the analysis is in the multiple representations from which the constraints acting on the work may be analysed. Future research needs to challenge the assumptions behind these constraints in order to develop new ways of working. Copyright © 2013 Elsevier Ltd and The Ergonomics Society. All rights reserved.

  9. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  10. Technical basis for environmental qualification of computer-based safety systems in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Tanaka, T.J.; Antonescu, C.E.

    1997-01-01

    This paper summarizes the results of research sponsored by the US Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. This research was conducted by the Oak Ridge National Laboratory (ORNL) and Sandia National Laboratories (SNL). ORNL investigated potential failure modes and vulnerabilities of microprocessor-based technologies to environmental stressors, including electromagnetic/radio-frequency interference, temperature, humidity, and smoke exposure. An experimental digital safety channel (EDSC) was constructed for the tests. SNL performed smoke exposure tests on digital components and circuit boards to determine failure mechanisms and the effect of different packaging techniques on smoke susceptibility. These studies are expected to provide recommendations for environmental qualification of digital safety systems by addressing the following: (1) adequacy of the present preferred test methods for qualification of digital I and C systems; (2) preferred standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging in qualification testing for equipment that is to be located in mild environments; and (5) determination of an appropriate approach to address smoke in a qualification program

  11. Three technical issues in fatigue damage assessment of nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Shah, V.N.

    1991-01-01

    This paper addresses three technical issues that affect the fatigue damage assessment of nuclear power plant components: the effect of the environment on the fatigue life, the importance of the loading sequence in calculating the fatigue crack-initiation damage, and the adequacy of current inservice inspection requirements and methods to characterize fatigue cracks. The environmental parameters that affect the fatigue life of carbon and low alloy steel components are the sulphur content in the steel, the temperature, the amount of dissolved oxygen in the coolant, and the presence of oxidizing agents such as copper oxide. The occurrence of large-amplitude stress cycles early in a component's life followed by low-amplitude stress cycles may cause crack initiation at a cumulative usage factor less than 1.0. The current inservice inspection requirements include volumetric inspections of welds but not of some susceptible sites in the base metal. In addition, the conventional ultrasonic testing techniques need to be improved for reliable detection and accurate sizing of fatigue cracks. 28 refs., 4 figs., 1 tab

  12. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    Energy Technology Data Exchange (ETDEWEB)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  13. Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants

    International Nuclear Information System (INIS)

    Sill, C.W.; Scarpellino, C.D.; Tkachyk, J.W.; Grey, A.E.; Frank, C.W.

    1985-05-01

    Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented

  14. Technical and economic viability of electric power plants on the basis of renewable energy resources regarding hierarchical structure

    Directory of Open Access Journals (Sweden)

    Balzannikov Mikhail

    2017-01-01

    Full Text Available The article deals with power stations working on the basis of non-renewable energy resources and finite resources which will inevitably come to depletion in the future. These installations produce considerable negative impact on the environment, including air pollution. It is noted that considerable amounts of emissions of harmful substances accounts for the share of small thermal installations which aren’t always considered in calculations of pollution. The author specifies that emission reduction of harmful substances should be achieved due to wider use of environmentally friendly renewable energy resources. It is recommended to use hierarchical structure with the priority of ecological and social conditions of the region for technical and economic viability of consumers’ power supply systems and installations, based on renewable energy resources use. At the same time the author suggests considering federal, regional and object levels of viability. It is recommended to consider the main stages of lifecycle of an object for object level: designing, construction, operation, reconstruction of an object and its preservation. The author shows the example of calculation of power plant efficiency, based on renewable energy resources during its reconstruction, followed by power generation increase.

  15. Independent verification of a material balance at a LEU fuel fabrication plant. Program for technical assistance to IAEA safeguards

    International Nuclear Information System (INIS)

    Sorenson, R.J.; McSweeney, T.I.; Hartman, M.G.; Brouns, R.J.; Stewart, K.B.; Granquist, D.P.

    1977-11-01

    This report describes the application of methodology for planning an inspection according to the procedures of the International Atomic Energy Agency (IAEA), and an example evaluation of data representative of low-enriched uranium fuel fabrication facilities. Included are the inspection plan test criteria, the inspection sampling plans, the sample data collected during the inspection, acceptance testing of physical inventories with test equipment, material unaccounted for (MUF) evaluation, and quantitative statements of the results and conclusions that could be derived from the inspection. The analysis in this report demonstrates the application of inspection strategies which produce quantitative results. A facility model was used that is representative of large low-enriched uranium fuel fabrication plants with material flows, inventory sizes, and compositions of material representative of operating commercial facilities. The principal objective was to determine and illustrate the degree of assurance against a diversion of special nuclear materials (SNM) that can be achieved by an inspection and the verification of material flows and inventories. This work was performed as part of the USA program for technical assistance to the IAEA. 10 figs, 14 tables

  16. Experiences with a technically oriented plant management system; Erfahrungen mit einem technisch orientierten Betriebs-Management-System

    Energy Technology Data Exchange (ETDEWEB)

    Haffmann, E. [GiS Gesellschaft fuer integrierte Systemplanung mbH, Erlangen (Germany)

    2000-07-01

    This contribution first deals with the duality of mercantile and technical plant management systems. The following aspects are considered: reasons for and history of this duality; different approaches taken by mercantile and technical plant management systems; differences in the standardisability of mercantile and technical tasks. Dissolution of the duality through coordinated interplay. The author then goes on to explain the most important components of technically oriented maintenance management. These include the collection of technical plant data (with maintenance-relevant data and relations); the establishment of recurring tasks, the commissioning method (involving occupational safety, packaging and evaluation), compilation of manuals, reporting and accompanying plant documentation. The following tools are useful for DP-assisted maintenance: depiction of organisational and operational structures (authorisation system + IBFS application); workflow systems; modelling (data and object models); navigators; form and dialogue generators; integration of external software (project planning, CAD and Office); interface to mercantile systems. Some highlights of the C/S-IBFS were demonstrated in practice at the symposium. [German] Das Referat behandelt zunaechst die Dualitaet von kaufmaennischen und technischen Betriebs-Management-Systemen anhand folgender Aspekte: - Gruende und Historie dieser Dualitaet, - unterschiedliche Loesungsansaetze von kaufmaennischen und technischen Betriebs-Management-Systemen, - unterschiedliche Standardisierbarkeit von kaufmaennischen und technischen Aufgabenstellungen, - Aufloesung der Dualitaet durch koordniertes Zusammenwirken. Sodann werden wichtige Bausteine eines technisch orientierten Instandhaltungs-Managements erlaeutert. Dazu gehoeren die technische Anlagenerfassung (mit instandhaltungsrelevanten Daten und Relationen), die Einrichtung wiederkehrender Aufgaben, das Arbeitsauftragsverfahren (mit Arbeitssicherheit, Paketierung und

  17. Implications of power uprates on safety margins of nuclear power plants. Report of a technical meeting

    International Nuclear Information System (INIS)

    2004-09-01

    The safety of nuclear power plants (NPPs) is based on the defence in depth concept, which relies on successive physical barriers (fuel matrix, cladding, primary system pressure boundary and containment) and other provisions to control radioactive materials and on multiple levels of protection against damage to these barriers. Deterministic safety analysis is an important tool for conforming the adequacy and efficiency of provisions within the defence in depth concept and is used to predict the response of an NPP in predetermined operational states. This type of safety analysis applies a specific set of rules and specific acceptance criteria. Deterministic analysis is typically focused on neutronic, thermohydraulic, radiological and structural aspects, which are often analysed with different computational tools. The advanced computational tools developed for deterministic safety analysis are used for better establishment and utilization of licensing margins or safety margins in consideration of analysis results. At the same time, the existence of such margins ensures that NPPs operate safely in all modes of operation and at all times. To properly assess and address the existing margins and to be able to take advantage of unnecessary conservatisms, state of the art analytical tools intended for safety assessment have been developed. Progress made in the development and application of modern codes for safety analysis and better understanding of phenomena involved in plant design and operation enable the analysts to determine safety margins in consideration of analysis results (licensing margins) with higher precision. There is a general tendency for utilities to take advantage of unnecessarily large conservatisms in safety analyses and to utilize them for reactor power uprates, better utilization of nuclear fuel, higher operational flexibility and for justification of lifetime extension. The present publication sets forth the results of a Technical Meeting on the

  18. Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Research and Development Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, E.S.; Homer, G.B.; Shaber, C.R.; Thurow, T.L.

    1981-11-17

    The Raft River Geothermal Site is located in Southern Idaho's Raft River Valley, southwest of Malta, Idaho, in Cassia County. EG and G idaho, Inc., is the DOE's prime contractor for development of the Raft River geothermal field. Contract work has been progressing for several years towards creating a fully integrated utilization of geothermal water. Developmental progress has resulted in the drilling of seven major DOE wells. Four are producing geothermal water from reservoir temperatures measured to approximately 149 C (approximately 300 F). Closed-in well head pressures range from 69 to 102 kPa (100 to 175 psi). Two wells are scheduled for geothermal cold 60 C (140 F) water reinjection. The prime development effort is for a power plant designed to generate electricity using the heat from the geothermal hot water. The plant is designated as the ''5 MW(e) Raft River Research and Development Plant'' project. General site management assigned to EG and G has resulted in planning and development of many parts of the 5 MW program. Support and development activities have included: (1) engineering design, procurement, and construction support; (2) fluid supply and injection facilities, their study, and control; (3) development and installation of transfer piping systems for geothermal water collection and disposal by injection; and (4) heat exchanger fouling tests.

  19. Internal Technical Report, Safety Analysis Report 5 MW(e) Raft River Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, E.S.; Homer, G.B.; Spencer, S.G.; Shaber, C.R.

    1980-05-30

    The Raft River Geothermal Site is located in Southern Idaho's Raft River Valley, southwest of Malta, Idaho, in Cassia County. EG and G idaho, Inc., is the DOE's prime contractor for development of the Raft River geothermal field. Contract work has been progressing for several years towards creating a fully integrated utilization of geothermal water. Developmental progress has resulted in the drilling of seven major DOE wells. Four are producing geothermal water from reservoir temperatures measured to approximately 149 C (approximately 300 F). Closed-in well head pressures range from 69 to 102 kPa (100 to 175 psi). Two wells are scheduled for geothermal cold 60 C (140 F) water reinjection. The prime development effort is for a power plant designed to generate electricity using the heat from the geothermal hot water. The plant is designated as the ''5 MW(e) Raft River Research and Development Plant'' project. General site management assigned to EG and G has resulted in planning and development of many parts of the 5 MW program. Support and development activities have included: (1) engineering design, procurement, and construction support; (2) fluid supply and injection facilities, their study, and control; (3) development and installation of transfer piping systems for geothermal water collection and disposal by injection; and (4) heat exchanger fouling tests.

  20. TECHNICAL AND TECHNOLOGICAL ASPECTS IN PLANT PROTECTION IN THE PRECISION FARMING SYSTEM

    Directory of Open Access Journals (Sweden)

    Mladen Jurišić

    2015-06-01

    Full Text Available The basic premise of precision farming as a larger amount of information is its availability to the farmer in making decision. Direct comparison of perennial parameters obtained from the plot results in purposefully, argumentative and optimal use of resources for work (while keeping in mind the ecological impact. Today, the development of satellite navigation technology and monitoring of agricultural machinery, and reducing the cost of these devices again revived the question of the precision agriculture application. Advanced farmers in developed agricultural countries already regularly apply some of the technological possibilities of precision farming. Precision agriculture and plant protection allow the farmer realizing high incomes while keeping safe natural resources. Using modern GIS technology machines collect data directly from the plot using sensors and integrate themselves into the data processing system. Processed information is used by a farmer taking GreenStar system for the new planned operation and achieving significant time and money spare. Precision agriculture offers the possibility of optimal care of each plant, not just the average, or the entire field. Low risk investments are one of the main factors of choice precise plant protection. The use of pilotless aircrafts remote sensing allow fast and economical obtaining data and sufficient precision information. Using modern technology such as Variable Rate Application (applying a variable volume and GreenStar software package it is possible to regulate the amount of care and protection.

  1. The concurrent validity of the technical test battery as an indicator of work performance in a telecommunications company

    Directory of Open Access Journals (Sweden)

    Marelize Barnard

    2005-10-01

    Full Text Available The purpose of this study was to assess the concurrent validity of the Technical Test Battery (TTB in a South African telecommunications institution. The Technical Test Battery (TTB was administered to a sample of 107 technical officers. Their test scores were compared to the scores obtained from a job performance rating scale specifically designed for this position on the basis of a thorough job analysis. The TTB demonstrated high concurrent validity as an indicator of work performance for technical posts in the telecommunications environment. These results suggest that the TTB may have a high predictive validity for performance in technical positions. The findings and implications of the study are discussed. Opsomming Die doel van hierdie studie was om die samevallende geldigheid van die “Technical Test Battery (TTB�? in ’n Suid-Afrikaanse telekommunikasie instansie te bepaal. Die TTB is op ’n steekproef van 107 tegniese personeel toegepas. Die toetstellings is in verband gebring met die tellings van ’n werksprestasiemaatstaf wat spesifiek vir die pos ontwikkel is op grond van ’n deeglike posanalise. Daar is bevind dat die TTB ’n hoë samevallende geldigheid as aanduider van werksprestasie vir tegniese poste in the telekommunikasiebedryf toon. Dié resultate dui op ’n sterk moontlikheid dat die TTB ’n goeie voorspeller van werksprestasie vir tegniese beroepe kan wees. Die bevindinge en implikasies van die studie word bespreek.

  2. Technical and economic evaluation of processes for krypton-85 recovery from power fuel-reprocessing plant off-gas

    International Nuclear Information System (INIS)

    Waggoner, R.C.

    1982-08-01

    A technical and economical analysis has been made of methods for collecting and concentrating krypton from the off-gas from a typical nuclear fuel reprocessing plant. The methods considered were cryogenic distillation, fluorocarbon absorption, mordenite adsorption, and selective permeation. The conclusions reached were: Cryogenic distillation is the only demonstrated route to date. Fluorocarbon absorption may offer economic and technical advantages if fully developed and demonstrated. Mordenite adsorption has been demonstrated only on a bench scale and is estimated to cost more than either cryogenic distillation or fluorocarbon absorption. Selective permeation through a silicone rubber membrane is not sufficiently selective for the route to be cost effective

  3. Technical update on pressure suppression type containments in use in U.S. light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1978-07-01

    In 1972, Dr. S. H. Hanauer (Technical Advisor to the NRC's Executive Director for Operations) wrote a memorandum that raised several questions on the viability of pressure suppression containment concepts. The concerns raised by Dr. Hanauer have recently become the subject of considerable discussion by several members of the U.S. Congress and public. The report provides a response to these expressed concerns and a status summary for various technical matters that relate to the safety of pressure suppression type containments for light water cooled reactor plants

  4. The Apatity nuclear heating plant project: modern technical and economic issues of nuclear heat application in Russia

    International Nuclear Information System (INIS)

    Adamov, E.O.; Romenkov, A.A.

    1998-01-01

    Traditionally Russia is a country with advanced structure of centralized heat supply. Many thermal plants and heating networks need technical upgrading to improve their technical and economic efficiency. Fossil fuelled heating capacities have a negative influence on ecology, which can be seen especially in the northern regions of Russia. Furthermore, fossil fuel prices are rising in Russia. The above factors tend to intensify the need for alternative heat sources being capable of solving the problem. Nuclear heat sources may be the alternative. In this paper, the main features of a proposed NHP in the Murmansk region are summarized. (author)

  5. Causal Effects of Career-Technical Education on Postsecondary Work Outcomes of Individuals with High-Incidence Disabilities

    Science.gov (United States)

    Lee, Heok In; Rojewski, Jay W.; Gregg, Noel

    2016-01-01

    Using data from the National Longitudinal Transition Study-2, a propensity score analysis revealed significant causal effects for a secondary career and technical education (CTE) concentration on the postsecondary work outcomes of adolescents with high-incidence disabilities. High school students identified as CTE concentrators (three or more high…

  6. Mixed Methods in Education Research. IES Technical Working Group Meeting. Meeting Summary (Washington, DC, May 29, 2015)

    Science.gov (United States)

    Institute of Education Sciences, 2015

    2015-01-01

    This meeting summary is organized into two major sections. The first section captures the individual contribution of meeting participants, including both Institute of Education Sciences (IES) staff and the invited technical working group members. The second section captures themes that arose during the group discussions, which were organized…

  7. Report on generation IV technical working group 3 : liquid metal reactors

    International Nuclear Information System (INIS)

    Lineberry, M. J.; Rosen, S. L.; Sagayama, Y.

    2002-01-01

    This paper reports on the first round of R and D roadmap activities of the Generation IV (Gen IV) Technical Working Group (TWG) 3, on liquid metal-cooled reactors. Liquid metal coolants give rise to fast spectrum systems, and thus the reactor systems considered in this TWG are all fast reactors. Gas-cooled fast reactors are considered in the context of TWG 2. As is noted in other Gen IV papers, this first round activity is termed ''screening for potential'', and includes collecting the most complete set of liquid metal reactor/fuel cycle system concepts possible and evaluating the concepts against the Gen IV principles and goals. Those concepts or concept groups that meet the Gen IV principles and which are deemed to have reasonable potential to meet the Gen IV goals will pass to the next round of evaluation. Although we sometimes use the terms ''reactor'' or ''reactor system'' by themselves, the scope of the investigation by TWG 3 includes not only the reactor systems, but very importantly the closed fuel recycle system inevitably required by fast reactors. The response to the DOE Request for Information (RFI) on liquid metal reactor/fuel cycle systems from principal investigators, laboratories, corporations, and other institutions, was robust and gratifying. Thirty three liquid metal concept descriptions, from eight different countries, were ultimately received. The variation in the scope, depth, and completeness of the responses created a significant challenge for the group, but the TWG made a very significant effort not to screen out concepts early in the process

  8. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The discussion which followed the different presentations highlighted the following points: • All the Member States representatives participating in the technical meeting welcomed this IAEA initiative and expressed their potential interest in contributing to the catalogue; • Not all the countries with a fast reactor programme were represented at the meeting. In particular, it was noted that there was no participation from China, the Russian Federation and the USA. Even contribution from Sweden and Spain would be beneficial. It will be a task of the IAEA Secretariat to try involving also these countries in the preparation of the catalogue; • The catalogue will focus only on experimental facilities supporting development of liquid metal cooled fast reactors (Sodium, Lead and Lead-Bismuth). For the time being, facilities in support of GFR and MSR research will not be included; • As for countries involved in HLM technology research, only European countries were participating at the meeting, i.e. Belgium, France, Italy and Germany. In order to avoid duplication of the work performed within the European project ADRIANA, representatives from these countries underlined that a condition for their contribution to the IAEA catalogue is the involvement of non-European countries with HLM research programmes; • The advice from the Member States is fundamental to clearly define scope, objectives and content of the catalogue. The plan for its drafting has also to be further discussed with Member States representatives; • The catalogue is also intended to identify gaps and future needs that require further R&D initiatives; • The catalogue will be a useful tool to set up international collaboration

  9. Forty-Fourth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2011-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 43rd TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Project&Budget (P&B) biennium 2012-2013; - Review the IAEA’s ongoing information exchange and coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.)

  10. Reality and Analysis: Personal and Technical Reflections on the Working Lives of Six Women.

    OpenAIRE

    Chen, M.; Jhabvala, R.; Kanbur, R.; Mirani, N.; Osner, Karl (Eds) WIEGO

    2004-01-01

    A group of development analysts had a dialogue about labor market, trade and poverty issues in 2004. They preceded the dialogue with exposure to the realities of the lives of six remarkable women from the Self-Employed Women's Association (SEWA) in Gujarat, India. The struggles faced by the authors provided the frame for the technical dialogue that followed. This is a Compendium of personal and technical reflections of the analysts involved in the exercise.

  11. Forty-Sixth Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were to: • Review the current status and the progress since the 45th TWG-FR meeting of FR and ADS technology development activities in IAEA Member States; • Review the activities (past, present and planned) of the IAEA’s project 1.1.5.3, “Support for fast reactor research, technology development and deployment” to ensure that they remain relevant to the needs of Member States; • Provide the experts group with updates to advise the IAEA on FR and ADS activities, including on proposals for relevant studies and reviews; • Serve as a means for exchanging information on national and international FR and ADS programmes; • Review the main achievements and outcomes of the “International Conference on Fast Reactors and Related Fuel Cycle: Safe Technologies and Sustainable Scenarios – FR13”, held on 4 – 7 March 2013 in Paris, France; • Promote the exchange of technical information by proposing topics for, and assisting in the organization of, IAEA Workshops and Technical Meetings for 2014-2015 and further, and • Review the IAEA’s concluded, on-going and planned coordinated research projects (CRPs) in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, Euratom, etc.)

  12. Modular construction of nuclear power plants in Korea and technical issues - 15051

    International Nuclear Information System (INIS)

    Kim, T.I.; Kim, K.K.; Yoon, J.J.; Han, G.E.

    2015-01-01

    The construction of nuclear power plants (NPPs) is the process of installing structures, systems and components (SCCs) of NPPs within a targeted time and a budget while ensuring quality and safety. Recently various efforts have been made in the nuclear industry to construct NPPs more effectively and modular construction has been highlighted as one of the most effective methods. Modular construction has been known to be effective in reducing construction time, allocating labor and equipment more efficiently while ensuring quality. The installation of structures and systems requires stable provision of labor force which is essential to keep the installation work of bulk materials such as re-bars, pipes and so forth in a construction site over a long period. Especially, in the case of the structure work, it is greatly affected by weather conditions such as rainfall, snow and wind, and discontinuity of installation work due to weather is directly related with success of a construction project. The most significant feature of modular construction is that SSCs could be pre-fabricated at an off-site factory or an assembly shop near a construction site, which provides stable labor force and favorable work condition impervious to weather. Reinforced concrete is largely used in NPPs and re-bar and form works are time consuming requiring lots of labor force at a construction site. Various efforts have been made to install re-bars and forms at the same time, which led to the development of SC structures. SC structures are composed of face steel plates which work as forms for concrete pouring as well as reinforcement for concrete. In this paper, we are going to introduce module types applicable to construction of NPPs and the status of modular construction in Korea. In addition, several issues will be addressed for the successful application of modular construction

  13. Development of Molten-Salt Heat Transfer Fluid Technology for Parabolic Trough Solar Power Plants - Public Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Grogan, Dylan C. P.

    2013-08-15

    Executive Summary This Final Report for the "Development of Molten-Salt Heat Transfer Fluid (HTF) Technology for Parabolic Trough Solar Power Plants” describes the overall project accomplishments, results and conclusions. Phase 1 analyzed the feasibility, cost and performance of a parabolic trough solar power plant with a molten salt heat transfer fluid (HTF); researched and/or developed feasible component options, detailed cost estimates and workable operating procedures; and developed hourly performance models. As a result, a molten salt plant with 6 hours of storage was shown to reduce Thermal Energy Storage (TES) cost by 43.2%, solar field cost by 14.8%, and levelized cost of energy (LCOE) by 9.8% - 14.5% relative to a similar state-of-the-art baseline plant. The LCOE savings range met the project’s Go/No Go criteria of 10% LCOE reduction. Another primary focus of Phase 1 and 2 was risk mitigation. The large risk areas associated with a molten salt parabolic trough plant were addressed in both Phases, such as; HTF freeze prevention and recovery, collector components and piping connections, and complex component interactions. Phase 2 analyzed in more detail the technical and economic feasibility of a 140 MWe,gross molten-salt CSP plant with 6 hours of TES. Phase 2 accomplishments included developing technical solutions to the above mentioned risk areas, such as freeze protection/recovery, corrosion effects of applicable molten salts, collector design improvements for molten salt, and developing plant operating strategies for maximized plant performance and freeze risk mitigation. Phase 2 accomplishments also included developing and thoroughly analyzing a molten salt, Parabolic Trough power plant performance model, in order to achieve the project cost and performance targets. The plant performance model and an extensive basic Engineering, Procurement, and Construction (EPC) quote were used to calculate a real levelized cost of energy (LCOE) of 11.50

  14. Experience in monitoring ageing phenomena for improving nuclear power plant availability. Proceedings of a specialists' meeting. Working material

    International Nuclear Information System (INIS)

    1992-01-01

    For more than thirty years nuclear power plants have been supplying electricity to national grids. Today, the nuclear power community is facing great challenges. The safe, reliable operation of existing nuclear power plants (NPPs) must continue to be ensured. From an economic viewpoint, because of the long lead times associated with bringing new plants into service, securing the continued operation of existing plants for their planned lifetimes and possible life extension will be very important in the near term for meeting electrical power demands. The IAEA programmes in nuclear power plant ageing and life extension and in control and instrumentation promote technical information exchange between Member States with new programmes, offers assistance to Member States with an interest in reliability of NPP components, in-service inspection methods and programmes using on-line techniques, component monitoring and special technological topics of nuclear reactors. Significant experience already exists in the nuclear industry in developing and applying the monitoring techniques for different nuclear power plant applications, especially in monitoring of ageing phenomena for improving NPP availability. The purpose of this Specialists' Meeting was to bring together experts from operations, design, research and development and licensing to share their experience in: ageing mechanics of key structural components, methods of monitoring such ageing, tools for cost-effective implementation of the methods and methodologies, life management approaches and examples from current reactors, future direction for monitoring of key structural components in nuclear power plants. The meeting was organized by the IAEA International Working Groups on Life Management of Nuclear Power Plants (IWG-LMNPP) and Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) in co-operation with the Czechoslovak Atomic Energy Commission and Skoda concern. Around 40 participants from 10 countries

  15. Experience in monitoring ageing phenomena for improving nuclear power plant availability. Proceedings of a specialists' meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    For more than thirty years nuclear power plants have been supplying electricity to national grids. Today, the nuclear power community is facing great challenges. The safe, reliable operation of existing nuclear power plants (NPPs) must continue to be ensured. From an economic viewpoint, because of the long lead times associated with bringing new plants into service, securing the continued operation of existing plants for their planned lifetimes and possible life extension will be very important in the near term for meeting electrical power demands. The IAEA programmes in nuclear power plant ageing and life extension and in control and instrumentation promote technical information exchange between Member States with new programmes, offers assistance to Member States with an interest in reliability of NPP components, in-service inspection methods and programmes using on-line techniques, component monitoring and special technological topics of nuclear reactors. Significant experience already exists in the nuclear industry in developing and applying the monitoring techniques for different nuclear power plant applications, especially in monitoring of ageing phenomena for improving NPP availability. The purpose of this Specialists' Meeting was to bring together experts from operations, design, research and development and licensing to share their experience in: ageing mechanics of key structural components, methods of monitoring such ageing, tools for cost-effective implementation of the methods and methodologies, life management approaches and examples from current reactors, future direction for monitoring of key structural components in nuclear power plants. The meeting was organized by the IAEA International Working Groups on Life Management of Nuclear Power Plants (IWG-LMNPP) and Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) in co-operation with the Czechoslovak Atomic Energy Commission and Skoda concern. Around 40 participants from 10 countries.

  16. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

  17. Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

  18. Use Of ProductionService Work In Enhancing Skill Acquisition In Technical Colleges In North Central Nigeria

    Directory of Open Access Journals (Sweden)

    Peter Ashlame Agu

    2015-08-01

    Full Text Available Skill acquisition is a critical component of any vocational or technical training program. When this component is missing or falls below expectation it tends to defeat the objectives or the essence of the program. In Nigeria many skill acquisition institutions experience great challenges in trying to provide the necessary facilities required for effective vocational training of those enrolled in their programs because of paucity of funds. The result is that students graduate from the programs without adequate employability skills for meaningful productiveservice work after leaving school. In realization of this shortfall government has directed technical colleges to establish what is called ProductionService Work PSW into its curriculum. This is with the view that in the event that there is shortfall in the supply of training facilities by sponsors of the programs jobs could be brought in from inside or outside the school which could provide opportunity for students to acquire hands-on experience that would equip them with requisite skills for post-graduation work. As laudable as this initiative appears to be many schools in the North Central Nigeria are yet to implement the directive of the federal government in their schools and even where this has been done its implementation does not appear to be viable. Over the years different technical colleges have adopted different approaches toward the establishment and management of productionservice work in their schools. While some have recorded appreciable success in its implementation others seem to exist only in name. The present study therefore sought to identify the current practices employed in the use of PSW in technical colleges the appropriateness of the practices in use and the alternative practices that could be adopted to improve and guide the implementation of the program with a view to enhancing the acquisition of employability skills in technical colleges in North Central Nigeria.

  19. A technical and financial analysis of two recuperated, reciprocating engine driven power plants. Part 2: Financial analysis

    International Nuclear Information System (INIS)

    Orbaiz, Pedro Jose; Brear, Michael J.

    2014-01-01

    Highlights: • The financial performance of two hybrid power plants is analyzed. • Biomass and solar thermal energy are used as the renewable energy inputs. • The LCOE of both power plants is estimated using reference data. • The proposed power plants are of comparable LCOE to natural gas combined cycle. • Hybrid cycles resulted in cost-effective renewable energy generation. - Abstract: This paper is the second of a two part study that analyses the technical and financial performance of particular, recuperated engine systems. This second paper examines the financial performance of two hybrid (renewable/fossil), chemically recuperated power plants. One of these plants uses the combustion of biomass as the renewable energy input. The other assumes that solar thermal energy is used. This financial analysis estimates the so-called Levelized Cost of Electricity (LCOE) of both hybrids using reference data from several sources. Using consistent financial inputs, the LCOE of both hybrid plants is found to be comparable to the LCOE of natural gas combined cycle (NGCC) power generation. Further, the LCOE of the renewable portion of the hybrid plants’ total power output is significantly cheaper than that of all the renewable plants examined in the EPRI report, and is competitive with the fossil plants. As a result, the proposed hybrids appear to be a cost-effective form of greenhouse gas mitigation

  20. Technical assessment of agricultural biogas plants. Utilization ratio and energy efficiency; Verfahrenstechnische Bewertung landwirtschaftlicher Biogasanlagen. Auslastung und energetische Effizienz

    Energy Technology Data Exchange (ETDEWEB)

    Effenberger, Mathias; Kissel, Rainer; Lehner, Andreas; Gronauer, Andreas [Bayerische Landesanstalt fuer Landwirtschaft, Freising (Germany). Arbeitsgruppe Biogastechnologie und Reststoffmanagement

    2008-07-01

    Technical indicators of six selected modern agricultural biogas plants (BGP) were determined to evaluate utilization ratio and energy efficiency. In all of these plants, renewable raw materials were treated in combination with animal manure. At a specific installed electrical capacity between 0.09 and 0.25 kW per m{sup 3} usable digester volume, electrical utilization ratios between 88 and 98 % were achieved. The combination of these two characteristic values may be used as a first indicator of process stability and functionality of a BGP. The external utilization ratio for the off-heat from the combined-heat-and-power unit was between 0 and 46 %. (orig.)

  1. Meeting of the Technical Working Group on Fast Reactors (TWG-FR) (41st Annual Meeting). Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 40th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2008, 2009, 2010 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2008-2009

  2. Security during the Construction of New Nuclear Power Plants: Technical Basis for Access Authorization and Fitness-For-Duty Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Branch, Kristi M.; Baker, Kathryn A.

    2009-09-01

    A technical letter report to the NRC summarizing the findings of a benchmarking study, literature review, and workshop with experts on current industry standards and expert judgments about needs for security during the construction phase of critical infrastructure facilities in the post-September 11 U.S. context, with a special focus on the construction phase of nuclear power plants and personnel security measures.

  3. Installation Of 2MW Wind Power Plant In Northern Cyprus Technical Economical And Environmental Analysis

    Directory of Open Access Journals (Sweden)

    Aliyu Aliyu

    2017-11-01

    Full Text Available The impetus for the work presented here arose from the fact that the demand for renewable energy grows and the supply of the non-renewable energy is at the decreasing level. An increasing percentage of total energy produced globally is moving to renewable forms. Wind energy enjoys increasing deployment for power generation due to the economic benefits associated with it.Turkish Republic of Northern Cyprus TRNC has abundance of renewable energy it has an average wind speed of 4.30ms and 5.04ms at 10m and 50m respectively. The economic analysis of is plant shows that the wind farm has an investment cost of 2300000 with 333217.8 as annual savings. The simple payback was calculated to be 7 years the savings to investment ratio was found to be 3.62 the net present value turn to be positive while the return on investment was 14.48.

  4. Detroit Works Long-Term Planning Project: Engagement Strategies for Blending Community and Technical Expertise

    Directory of Open Access Journals (Sweden)

    Toni L. Griffin

    2014-10-01

    Full Text Available In January 2013, civic leaders, community stakeholders, and residents came together to release Detroit Future City: 2012 Detroit Strategic Framework Plan, a guiding blueprint for transforming Detroit from its current state of population loss and excessive vacancy into a model for the reinvention of post-industrial American cities. Three years prior, the U.S. Census had reported that the city had lost 24% of its population over the last decade and had experienced a 20% increase in vacant and abandoned property, bringing total vacancy to roughly the size of Manhattan. In addition to physical and economic challenges, Detroiters had also acknowledged significant barriers to effective civic engagement. Foremost among these barriers were a profound sense of immobilization, planning fatigue, and a general perception of cynicism about planning and engagement efforts. These challenges were compounded by historic racial dynamics and tension. This case study elaborates on the comprehensive and innovative civic engagement executed in a citywide planning process called the Detroit Works Project, which took place from late 2010 through late 2012. For the citywide planning process to be successful and sustainable, civic leaders and project funders committed to a planning initiative that would be different from previous efforts, in large part because the “owners” of the process would be diverse and inclusive across all community sectors. The case study, written by three of the key consultants from the project, describes four key civic engagement strategies deployed in the creation of the strategic framework: (1 addressing profound challenges of culture, race, and politics by deliberately building trust; (2 elevating community expertise by fostering a sense of ownership of the process; (3 blending technical and community expertise; and (4 viewing civic engagement as an ongoing two-way conversation rather than a series of large-scale episodic events. This

  5. In situ leach uranium mining. Proceedings of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-03-01

    At the beginning of 1996 there were 437 nuclear power plants in operation with a combined electricity generating capacity of 344 GWe (net gigawatts electric). This represents nearly a 100% increase over the last decade. In 1995 over 2228 TWh (terawatt hours) electricity were generated, equivalent to about 17% of the world's total electricity. To achieve this, about 61 400 tonnes U were required as nuclear fuel. The 15 year decline of the spot uranium price, as indicated by Nuexco Exchange Value (NEV) and other indices, which reached an all time low annual average in 1994 of $18.33/kg U ($7.05/pound U 3 O 8 ), has had a profound impact on uranium related activities. This led to the massive reduction and realignment of all uranium related activities as the worldwide uranium market adjusted from over-production. Because of the economic advantages of properly run in situ leach technology on carefully selected uranium orebodies, relatively more ISL mining facilities have been kept in operation than conventional mining operations. In 1995 world uranium production of about 34 000 t uranium met only about 55% of world requirements. An estimated 16% of production came from ISL mining. In 1996 ISL mining was estimated to have produced over 5600 tU, or over 15% of estimated world production of 36 400 tU. The importance of ISL mining is expected to increase, as the technology has economic and environmental advantages for producing uranium from carefully selected deposits when projects are properly designed and operated by experienced personnel. Several countries host sandstone type uranium deposits, the only type where commercial ISL projects have been developed. ISL uranium mining technology was developed independently in the USA and the former Soviet Union and associated non-WOCA (world outside centrally planned economic areas) countries starting in the 1960s and 1970s. Since the opening of relations between the two areas in the early 1990s there has been a high level of

  6. Comparing cultural profiles of MCR operators with those of non-MCR operators working in domestic Nuclear Power Plants

    International Nuclear Information System (INIS)

    Park, Jinkyun; Jung, Wondea

    2015-01-01

    Operation experience of complex socio-technical systems such as Nuclear Power Plants (NPPs) shows that most significant events are attributable to human error. Thus, various kinds of Human Reliability Analysis (HRA) techniques were used to manage human error for safety-critical tasks. However, a lack of available HRA data is a critical issue in conducting an HRA. For this reason, many researchers have tried to provide HRA data extracted from simulated emergency conditions. Unfortunately, it is still doubtful to directly use these HRA data because different operational cultures may result in different human performances even under a similar task context. From this concern, previous studies claimed that Main Control Room (MCR) operators working in different NPPs share very similar cultural profile. In order to confirm this claim, the culture profiles of operating personnel (i.e., non-MCR and MCR operators) working in domestic NPPs are compared. As a result, although some discrepancies are observed, it is positive to say that operating personnel of NPPs share similar cultural profiles to some extent. This result can be regarded as the first step to provide technical underpinnings that are helpful for understanding human performance data collected from different countries. - Highlights: • National and organizational culture of MCR and non-MCR operators are compared. • Organizational culture profiles are almost identical. • National culture profiles are not quite different overall. • Operating personnel in Nuclear Power Plants seems to share similar cultural profiles

  7. Analysis of Work Design in Rubber Processing Plant

    OpenAIRE

    Wahyuni Dini; Nasution Harmein; Budiman Irwan; Wijaya Khairini

    2018-01-01

    The work design illustrates how structured jobs, tasks, and roles are defined and modified and their impact on individuals, groups, and organizations. If the work is not designed well, the company must pay greater costs for workers’ health, longer production processes or even penalties for not being able to meet the delivery schedule. This is visible to the condition in a rubber processing factory in North Sumatra. Work design aspects such as layouts, machinery and equipment, worker's physica...

  8. A selection of problems related to safe working conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Brunner, K.H.

    1984-01-01

    Two representative examples were chosen to demonstrate that the problems related to safe working conditions can be solved with work being prepared extensively and in detail taking into consideration radiation protection and conventional job safety measures and with qualified staff. Most of the job safety problems in nuclear power plants are pretty much the same as in conventional plants. Despite successful implementation of employment and radiation protection in nuclear power plants, improvements in detail are possible and make sense. (orig.) [de

  9. Occupational hazard evaluation of working population in a select automotive industrial plant.

    Science.gov (United States)

    Wójcik, Alicja; Borzecki, Zdzisław; Kowalska, Edyta; Borzecki, Andrzej

    2004-01-01

    The research was conducted in the selected vehicle industry plant. Work conditions were assessed on the assembly line by measuring chemical and physical factors. Exposure to noise in the investigated plant exceeded the values of permissible standards. The pollution on the posts did not exceed the standards except singular concentrations. While assessing the values of chemical factors concentration, no toxicological danger was revealed in the investigated population. The work conditions of the investigated plant did not create the danger of professional diseases.

  10. 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

  11. 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

  12. Technical isomorphism at work : ERP-embedded similarity-enhancing mechanisms

    NARCIS (Netherlands)

    Batenburg, Ronald; Benders, Jos; van der Blonk, Heico

    2008-01-01

    Purpose - The purpose of this paper is to discuss the mechanisms inducing a user organization to conform with enterprise resource planning (ERP)-embedded organizational logics and accompanying implementation procedures. Design/methodology/approach - Based around the notion of technical isomorphism,

  13. Teaching Technical Writing and Editing -- In-House Programs That Work. Anthology Series No. 5.

    Science.gov (United States)

    Shaw, James G., Ed.

    The 12 articles in this publication provide indepth treatment of important aspects of in-house training programs for technical writing and editing. The articles deal with the following topics: the value of an in-house writing course, teaching in industry, developing an in-house writing course for engineers and scientists, a new approach to…

  14. Applicability of Socio-Technical Model (STM in Working System of Modern Organizations

    Directory of Open Access Journals (Sweden)

    Rosmaini Tasmin

    2011-10-01

    Full Text Available Knowledge has been identified as one of the most important resources in organization that contributes to competitive advantages. Organizations around the world realize and put into practice an approach that bases on technological and sociological aspects to fill-up the gaps in their workplaces. The Socio-Technical Model (STM is an established organizational model introduced by Trist since 1960s at Tavistock Institute, London. It relates two most common components exist in all organizations, namely social systems (human and technological systems (information technology, machinery and equipment in organizations over many decades. This paper reviews the socio-technical model from various perspectives of its developmental stages and ideas written by researchers. Therefore, several literature reviews on socio-technical model have been compiled and discussed to justify whether its basic argument matches with required practices in Techno-Social environments. Through a socio-technical perspective on Knowledge Management, this paper highlights the interplay between social systems and technological system. It also suggests that management and leadership play critical roles in establishing the techno-social perspective for the effective assimilation of Knowledge Management practices.

  15. Technical feasibility of reuse of effluent generated from reverse osmosis system in a pharmaceutical plant

    Directory of Open Access Journals (Sweden)

    Bárbara de A. S. de Andrade

    2017-09-01

    Full Text Available Reuse reduces the consumption of freshwater supplies and the negative environmental impact caused by the discharge of industrial effluents. Some industries have already adopted this practice; however, no studies were found in the literature regarding this subject in the pharmaceutical industry. This work investigated the potential reuse of effluent (concentrate generated from the Reverse Osmosis/Electro-deionization System (RO/EDI that is used for the production of purified water in a Brazilian pharmaceutical plant. This industrial complex consumed about 200,000 m3 of water per year between 2012 and 2013 to produce one million of doses of vaccines, i.e., 2 L of water per dose of vaccine produced. During this period, the RO/EDI produced 27,000 m3 of purified water annually and generated 24,000 m3 of effluent (concentrate. This amount of effluent could be used to supply the production of industry steam (boilers and/or cold water (cooling towers that annually consumed an average of 12,000 m3 and 40,000 m3, respectively. The reuse of this effluent would result in a gross financial savings of 96,000 USD per year, excluding the costs of installation and control. From what has been researched in the literature, this work showed for the first time the possibility of reuse of effluent from RO/EDI System in the pharmaceutical industry.

  16. Analysis of Work Design in Rubber Processing Plant

    Directory of Open Access Journals (Sweden)

    Wahyuni Dini

    2018-01-01

    Full Text Available The work design illustrates how structured jobs, tasks, and roles are defined and modified and their impact on individuals, groups, and organizations. If the work is not designed well, the company must pay greater costs for workers’ health, longer production processes or even penalties for not being able to meet the delivery schedule. This is visible to the condition in a rubber processing factory in North Sumatra. Work design aspects such as layouts, machinery and equipment, worker's physical working environment, work methods, and organizational policies have not been well-organized. Coagulum grinding machines into sheets are often damaged, resulting in 4 times the delay of product delivery in 2016, the presence of complaints of heat exposure submitted by workers, and workstation that has not been properly arranged is an indication of the need for work design. The research data will be collected through field observation, and distribution of questionnaires related aspects of work design. The result of the analysis depends on the respondent's answer from the distributed questionnaire regarding the 6 aspects studied.

  17. Analysis of Work Design in Rubber Processing Plant

    Science.gov (United States)

    Wahyuni, Dini; Nasution, Harmein; Budiman, Irwan; Wijaya, Khairini

    2018-02-01

    The work design illustrates how structured jobs, tasks, and roles are defined and modified and their impact on individuals, groups, and organizations. If the work is not designed well, the company must pay greater costs for workers' health, longer production processes or even penalties for not being able to meet the delivery schedule. This is visible to the condition in a rubber processing factory in North Sumatra. Work design aspects such as layouts, machinery and equipment, worker's physical working environment, work methods, and organizational policies have not been well-organized. Coagulum grinding machines into sheets are often damaged, resulting in 4 times the delay of product delivery in 2016, the presence of complaints of heat exposure submitted by workers, and workstation that has not been properly arranged is an indication of the need for work design. The research data will be collected through field observation, and distribution of questionnaires related aspects of work design. The result of the analysis depends on the respondent's answer from the distributed questionnaire regarding the 6 aspects studied.

  18. Analysis of Waste in the Production of Flour California Red Worm (eisenia foet) in Manabí Technical Universitypilot Plant

    OpenAIRE

    Ulbio Alcívar-Cedeño; Alex Dueñas-Rivadeneira; Eli Sacon-Vera; Gretel Villanueva-Ramos; Luis Bravo-Sánchez

    2016-01-01

    The necessity for have efficient tools in the environmental assessment of production processesis treated in this paper. This work is related to a previous work made in the Technical University of Manabi, forprotein supplements production from unconventional raw materials, specifically Earthworm (Eisenia foetida)flour, using various ecotoxicological methods to evaluategeneratedwaste in pilot production, in order to contribute to compliance the environmental regulations.Liquid wastes generated ...

  19. The reproductive function state of women working at the Smolensk nuclear power plant in shops with hazard working conditions

    International Nuclear Information System (INIS)

    Lyaginskaya, A.M.; Osipov, V.A.; Bugrova, T.I.; Kreusheva, I.F.; Plitkina, V.M.; Karepanova, L.A.; Afanas'eva, R.V.

    2001-01-01

    The reproductive function state of female workers at the Smolensk nuclear power plant in shops with hazardous working conditions is estimated. Female workers occupied in major shops of the Smolensk nuclear power plant are interviewed and subjected to a questionnaire. Individual medical care records of pregnant women and newborns are analyzed. Health statistics data for the town of Desnogorsk are used for comparison. Indicators of the reproductive function among female workers occupied from 1984 up to 1998 at the Smolensk nuclear power plant in workplaces with hazardous working conditions have not been shown to differ from those among the general female population in the town of Desnogorsk: neither these indicators deteriorated during the 14 year period of work as compared with the initial level [ru

  20. MDEP Technical Report TR-DICWG-01. Technical Report on the Relational Structure of the Digital Instrumentation and Controls Working Group (DICWG) Common Positions

    International Nuclear Information System (INIS)

    2016-10-01

    Unlike other technical disciplines, digital instrumentation and controls (DI and C) is a field which reflects the constant evolution in electrical and electronics technologies. The continual evolution in DI and C technology presents challenges for power plant operators, designers, suppliers, as well as the regulators. Contemporary regulations and guidance can be made either obsolete or insufficient as technology changes push the boundaries of what was originally considered or completely change the assumptions that were the foundation when they were first enacted. As such, producing timely and practical guidance is essential to the safe operation of nuclear plants. The goal of MDEP is not to independently develop new regulatory standards. The overall philosophy of MDEP DICWG is to use the collective knowledge and experiences from nuclear power regulatory organisations from around the world to effectively and efficiently create CPs to address current and future DI and C topics of concern to its member countries. The CPs provide an effective and efficient means to convey a general framework that includes input from both member countries and international standards organisations. Each CP produced by DICWG represents an agreed upon approach to address the specific topic for which it has been created. CPs are not legally binding and do not constitute additional obligations for the regulatory organisations or the licensees but are guidelines, recommendations or assessments that the MDEP participants agree are good to highlight during their safety reviews of new reactors. MDEP member countries may decide to implement the CPs through their own national regulatory processes. The topics that are addressed in current and upcoming CPs reflect a wide variety of technical topics that are challenging in the DI and C field and oftentimes require a holistic approach to reach resolution. The topics for CPs are selected based upon the use of DI and C in new reactor designs, issues of

  1. 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.

  2. Acceptability analysis of technical-scale plants for electricity generation; Ansatz zur Akzeptabilitaetsanalyse grosstechnischer Anlagen zur Stromerzeugung

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, Katharina; Koch, Marco K. [Bochum Univ. (Germany). AG Reaktorsimulation und -sicherheit

    2013-03-15

    Public acceptance of technical-scale plants for electricity generation is an indispensable prerequisite for the long-term continuity of supply of electricity. Even though nuclear power in Germany continues to meet with particularly grave objections, this is no longer an exception. Problems associated with the rapidly declining willingness of the public to accept specific disadvantages connected with electricity generation are confronting not only nuclear, but also large fossil-fired and renewable-resource power plants. To investigate to what extent these objections based on subjective heuristics are justified, a model is developed for analyzing the objective acceptability of electricity-producing large power plants, which allows the assessment of their acceptability to be measured on the basis of quantitative analysis of the discrepancies between acceptability and acceptance and may serve as a tool for promoting public acceptance. (orig.)

  3. 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

  4. First technical report about tracer applications to processes assessment in a portable water potabilizing plant

    International Nuclear Information System (INIS)

    Suarez Antola, R.; Giosa Porley, P.

    1996-03-01

    Radioactive and fluorescent tracers were applied to measure the distribution of residence times in each of the four subsystems of a portable water purifying plant: the mechanical flocculation unit, the hydraulic flocculation unit, the sedimentation unit, and the sand filter. This report begins by a revision of the physicochemical processes produced in each of the above mentioned subsystems, connected in series. Then a mathematical model of residence time distribution for each unit is constructed, with free parameters that can be estimated from the experimental results obtained with tracers. Tracer methodology for this kind of field experiment is reviewed. Their possible short comes are briefly discussed for each of the intended tracers. The tracer experiments done with rhodamine and uranine are described. The experimental results are reported and the residence time distributions obtained with different tracers were carefully compared. In order to make the field experiments, five different values of global water flow were sustained, pumping in steady state: two under the nominal (design) value, two above the design flow and one equal to the nominal water flow. The model parameters were determined using a software package, D TR , made in France and supplied by the IAEA in the framework of the project. It was discovered that the diffuser in the sedimentation unit was not working as intended, and some guidelines for its re-design could be given to the process engineers. Also, process engineers received information about some amount of by-pass flow and death zones, as well as their variations with plant's global water flow

  5. Survey and analysis of work structure in nuclear power plants. Final report

    International Nuclear Information System (INIS)

    Bauman, M.B.; Pain, R.F.; Van Cott, H.P.; Davidson, M.K.

    1983-06-01

    Work-structure factors are those factors that relate to the way in which work at all levels in a plant is organized, staffed, managed, rewarded, and perceived by plant personnel. Research over many years has demonstrated that these work-structure factors are closely correlated with organizational effectiveness, safety, and profitability. The work structure of ten nuclear power plants was assessed using questionnaires. Structured critical incident interviews were conducted to verify the questionnaire results. The study revealed that a variety of work-structure factor problem areas do exist in nuclear power plants. The study recommends a prioritized set of candidate research issues to be considered as part of EPRI's Work Structure and Performance Research Program

  6. Technical and economical aspects of a large and a small plant for irradiation of liquid waste

    International Nuclear Information System (INIS)

    Herrnhut, H.; Marsch, U.; Bosshard, E.

    1976-01-01

    Description of the further development of the irradiation plant for sewage sludge which is in operation at the sewage water treatment plant of the Abwasserverband Ampergruppe at Geiselbullach. Taking into consideration the operating experience, the conception of the plant was optimized, the design was simplified. The loading and reloading of the radioactive sources could now be carried out during operation of the plant. The economical aspects were considered too and the calculated cost of the treatment was summarized in a table. (author)

  7. 75 FR 62096 - Agricultural Technical Advisory Committees for Trade in Tobacco, Cotton, Peanuts and Planting...

    Science.gov (United States)

    2010-10-07

    ... many of the issues that the GFO committee addresses, such as genetically modified organisms, new... modifying the existing structure of both the Agricultural Technical Advisory Committees (ATAC) for Trade in...

  8. Students’ Cognitive Abilities in Plant Anatomy Practical Work

    Science.gov (United States)

    Setiono, S.; Rustaman, N. Y.; Rahmat, A.; Anggraeni, S.

    2017-09-01

    Cognitive abilities is fundamental for the students, as it is closely related to higher thinking skills such as the ability to think critically, creatively, and problem solving. This descriptive study aims to investigate the cognitive abilities of biology prospective teachers in the course of Plant Anatomy Practicum based on the cognitive process dimension and dimensions of knowledge the using the framework of Revision of Bloom taxonomy. A number of biology prospective teachers was involved in this study (n=42). The instrument used to collect data for students’ cognitive process mastery in the form of multiple choice with 5 options. Research finding shows that the average student’s cognitive ability is 68.10. The acquisition of knowledge mastery of cognitive ability is still under the criterion of mastery in the course of the Plant Anatomy Practicum (75). Validity and reliability of the instrument (0,71) and (0,81). It is necessary to design lecture programs both in the class and laboratory to develop student’ cognitive abilities.

  9. Independent technical review of the Bin and Alcove test programs at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-12-01

    This Independent Technical Review (ITR) assessed the need for and technical validity of the proposed Bin and Alcove test programs using TRU-waste at the WIPP site. The ITR Team recommends that the planned Bin and Alcove tests be abandoned, and that new activities be initiated in support of the WIPP regulatory compliance processes. Recommendations in this report offer an alternate path for expeditiously attaining disposal certification and permitting

  10. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were: - To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; - To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; - To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; - To discuss the results of studies and on-going R&D activities that address cost reduction and the future economic competitiveness of fast reactors; and - To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

  11. 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

  12. Technical Meeting on the Implementation of Fast Reactor Data Retrieval and Knowledge Preservation Activities. Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The current Technical Meeting was convened to foster the development of the FRKP initiative, in general, and, more specifically, to advance the development of the FRKP Portal. Its objectives were therefore: 1. To review the implementation status of the FRKP Portal prototype; 2. To review the availability of FR-related document collections made accessible through the FRKP Portal; 3. To locate sources of FR-related digital items to be made accessible through the FRKP portal

  13. Technical meeting on decommissioning of fast reactors after sodium draining. Working material

    International Nuclear Information System (INIS)

    2005-01-01

    The objective of the technical meeting was to provide a forum for in-depth scientific and technical exchange on topics related to the decommissioning experience with fast reactors, in particular with regard to the decommissioning of components after sodium draining. Accordingly, the scope of the meeting covers the review and analyses of the experience gained from the decommissioning of both active sodium loops and sodium cooled fast reactors (e.g., KNK II, Superphenix, RAPSODIE, EBR-II, FERMI, BN-350, BR-10). It is expected that the outcome of the meeting will contribute to the Agency initiative to preserve fast reactor data and knowledge. The main focus of the technical meeting was given on the decommissioning of both active loop and reactor components (e.g., the primary vessel of a sodium-cooled reactor) that have been drained of sodium, but that still conserve some residual amounts of sodium (e.g., films covering the entire surface of the component, or particular sodium heels that cannot be drained)

  14. Technical notes for the conceptual design for an atmospheric fluidized-bed direct combustion power generating plant. [570 MWe plant

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-04-01

    The design, arrangement, thermodynamics, and economics of a 592 MW(e) (nominal gross) electric power generating plant equipped with a Babcock and Wilcox Company (B and W) atmospheric fluidized bed (AFB) boiler are described. Information is included on capital and operating costs, process systems, electrical systems, control and instrumentation, and environmental systems. This document represents a portion of an overall report describing the conceptual designs of two atmospheric fluidized bed boilers and balance of plants for the generation of electric power and the analysis and comparison of these conceptual designs to a conventional pulverized coal-fired electric power generation plant equipped with a wet limestone flue gas desulfurization system.

  15. Technical notes for the conceptual design for an atmospheric fluidized-bed direct combustion power generating plant. [570 MWe plant

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-04-01

    The design, arrangement, thermodynamics, and economics of a 578 MW(e) (nominal gross) electric power generating plant equipped with a Foster Wheeler Energy Corporation (FWEC) atmospheric fluidized bed (AFB) boiler are described. Information is included on capital and operating costs, process systems, electrical systems, control and instrumentation, and environmental systems. This document represents a portion of an overall report describing the conceptual designs of two atmospheric fluidized bed boilers and balance of plants for the generation of electric power and the analysis and comparison of these conceptual designs to a conventional pulverized coal-fired electric power generation plant equipped with a wet limestone flue gas desulfurization system.

  16. 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

  17. Use of probabilistic safety assessment in the regulatory process. Report of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    A Technical Committee Meeting (TCM) was organized between 5-8 December 1994 to discuss and review the international situation in connection with the use made, whether formally or informally, by regulatory bodies of probabilistic safety assessment (PSA) in the course of their work, and the related question of the use and value of adopting probabilistic safety criteria (PSC) as an aid to judging the results of PSAs. The document includes the output from the four working groups, as well as 11 papers from the 12 papers presented to the TCM. A separate abstract was prepared for each paper. Refs, figs, tabs

  18. IMPROVEMENT OF SYSTEMS OF TECHNICAL WATER SUPPLY WITH COOLING TOWERS FOR STEAM POWER PLANTS TECHNICAL AND ECONOMIC INDICATORS PERFECTION. Part 1

    Directory of Open Access Journals (Sweden)

    Yu. A. Zenovich-Leshkevich-Olpinskiy

    2016-01-01

    Full Text Available In order to reduce the temperature of cooling water and increase the efficiency of use of power resources the main directions of modernization of systems of technical water supply with cooling towers at steam power plants are presented. The problems of operation of irrigation systems and water distribution systems of cooling towers are reviewed. The design of heat and mass transfer devices, their shortcomings and the impact on the cooling ability of the cooling tower are also under analysis. The use of droplet heat and mass transfer device based on the lattice polypropylene virtually eliminates the shortcomings of the film and droplet-film heat and mass transfer devices of the cooling tower, increasing lifetime, and improving the reliability and efficiency of the operation of the main equipment of thermal power plants. The design of the water distribution devices of cooling towers is also considered. It is noted that the most effective are water-spattering low-pressure nozzles made of polypropylene that provides uniform dispersion of water and are of a high reliability and durability.

  19. Modernization of the automation control system of technological processes at the preparation plant in the conditions of technical re-equipment

    Science.gov (United States)

    Lyakhovets, M. V.; Wenger, K. G.; Myshlyaev, L. P.; Shipunov, M. V.; Grachev, V. V.; Melkozerov, M. Yu; Fairoshin, Sh A.

    2018-05-01

    The experience of modernization of the automation control system of technological processes at the preparation plant under the conditions of technical re-equipment of the preparation plant “Barzasskoye Tovarischestvo” LLC (Berezovsky) is considered. The automated process control systems (APCS), the modernization goals and the ways to achieve them are indicated, the main subsystems of the integrated APCS are presented, the enlarged functional and technical structure of the upgraded system is given. The procedure for commissioning an upgraded system is described.

  20. An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon

    2013-01-01

    Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system

  1. An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

  2. Work of plant data acquisition system for 'MONJU'

    International Nuclear Information System (INIS)

    Hashimoto, Daisuke; Komatsu, Keiichi; Eguchi, Kenji; Morizono, Koji

    2007-01-01

    The fast breeder reactor 'MONJU' (hereafter 'MONJU') is equipped with the system called 'MONJU Integrated Data Acquisition System (MIDAS)' to effectively acquire, accumulate and analyze relevant real-plant process data gathered from the system start-up test. At present, 'MONJU' has been suspended due to a sodium leak accident that occurred in 1995. However, the main part of remodeling construction to prevent sodium leaks was completed in May, 2007 and 'MONJU' is highly expected to resume its operations, stepping into the practical testing phase. In this situation, 'MIDAS' has been replaced with an upgraded version before the system start-up test was resumed. This paper describes overview of the new 'MIDAS' system. (author)

  3. Tailored Working Fluids for Enhanced Binary Geothermal Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Mahmoud, Ahmad [United Technologies Research Center, East Hartford, CT (United States)

    2013-01-29

    United Technologies Research Center (UTRC), in collaboration with the Georgia Institute of Technology and the National Institute of Standards and Technology will evaluate and develop fundamental and component level models, conduct experiments and generate data to support the use of mixed or enhanced working fluids for geothermal power generation applications.

  4. Integrating women into operator type work at N Reactor Plant

    International Nuclear Information System (INIS)

    Vinther, A.P.

    1976-01-01

    The Affirmative Action Plan in place at the Hanford complex has the goal of filling jobs in all phases of the work force with qualified minority personnel. The paper deals with the special concern, adjustments, and results achieved within UNI as a result of integrating qualified women candidates into the operator and technologist training program

  5. Technical analysis of magneto-inductive crane cables in nuclear power plants. Application crane Cofrentes Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gavilan Moreno, C. J.

    2010-01-01

    In 2009, the Cofrentes Nuclear Power Plant made a study about crane inspection techniques available on the market and other industries. The result was the location of the magneto-inductive technique inspection. Its use provides an objective assessment of the resistant section and; through these data; it could be made calculations as the maximum voltage allowed. Therefore, the technique is proven and available to all nuclear power plants.

  6. IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    issues apply to new build projects as well. Technical experts and managers from the field of instrumentation and control, process control, human factors engineering, licensing, and computer applications are invited to a Technical Meeting dealing with all important aspects of control room modernization projects. The subject of the present technical meeting was suggested by the members of the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) and supported by a number of IAEA meetings on NPP I and C Systems. Additional information on the Technical Working Group, and on the activities of the IAEA Division of Nuclear Power is available on The purpose of the meeting is to provide an international forum for presentations and discussions of experience with various aspects of the integration of analog and digital instrumentation and control systems in hybrid main control rooms, as applicable to both existing plants and planned (or in-progress) new plant builds. Promising new technologies and future trends in development will be also discussed. The meeting is intended for experts and managers in the I and C field from nuclear power utilities, vendor companies, licensing bodies, research organizations and academic institutions.

  7. The Planning of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeborg, T U; Haeffner, E; Hultgren, Aa

    1963-10-15

    A shielded volume (42 m{sup 3}) in the hot laboratory at Kjeller, Norway, has been used for the installation of a small pilot plant intended for studies on nuclear fuel reprocessing. During the first period of operation (1963) a plutonium separation method (the Silex process) developed at AB Atomenergi will be studied. This document is a description of the project during the stage of technical planning and chemical process development.

  8. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    International Nuclear Information System (INIS)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report

  9. High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

    1995-06-01

    The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

  10. Setting technical and economic features regarding nuclear heating plants implementation for heat supply in Romania by the year 2010

    International Nuclear Information System (INIS)

    Romascu, G.; Constantin, L.; Gheorghe, A.; Ciocanescu, M.; Ionescu, M.

    2008-01-01

    This paper presents the world wide preoccupation concerning the implementation of nuclear heating plants for fulfilling the heat demand and the main technical data of the reactors destined to such NHP's. The second part of this paper shows technical and economic aspects related to the implementation of NHP's equipped with nuclear thermal reactor specialized in the exclusive heat supply in Romania at the level of the year 2010. Among these aspects the following are mentioned: - the results of researches and the world wide achievements; - the development and structure of the production and of the thermal electric energy as well as the feasibility for covering the demands for nuclear sources; - the impact on environment of various technologies for the production of thermal energy with conventional fuels comparing with NHP; - the philosophy from economic stand point for the covering part of the NHP heat demand. (authors)

  11. Preparation and concept of geodesy work on the Temelin nuclear power plant site

    International Nuclear Information System (INIS)

    Vincik, K.; Zdobinsky, J.

    1989-01-01

    Listed are the main partners in the Temelin nuclear power plant construction (investor, general designer, building and equipment parts suppliers), the main specifications of the power plant, the layout of buildings, the types of construction documentation, and the concept of geodesy work. A network was laid out comprising 9 points and a local coordinate system and an elevation system for design work were determined. Within the layout, a network of basic elevation points with depth stabilization and a starting 6-point level network were proposed. The updating is described of the layout network and of the organization of geodesy work during the construction of the Temelin nuclear power plant. (E.J.)

  12. New technical knowledge to be implemented to the revision of rules on pipe wall thinning management for PWR Plants. 2006 edition

    International Nuclear Information System (INIS)

    Hirai, Junya; Amano, Yoichi; Nakamura, Takao

    2013-01-01

    Rules for PWR plant pipe wall thinning management were formulated by the Japan Society of Mechanical Engineers in 2006. Since then thinning management of Japanese PWR plants has been carried out based on this rule. Pipe wall thinning phenomena to be dealt with in this rule have been identified in many piping components of power plants. New technical knowledge has been accumulated since the issuance of 2006 edition. We have formulated these knowledge and information about the thinning phenomena in PWR power plants. Given the history of application of this rule, we have to make our best effort to carry out a study of latest technical knowledge and implement them to the revision of rule and improve pipe wall thinning management. This paper summarizes the new technical knowledge and basis to be implemented to the revision of rules on pipe wall thinning management for PWR plants in Japan. (author)

  13. Testing of energy assessment of technical plants, in accordance with the Energy Performance of Buildings Directive, EPBD; Testing av Energivurdering av tekniske anlegg iht Bygningsenergidirektivet, EPBD

    Energy Technology Data Exchange (ETDEWEB)

    Birkeland, Harald

    2008-06-15

    The consulting company Norwegian Energy has previously worked out proposals for inspection systems for technical plants, in accordance with the EU Energy Performance of Buildings Directive, abbreviated EPBD. This project has consisted in practice testing of the proposed inspection systems. In this respect agreements have been made with a number of companies working with heating boiler inspections as well as ventilation and cooling. Testing experiences have been summed up in this report. The most important experiences from this project concern practical matters: The main challenge is to find data and documentation on the plant. Use of time and resources is part of this challenge. The forms must be simplified, with less information to fill in. Some adjustments have been proposed to the previously proposed procedure. The content of the inspection should be clearly defined, without any options for simplifications. Eligibility requirements: There is clearly a need for training and certification procedures for companies/persons which are permitted to carry out inspections according to the EPBD. A proposal for such procedures has been worked out. The inspection should contain both a declaration of impartiality and a guarantee from the inspector that all identified points of improvement have been described. (EW)

  14. State of the art for noise reduction in biogas plants. Sound technical analyses, research, investigations

    International Nuclear Information System (INIS)

    2014-01-01

    Approximately 480 biogas plants are currently being built in Mecklenburg-Vorpommern, which were mainly built in an agricultural context. At the beginning of 2014 about 15 percent of the country's electricity was generated by domestic biogas plants. This publication is intended to serve as a guide to the authorities, planners and engineers, in order to be able to plan, erect and operate biogas plants in the most conflict-free manner. [de

  15. Software for automated evaluation of technical and economic performance factors of nuclear power plant units

    International Nuclear Information System (INIS)

    Cvan, M.; Zadrazil, J.; Barnak, M.

    1989-01-01

    Computer codes TEP V2, TEP EDU and TEP V1 are used especially in real-time evaluation of technical and economic performance factors of the power unit. Their basic functions include filtration of credibility of input data obtained by measurement, simultaneous calculation of flows of various types of energy, calculation of technical and economic factors, listings and filing of the results. Code ZMEK is designed for executing changes in the calculation constants file for codes TEP V2 and TEP EDU. Code TEP DEN is used in processing the complete daily report on the technical and economic performance factors of the unit. Briefly described are the basic algorithms of credibility filtration for the measured quantities, the methodology of fundamental balances and the method of guaranteeing the continuity of measurement. Experiences are given with the use of the codes, and the trends are outlined of their future development. (J.B.). 5 refs

  16. PV-Plants in autarky or network coupled operation: technical and economic comparison accordingly to practical investigations

    International Nuclear Information System (INIS)

    Ajib, Salman; Seitz, Thomas; Petzold, Reinhardt

    2006-01-01

    PV-Plants can be operated, as known, using autarky or network coupled operation modes, The first operation mode is recommended in the places which locate away from the electrical supply network. However the PV-plants, when using network coupled mode, can be used in all of the places, where the sunlight is suitable and there is a sufficient place to establish these plants in the required size. The differences between the two operation modes are the additional components and the dimensioning of the PV-plants. The whole needed electrical energy must be obtained from the PV-plants, when the autarky operation mode is used. In contrast to this, this energy can be provided by the PV-plants or by the electrical supply network when the network coupled operation mode is used, therefore a network coupled PV-plants need a careful initial planning and installation. In this paper the function principles and the components of these PV-plants in the two operation modes will be presented. In addition to this, the results obtained from the investigation of PV-plants while working with nominal power of P= 1 kW p will be analyzed and discussed too. After that the dimensioning steps and the economic evaluation will be depicted.(Author)

  17. Nuclear Forensics International Technical Working Group (ITWG): a collaboration of scientists, law enforcement officials, and regulators working to combat nuclear terrorism and proliferation

    Energy Technology Data Exchange (ETDEWEB)

    Schwantes, Jon M.

    2013-10-25

    Founded in 1996 upon the initiative of the “Group of 8” governments (G8), the Nuclear Forensics International Technical Working Group (ITWG) is an ad hoc organization of official Nuclear Forensics practitioners (scientists, law enforcement, and regulators) that can be called upon to provide technical assistance to the global community in the event of a seizure of nuclear or radiological materials. The ITWG is supported by and is affiliated with nearly 40 countries and international partner organizations including the International Atomic Energy Agency (IAEA), EURATOM, INTERPOL, EUROPOL, and the United Nations Interregional Crime and Justice Research Institute (UNICRI) (Figure 1). Besides providing a network of nuclear forensics laboratories that are able to assist the global community during a nuclear smuggling event, the ITWG is also committed to the advancement of the science of nuclear forensic analysis, largely through participation in periodic table top and Collaborative Materials Exercises (CMXs). Exercise scenarios use “real world” samples with realistic forensics investigation time constraints and reporting requirements. These exercises are designed to promote best practices in the field and test, evaluate, and improve new technical capabilities, methods and techniques in order to advance the science of nuclear forensics. Past efforts to advance nuclear forensic science have also included scenarios that asked laboratories to adapt conventional forensics methods (e.g. DNA, fingerprints, tool marks, and document comparisons) for collecting and preserving evidence comingled with radioactive materials.

  18. MDEP Technical Report TR-CSWG-02. Technical Report on Lessons Learnt on Achieving Harmonisation of Codes and Standards for Pressure Boundary Components in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2013-01-01

    This report was prepared by the Multinational Design Evaluation Program's (MDEP's) Codes and Standards Working Group (CSWG). The primary, long-term goal of MDEP's CSWG is to achieve international harmonisation of codes and standards for pressure-boundary components in nuclear power plants. The CSWG recognised early on that the first step to achieving harmonisation is to understand the extent of similarities and differences amongst the pressure-boundary codes and standards used in various countries. To assist the CSWG in its long-term goals, several standards developing organisations (SDOs) from various countries performed a comparison of their pressure-boundary codes and standards to identify the extent of similarities and differences in code requirements and the reasons for their differences. The results of the code-comparison project provided the CSWG with valuable insights in developing the subsequent actions to take with SDOs and the nuclear industry to pursue harmonisation of codes and standards. The results enabled the CSWG to understand from a global perspective how each country's pressure-boundary code or standard evolved into its current form and content. The CSWG recognised the important fact that each country's pressure-boundary code or standard is a comprehensive, living document that is continually being updated and improved to reflect changing technology and common industry practices unique to each country. The rules in the pressure-boundary codes and standards include comprehensive requirements for the design and construction of nuclear power plant components including design, materials selection, fabrication, examination, testing and overpressure protection. The rules also contain programmatic and administrative requirements such as quality assurance; conformity assessment (e.g., third-party inspection); qualification of welders, welding equipment and welding procedures; non-destructive examination (NDE) practices and

  19. Civil engineering work

    International Nuclear Information System (INIS)

    Cousyn, Rene; Goubin, Jean.

    1977-01-01

    Although it does not require a specifically new technicality, the Civil Engineering site of a nuclear power plant is a complex work. Considering as an example the power plant currently in construction at Tricastin, the authors describe the main Civil Engineering work and task organization applied to carry it out [fr

  20. 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

  1. Technical meeting on 'Primary coolant pipe rupture event in liquid metal cooled fast reactors'. Working material

    International Nuclear Information System (INIS)

    2003-01-01

    In Liquid Metal cooled Fast Reactors (LMFR) or in accelerator driven sub-critical systems (ADS) with LMFR like sub-critical cores, the primary coolant pipes (PCP) connect the primary coolant pumps to the grid plate. A rupture in one of these pipes could cause significant loss of coolant flow to the core with severe consequences. In loop type reactors, all primary pipelines are provided with double envelopes and inter-space coolant leak monitoring systems that permit leak detection before break. Thus, the PCP rupture event can be placed in the beyond design basis event (BDBE) category. Such an arrangement is difficult to incorporate for pool type reactors, and hence it could be argued that the PCP rupture event needs to be analysed in detail as a design basis event (DBE, category 4 event). The primary coolant pipes are made of ductile austenitic stainless steel material and operate at temperatures of the cold pool and at comparatively low pressures. For such low stressed piping with negligible creep and embrittlement effects, it is of interest to discuss under what design provisions, for pool type reactors, the guillotine rupture of PCP could be placed in the BDBE category. The topical Technical Meeting (TM) on 'Primary Coolant Pipe Rupture Event in Liquid Metal Cooled Reactors' was called to enable the specialists to present the philosophy and analyses applied on this topic in the various Member States for different LMFRs. The scope of the Technical Meeting was to provide a global forum for information exchange on the philosophy applied in the various participating Member States and the analyses performed for different LMFRs with regard to the primary coolant pipe rupture event. More specifically, the objectives of the Technical Meeting were to review the safety philosophy for the PCP rupture event in pool type LMFR, to assess the structural reliability of the PCP and the probability of rupture under different conditions (with/without in-service inspection), to

  2. Technical characteristics of new generation of nuclear power plants; Charakterystyka techniczna elektrowni jadrowych nowej generacji

    Energy Technology Data Exchange (ETDEWEB)

    Janczak, R.; Mikulski, A.; Staron, E. [Instytut Energii Atomowej, Swierk-Otwock (Poland)

    1997-12-31

    The concept of Advanced Light Water Reactors (ALWR) as a new generation of nuclear reactors for energetics have been presented. The influence of reactor accidents (TMI and Chernobyl) on technical and scientific development of nuclear reactors has been discussed from the view point of safety assurance and requirements being defined by American and European Nuclear Regulatory commission. 12 refs, 14 figs.

  3. Report on the FR Germany: US technical workshop on near-real-time material accounting for reprocessing plants

    International Nuclear Information System (INIS)

    Weh, R.; Hakkila, E.A.; Canty, M.J.

    1986-01-01

    A technical workshop on the subject of near-real-time material accounting in an industrial scale reprocessing plant was held. Organized within the context of the US DOE - FR German Ministry of Research and Technology (BMFT) agreement in the field of international safeguards, the workshop was initiated by the Deutsche Gesellschaft fur Wiederaufarbeitung von Kernbrennstoffen, responsible for the construction and operation of a planned industrial scale reprocessing plant in the FR Germany. The workshop's objective was to establish the current state of the art for near-real-time accounting and to bring out a common understanding and consensus among experts from both countries which seve as a basis for the definition of problems still to be solved. A summary of the workshop presentations, preliminary conclusions drawn by the experts attending as well as some implications for the application of dynamic balancing are given

  4. Scientific-technical cooperation with foreign (esp. Europe and INSC partner countries) nuclear regulatory authorities and their technical support organizations in the fields of nuclear safety of operating nuclear power plants and on the concept evaluation of generation 3+ plants. Final report

    International Nuclear Information System (INIS)

    Wolff, Holger

    2016-09-01

    The BMUB/BfS-Project 3614I01512 forms the frame of the GRS for the scientific-technical cooperation with Technical Support Organisations and Nuclear Regulatory Authorities in the field of nuclear safety in operating NPPs and for the concept evaluation of generation 3 + plants in Europe and INSC Partner Countries. In the present final project report results are described which were gained within the project duration 15.10.2014 up to the 30.09.2016 in the following working packages: Investigations following the catastrophe of Fukushima Daiichi, Evaluation of selected National Action Plans, DBA and severe accident analyses for NPP with PWR (WWER-440, WWER-1000), cooperation with INSC partner countries on DBA, BDBA and severe accident analyses for WWER plants of generation 3 + and building NRA and safety evaluation capacities and decommissioning of nuclear facilities and disposal of radioactive waste. The results are preceded by an outline on the activities related to the project management and to the planning of the bilateral work.

  5. Technical and economic working domains of industrial heat pumps: Part 2 - ammonia-water hybrid absorption-compression heat pumps

    DEFF Research Database (Denmark)

    Jensen, Jonas Kjær; Ommen, Torben Schmidt; Markussen, Wiebke Brix

    2015-01-01

    The ammonia-water hybrid absorption-compression heat pump (HACHP) has been proposed as a relevant technology for industrial heat supply, especially for high sink temperatures and high temperature glides in the sink and source. This is due to the reduced vapour pressure and the non-isothermal phase...... change of the zeotropic mixture, ammonia-water. To evaluate to which extent these advantages can be translated into feasible heat pump solutions, the working domain of the HACHP is investigated based on technical and economic constraints. The HACHP working domain is compared to that of the best available...... vapour compression heat pump with natural working fluids. This shows that the HACHP increases the temperature lifts and heat supply temperatures that are feasible to produce with a heat pump. The HACHP is shown to be capable of delivering heat supply temperatures as high as 150 °C and temperature lifts...

  6. Technical and Economic Working Domains of Industrial Heat Pumps: Part 2 - Ammonia-Water Hybrid Absorption-Compression Heat Pumps

    DEFF Research Database (Denmark)

    Jensen, Jonas Kjær; Ommen, Torben Schmidt; Markussen, Wiebke Brix

    2014-01-01

    The ammonia-water hybrid absorption-compression heat pump (HACHP) is a relevant technology for industrial heat supply, especially for high sink temperatures and high temperature glides in the sink and source. This is due to the reduced vapour pressure and the non-isothermal phase change...... of the zeotropic mixture, ammonia-water. To evaluate to which extent these advantages can be translated into feasible heat pump solutions, the working domain of the HACHP is investigated based on technical and economic constraints. The HACHP working domain is compared to that of the best possible vapour...... compression heat pump with natural working fluids. This shows that the HACHP increases the temperature lifts and heat supply temperatures that are feasible to produce with a heat pump. The HACHP is shown to be capable of delivering heat supply temperatures as high as 140 XC and temperature lifts up to 60 K...

  7. Analyzing Effective Communication in Mathematics Group Work: The Role of Visual Mediators and Technical Terms

    Science.gov (United States)

    Ryve, Andreas; Nilsson, Per; Pettersson, Kerstin

    2013-01-01

    Analyzing and designing productive group work and effective communication constitute ongoing research interests in mathematics education. In this article we contribute to this research by using and developing a newly introduced analytical approach for examining effective communication within group work in mathematics education. By using data from…

  8. Technical feasibility of the electrode ionization process for the makeup water treatment system of the thermal cycle of the CAREM-25 nuclear power plant

    International Nuclear Information System (INIS)

    Ramilo, Lucia B.; Chocron, Mauricio

    2003-01-01

    In thermal cycles of PWRs nuclear power plants with once-through steam generators as the CAREM-25, makeup water of very high purity is required to minimizing the induction of corrosion phenomena, fundamentally in the steam generators and other thermal cycle components. The makeup water treatment systems include several stages, of which the demineralization is the purification stage. The required makeup water purity is obtained in this stage. Historically, ultrapure water systems were based completely on ion exchange technology. Now, the electrode ionization process (EDI) has replaced the ion exchange technology used traditionally in the demineralization stage. Continuous demineralization in an EDI stack consists of three coupled processes: ion exchange, continuous ion removal by transport through the ion exchange resin and membranes into the concentrate stream, continuous regeneration by hydrogen and hydroxyl ions derived from the water splitting reaction and driven by the applied direct current. EDI process allows to obtain ultrapure water, with practically no use of chemical reagents and with technologies of continuous process. The objective of this work is the analysis of the electrode ionization process (EDI) for its implementation in the makeup water treatment system of the thermal cycle of the CAREM-25 nuclear power plant. The obtained results allow to assure the technical feasibility of implementation of the electrode ionization process, EDI, in the makeup water treatment system of the thermal cycle of this Argentinean nuclear power plant. (author)

  9. Computerization of operation and maintenance for nuclear power plants. Working material

    International Nuclear Information System (INIS)

    1994-01-01

    This report provides a resource for computerization of activities in plant operation and maintenance. Experience gained from design and implementation of various computer systems around the world is described. The material may be useful as a guide to modification and upgrading of existing plants as well as design and engineering of new plants. It should be particularly of interest to managers and engineers who are engaged in planning, bidding, specifying or designing computer systems for operation and maintenance applications. The technical document is the result of a series of advisory and consultant meetings held by the IAEA in Vienna in 1991 - 1994. The document was prepared with the participation of experts from Canada, France, Germany, Hungary, Japan, Russia, Sweden, United Kingdom, and the United States. Refs, figs and tabs

  10. Use and development of coupled computer codes for the analysis of accidents at nuclear power plants. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-01-01

    Computer codes are widely used in Member States for the analysis of safety at nuclear power plants (NPPs). Coupling of computer codes, a further tool for safety analysis, is especially beneficial to safety analysis. The significantly increased capacity of new computation technology has made it possible to switch to a newer generation of computer codes, which are capable of representing physical phenomena in detail and include a more precise consideration of multidimensional effects. The coupling of advanced, best estimate computer codes is an efficient method of addressing the multidisciplinary nature of reactor accidents with complex interfaces between disciplines. Coupling of computer codes is very advantageous for studies which relate to licensing of new NPPs, safety upgrading programmes for existing plants, periodic safety reviews, renewal of operating licences, use of safety margins for reactor power uprating, better utilization of nuclear fuel and higher operational flexibility, justification for lifetime extensions, development of new emergency operating procedures, analysis of operational events and development of accident management programmes. In this connection, the OECD/NEA Working Group on the Analysis and Management of Accidents (GAMA) recently highlighted the application of coupled computer codes as an area of 'high collective interest'. Coupled computer codes are being developed in many Member States independently or within small groups composed of several technical organizations. These developments revealed that there are many types and methods of code coupling. In this context, it was believed that an exchange of views and experience while addressing these problems at an international meeting could contribute to the more efficient and reliable use of advanced computer codes in nuclear safety applications. The present publication constitutes the report on the Technical Meeting on Progress in the Development and Use of Coupled Codes for Accident

  11. Heat integration of an Olefins Plant: Pinch Analysis and mathematical optimization working together

    Directory of Open Access Journals (Sweden)

    M. Beninca

    2011-03-01

    Full Text Available This work explores a two-step, complexity reducing methodology, to analyze heat integration opportunities of an existing Olefins Plant, identify and quantify reduction of energy consumption, and propose changes of the existing heat exchanger network to achieve these goals. Besides the analysis of plant design conditions, multiple operational scenarios were considered to propose modifications for handling real plant operation (flexibility. On the strength of plant complexity and large dimension, work methodology was split into two parts: initially, the whole plant was evaluated with traditional Pinch Analysis tools. Several opportunities were identified and modifications proposed. Modifications were segregated to represent small and independent portions of the original process. One of them was selected to be re-analyzed, considering two scenarios. Reduction of problem dimension allowed mathematical methodologies (formulation with decomposition, applying LP, MILP and NLP optimization methods to synthesize flexible networks to be applied, generating a feasible modification capable of fulfilling the proposed operational scenarios.

  12. Removal action work plan for the YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1998-03-01

    The US Department of Energy is conducting environmental restoration activities at the Y-12 Plant in Oak Ridge, Tennessee. As part of these efforts, a removal action is planned for the former YS-860 Firing Ranges as described in the Action Memorandum for the project. This removal action work plan (RmAWP) is focused on the former YS-860 Firing Ranges, located outside the primary fenceline at the eastern end of the plant. This RmAWP defines the technical approach, procedures, and requirements for the removal of lead-contaminated soil and site restoration of the former YS-860 Firing Ranges at the Y-12 Plant. This RmAWP describes excavation, verification/confirmatory sampling, and reporting requirements for the project. Lower tier plans associated with the RmAWP, which are submitted as separate stand-alone documents, include a field sampling and analysis plan, a health and safety plan, a quality assurance project plan, a waste management plan, a data management implementation plan, and a best management practices plan. A site evaluation of the YS-86O Firing Ranges conducted in 1996 by Lockheed Martin Energy Systems, Inc., determined that elevated lead levels were present in the Firing Ranges target berm soils. The results of this sampling event form the basis for the removal action recommendation as described in the Action Memorandum for this project. This RmAWP contains a brief history and description of the Former YS-860 Firing Ranges Project, along with the current project schedule and milestones. This RmAWP also provides an overview of the technical requirements of the project, including a summary of the approach for the removal activities. Finally, the RmAWP identifies the regulatory requirements and the appropriate removal action responses to address applicable or relevant and appropriate requirements to achieve the project goals of substantially reducing the risk to human health and the environment

  13. Analysis of change orders in geotechnical engineering work at INDOT : [technical summary].

    Science.gov (United States)

    2011-01-01

    There was a perception at INDOT that the number of change orders connected with geotechnical work was excessive, and that, as a consequence, geotechnical projects were not completed on time or within budget. It was reported that INDOT construction pr...

  14. The decommissioning of WWER type nuclear power plants. Final report on an IAEA regional technical co-operation project

    International Nuclear Information System (INIS)

    2000-01-01

    Numerous WWER-440 nuclear power plants are in operation in central and eastern Europe and a small number have already been shut down. In addition to reactors already shut down, many other reactors will reach the end of their design lifetime in a few years and become candidates for decommissioning. It is unfortunate that little consideration was devoted to decommissioning of WWER-440 reactors at the plant design and construction stage, and little emphasis was placed on planning for decommissioning. It is within this context that the IAEA launched a regional technical co-operation project in 1994 with the aim of providing guidance on planning and management of decommissioning for WWERs. The project, which had a duration of four years (1995-1998), included the organization of workshops and scientific visits to countries having WWERs and other countries where active decommissioning projects were under way. Eventually, participants suggested the consolidation of expert guidance and collective opinions into a TECDOC, which was drafted by both designated participants from project recipient countries and invited experts. The TECDOC has the aim of serving as a stimulus for all concerned parties in central and eastern European countries to initiate concrete decommissioning planning, including assessment of existing and required resources for the eventual implementation of decommissioning plans. In addition, the regional technical co-operation project has managed to bring together in this TECDOC a number of good practices that could be useful in WWER-440 decommissioning

  15. ORGANIZATION AND METHOD FOR THE REMOTE LABORATORY WORK OF GENERAL TECHNICAL DISCIPLINE

    Directory of Open Access Journals (Sweden)

    Alfia Sh. Salakhova

    2014-01-01

    Full Text Available The article is devoted to the important problem – use of distant technologies in engineering education in the laboratory experiments. The role of distant experiment in the modern engineering education is discussed. The authors consider structure of the distant system to real experiments control and the method of realization distant laboratory work in the educational process. The analysis of distant laboratory work effectiveness is discussed. 

  16. Technical session 4: Health and safety issues. Working environment control in beryllium handling area

    International Nuclear Information System (INIS)

    Yonehara, K.; Natori, Y.; Tatenuma, K.; Nakamichi, Masaru

    2016-01-01

    Beryllium (Be) and its intermetallic compound (beryllide) are recommended from Japan as the most promising solid neutron multiplier for nuclear fusion power plant. The shape as the neutron multiplier is small sphere (pebble), and the mass production technology of it must be developed urgently. Beryllium is the substance regulated by the law of Ordinance on Prevention of Hazards Due to Specified the Chemical Substances Control. We'll report on a way of the operational environmental management to make a safe Be handling area for the Be handling researchers and workers. (author)

  17. Job creation, heterogeneous workers and technical change : matched worker/plant data : evidence from Norway

    OpenAIRE

    Salvanes, Kjell G.; Førre, Svein Erik

    2001-01-01

    Abstract: Using matched worker/plant level data for Norway, theories explaining the change in skill composition are assessed using direct evidence on the job creation and destruction for high, medium and low skilled workers. Skill based job creation is analysed in detail for plants in a high-skill service sector and in low- and high-tech manufacturing sectors. Given a compressed wage structure in Norway and increased supply of high skilled workers, the supply of skills may also explain the...

  18. Should the service life of nuclear power plants be limited for technical reasons?

    International Nuclear Information System (INIS)

    Schomer, E.

    1995-01-01

    German nuclear power plant operating licenses take into account the fact that the design lifetime of the facilities is 40 years. The technological lifetime, however, is governed by actual ageing processes and operational burden. The service life of nuclear power plants can be extended by replacement of the steam generator and by repair or replacement of the reactor pressure vessel or parts thereof. Attention is also paid to the reactor protection systems. (J.B.). 8 figs

  19. Social and economic impacts of the Trojan Nuclear Power Plant: a confirmatory technology assessment. Technical report

    International Nuclear Information System (INIS)

    Wenk, E. Jr.; Bereano, P.L.; Douglass, J.; Watson, R.H.; Zemansky, G.M.

    1979-10-01

    The Trojan nuclear plant located 32 miles northwest of Portland, Oregon was chosen for a case study. A background of the physical, demographic, economic, and political context of the communities is provided. This is followed by an evaluation of the impacts of plant construction and operation including local taxation, employment, business activity and income, demography, public utilities and transportation, land use, housing, recreation, culture and lifestyle, public safety, education, health care, and politics and institutions

  20. Nuclear heat generating plants - technical concepts and market potentials. Chapter 8

    International Nuclear Information System (INIS)

    Thoene, E.

    1988-01-01

    To determine the advantages and disadvantages of different heat generating systems, a comparison is made between nuclear heat generating plants and competing heat generating systems. Nuclear heat generating plant concepts in practice have to compete with a wide range of existing and new fossil heat generating technologies of the most different capacities, ranging from combined heat and power generation to individual heating in one-family houses. Heat generation costs are calculated by means of a dynamic annuity method from an economic point of view. The development of real prices of fossil energy sources is based on two scenarios characterized as follows: scenario I - insignificant price increase by the year 2000, then stagnant; scenario II - moderate price increase by the year 2010, then stagnant. As a result of that systems comparison it can be stated that the considered nuclear heat generating plants may be an interesting competitive heat generation option, provided the assumptions on which the study is based can be implemented. This applies especially to investment costs. At the same time those plants contribute to a diversification of energy source options on the heat market. Their use leads to a reduction of fossil fuel imports, increasing at the same time short- and long-term supply guarantees. If nuclear heat generating plants substitute fossil heat generating plants, or render the construction of new ones superfluous, they contribute to avoiding chemical air pollutants. (orig./UA) [de

  1. Physicochemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

    International Nuclear Information System (INIS)

    Khakimov, N.; Nazarov, Kh.M.; Khojiyon, M.; Mirsaidov, I.U.; Nazarov, K.M.; Barotov, B.B.

    2012-01-01

    Physicochemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective for reprocessing is Chkalovsk tailing's wastes. Engineer and geological condition and content of radionuclides in wastes are investigated. It is determined that considered wastes by radioactivity are low-active and they can be reprocessed with the purpose of U 3 O 8 production. Grinding, crumbling, thickening and etc. operations are decreased during the wastes reprocessing process. Uranium output is more than 90%. Optimal parameters of products extraction from uranium mining industry wastes are found. Characteristics of mine and technical waters of uranium industry wastes are studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of State Enterprise 'Vostokredmet' by classical methods of uranium leaching are studied. Kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk city) is investigated. Carried out investigations are revealing the flow mechanism process of residues' sulfuric leaching and enable selection of radiation regime of U 3 O 8 production. Kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes is studied. High sorption properties of apricot's shell comparing to other sorbents are revealed. Basic process flow diagram for reprocessing of uranium tailing wastes is developed as well as diagram for uranium extraction from mine and technical waters from uranium industry wastes which consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration, drying.

  2. Development of technical information basis of aging management for nuclear power plants

    International Nuclear Information System (INIS)

    Kanno, M.

    2007-01-01

    In order to implement effective safety regulations on aging management for reactor facilities etc., the information on important technology issues, the latest technical knowledge including evaluation technology, test and research outcomes, related codes and standards, regulation information, operation experiences such as accidents and trouble, etc. with respect to aging-induced deterioration in and outside Japan and in other industries, were collected, organized and evaluated. (author)

  3. Physicochemical basics for production of uranium concentrate from wastes of hydrometallurgical plants and technical waters

    International Nuclear Information System (INIS)

    Khakimov, N.; Nazarov, Kh.M.; Khojiyon, M.; Mirsaidov, I.U.; Nazarov, K.M.; Barotov, B.B.

    2012-01-01

    Physicochemical and technological basics for reprocessing of uranium industry wastes of Northern Tajikistan shows that the most perspective for reprocessing is Chkalovsk tailing's wastes. Engineer and geological condition and content of radionuclides in wastes are investigated. It is determined that considered wastes by radioactivity are low-active and they can be reprocessed with the purpose of U 3 O 8 production. Grinding, crumbling, thickening and etc. operations are decreased during the wastes reprocessing process. Uranium output is more than 90%. Optimal parameters of products extraction from uranium mining industry wastes are found. Characteristics of mine and technical waters of uranium industry wastes are studied. Characteristics of mine and technical waters of Kiik-Tal and Istiklol city (former Taboshar) showed the expediency of uranium oxide extraction from them. The reasons for non-additional recovery extraction from dumps of State Enterprise 'Vostokredmet' by classical methods of uranium leaching are studied. Kinetics of sulfuric leaching of residues from anthropogenic deposit of Map 1-9 (Chkalovsk city) is investigated. Carried out investigations are revealing the flow mechanism process of residues' sulfuric leaching and enable selection of radiation regime of U 3 O 8 production. Kinetics of sorption process of uranium extraction from mine and technical waters of uranium industry wastes is studied. High sorption properties of apricot's shell comparing to other sorbents are revealed. Basic process flow diagram for reprocessing of uranium tailing wastes is developed as well as diagram for uranium extraction from mine and technical waters from uranium industry wastes which consists of the following stages: acidification, sorption, burning, leaching, sedimentation, filtration, drying.

  4. AN ANALYSIS OF TECHNICAL SECURITY CONTROL REQUIREMENTS FOR DIGITAL I&C SYSTEMS IN NUCLEAR POWER PLANTS

    Directory of Open Access Journals (Sweden)

    JAE-GU SONG

    2013-10-01

    Full Text Available Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

  5. Education and research when dismantling nuclear plants at the Technical University Dresden

    International Nuclear Information System (INIS)

    Hurtado, A.; Anthofer, A.; Cloppenborg, T.; Schreier, M.

    2013-01-01

    With the decision by the German government in 2011 to revoke the operating permission from 8 of the existing 17 German nuclear power plants, the responsibility of decommissioning and dismantling these plants has moved back into the focus of public awareness. Under the current legal conditions, the last nuclear plant will be disconnected from the grid on 31.12.2022 and this will create an enormous challenge for all the involved approving authorities, expert organisations, as well as companies involved in dismantling the plants. The development of new and efficient dismantling technologies and strategies is required to perform these highly responsible tasks. On the other hand, the nuclear competence and knowhow, as well as the promotion of young talents in the relevant scientific fields must be preserved. Technological and economic solutions are in demand for the various plants due to the different specifics of nuclear power plants. This will still require e.g. in the field of radiation protection highly qualified and well trained staff in future. The training of these skilled employees will require expanding the subject matter taught at universities, colleges and polytechnics to suit the changed parameters. The chair for hydrogen and nuclear energy technology at the TU Dresden will in future offer lectures as part of a new teaching discipline with the focus on dismantling and disposal. The course 'Dismantling nuclear power plants' took place for the first time in the summer semester 2013. It is organised as a three-day block seminar with an excursion to the company NIS Ingenieurgesellschaft mbH in Alzenau. The company NIS is a subsidiary of the Siempelkamp Nukleartechnik GmbH. This article intends to provide an overview of the contents of the courses and the impressions of the participants. In this way the TU Dresden is making a further contribution to preserving nuclear competence and inter-disciplinary dialogue. (orig.)

  6. Development of a daily maintenance work management system for nuclear power plants

    International Nuclear Information System (INIS)

    Yoshimura, Sadanori; Maita, Keikichi; Ogawa, Koutaro; Tabata, Nobuyuki; Shibuya, Shinya

    1999-01-01

    Maintenance work plays an important role in keeping the safety and reliability of nuclear power plants. Especially, with the recent trends of reducing the outage length, safe and reliable execution of maintenance work is more earnestly required than ever. Taking this situation into account, a daily maintenance work management system has been developed to support the execution of maintenance work for nuclear power plants. This system supports maintenance personnel in writing and approving the daily work instruction sheet and reduces their workload by providing predetermined lists of items necessary for filling up the sheet and by applying an electronic approval procedure. It also provides information through a computer network to improve the communication among maintenance personnel. For work steps to be treated in the daily work instruction sheet, an analysis was made to identify potential human errors and related counter measures, which were then linked to safety and quality assurance instructions of the sheet. Based on this information, the system automatically presents the safety and quality assurance instructions related to the work content listed in the sheet to improve the appropriateness of the instructions. A prototype of the daily maintenance work management system was developed and a trial use was made for actual periodic maintenance work at a nuclear power plant. This experience shows the usefulness of the system in reducing the workload of maintenance personnel and in providing safer work instructions. (author)

  7. Technical work plan for Surface Impoundments Operable Unit engineering support studies

    International Nuclear Information System (INIS)

    1995-11-01

    This document provides a comprehensive work plan which, when utilized as a data collection guide for field activities, will provide the necessary information required to complete a report on geotechnical properties of the sediments contained in the Surface Impoundments Operable Unit at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Detailed guidance is provided for the following activities: collection of samples from the impoundments; compressive strength testing of the raw sediments; compressive strength testing of the structurally modified (lime and cement additives) sediments; testing for sediment physical properties and settling rates; testing for sediment dewatering characteristics; testing for radiation activity during the field work; testing for polymer additions that may enhance settling. The work plan additionally provides guidance and examples for the preparation of documents necessary to establish readiness for safe and satisfactory performance of the field activities. An outline for the format requested for a report of these data is also provided

  8. Technical work plan for Surface Impoundments Operable Unit engineering support studies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    This document provides a comprehensive work plan which, when utilized as a data collection guide for field activities, will provide the necessary information required to complete a report on geotechnical properties of the sediments contained in the Surface Impoundments Operable Unit at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Detailed guidance is provided for the following activities: collection of samples from the impoundments; compressive strength testing of the raw sediments; compressive strength testing of the structurally modified (lime and cement additives) sediments; testing for sediment physical properties and settling rates; testing for sediment dewatering characteristics; testing for radiation activity during the field work; testing for polymer additions that may enhance settling. The work plan additionally provides guidance and examples for the preparation of documents necessary to establish readiness for safe and satisfactory performance of the field activities. An outline for the format requested for a report of these data is also provided.

  9. Nuclear power plant and childhood leukaemia - Report by the pluralist working group

    International Nuclear Information System (INIS)

    Sommelet, Daniele; Barbey, Pierre; Baruchel, Andre; Bey, Pierre; Catelinois, Olivier; Vacquier, Blandine; Chartier, Michel; Chenal, Christian; Clavel, Jacqueline; De Vathaire, Florent; Grosche, Bernd; Faure, Claire; Jacob, Sophie; Laurier, Dominique; Marignac, Yves; Unwin, Philippe; Vernez, David; Gagniere, Bertrand; Perel, Yves

    2011-04-01

    nuclear power plant and the risk of leukaemia in children? There is no official answer to this question, barring that exposure to high doses or to high dose rates increases the risk. Many other genetic and environmental causes must also be taken into consideration, in order to prevent any misunderstanding. The molecular heterogeneity of leukaemia must also be taken into account when interpreting the data. Despite this complexity, the general public needs objective, comprehensible information. Scientists are under the obligation to meet the legitimate expectations of a society that is not only fully aware of its 'right to know', but is also eager for greater humanity and trust. For the reasons listed above, an independent, pluralist, technical working group composed of French and foreign experts with complementary skills and interests was created with the following mandate: - Issue an opinion on the available epidemiological knowledge of the effects of nuclear power plant (NPP), focusing in particular on the risk of childhood leukaemia; - Define the research needed to improve the existing data; - Help to deliver clear, transparent and regular information to the general public.; - Draw up guidelines for improving the existing knowledge on the link between childhood leukaemia and nuclear power plant (especially the impact of very low doses of ionising radiations). These guidelines will be made public. - Present the progress of this work to a national committee tasked with planning and monitoring the measures needed to improve the available knowledge of the effects of discharge from the nuclear industry on the health of people living nearby

  10. Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations

  11. Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    The 35th Annual Meeting of the Technical Working Group on Fast Reactors TWG-FR, previously International Working Group on Fast Reactors (IWG-FR, created in 1967), was hosted by the Forschungszentrum Karlsruhe (FZK) and was attended by TWG-FR members and advisers from the following Member States: Brazil, China, France, Germany, India, Japan, the Republic of Kazakhstan, the Republic of Korea, the Russian Federation, and the United States of America. The objectives of the meeting were: to exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); to review the progress since the 34th TWG-FR Annual Meeting, including the status of the actions; to consider meeting arrangements for 2002 and 2003; to review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations.

  12. Establishment of the technical basis for applying viscous dampers to nuclear power plants

    International Nuclear Information System (INIS)

    Narahara, Yukiko; Higuchi, Tomokazu; Katayama, Hiroshi; Ito, Ryo; Hattori, Kiyoshi; Nakajima, Jun

    2017-01-01

    For the purpose of introducing viscous dampers to nuclear power plants, the damping characteristic of the viscous damper under specific conditions in nuclear power plants was examined. In particular the seismic response analysis method, the design evaluation method, and the maintenance and management guideline were studied. In the viscous dampers characteristic test, the damping characteristics under earthquake motion and the environmental condition of nuclear power plants have been examined. From the test results, if the parameters such as vibration amplitude, vibration frequency, repeated load, temperature, and radiation are considered, there is a possibility of viscous damper application to components in nuclear power plants. In order to evaluate the applicability of the complex modal analysis method using response spectrum, comparison with the time history response analysis result was performed using a PWR steam generator analysis model. The evaluation result from the complex modal analysis method was in good agreement with the time history response analysis result, and the availability of this method was confirmed. From the test results, considerations in design and maintenance in the case of applying viscous dampers to nuclear power plants were selected. The bases of the design evaluation method and the maintenance and management guideline were developed. (author)

  13. A Study of Time Spent Working at Learning Centers. Technical Report #17.

    Science.gov (United States)

    Omori, Sharon; And Others

    This study examined the proportion of time children in the Kamehameha Early Education Program schools spend at actual school work in learning centers. Systematic time-sampled observations using multiple observers were conducted in December-January and again in March-April. The subjects, 12 children (6 kindergarteners and 6 first graders) were…

  14. Enhanced technical and economic working domains of industrial heat pumps operated in series

    DEFF Research Database (Denmark)

    Ommen, Torben; Jensen, Jonas Kjær; Markussen, Wiebke Brix

    2015-01-01

    By operating heat pumps (HPs) in series, it is possible to obtain closer match between working fluid and sink- and source streams, resulting in higher coefficient of performance (COP). For industrial HPs, it was found that serial connection of either two or three units results in an increase in COP...

  15. Analysis of traffic signal work backlog in Louisiana : technical assistance report.

    Science.gov (United States)

    1995-07-01

    A review of Traffic Services' traffic signal work records reveals the source of the backlog. During the 1980's, the department experienced personnel cutbacks and hiring freezes that caused the number of field personnel to drop from 40 to 24. Simultan...

  16. Technical basis for beta skin dose calculations at the Y-12 Plant

    International Nuclear Information System (INIS)

    Thomas, J.M.; Bogard, R.S.

    1994-03-01

    This report describes the methods for determining shallow dose equivalent to workers at the Oak Ridge Y-12 Plant from skin contamination detected by survey instrumentation. Included is a discussion of how the computer code VARSKIN is used to calculate beta skin dose and how the code input parameters affect skin dose calculation results. A summary of Y-12 Plant specific assumptions used in performing VARSKIN calculations is presented. Derivations of contamination levels that trigger the need for skin dose assessment are given for both enriched and depleted uranium with the use of Y-12 Plant site-specific survey instruments. Department of Energy recording requirements for nonuniform exposure of the skin are illustrated with sample calculations

  17. JOYO MK-III modification work on heat transport system. Working plan and plant control

    International Nuclear Information System (INIS)

    Isozaki, K.; Ichige, S.; Ohshima, J.

    2002-07-01

    The MK-III project to improve the irradiation capability of the experimental fast reactor JOYO have been in underway since 1987. The increase of fast neutron flux and the enlargement of that field increase the reactor thermal rate from 100 MWt to 140 MWt. To increase cooling capacity of heat transport system, intermediate heat exchangers (IHXs), dump heat exchangers (DHXs), piping connecting to IHXs and DHXs, main motors on primary and secondary main circulation pumps were replaced. The replacement of these large components was carried out under following hard conditions. 1) Limitation of work space, 2) Fuel subassembly and molten sodium in the reactor vessel, 3) high radiation circumstances for primary cooling system, 4) treatment of radioactive sodium (radioactive sodium and corrosion product such as 60 Co, 54 Mn). There are little experiences of this kind of work in the world. Therefore the organization, working plan and safety management points were carefully examined and established, based on the previous experience of JOYO operation and maintenance, research and development results of safety treatment of sodium, experience of previous work on sodium facilities. Followings results were obtained and effectiveness was confirmed in the work. (1) Development of most suitable working plan derived from elements and full size mock up experiments, reduction of exposure time by workers training, reduction of radiation dose by installation of temporal radiation shielding were useful to reduce radiation dose. The usage of seal bag was useful to prevent the contamination spreading over. (2) The usage of seal bag, oxygen concentration monitoring in the seal bag, nitrogen concentration monitoring in the cooling system cover gas, low pressure control of cover gas were useful to reduce the inflow of oxygen to cooling system. (3) The bite cutting method for piping in air and press down cutting by roller cutter in the seal bag to prevent inflow of cutting piece, stopper

  18. Technical design considerations in the provision of a commercial MOX plant

    International Nuclear Information System (INIS)

    Elliott, M.F.

    1997-01-01

    The Sellafield MOX Plant (SMP) has a design production target of 120 t/year Heavy Metal of mixed uranium dioxide and plutonium dioxided (MOX) fuel. It will have the capability to produce fuel with fissile enrichments up to 10%. The feed materials are those arising from reprocessing operations on the Sellafield site, although the plant also has the capability to receive and process plutonium from overseas reprocessing plants. The ability to produce 10% enriched fuels, together with the requirement to use high burn-up feed has posed a number of design challenges to prevent excessive powder temperatures within the plant. As no stimulants are available to represent the heat generating nature of plutonium powders, it is difficult to prove equipment design by experiment. Extensive use has therefore been made of finite element analysis techniques. The requirement to process material of low burn-up (i.e. high fissile enrichment) has also impacted on equipment design in order to ensure that criticality limits are not exceeded. This has been achieved where possible by 'safe by geometry' design and, where appropriate, by high integrity protection systems. SMP has been designed with a high plant availability but at minimum cost. The requirement to minimize cost has meant that high availability must be obtained with the minimum of equipment. This had led to major challenges for equipment designers in terms of both the reliability and also the maintainability of equipment. Extensive use has been made of theoretical modelling techniques which have given confidence that plant throughput can be achieved. (author). 1 fig

  19. Analytical technical of lightning surges induced on grounding mesh of PWR nuclear power plant

    International Nuclear Information System (INIS)

    Ikeda, I.; Tani, M.; Yonezawa, T.

    1990-01-01

    An analytical lightning surge technique is needed to make a qualitative and predictive evaluation of transient voltages induced on local grounding meshes and instrumentation cables by a lightning strike on a lightning rod in a PWR plant. This paper discusses an experiment with lightning surge impulses in a PWR plant which was setup to observe lightning caused transient voltages. Experimental data when compared with EMTP simulation results improved the simulation method. The improved method provides a good estimation of induced voltages on grounding meshes and instrumentation cables

  20. Design and implementation of the control system for nuclear plant VVER-1000. Instrumentation (program technical complexes)

    International Nuclear Information System (INIS)

    Siora, A.; Tokarev, V.; Bakhmach, E.

    2004-01-01

    Program-technical complexes (PTC) are designed as control and protection systems in water-moderated atomic reactors, including emergency and preventive systems, automatic control, unloading, reactor capacity limitation and accelerated preventive protection systems. Utilization of programmable logic integrated circuits from world leading manufacturers makes the complexes simple in structure, compact, with low energy demands and mutually independent for key and supporting functions The results of PTC assessment and implementation in Ukraine are outlined. Opportunities for a future development of RADIJ company in the area of control and protection systems for VVER reactors are also discussed

  1. Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

    International Nuclear Information System (INIS)

    1997-07-01

    This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs

  2. Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs.

  3. Strategies and policies for nuclear power plant life management. Proceedings of the IAEA specialists meeting. Working document

    International Nuclear Information System (INIS)

    1998-01-01

    The purpose of the Specialists Meeting organized by the IAEA was to provide an international forum for discussing of recent results in national and utility experience in development of nuclear power plant life management programmes and their technical, regulatory and economic assessments. Plant life management requires detailed knowledge of ageing degradation of the components and the results of mitigation technologies. The basic conclusion includes the need of Guide on NPP Life management which should encompass: plant safety; plant availability; plant operating life extension; human resources policy; research and development needs

  4. Relationship between sociopsychological factors and technical and economic indices of work of drivage teams

    Energy Technology Data Exchange (ETDEWEB)

    Pershin, V.V.; Volkov, V.M.

    1986-11-01

    An attempt is described to define the level of harmony within mine drivage teams using mathematical methods in a sociological application. This procedure is derived from a work by Z.S. Coleman. A set ot 10 questions concerning relations with team members was put to each of the members of 7 drivage teams at Kuzbass mines. The answers were assessed on a points scale from lesser to greater harmony within the team. These points were then summarized and mathematically processed. Equations were derived for the degree of harmony or alienation of individual team members and for the degree of harmony attributable to relations both at and outside work. Computer processing of the data obtained revealed a good correlation between the degree of harmony within drivage teams and average monthly earnings. 3 references.

  5. IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    In response to needs expressed by Member States and within a broader IAEA-wide effort in nuclear knowledge preservation, the IAEA has been carrying out a dedicated initiative on Fast Reactor Data Knowledge Preservation (FRKP). The main objectives of the FRKP initiative are to: • Halt the on-going loss of information related to Fast Reactors (FR); • Collect, retrieve, preserve and make accessible already existing data and information on FR. These objectives require the implementation of activities supporting digital document archival, exchange, search and retrieval and facilitating, by developing and using suitable standards and IT tools, the knowledge preservation over the next decades. To this purpose the IAEA has developed the Fast Reactor Knowledge Organization System (FRKOS), a web-based application employing IAEA methodology and approach for categorization of FR knowledge domain, which allows creating a comprehensive and well-structured international inventory of fast reactor data and information provided by different Member States. The resulting Web Portal is established and maintained by the IAEA. The IAEA knowledge preservation initiatives and tools in the field of fast neutron systems - which were presented and very well received during the recent IAEA Fast Reactor and Related Fuel Cycles Conference (FR13) - are supposed to be of interest for national nuclear authorities, regulators, scientific and research organizations, commercial companies and all other stakeholders involved in fast reactor activities at national or international level. The objectives of the technical meeting were to: • Exchange information between the member states/international organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • Present and discuss the member states’/international organizations’ policies and conditions for releasing to the IAEA both publicly

  6. Experiences with the technical cooperation project TC MEX 04/53. Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant. Management program of the plant life (PLIM)

    International Nuclear Information System (INIS)

    Arganis J, C.R.; Aguilar T, J.A.; Guevara M, A.; Garcia M, C.; Martinez G, R.R.; Griz C, M.M.; Sanchez M, M.A.; Diaz O, R.C.

    2006-01-01

    In the biennium 2005-2006 the project of technical cooperation with the International Atomic Energy Agency OIEA TC MEX 04/53 'Evaluation of the integrity and extension of life of the Laguna Verde nuclear power plant Plant life handling program (PLIM)' was approved, which has as objective the one to begin the actions to apply the methodology of Handling of life of Plant (PLIM) in the Unit I (Ul) of the Laguna Verde Nucleo electric Central (CNLV), in order to obtain the Renovation of License (LR), in a long term (2020). To apply this methodology 5 systems they were selected, structures or components (SEC) to carry out the handling programs of the one aging (AMP), and PLIM which are: The encircling of the reactor core (Core Shroud), the pressure vessel of the reactor (Reactor Pressure Vessel), the one primary container (Primary Containment), the system of feeding water (Reactor Feed Water) and cables, which were not in this work to be of another nature. The report presents the more important aspects considered in these systems for their programs of AMP and PLIM, as like a revision of those selection processes and evaluation (screening and scoping) for the application of PLIM in the systems of the Ul of the CNLV. (Author)

  7. First generation of fusion power plants: Design and technology. Proceedings of the 2. IAEA technical meeting

    International Nuclear Information System (INIS)

    2008-01-01

    This series of meetings has been initiated under recommendation of the International Fusion Research Council for the IAEA and is expected to initiate, develop and mature ideas on fusion strategy that would be of benefit for all players. The present objectives of this meeting are to provide a forum to discuss concepts, technology and environmental aspects of future fusion power plants, the next step following ITER, their role in future energy mix and to assess a selection of urgent topics aiming at identifying the physics and the technological requirements that ITER and a fusion grade materials developing programme will have to address to support the construction of a DEMO(s) fusion power plant(s) prototype demonstrating viable economics. The meeting was organized in five sessions addressing five topics: - (PPCA) Power Plant Concepts and systems Analysis. - (MCP) Materials analysis/Components design/Plasma requirements - (NE) Non-Electric applications of fusion - (SESE) Social, Economic, Safety and Environmental aspects of fusion - (EP) Energy Policy, strategy and scenario for fusion development. A summary session took place at the end of the meeting. Thirty-three participants representing 12 Countries and 3 International Organizations were present at the meeting

  8. Determination of installation capacity in reservoir hydro-power plants considering technical, economical and reliability indices

    DEFF Research Database (Denmark)

    Hosseini, S.M.H.; Forouzbakhsh, Farshid; Fotouh-Firuzabad, Mahmood

    2008-01-01

    One of the most important issues in planning the ‘‘reservoir” type of hydro-power plants (HPP) is to determine the installation capacity of the HPPs and estimate its annual energy value. In this paper, a method is presented. A computer program has been developed to analyze energy calculation...

  9. Technical evaluation of the G.E. Transportable Modular AZTECH Plant topical report

    International Nuclear Information System (INIS)

    Henscheid, J.W.; Stalker, A.E.

    1985-12-01

    This report summarizes EG and G Idaho's review of the General Electric Company's topical report on their Transportable Modular AZTECH Plant. The review evaluated compliance with pertinent codes, standards and regulations. The initial review was discussed with G.E. and all outstanding issues resolved before this final evaluation was made

  10. Physical protection of nuclear power plants-technical and legal aspects

    International Nuclear Information System (INIS)

    Castro Martins, O.J. de.

    1978-04-01

    The nuclear power plants are defined according to the definitions included in the Brazilian legislation and international conventions and their physical protection is analysed. Besides, the differences and the relations among nuclear security, safeguards and physical protection are established. (A.L.) [pt

  11. Development of a support system to make economic and technical assessments for the issues relating to plant life extension

    International Nuclear Information System (INIS)

    Takao, T.; Soneda, N.; Sakai, T.

    1994-01-01

    To realize the life extension of nuclear power plants, overall evaluation for the plant is required, which covers technology, economy such as cost of repair or/and replacement of components, and regal regulations for licensing. A prototype of integrated assessment support system for life extension ''INPLEX'' have developed in order to evaluate the technical and economic issues relating to the plant life extension and to make a life extension scenario. Analysis procedure of INPLEX is as follows. A comparison of the cost between the life extension and the reconstruction is made to see whether the life extension is cost effective or not. Next, components required detailed assessments are selected, and the residual life assessment of these components are made. After those procedures life extension measures are selected and the implementation time schedule is set on the basis of the formulas for predicting the degradation of the components and the component reliability data. Finally the implementation time schedule is optimized from the viewpoint of economy, and the life extension scenario is proposed. INPLEX also has the data base ''PRINS'', in which information and data related to life extension are registered, such as component degradation experiences, degradation management methodologies, degradation mitigation measures, and so on. PRINS can be referred at any time during the operation of INPLEX

  12. Technical and economical feasibility studies and preliminary plan of a heavy water plant by the criogenic distillation method of hydrogen

    International Nuclear Information System (INIS)

    Dias Vargas, F.

    1983-01-01

    This paper presents the pre-feasibility study of a heavy water production plant, both from the technical and economical point of view. Criogenic distillation of hydrogen is used as the final enrichment stage. The deuterium source is water treated previously by a process of enrichment based on the water-hydrogen isotopic exchange. The economical analysis is aimed at the study of the feasibility of the installation of a heavy water moderated reaction in Chile. General properties of heavy water are presented and also the various materials of its enrichment at the industrial scale. The plant itself has a first stage based on the water-hydrogen isotopic exchange procesS, where deuterium is extracted from the water by the hydrogen which is subsequently treated in a criogenic distillation stage. An important fact of the plant analysis is the calculation of heat exchangers mainly in relation to the problem posed by tHe hydrogen's low point of liquifaction. The distillation units are also treated and designed. The economic evaluation produces project diScount rates of 15.71% and 21.97%, for 25 tons/year and 40 tons/year of production capacity. The heavy water price used for these evaluation was 600 $/Kg

  13. Computation code TEP 1 for automated evaluation of technical and economic parameters of operation of WWER-440 nuclear power plant units

    International Nuclear Information System (INIS)

    Zadrazil, J.; Cvan, M.; Strimelsky, V.

    1987-01-01

    The TEP 1 program is used for automated evaluation of the technical and economic parameters of nuclear power plant units with WWER-440 reactors. This is an application program developed by the Research Institute for Nuclear Power Plants in Jaslovske Bohunice for the KOMPLEX-URAN 2M information system, delivered by the USSR to the V-2 nuclear power plants in Jaslovske Bohunice and in Dukovany. The TEP 1 program is written in FORTRAN IV and its operation has two parts. First the evaluation of technical and economic parameters of operation for a calculation interval of 10 mins and second, the control of the calculation procedure, follow-up on input data, determination of technical and economic parameters for a lengthy time interval, and data printout and storage. The TEP 1 program was tested at the first unit of the V-2 power plant and no serious faults appeared in the process of the evaluation of technical and economic parameters. A modification of the TEP 1 programme for the Dukovany nuclear power plant is now being tested on the first unit of the plant. (Z.M.)

  14. Technical meeting (TM) to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Technical Working Group on Fast Reactors (TWG-FR) (37th annual meeting). Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The objectives of the 37th Annual Meeting of the Technical Working Group on Fast Reactors, were to: 1) exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); 2) review the progress since the 36th TWG-FR Annual Meeting, including the status of the actions; 3) consider meeting arrangements for 2004 and 2005; 4) review the Agency's co-ordinated research activities in the field of FRs and ADS, as well as co-ordination of the TWG-FR's activities with other organizations. The participants made presentations on the status of the respective national programmes on FR and ADS development. A summary of the highlights for the period since the 36th TWG-FR Annual Meeting is included in this proceedings. Annex IV contains the Review of National Programs on Fast Reactors and Accelerator Driven Systems (ADS), and the TWG-FR Activity Report for the Period May 2003-April 2004.

  15. Using a third party for nuclear plant civil works, one of a solution for nuclear safety

    International Nuclear Information System (INIS)

    Chandeze, A.

    2010-01-01

    Issues that may happen during the construction of civil works of a nuclear power plant are numerous: concrete, reinforcement bars positioning, welding of the liner... On top of the above, quality and nuclear safety assurance is increasingly required by nuclear authorities to keep the current nuclear renaissance steady regarding public opinion. The speaker will present the benefits of using a third party during these civil works phases and about the value created for the circle of actors through a risk based inspection program. Going through the main stages of design and construction of civil works of a nuclear power plant, the main actors involved, their positioning and the role of a voluntary independent third party inspection body, the speaker demonstrates that an independent third party, voluntarily chosen by a Utility and nuclear power plant engineering company, may give confidence to each party. (authors)

  16. Technical Survey on Applications of Wireless Sensor Networks in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jiang, Jin; Bari, Ataul; Chen, Dongyi; Hashemian, Hash M.

    2014-01-01

    Even though there is no general consensus on using wireless technologies in nuclear power plants, potential applications of wireless sensor networks within nuclear power plants (NPPs) has been investigated. The topics of interests include potential interaction of wireless sensor networks with the sensitive protection equipment, radiation damage of the electronics on board sensor nodes, optimal placement of relay nodes that collect and forward data in the network, and possible applications, such as radiation dose and level monitoring, and equipment condition monitoring. Several wireless sensor networks have been deployed on site of NPPs on a trial basis to perform these tasks. Different aspects of deployment of such wireless sensor networks in NPPs have also been examined. Industrial standards or guidelines for deployment of WSNs in NPPs are also been considered. This paper examines the state of the art of wireless sensor networks in NPPs

  17. Technical Characteristics of the Process Information System - Nuclear Power Plant Krsko

    International Nuclear Information System (INIS)

    Mandic, D.; Smolej, M.

    1998-01-01

    process Information System (PIS) of Nuclear Power Plant Krsko (NEK) is newly installed distributed and redundant process computer system which was built in NEK (Phase I: 1991-1995) to integrate the following main functions: - Signal Data Acquisition from the technological processes and environment - Implementation of the basic SCADA functions on the real time process signals data base - Execution of complex plant specific application programs - Advanced MMI (Man Machine Interface) features for users in MCR - Process data transfer to other than Main Control Room (MCR) locations - Process data archiving and capability to retrieve same data for future analysis PIS NEK architecture consists of three hierarchically interconnected hardware platforms: - PIS Level 1, DAS (Data Acquisition System) Level - PIS Level2, Level for MMI, application programs and process data archiving - PIS Level 3, Level for distribution of process data to remote users of PIS data. (author)

  18. Integrated automatic non-destructive testing in industrial production and in the operation of technical plant

    International Nuclear Information System (INIS)

    Hoeller, P.

    1989-01-01

    The article deals with non-destructive testing (NDT) in automated manufacture and in the automated operation of industrial plant. In both areas of application, the tests are coupled to the process (real time operation) and the results are used for the control of manufacture or of the course of the process. The control process can be coupled to the process in open loop or closed loop. The subject is explained by the following examples: 1) Automated testing of sheets in a steelworks. 2) Automatic NDT on machine parts in tempering and machining by the 3MA system (3MA: micro-magnetic, multi-parameter, micro-structure and stress analysis). 3) Automated ultrasonic testing in manufacture and in the operation of plants with the ALOK data collection and processing system (ALOK: amplitude, running time, location curves). 4) Automated wheel running surface test on Intercity experimental train, and 5) automated level measurement on BWR pressure vessels. (orig./MM) [de

  19. Technical Survey on Applications of Wireless Sensor Networks in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Jin; Bari, Ataul [University of Western Ontario, Ontario (Canada); Chen, Dongyi [University of Electronic Science and Technology of China, Chengdu (China); Hashemian, Hash M. [AMS Technology Center, Knoxville (United States)

    2014-08-15

    Even though there is no general consensus on using wireless technologies in nuclear power plants, potential applications of wireless sensor networks within nuclear power plants (NPPs) has been investigated. The topics of interests include potential interaction of wireless sensor networks with the sensitive protection equipment, radiation damage of the electronics on board sensor nodes, optimal placement of relay nodes that collect and forward data in the network, and possible applications, such as radiation dose and level monitoring, and equipment condition monitoring. Several wireless sensor networks have been deployed on site of NPPs on a trial basis to perform these tasks. Different aspects of deployment of such wireless sensor networks in NPPs have also been examined. Industrial standards or guidelines for deployment of WSNs in NPPs are also been considered. This paper examines the state of the art of wireless sensor networks in NPPs.

  20. Critical excitation method for calculating earthquake effects on nuclear plant structures: an assessment study. Technical report

    International Nuclear Information System (INIS)

    Bedrosian, B.; Barbela, M.; Drenick, R.F.; Tsirk, A.

    1980-10-01

    The critical excitation method provides a new, alternative approach to methods presently used for seismic analysis of nuclear power plant structures. The critical excitation method offers the advantages that: (1) it side-steps the assumptions regarding the probability distribution of ground motions, and (2) it does not require an artificial, and to some extent arbitrarily generated, time history of ground motion, both features to which structural integrity analyses are sensitive. Potential utility of the critical excitation method is studied from the user's viewpoint. The method is reviewed and compared with the response spectrum method used in current practice, utilizing the reactor buildings of a PWR and a BWR plant in case studies. Two types of constraints on critical excitation were considered in the study. In one case, only an intensity limit was used. In the other case, imposition of an intensity limit together with limits on the maximum acceleration and/or velocity for the critical excitation is considered