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Sample records for document passive plant

  1. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  2. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  3. Utility requirements for advanced LWR passive plants

    International Nuclear Information System (INIS)

    Yedidia, J.M.; Sugnet, W.R.

    1992-01-01

    LWR Passive Plants are becoming an increasingly attractive and prominent option for future electric generating capacity for U.S. utilities. Conceptual designs for ALWR Passive Plants are currently being developed by U.S. suppliers. EPRI-sponsored work beginning in 1985 developed preliminary conceptual designs for a passive BWR and PWR. DOE-sponsored work from 1986 to the present in conjunction with further EPRI-sponsored studies has continued this development to the point of mature conceptual designs. The success to date in developing the ALWR Passive Plant concepts has substantially increased utility interest. The EPRI ALWR Program has responded by augmenting its initial scope to develop a Utility Requirements Document for ALWR Passive Plants. These requirements will be largely based on the ALWR Utility Requirements Document for Evolutionary Plants, but with significant changes in areas related to the passive safety functions and system configurations. This work was begun in late 1988, and the thirteen-chapter Passive Plant Utility Requirements Document will be completed in 1990. This paper discusses the progress to date in developing the Passive Plant requirements, reviews the top-level requirements, and discusses key issues related to adaptation of the utility requirements to passive safety functions and system configurations. (orig.)

  4. EP1000 passive plant description

    International Nuclear Information System (INIS)

    Saiu, G.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In Phase I of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) will be completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. The second part, 'Phase 2B', includes both the analyses and evaluations required to demonstrate the adequacy of the design, and to support the preparation of Safety Case Report. The second part of Phase 2 of the program will start at the beginning of 1999 and will be completed in the 2001. Incorporation of the EUR has been a key design requirement for the EP1000 from the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. This paper integrates and updates the plant description reported in the IAEA TECDOC-968. The most significant developments of the EP1000 plant design during Phase 2A of the EPP program are described and reference is made to the key design requirements set by the EUR Rev. B document. (author)

  5. Protocol Monitoring Passive Solar Energy. Background document

    International Nuclear Information System (INIS)

    Van den Ham, E.R.

    1998-01-01

    A method has been developed by means of which the contribution of passive solar energy to the Dutch energy balance can be quantified univocally. The monitoring will be directed at the absolute amount of used solar energy, the relative contribution of passive solar energy to the energy demand in the Netherlands, and the average efficiency of passive solar energy systems. Based on a model of the total building stock the quantities to be monitored can be determined. The most important parameters in the model are: the window surface per orientation, the average U-value (heat transfer coefficient) of windows, the average ZTA-value (incoming solar radiation factor) of windows, and the presence of sun lounges and atriums

  6. Passive Nuclear Plants Program (UPDATE)

    International Nuclear Information System (INIS)

    Chimeno, M. A.

    1998-01-01

    The light water passive plants program (PCNP), today Advanced Nuclear Power Plants Program (PCNA), was constituted in order to reach the goals of the Spanish Electrical Sector in the field of advanced nuclear power plants, optimize the efforts of all Spanish initiatives, and increase joint presence in international projects. The last update of this program, featured in revision 5th of the Program Report, reflects the consolidation of the Spanish sector's presence in International programs of the advanced power plants on the basis of the practically concluded American ALWR program. Since the beginning of the program , the PCNP relies on financing from the Electrical sector, Ocide, SEPI-Endesa, Westinghouse, General Electric, as well as from the industrial cooperators, Initec, UTE (Initec- Empresarios Agrupados), Ciemat, Enusa, Ensa and Tecnatom. The program is made up of the following projects, already concluded: - EPRI's Advanced Light Water Plants Certification Project - Westinghouse's AP600 Project - General Electric's SBWR Project (presently paralyzed) and ABWR project Currently, the following project are under development, at different degrees of advance: - EPP project (European Passive Plant) - EBWR project (European Advanced Boiling Water Reactor)

  7. Nuclear power plants documentation system

    International Nuclear Information System (INIS)

    Schwartz, E.L.

    1991-01-01

    Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

  8. Plants for passive cooling. A preliminary investigation of the use of plants for passive cooling in temperate humid climates

    Energy Technology Data Exchange (ETDEWEB)

    Spirn, A W; Santos, A N; Johnson, D A; Harder, L B; Rios, M W

    1981-04-01

    The potential of vegetation for cooling small, detached residential and commercial structures in temperate, humid climates is discussed. The results of the research are documented, a critical review of the literature is given, and a brief review of energy transfer processes is presented. A checklist of design objectives for passive cooling, a demonstration of design applications, and a palette of selected plant species suitable for passive cooling are included.

  9. EP 1000 -The European Passive Plant

    International Nuclear Information System (INIS)

    Cummins, Ed; Oyarzabal, Mariano; Saiu, Gianfranco

    1998-01-01

    A group of European utilities, along with Westinghouse and its industrial partner GENESI (an Italian consortium including ANSALDO and FIAT) initiated a program to evaluate Westinghouse passive nuclear plant technology for application in Europe. The European utility group consisted of: Agrupacion electrica para al Desarrollo Technologico Nuclear (DTN), Spain; Electricite de France; ENEL, SpA., Italy; IVO Power Engineering, Ltd., Finland; Scottish Nuclear Limited (acting for itself on behalf of Nuclear Electric plc, U.K.; Tractebel Energy Engineering, Belgium; UAK (represented by NOK-Beznau), Switzerland; and Vattenfall AB, Ringhals, Sweden. The European Passive Plant (EPP) program, which began in 1994, is an evaluation of the Westinghouse 600 MWe AP 600 and 1000 MWe Simplified Pressurized Water Reactor (SPWR) designs in meeting the European Utility Requirements (EUR), and where necessary, modifying the design to achieve compliance. Phase 1 or the EPP program was completed and included the two major tasks of evaluating the effect of the EUR on the Westinghouse nuclear island and developing the EP 1000, a 1000 MWe passive plant reference design that conforms to the EUR and would be licensable in Europe. The EP 1000 closely follows the Westinghouse SPWR design for safety systems and containment and the AP 600 design for auxiliary systems. It also includes features that where required to meet the EUR and key European licensing requirements. The primary circuit of the EP 1000 retains most of the general features of the current-day designs, but some evolutionary features to enhance reliability, simplicity of operation, ease of maintenance, and plant safety have been incorporated into the design. The core, reactor vessel, and reactor internals of the EP 1000 are similar to those of currently operating Westinghouse PWR plants, but several new features are included to enhance the performance characteristics. The basic EP 1000 safety philosophy is based on use of inherent

  10. Westinghouse Advances in Passive Plant Safety

    International Nuclear Information System (INIS)

    Bruschi, H. J.; Manager, General; Gerstenhaber, E.

    1993-01-01

    On June 26, 1992, Westinghouse submitted the Ap600 Standard Safety Analysis Report and comprehensive PIRA results to the U. S. NRC for review as part of the Ap600 design certification program. This major milestone was met on time on a schedule set more than 3 years before submittal and is the result of the cooperative efforts of the U. S. Department of Energy (DOE), the Electric Power Requirements Program, and the Westinghouse Ap600 design team. These efforts were initiated in 1985 to develop a 600 MW advanced light water reactor plant design based on specific technical requirements established to provide the safety, simplicity, reliability, and economics necessary for the next generation of nuclear power plants. The Ap600 design achieves the ALRR safety requirements through ample design margins, simplified safety systems based on natural driving forces, and on a human-engineered man-machine interface system. Extensive Probabilistic Risk evolution, have recently shown that even if none of the active defense-in-depth safety systems are available, the passive systems alone meet safety goals. Furthermore, many tests in an extensive test program have begun or have been completed. Early tests show that passive safety perform well and meet design expectations

  11. UO3 plant turnover - facility description document

    International Nuclear Information System (INIS)

    Clapp, D.A.

    1995-01-01

    This document was developed to provide a facility description for those portions of the UO 3 Facility being transferred to Bechtel Hanford Company, Inc. (BHI) following completion of facility deactivation. The facility and deactivated state condition description is intended only to serve as an overview of the plant as it is being transferred to BHI

  12. Plant aging and design bases documentation

    International Nuclear Information System (INIS)

    Kelly, J.

    1985-01-01

    As interest in plant aging and lifetime extension continues to grow, the need to identify and capture the original design bases for the plant becomes more urgent. Decisions on lifetime extension and availability must be based on a rational understanding of design input, assumptions, and objectives. As operating plant time accumulates, the history of the early design begins to fade. The longer the utility waits, the harder it will be to re-establish the original design bases. Therefore, the time to develop this foundation is now. This paper demonstrates the impact that collecting and maintaining the original design bases of the plant can have on a utility's lifetime extension program. This impact becomes apparent when considering the technical, regulatory and financial aspects of lifetime extension. It is not good enough to know that the design information is buried somewhere in the corporate archives, and that given enough time, it could be retrieved. To be useful to the lifetime extension program, plant design information must be concise, readily available (i.e., retrievable), and easy to use. These objectives can only be met through a systematic program for collecting and presenting plant design documentation. To get the maximum benefit from a lifetime extension program, usable design bases documentation should be available as early in the plant life as possible. It will help identify areas that require monitoring today so that data is available to make rational decisions in the future

  13. Westinghouse AP1000 advanced passive plant: design features and benefits

    International Nuclear Information System (INIS)

    Walls, S.J.; Cummins, W.E.

    2003-01-01

    The Westinghouse AP1000 Program is aimed at implementing the AP1000 plant to provide a further major improvement in plant economics while maintaining the passive safety advantages established by the AP600. An objective is to retain to the maximum extent possible the plant design of the AP600 so as to retain the licensing basis, cost estimate, construction schedule, modularization scheme, and the detailed design from the AP600 program. Westinghouse and the US Nuclear Regulatory Commission staff have embarked on a program to complete Design Certification for the AP1000 by 2004. A pre-certification review phase was completed in March 2002 and was successful in establishing the applicability of the AP600 test program and AP600 safety analysis codes to the AP1000 Design Certification. On March 28, 2002, Westinghouse submitted to US NRC the AP1000 Design Control Document and Probabilistic Risk Assessment, thereby initiating the formal design certification review process. The results presented in these documents verify the safety performance of the API 000 and conformance with US NRC licensing requirements. Plans are being developed for implementation of a series of AP1000 plants in the US. Key factors in this planning are the economics of AP1000, and the associated business model for licensing, constructing and operating these new plants. Similarly plans are being developed to get the AP1000 design reviewed for use in the UK. Part of this planning has been to examine the AP1000 design relative to anticipated UK safety and licensing issues. (author)

  14. ESBWR passive heat exchanger design and performance - reducing plant development costs

    International Nuclear Information System (INIS)

    Lumini, E.; Upton, H.A.; Billig, P.F.; Masoni, P.

    1996-01-01

    The EUROPEAN Simplified Boiling Water Reactor (ESBWR) is a nuclear plant that builds on the solid technological foundation of the Simplified Boiling Reactor (SBWR) design. The major objective of the ESBWR program is to develop a plant design that utilizes the basic simplicity of the SBWR design that utilizes the basic simplicity of the SBWR design features to improve overall economics and to meet the specific requirements found in the European Utility Requirements Documents (EUR). The design is being developed by an international team of utilities, designers and researchers with the objective of meeting European utility and regulatory requirements. The overall approach to improve the commercial attractiveness of the ESBWR compared to the SBWR was to take advantage of the modular design of the passive safety system, the economy of scale, as well as the advantage of simpler systems of the passive plant to reduce overall material quantities and improve plant economics. To take advantage of the economy of scale, the power level of ESBWR was increased to 1190 MWe. Because of the modular nature of the passive safety systems in SBWR, in increase in thermal power of ESBWR to 3613 MWt only requires that the number of Passive Containment Condensers to maintain the passive safety features of ESBWR to four 33 MWt units for ESBWR. This paper reviews the Passive Containment Cooling (PCC) and Isolation Condenser (IC) unit design and addresses their use in the passive safety systems of the 3613 MWt ESBWR. The specific design differences and the applicability of the test completed at the SIET PANTHERS test facility in Piacenza, Italy are addressed as well as outlining additional qualification tests that must be completed on the PCC and IC unit design if they are to used in the passive safety systems of the ESBWR. This paper outlines the test results obtained from the prototype PCC and IC PANTHERS tests facility in Piacenza, Italy which have been used to design the ESBWR PCC/1C

  15. Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Soon Heung; Kim, Sang Ho; Choi, Jae Young

    2013-01-01

    Highlights: • We newly propose the design concept of integrated passive safety system (IPSS). • It has five safety functions for decay heat removal and severe accident mitigation. • Simulations for IPSS show that core melt does not occur in accidents with SBO. • IPSS can achieve the passive in-vessel retention and ex-vessel cooling strategy. • The applicability of IPSS is high due to the installation outside the containment. -- Abstract: The design concept of integrated passive safety system (IPSS) which can perform various passive safety functions is proposed in this paper. It has the various functions of passive decay heat removal system, passive safety injection system, passive containment cooling system, passive in-vessel retention and cavity flooding system, and filtered venting system with containment pressure control. The objectives of this paper are to propose the conceptual design of an IPSS and to estimate the design characters of the IPSS with accident simulations using MARS code. Some functions of the IPSS are newly proposed and the other functions are reviewed with the integration of the functions. Consequently, all of the functions are modified and integrated for simplicity of the design in preparation for beyond design based accidents (BDBAs) focused on a station black out (SBO). The simulation results with the IPSS show that the decay heat can be sufficiently removed in accidents that occur with a SBO. Also, the molten core can be retained in a vessel via the passive in-vessel retention strategy of the IPSS. The actual application potential of the IPSS is high, as numerous strong design characters are evaluated. The installation of the IPSS into the original design of a nuclear power plant requires minimal design change using the current penetrations of the containment. The functions are integrated in one or two large tanks outside the containment. Furthermore, the operation time of the IPSS can be increased by refilling coolant from the

  16. ESBWR-an economical passive plant design

    International Nuclear Information System (INIS)

    Arnold, H.; Stoop, P.M.; Gonzales, A.; Rao, A.

    1996-01-01

    The ESBWR is a plant design that builds on the GKN Dodewaard natural-circulation reactor and the simplified boiling water reactor (SBWR) design. The major objective of the ESBWR program, which has been in place for the past 3 yr, is to develop a plant design with proven technology that improves the overall plant economics. It utilizes the experience and basic simplicity of the Dodewaard plant and 670-MW(electric) SBWR design features. The design is being developed by an international team of utilities, designers, and researchers. It is being designed to meet the utility and regulatory requirements of Europe. It also addresses the key economic challenges for future nuclear power stations

  17. Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

    International Nuclear Information System (INIS)

    SCHWEHR, B.A.

    1999-01-01

    This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

  18. ESBWR-An economical passive plant design

    International Nuclear Information System (INIS)

    Gonzalez Lopez, A.; Rao, A.

    1996-01-01

    This paper provides an overview of the design features of the European Simplified Boiling Water Reactor (ESBWR) design. The ESBWR is a plant design that builds on the Simplified Boiling Water Reactor (SBWR) design described in Reference 1 and 2. The major objective of the ESBWR programme is to develop a plant design that utilizes the basic simplicity of the SBWR design features to improve overall economics as discussed in Reference 3. The design is being developed by an international team of utilities, designers and researchers, with the objective of applying it to the utility and regulatory requirements of Europe. (Author)

  19. Soil Moisture Active Passive (SMAP) Mission Level 4 Carbon (L4_C) Product Specification Document

    Science.gov (United States)

    Glassy, Joe; Kimball, John S.; Jones, Lucas; Reichle, Rolf H.; Ardizzone, Joseph V.; Kim, Gi-Kong; Lucchesi, Robert A.; Smith, Edmond B.; Weiss, Barry H.

    2015-01-01

    This is the Product Specification Document (PSD) for Level 4 Surface and Root Zone Soil Moisture (L4_SM) data for the Science Data System (SDS) of the Soil Moisture Active Passive (SMAP) project. The L4_SM data product provides estimates of land surface conditions based on the assimilation of SMAP observations into a customized version of the NASA Goddard Earth Observing System, Version 5 (GEOS-5) land data assimilation system (LDAS). This document applies to any standard L4_SM data product generated by the SMAP Project.

  20. Use of passive systems to improve plant operation and maintenance

    International Nuclear Information System (INIS)

    Shah, D.

    2000-01-01

    In a deregulated future, a utility's strength will depend on its ability to be cost competitive in the marketplace. However, the competitive advantage of nuclear power will depend on each owner's ability to reduce Operating and Maintenance (O and M) costs without sacrificing nuclear safety. The use of passive systems (i.e., systems without any moving parts) can reduce plant O and M costs while increasing safety in nuclear power plants. (author)

  1. Preparation of plant and system design description documents

    International Nuclear Information System (INIS)

    1989-01-01

    This standard prescribes the purpose, scope, organization, and content of plant design requirements (PDR) documents and system design descriptions (SDDs), to provide a unified approach to their preparation and use by a project as the principal means to establish the plant design requirements and to establish, describe, and control the individual system designs from conception and throughout the lifetime of the plant. The Electric Power Research Institute's Advanced Light Water Reactor (LWR) Requirements Document should be considered for LWR plants

  2. Advanced passive technology: A global standard for nuclear plant requirements

    International Nuclear Information System (INIS)

    Novak, V.

    1994-01-01

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

  3. From Dodewaard to a modern economic passive plant-ESBWR

    International Nuclear Information System (INIS)

    Arnold, H.; Yadigaroglu, G.; Stoop, P.M.; Gonzales, A.; Rao, A.S.

    1996-01-01

    For over 25 years the Dodewaard nuclear plant has produced electricity with one of the highest reliability of any nuclear power plant in the world. Almost 10 years ago when some designers looked at the features to incorporate in a modern mid-size Boiling Water Reactor (SBWR) design that was developed by an international team and consisted of natural circulation and passive safety injection and decay heat removal. Since the passive decay heat removal was a major new technology area, an extensive test program was developed and conducted - utilizing newly constructed large scale integrated system test facility at the Paul Scherrer Institute, Switzerland. The development of any modern reactor is time consuming and expensive, hence, the design and technology was done as part of an international team effort. This paper provides an overview of the international design and technology effort and discusses how the development costs were minimized through cooperation. The result of the design effort showed that overall plant economics could be improved by a power level increase, supported by some modest design changes. This paper provides the approach and key results of this multi-year international design effort to develop a modern, larger scale, passive plant - the European Simplified Boiling Water Reactor (ESBWR). This effort, in addition to developing an economic nuclear power station, also demonstrates how the benefits of international cooperation can be utilized to keep development costs reasonable. An overview is also provided of the planned research efforts to extend existing technology to the ESBWR. (authors)

  4. Documentation and Nutritional profile of some selected food plants ...

    African Journals Online (AJOL)

    Documentation and Nutritional profile of some selected food plants of Otwal and Ngai sun counties Oyam District, Northern Uganda. ... However, it should be noted that there is a general decline in the consumption of wild plants, despite the apparent high nutritional values. The conservation of wild food plants is not taking ...

  5. Comparing herbaceous plant communities in active and passive riparian restoration.

    Directory of Open Access Journals (Sweden)

    Elise S Gornish

    Full Text Available Understanding the efficacy of passive (reduction or cessation of environmental stress and active (typically involving planting or seeding restoration strategies is important for the design of successful revegetation of degraded riparian habitat, but studies explicitly comparing restoration outcomes are uncommon. We sampled the understory herbaceous plant community of 103 riparian sites varying in age since restoration (0 to 39 years and revegetation technique (active, passive, or none to compare the utility of different approaches on restoration success across sites. We found that landform type, percent shade, and summer flow helped explain differences in the understory functional community across all sites. In passively restored sites, grass and forb cover and richness were inversely related to site age, but in actively restored sites forb cover and richness were inversely related to site age. Native cover and richness were lower with passive restoration compared to active restoration. Invasive species cover and richness were not significantly different across sites. Although some of our results suggest that active restoration would best enhance native species in degraded riparian areas, this work also highlights some of the context-dependency that has been found to mediate restoration outcomes. For example, since the effects of passive restoration can be quite rapid, this approach might be more useful than active restoration in situations where rapid dominance of pioneer species is required to arrest major soil loss through erosion. As a result, we caution against labeling one restoration technique as better than another. Managers should identify ideal restoration outcomes in the context of historic and current site characteristics (as well as a range of acceptable alternative states and choose restoration approaches that best facilitate the achievement of revegetation goals.

  6. Passive restoration augments active restoration in deforested landscapes: the role of root suckering adjacent to planted stands of Acacia koa

    Science.gov (United States)

    Paul G. Scowcroft; Justin T. Yeh

    2013-01-01

    Active forest restoration in Hawaii’s Hakalau Forest National Wildlife Refuge has produced a network of Acacia koa tree corridors and islands in deforested grasslands. Passive restoration by root suckering has potential to expand tree cover and close gaps between planted stands. This study documents rates of encroachment into grassland, clonal...

  7. Plant experience with check valves in passive systems

    Energy Technology Data Exchange (ETDEWEB)

    Pahladsingh, R R [GKN Joint Nuclear Power Plant, Dodewaard (Netherlands)

    1996-12-01

    In the design of the advanced nuclear reactors there is a tendency to introduce more passive safety systems. The 25 year old design of the GKN nuclear reactor is different from the present BWR reactors because of some special features, such as the Natural Circulation - and the Passive Isolation Condenser system. When reviewing the design, one can conclude that the plant has 25 years of experience with check valves in passive systems and as passive components in systems. The result of this experience has been modeled in a plant-specific ``living PSA`` for the plant. A data-analysis has been performed on components which are related to the safety systems in the plant. As part of this study also the check valves have been taken in consideration. At GKN, the check valves have shown to be reliable components in the systems and no catastrophic failures have been experienced during the 25 years of operation. Especially the Isolation Condenser with its operation experience can contribute substantially to the insight of check valves in stand-by position at reactor pressure and operating by gravity under different pressure conditions. With the introduction of several passive systems in the SBWR-600 design, such as the Isolation Condensers, Gravity Driven Cooling, and Suppression Pool Cooling System, the issue of reliability of check valves in these systems is actual. Some critical aspects for study in connection with check valves are: What is the reliability of a check valve in a system at reactor pressure, to open on demand; what is the reliability of a check valve in a system at low pressure (gravity), to open on demand; what is the reliability of a check valve to open/close when the stand-by check wave is at zero differential pressure. The plant experience with check valves in a few essential safety systems is described and a brief introduction will be made about the application of check valves in the design of the new generation reactors is given. (author). 6 figs, 1 tab.

  8. From dodewaard to a modern economic passive plant-ESBWR

    International Nuclear Information System (INIS)

    Gonzalez Lopez, A.; Arnold, H.; Yadigaroglu, G.; Stoop, P.M.; Rao, A.

    1997-01-01

    For over 25 years the Dodewaard nuclear plant has produced electricity with one of the highest reliability of any power plant in the world. Almost 10 years ago when some designers looked at the features to incorporate in a modern mid-size BWR design, they chose some of the key features of Dodewaard natural circulation and passive safety. Over the years this design evolved into a 670 SBWR design that was developed by an international team and consisted of natural circulation and passive safety injection and decay heat removal. Since the passive decay heat removal was a major new technology area, an extensive test program was developed and conducted utilizing newly constructed large scale integrated system test facility at the Paul Scherrer Institute, Switzerland. The development of any modern reactor is time consuming and expensive, hence, the design and technology was done as part of an international team effort. This paper provides an overview of the international design and technology effort and discusses how the development costs were minimized through cooperation. (Author)

  9. Advanced passive technology: A global standard for nuclear plant requirements

    Energy Technology Data Exchange (ETDEWEB)

    Novak, V

    1994-12-31

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy` (DOE). The preliminary design was cornpleved in 1989. AP6OO`s Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance.

  10. Passive safety features for next generation CANDU power plants

    International Nuclear Information System (INIS)

    Natalizio, A.; Hart, R.S.; Lipsett, J.J.; Soedijono, P.; Dick, J.E.

    1989-01-01

    CANDU offers an evolutionary approach to simpler and safer reactors. The CANDU 3, an advanced CANDU, currently in the detailed design stage, offers significant improvements in the areas of safety, design simplicity, constructibility, operability, maintainability, schedule and cost. These are being accomplished by retaining all of the well known CANDU benefits, and by relying on the use of proven components and technologies. A major safety benefit of CANDU is the moderator system which is separate from the coolant. The presence of a cold moderator reduces the consequences arising from a LOCA or loss of heat sink event. In existing CANDU plants even the severe accident - LOCA with failure of the emergency core cooling system - is a design basis event. Further advances toward a simpler and more passively safe reactor will be made using the same evolutionary approach. Building on the strength of the moderator system to mitigate against severe accidents, a passive moderator cooling system, depending only on the law of gravity to perform its function, will be the next step of development. AECL is currently investigating a number of other features that could be incorporated in future evolutionary CANDU designs to enhance protection against accidents, and to limit off-site consequences to an acceptable level, for even the worst event. The additional features being investigated include passive decay heat removal from the heat transport system, a simpler emergency core cooling system and a containment pressure suppression/venting capability for beyond design basis events. Central to these passive decay heat removal schemes is the availability of a short-term heat sink to provide a decay heat removal capability of at least three days, without any station services. Preliminary results from these investigations confirm the feasibility of these schemes. (author)

  11. Plant control impact on IFR power plant passive safety response

    International Nuclear Information System (INIS)

    Vilim, R.B.

    1993-01-01

    A method is described for optimizing the closed-loop plant control strategy with respect to safety margins sustained in the unprotected upset response of a liquid metal reactor. The optimization is performed subject to the normal requirements for reactor startup, load change and compensation for reactivity changes over the cycle. The method provides a formal approach to the process of exploiting the innate self-regulating property of a metal fueled reactor to make it less dependent on operator action and less vulnerable to automatic control system fault and/or operator error

  12. Game Design Document Format For Video Games With Passive Dynamic Difficulty Adjustment

    Directory of Open Access Journals (Sweden)

    Pratama Wirya Atmaja

    2016-07-01

    satisfaction of its players is the primary mean to measure its quality. One important element of player’s satisfaction is a proper difficulty level, which is neither too easy nor too hard. The current state-of-the-art way to implement it is with Dynamic Difficulty Adjustment (DDA, which allows the difficulty level of a video game to be adjusted at run-time. Currently, the most popular type of DDA is the passive one. Meanwhile, Game Design Document (GDD is an important artefact in the development process of a video game software, and there is still no GDD format that supports the design of passive DDA mechanism. The aim of this research was to find a new GDD format that supports the mechanism. We modified a general purpose GDD format by adding new parts for designing passive DDA mechanism. We tested the usefulness of the modified format in a testing process involving developers and players. The developers developed video games using the modified GDD format and the general purpose one. Their development processes were observed and evaluated to know if there were any difficulties. The resulting video games were played by the players to find which are better in terms of passive DDA mechanism. The result of developer testing showed that the modified format is better than the general purpose one. The result of player testing showed that the video games made with the modified format are better than their counterparts, albeit by an insignificant margin. Based on the results, we declare that the modified GDD format is successful.Keywords: Video game, requirement engineering, game design document, dynamic difficulty adjustment, software development.

  13. Predicting plant attractiveness to pollinators with passive crowdsourcing.

    Science.gov (United States)

    Bahlai, Christie A; Landis, Douglas A

    2016-06-01

    observations were not associated with Internet images, but were slightly associated with BP. Our results suggest that passively crowdsourced image data can potentially be a useful screening tool to identify candidate plants for pollinator habitat restoration efforts directed at wild bee conservation. Increasing our understanding of the attractiveness of a greater diversity of plants increases the potential for more rapid and efficient research in creating pollinator-supportive landscapes.

  14. Use of an advanced document system in post-refuelling updating of nuclear power plant documentation

    International Nuclear Information System (INIS)

    Puech Suanzes, P.; Cortes Soler, M.

    1993-01-01

    This paper discusses the results of the extensive use of an advanced document system to update documentation prepared by traditional methods and affected by changes in the period between two plant refuellings. The implementation of a system for the capture, retrieval and storage of drawings using optical discs is part of a plan to modernize production and management tools and to thus achieve better control of document configuration. These processes are consequently optimized in that: 1. The deterioration of drawings is detained with the help of an identical, updated, legible, reliable support for all users. 2. The time required to update documentation is reduced. Given the large number of drawings, the implementation method should effectively combine costs and time. The document management tools ensure optical disc storage control so that from the moment a drawing resides in the system, any modification to it is made through the system utilities, thus ensuring quality and reducing schedules. The system described was used to update the electrical drawings of Almaraz Nuclear Power Plant. Changes made during the eighth refuelling of Unit I were incorporated and the time needed to issue the updated drawings was reduced by one month. (author)

  15. Upgrading safety documentation for exported nuclear power plants

    International Nuclear Information System (INIS)

    Rosen, M.

    1978-01-01

    In view of the generally small regulatory staffs of importing countries, suggestions are given for upgrading the ''export edition'' of the traditionally supplied safety documentation by use of a Supplementary Information Report, written specifically for the needs of a smaller and/or less technically qualified staff, which would highlight the differences that exist between the facility to be constructed and the supposedly similar reference plant of the supplier country; by improvement of supporting safety documentation to allow for adequate understanding of significant safety parameters; and by attention to the needs of smaller countries in the critical operating regulations (Technical Specifications for Operation). (author)

  16. Inherent/passive safety in fusion power plants

    International Nuclear Information System (INIS)

    Piet, S.J.; Crocker, J.G.

    1986-01-01

    The concept of inherent or passive safety for fusion energy is explored, defined, and partially quantified. Four levels of safety assurance are defined, which range from true inherent safety to passive safety to protection via active engineered safeguard systems. Fusion has the clear potential for achieving inherent or passive safety, which should be an objective of fusion research and design. Proper material choice might lead to both inherent/passive safety and high mass power density, improving both safety and economics. When inherent or passive safety is accomplished, fusion will be well on the way to achieving its ultimate potential and to be a truly superior energy source for the future

  17. B plant standards/requirements identification document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) set forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the B Plant. This S/RID is applicable to the appropriate life cycle phases of design, construction,operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  18. The System 80+ Standard Plant design control document. Volume 20

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains 2 technical specifications bases as part of Appendix 16 A Tech Spec Bases. They are TS B3.8 Electrical Power Technical Systems Bases and TS B3.9 Refueling Operations Bases. All 3 parts of section 17 (QA) and all 10 parts of section 18 (Human Factors) of the ADM Design and Analysis are contained in this volume. Topics covered in section 17 are: design phase QA; operations phase QA; and design phase reliability assurance. Topics covered by section 18 are: design team organization; design goals; design process; functional task analysis; control room configuration; information presentation; control and monitoring; verification and validation; and review documents

  19. Future CANDU nuclear power plant design requirements document executive summary

    International Nuclear Information System (INIS)

    Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; S. A. Usmani

    1996-03-01

    The future CANDU Requirements Document (FCRED) describes a clear and complete statement of utility requirements for the next generation of CANDU nuclear power plants including those in Korea. The requirements are based on proven technology of PHWR experience and are intended to be consistent with those specified in the current international requirement documents. Furthermore, these integrated set of design requirements, incorporate utility input to the extent currently available and assure a simple, robust and more forgiving design that enhances the performance and safety. The FCRED addresses the entire plant, including the nuclear steam supply system and the balance of the plant, up to the interface with the utility grid at the distribution side of the circuit breakers which connect the switchyard to the transmission lines. Requirements for processing of low level radioactive waste at the plant site and spent fuel storage requirements are included in the FCRED. Off-site waste disposal is beyond the scope of the FCRED. 2 tabs., 1 fig. (Author) .new

  20. The System 80+ Standard Plant design control document. Volume 19

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains five technical specification bases that are part of Appendix 16 A of the ADM Design and Analysis. They are: TS B3.3 Instrumentation Bases; TS B3.4 RCS Bases; TS B3.5 ECCS Bases; TS B3.6 Containment Systems Bases; and TS B3.7 Plant Systems Bases

  1. The System 80+ Standard Plant design control document. Volume 2

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the following information of the CDM: (2.8) Steam and power conversion; (2.9) Radioactive waste management; (2.10) Tech Support Center; (2.11) Initial test program; (2.12) Human factors; and sections 3, 4, and 5. Also covered in this volume are parts 1--6 of section 1 (General Plant Description) of the ADM Design and Analysis

  2. The System 80+ Standard Plant design control document. Volume 15

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains all five parts of section 12 (Radiation Protection) of the ADM Design and Analysis. Topics covered are: ALARA exposures; radiation sources; radiation protection; dose assessment; and health physics program. All six parts and appendices A and B for section 13 (Conduct of Operations) of the ADM Design and Analysis are also contained in this volume. Topics covered are: organizational structure; training program; emergency planning; review and audit; plant procedures; industrial security; sabotage protection (App 13A); and vital equipment list (App 13B)

  3. The System 80+ Standard Plant design control document. Volume 18

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

  4. The System 80+ Standard Plant design control document. Volume 1

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the DCD introduction and contains sections 1 and parts 1--7 of section 2 of the CDM. Parts 1--7 included the following: (2.1) Design of SSC; (2.2) Reactor; (2.3) RCS and connected systems; (2.4) Engineered Safety Features; (2.5) Instrumentation and Control; (2.6) Electric Power; and (2.7) Auxiliary Systems

  5. The System 80+ Standard Plant design control document. Volume 10

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

  6. The System 80+ Standard Plant design control document. Volume 11

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers parts 6 and 7 and appendix 7A for section 7 (Instrumentation and Control) of the ADM Design and Analysis. The topics covered by these are: other systems required for safety; control systems not required by safety; and CMF evaluation of limiting faults. Parts 1--3 of section 8 (Electric Power) of the ADM are also included in this volume. Topics covered by these parts are: introduction; offsite power system; and onsite power system

  7. The System 80+ Standard Plant design control document. Volume 23

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains part 16 References and Appendix 19 A Design Alternatives for section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Also covered is section 20 Unresolved Safety Issues of the ADM Design and Analysis. Finally sections 1--6 of the ADM Emergency Operations Guidelines are contained in this volume. Information covered in these sections include: standard post-trip actions; diagnostic actions; reactor trip recovery guideline; LOCA recovery; SG tube rupture recovery

  8. The System 80+ Standard Plant design control document. Volume 21

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 1--10 of section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Topics covered are: methodology; initiating event evaluation; accident sequence determination; data analysis; systems analysis; external events analysis; shutdown risk assessment; accident sequence quantification; and sensitivity analysis. Also included in this volume are Appendix 19.8A Shutdown Risk Assessment and Appendix A to Appendix 19.8A Request for Information

  9. The System 80+ Standard Plant design control document. Volume 17

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 2-7 and appendix 15A for section 15 (Accident Analysis) of the ADM Design and Analysis. Topics covered in these parts are: decrease in heat removal; decrease in RCS flow rate; power distribution anomalies; increase in RCS inventory; decrease in RCS inventory; release of radioactive materials. The appendix covers radiological release models. Also contained here are five technical specifications for section 16 (Technical Specifications) of the ADM Design and Analysis. They are: TS 1.0 Use and Applications; TS 2.0 Safety Limits; TS 3.0 LCO Availability; TS 3.1 Reactivity Control; and TS 3.2 Power Distribution

  10. The System 80+ Standard Plant design control document. Volume 24

    International Nuclear Information System (INIS)

    1997-01-01

    This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains sections 7--11 of the ADM Emergency Operations Guidelines. Topics covered are: excess steam demand recovery; loss of all feedwater; loss of offsite power; station blackout recovery; and functional recovery guideline. Appendix A Severe Accident Management Guidelines and Appendix B Lower Mode Operational Guidelines are also included

  11. Passivity Enhancement in RES Based Power Plant with Paralleled Grid-Connected Inverters

    DEFF Research Database (Denmark)

    Bai, Haofeng; Wang, Xiongfei; Blaabjerg, Frede

    2016-01-01

    Harmonic instability is threatening the operation of power plants with multiple grid connected converters in parallel. To analyze and improve the stability of the grid connected converters, the passivity of the output admittance converters is first analyzed in this paper. It is shown that the non-passivity...

  12. PWR passive plant heat removal assessment: Joint EPRI-CRIEPI advanced LWR studies

    International Nuclear Information System (INIS)

    1991-03-01

    An independent assessment of the capabilities of the PWR passive plant heat removal systems was performed, covering the Passive Residual Heat Removal (PRHR) System, the Passive Safety Injection System (PSIS) and the Passive Containment Cooling System (PCCS) used in a 600 MWe passive plant (e.g., AP600). Additional effort included a review of the test programs which support the design and analysis of the systems, an assessment of the licensability of the plant with regard to heat removal adequacy, and an evaluation of the use of the passive systems with a larger plant. The major conclusions are as follows. The PRHR can remove core decay heat, prevents the pressurizer from filling with water for a loss-of-feedwater transient, and provides safety-grade means for maintaining the reactor coolant system in a safe shutdown condition for the case where the non-safety residual heat removal system becomes unavailable. The PSIS is effective in maintaining the core covered with water for loss-of-coolant accident pipe breaks to eight inches. The PCCS has sufficient heat removal capability to maintain the containment pressure within acceptable limits. The tests performed and planned are adequate to confirm the feasibility of the passive heat removal system designs and to provide a database for verification of the analytical techniques used for the plant evaluations. Each heat removal system can perform in accordance with Regulatory requirements, with the exception that the PRHR system is unable to achieve the required cold shutdown temperature of 200 F within the required 36-hour period. The passive heat removal systems to be used for the 600 MWe plant could be scaled up to a 900 MWe passive plant in a straightforward manner and only minimal, additional confirmatory testing would be required. Sections have been indexed separately for inclusion on the data base

  13. European passive plant program A design for the 21st century

    International Nuclear Information System (INIS)

    Adomaitis, D.; Oyarzabal, M.

    1998-01-01

    In 1994, a group of European utilities initiated, together with Westinghouse and its industrial partner GENESI (an Italian consortium including ANSALDO and FIAT), a program designated EPP (European Passive Plant) to evaluate Westinghouse passive nuclear plant technology for application in Europe. The following major tasks were accomplished: (1) the impacts of the European utility requirements (EUR) on the Westinghouse nuclear island design were evaluated; and (2) a 1000 MWe passive plant reference design (EP1000) was established which conforms to the EUR and is expected to be licensable in Europe. With respect to safety systems and containment, the reference plant design closely follows that of the Westinghouse simplified pressurized water reactor (SPWR) design, while the AP600 plant design has been taken as the basis for the EP1000 reference design in the auxiliary system design areas. However, the EP1000 design also includes features required to meet the EUR, as well as key European licensing requirements. (orig.)

  14. Methods for testing the logical structure of plant procedure documents

    International Nuclear Information System (INIS)

    Horne, C.P.; Colley, R.; Fahley, J.M.

    1990-01-01

    This paper describes an ongoing EPRI project to investigate computer based methods to improve the development, maintenance, and verification of plant operating procedures. This project began as an evaluation of the applicability of structured software analysis methods to operating procedures. It was found that these methods offer benefits, if procedures are transformed to a structured representation to make them amenable to computer analysis. The next task was to investigate methods to transform procedures into a structured representation. The use of natural language techniques to read and compile the procedure documents appears to be viable for this purpose and supports conformity to guidelines. The final task was to consider possibilities of automated verification methods for procedures. Methods to help verify procedures were defined and information requirements specified. These methods take the structured representation of procedures as input. The software system being constructed in this project is called PASS, standing for Procedures Analysis Software System

  15. Design and development of innovative passive valves for Nuclear Power Plant applications

    Energy Technology Data Exchange (ETDEWEB)

    Sapra, M.K., E-mail: sapramk@barc.gov.in; Kundu, S.; Pal, A.K.; Vijayan, P.K.; Vaze, K.K.; Sinha, R.K.

    2015-05-15

    Highlights: • Passive valves are self-acting valves requiring no external energy to function. • These valves have been developed for Advanced Heavy Water Reactor (AHWR) of India. • Passive valves are core components of passive safety systems of the reactor. • Accumulator Isolation Passive Valve (AIPV) has been developed and tested for ECSS. • AIPV provided passive isolation and flow regulation in ECCS of Integral Test Loop. - Abstract: The recent Fukushima accident has resulted in an increased need for passive safety systems in upcoming advanced reactors. In order to enhance the global contribution and acceptability of nuclear energy, proven evidence is required to show that it is not only green but also safe, in case of extreme natural events. To achieve and establish this fact, we need to design, demonstrate and incorporate reliable ‘passive safety systems’ in our advanced reactor designs. In Nuclear Power Plants (NPPs), the use of passive safety systems such as accumulators, condensing and evaporative heat exchangers and gravity driven cooling systems provide enhanced safety and reliability. In addition, they eliminate the huge costs associated with the installation, maintenance and operation of active safety systems that require multiple pumps with independent and redundant electric power supplies. As a result, passive safety systems are preferred for numerous advanced reactor concepts. In current NPPs, passive safety systems which are not participating in day to day operation, are kept isolated, and require a signal and external energy source to open the valve. It is proposed to replace these valves by passive components and devices such as self-acting valves, rupture disks, etc. Some of these innovative passive valves, which do not require external power, have been recently designed, developed and tested at rated conditions. These valves are proposed to be used for various passive safety systems of an upcoming Nuclear Power Plant being designed

  16. Conceptual benefits of passive nuclear power plants and their effect on component design

    International Nuclear Information System (INIS)

    DeVine, J.C. Jr.

    1996-01-01

    Today, nearly ten years after the advanced light water reactor (ALWR) Program was conceived by US utility leaders, and a decade and a half since a new nuclear power plant was ordered in the US, the ALWR passive plant is coming into its own. This design concept, a midsized simplified light water reactor, features extremely reliable passive systems for accident prevention and mitigation and combines proven experience with state-of-the-art engineering and human factors. It is now emerging as the front runner to become the next generation reactor in the US and perhaps around the world. Although simple and straightforward in concept, the passive plant is in many respects a significant departure from previous trends in reactor engineering. Successful implementation of this concept presents numerous challenges to the designers of passive plant systems and components. This paper provides a brief history of the ALWR program, it outlines the ALWR passive plant design objectives and principles, and it summarizes with examples their implications on component design. (orig.)

  17. The role of passive and inherent safety properties in Siemens/KWU nuclear power plants

    International Nuclear Information System (INIS)

    Gremm, O.

    1990-01-01

    In Siemens/KWU Nuclear Power Plants the applied safety concept consist of a well balanced combination of active, passive use well is inherent safety measures. In principle it is not possible to realise a safety concept exclusively with inherent and/or passive safety properties. The respective measures and arguments will be explained in detail in the presentation. In addition the Siemens/KWU safety concept with examples of the role of inherent and passive safety measures will be illustrated. (author). 9 refs, 9 figs

  18. Soil Seed Bank and Plant Community Development in Passive Restoration of Degraded Sandy Grasslands

    Directory of Open Access Journals (Sweden)

    Renhui Miao

    2016-06-01

    Full Text Available To evaluate the efficacy of passive restoration on soil seed bank and vegetation recovery, we measured the species composition and density of the soil seed bank, as well as the species composition, density, coverage, and height of the extant vegetation in sites passively restored for 0, 4, 7, and 12 years (S0, S4, S7, and S12 in a degraded grassland in desert land. Compared with S0, three more species in the soil seed bank at depths of 0–30 cm and one more plant species in the community was detected in S12. Seed density within the topsoil (0–5 cm was five times higher in S12 than that in S0. Plant densities in S7 and S12 were triple and quadruple than that in S0. Plant coverage was increased by 1.5 times (S4, double (S7, and triple (S12 compared with S0. Sørensen’s index of similarity in species composition between the soil seed bank and the plant community were high (0.43–0.63, but it was lower in short-term restoration sites (S4 and S7 than that in no and long-term restoration sites (S0 and S12. The soil seed bank recovered more slowly than the plant community under passive restoration. Passive restoration is a useful method to recover the soil seed bank and vegetation in degraded grasslands.

  19. Soil Moisture Active Passive (SMAP) Mission Level 4 Surface and Root Zone Soil Moisture (L4_SM) Product Specification Document

    Science.gov (United States)

    Reichle, Rolf H.; Ardizzone, Joseph V.; Kim, Gi-Kong; Lucchesi, Robert A.; Smith, Edmond B.; Weiss, Barry H.

    2015-01-01

    This is the Product Specification Document (PSD) for Level 4 Surface and Root Zone Soil Moisture (L4_SM) data for the Science Data System (SDS) of the Soil Moisture Active Passive (SMAP) project. The L4_SM data product provides estimates of land surface conditions based on the assimilation of SMAP observations into a customized version of the NASA Goddard Earth Observing System, Version 5 (GEOS-5) land data assimilation system (LDAS). This document applies to any standard L4_SM data product generated by the SMAP Project. The Soil Moisture Active Passive (SMAP) mission will enhance the accuracy and the resolution of space-based measurements of terrestrial soil moisture and freeze-thaw state. SMAP data products will have a noteworthy impact on multiple relevant and current Earth Science endeavors. These include: Understanding of the processes that link the terrestrial water, the energy and the carbon cycles, Estimations of global water and energy fluxes over the land surfaces, Quantification of the net carbon flux in boreal landscapes Forecast skill of both weather and climate, Predictions and monitoring of natural disasters including floods, landslides and droughts, and Predictions of agricultural productivity. To provide these data, the SMAP mission will deploy a satellite observatory in a near polar, sun synchronous orbit. The observatory will house an L-band radiometer that operates at 1.40 GHz and an L-band radar that operates at 1.26 GHz. The instruments will share a rotating reflector antenna with a 6 meter aperture that scans over a 1000 km swath.

  20. Development of passive condensers for accident localization systems at nuclear power plants in the former USSR

    International Nuclear Information System (INIS)

    Kuznecov, M.V.

    1992-01-01

    The development is summarized of passive condensers for accident localization systems at nuclear power plants (with RBMK and WWER reactors) in the former USSR. Basic properties and criteria defining their availability are described, as are experimental tests and technical solution optimization results. (author) 2 fig

  1. Pressure suppression pool mixing in passive advanced BWR plants

    International Nuclear Information System (INIS)

    Gamble, Robert E.; Nguyen, Thuy T.; Shiralkar, Bharat S.; Peterson, Per F.; Greif, Ralph; Tabata, H.

    2001-01-01

    In the SBWR passive boiling water reactor, the long-term post-accident containment pressure is determined by the combination of noncondensible gas pressure and steam pressure in the wetwell gas space. The suppression pool (SP) surface temperature, which determines the vapor partial pressure, is very important to overall containment performance. Therefore, the thermal stratification of the SP due to blowdown is of primary importance. This work looks at the various phases and phenomena present during the blowdown event and identifies those that are important to thermal stratification, and the scaling necessary to model them in reduced size tests. This is important in determining which of the large body of blowdown to SP data is adequate for application to the stratification problem. The mixing by jets from the main vents is identified as the key phenomena influencing the thermal response of the suppression pool and analytical models are developed to predict the jet influence on thermal stratification. The analytical models are implemented into a system simulation code, TRACG, and used to model thermal stratification behavior in a scaled test facility. The results show good general agreement with the test data

  2. IAEA activities in preparation of reglamentary documents on nuclear power plant safety

    International Nuclear Information System (INIS)

    Konstantinov, L.V.

    1976-01-01

    The activities of the IAEA in the field of working out practical rules and recommendations ensuring the nuclear power plant safety are discussed. The practical rules will establish the aims and the minimum of requirements, that must be carried out to ensure the necessary safety of systems, components and equipment of the nuclear power plant throughout the whole period of its exploitation. Described is the procedure of the document preparation, consisting of the collection of documents, edited in different countries, the integration of documents by the IAEA Secretariat, the consideratiom of documents by the Group of senior advisers, the preparation of the draft document, the additional wort at the document in accordaqce with the remarks of the IAEA member-countries, the edition and dissemination of documents. The necessity for the active participation of the CMEA member-countries in the development and discussion of documents concerning the nuclear power plant safety is stated [ru

  3. Passive safety systems and natural circulation in water cooled nuclear power plants

    International Nuclear Information System (INIS)

    2009-11-01

    Nuclear power produces 15% of the world's electricity. Many countries are planning to either introduce nuclear energy or expand their nuclear generating capacity. Design organizations are incorporating both proven means and new approaches for reducing the capital costs of their advanced designs. In the future most new nuclear plants will be of evolutionary design, often pursuing economies of scale. In the longer term, innovative designs could help to promote a new era of nuclear power. Since the mid-1980s it has been recognized that the application of passive safety systems (i.e. those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially improve economics of new nuclear power plant designs. The IAEA Conference on The Safety of Nuclear Power: Strategy for the Future, which was convened in 1991, noted that for new plants 'the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate'. Some new designs also utilize natural circulation as a means to remove core power during normal operation. The use of passive systems can eliminate the costs associated with the installation, maintenance, and operation of active systems that require multiple pumps with independent and redundant electric power supplies. However, considering the weak driving forces of passive systems based on natural circulation, careful design and analysis methods must be employed to ensure that the systems perform their intended functions. To support the development of advanced water cooled reactor designs with passive systems, investigations of natural circulation are conducted in several IAEA Member States with advanced reactor development programmes. To foster international collaboration on the enabling technology of passive systems that utilize natural circulation, the IAEA

  4. 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)

  5. A documentation system for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Glock, H.J.; Mueller, F.; Schwarz, H.

    1984-01-01

    A NPP's life cycle from the beginning of planning to its complete dismantling will last about 80 to 100 years. For this long time a documentation system has to be kept in stable working condition which provides access to an information base including 1.5 to 2 million pages and 200 to 250 thousand engineering drawings. As an appropriate base the documentation system IFODOK is proposed which is supported by computer and data base management software. In cooperation with NPP operating people a ground level thesaurus has been developed which is structured according to the rules of INFODOK's documentation language. The form of the information units which INFODOK maintains has been adapted to the requirements of KKW documentation and the related data record is described. Within a layer model the requirements to the software resulting from the demanded performance of the system are explained. The model also describes the interfaces between the substantial system components (application programs, data base management system, operating system) as well as within the different layers. The requirements which the system's hardware has to meet are described functionally and quantitatively in details. The application program' components have been extended by some functions. An automatic microfilm storage and retrieval system which may be integrated to the overall system and coupled to the computer by an interface is specified. The organization of the computer assisted documentation process including the required backup and refreshment procedures is described in its basic characteristics. This description of an DP system's prototype presents the base for the application of INFODOK to the documentation of NPP's information bases during their whole life time

  6. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    International Nuclear Information System (INIS)

    Demetri, K. J.; Leipner, C. I.; Marshall, M. L.

    2015-09-01

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  7. The Westinghouse AP1000 plant design: a generation III+ reactor with unique proven passive safety technology

    Energy Technology Data Exchange (ETDEWEB)

    Demetri, K. J.; Leipner, C. I.; Marshall, M. L., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Company, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2015-09-15

    The AP1000 plant is an 1100-M We pressurized water reactor with passive safety features and extensive plant simplifications and standardization that simplify construction, operation, maintenance, safety, and cost. The AP1000 plant is based on proven pressurized water reactor (PWR) technology, with an emphasis on safety features that rely solely on natural forces. These passive safety features are combined with simple, active, defense-in-depth systems used during normal plant operations which also provide the first level of defense against more probable events. This paper focuses on specific safety and licensing topics: the AP1000 plant robustness to be prepared for extreme events that may lead to catastrophic loss of infrastructure, such as the Fukushima Dai-ichi event, and the AP1000 plant compliance with the safety objectives for new plants. The first deployment of the AP1000 plant formally began in July 2007 when Westinghouse Electric Company and its consortium partner, the Shaw Group, signed contracts for four AP1000 units on coastal sites of Sanmen and Haiyang, China. Both sites have the planned ability to accommodate at least six AP1000 units; construction is largely concurrent for all four units. Additionally, the United States (U.S.) Nuclear Regulatory Commission (NRC) issued combined licenses (COLs) to allow Southern Nuclear Operating Company (SNC) and South Carolina Electric and Gas Company (SCE and G) to construct and operate AP1000 plants. Within this paper, the various factors that contribute to an unparalleled level of design, construction, delivery, and licensing certainty for any new AP1000 plant projects are described. These include: 1) How the AP1000 plant design development and reviews undertaken in the United States, China and Europe increase licensing certainty. 2) How the AP1000 passive plant robustness against extreme events that result in large loss of infrastructure further contributes to the licensing certainty in a post

  8. Operating experiences with passive systems and components in German nuclear power plants

    International Nuclear Information System (INIS)

    Maqua, M.

    1996-01-01

    Operating experience with passive systems and components is limited to the equipment installed in existing NPPs. In German power plants, this experience is available for equipment of the IAEA categories A, C and D. The presentation is focused on typical examples out of these three categories. An overview is given on the number of reported events and typical failure modes. Selected failures are discussed in detail. 1 ref., 6 figs, 7 tabs

  9. European passive plant program preliminary safety analyses to support system design

    International Nuclear Information System (INIS)

    Saiu, Gianfranco; Barucca, Luciana; King, K.J.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In the Phase 1 of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) was completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. Incorporation of the EUR has been a key design requirement for the EP1000 form the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. The present paper describes the EP1000 approach to safety analysis and, in particular, to the Design Extension Conditions that, according to the EUR, represent the preferred method for giving consideration to the Complex Sequences and Severe Accidents at the design stage without including them in the design bases conditions. Preliminary results of some DEC analyses and an overview of the probabilistic safety assessment (PSA) are also presented. (author)

  10. Operating experiences with passive systems and components in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Maqua, M [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Koeln (Germany)

    1996-12-01

    Operating experience with passive systems and components is limited to the equipment installed in existing NPPs. In German power plants, this experience is available for equipment of the IAEA categories A, C and D. The presentation is focused on typical examples out of these three categories. An overview is given on the number of reported events and typical failure modes. Selected failures are discussed in detail. 1 ref., 6 figs, 7 tabs.

  11. Interim results of the study of control room crew staffing for advanced passive reactor plants

    International Nuclear Information System (INIS)

    Hallbert, B.P.; Sebok, A.; Haugset, K.

    1996-01-01

    Differences in the ways in which vendors expect the operations staff to interact with advanced passive plants by vendors have led to a need for reconsideration of the minimum shift staffing requirements of licensed Reactor Operators and Senior Reactor Operators contained in current federal regulations (i.e., 10 CFR 50.54(m)). A research project is being carried out to evaluate the impact(s) of advanced passive plant design and staffing of control room crews on operator and team performance. The purpose of the project is to contribute to the understanding of potential safety issues and provide data to support the development of design review guidance. Two factors are being evaluated across a range of plant operating conditions: control room crew staffing; and characteristics of the operating facility itself, whether it employs conventional or advanced, passive features. This paper presents the results of the first phase of the study conducted at the Loviisa nuclear power station earlier this year. Loviisa served as the conventional plant in this study. Data collection from four crews were collected from a series of design basis scenarios, each crew serving in either a normal or minimum staffing configuration. Results of data analyses show that crews participating in the minimum shift staffing configuration experienced significantly higher workload, had lower situation awareness, demonstrated significantly less effective team performance, and performed more poorly as a crew than the crews participating in the normal shift staffing configuration. The baseline data on crew configurations from the conventional plant setting will be compared with similar data to be collected from the advanced plant setting, and a report prepared providing the results of the entire study

  12. Passive safety systems reliability and integration of these systems in nuclear power plant PSA

    International Nuclear Information System (INIS)

    La Lumia, V.; Mercier, S.; Marques, M.; Pignatel, J.F.

    2004-01-01

    Innovative nuclear reactor concepts could lead to use passive safety features in combination with active safety systems. A passive system does not need active component, external energy, signal or human interaction to operate. These are attractive advantages for safety nuclear plant improvements and economic competitiveness. But specific reliability problems, linked to physical phenomena, can conduct to stop the physical process. In this context, the European Commission (EC) starts the RMPS (Reliability Methods for Passive Safety functions) program. In this RMPS program, a quantitative reliability evaluation of the RP2 system (Residual Passive heat Removal system on the Primary circuit) has been realised, and the results introduced in a simplified PSA (Probabilistic Safety Assessment). The scope is to get out experience of definition of characteristic parameters for reliability evaluation and PSA including passive systems. The simplified PSA, using event tree method, is carried out for the total loss of power supplies initiating event leading to a severe core damage. Are taken into account: failures of components but also failures of the physical process involved (e.g. natural convection) by a specific method. The physical process failure probabilities are assessed through uncertainty analyses based on supposed probability density functions for the characteristic parameters of the RP2 system. The probabilities are calculated by MONTE CARLO simulation coupled to the CATHARE thermalhydraulic code. The yearly frequency of the severe core damage is evaluated for each accident sequence. This analysis has identified the influence of the passive system RP2 and propose a re-dimensioning of the RP2 system in order to satisfy the safety probabilistic objectives for reactor core severe damage. (authors)

  13. Activities of passive cooling applications and simulation of innovative nuclear power plant design

    International Nuclear Information System (INIS)

    Aglar, F.; Tanrykut, A.

    2002-01-01

    This paper gives a general insight on activities of the Turkish Atomic Energy Authority (TAEA) concerning passive cooling applications and simulation of innovative nuclear power plant design. The condensation mode of heat transfer plays an important role for the passive heat removal application in advanced water-cooled reactor systems. But it is well understood that the presence of noncondesable (NC) gases can greatly inhibit the condensation process due to the build up of NC gas concentration at the liquid/gas interface. The isolation condenser of passive containment cooling system of the simplified boiling water reactors is a typical application area of in-tube condensation in the presence of NC. The test matrix of the experimental investigation undertaken at the METU-CTF test facility (Middle East Technical University, Ankara) covers the range of parameters; Pn (system pressure) : 2-6 bar, Rev (vapor Reynolds number): 45,000-94,000, and Xi (air mass fraction): 0-52%. This experimental study is supplemented by a theoretical investigation concerning the effect of mixture flow rate on film turbulence and air mass diffusion concepts. Recently, TAEA participated to an international standard problem (OECD ISP-42) which covers a set of simulation of PANDA test facility (Paul Scherrer Institut-Switzerland) for six different phases including different natural circulation modes. The concept of condensation in the presence of air plays an important role for performance of heat exchangers, designed for passive containment cooling, which in turn affect the natural circulation behaviour in PANDA systems. (author)

  14. Integration of georeferencing, habitat, sampling, and genetic data for documentation of wild plant genetic resources

    Science.gov (United States)

    Plant genetic resource collections provide novel materials to the breeding and research communities. Availability of detailed documentation of passport, phenotypic, and genetic data increases the value of the genebank accessions. Inclusion of georeferenced sources, habitats, and sampling data in co...

  15. Seismic analysis of the Nuclear Fuel Service Reprocessing Plant at West Valley, New York: documentation

    International Nuclear Information System (INIS)

    Murray, R.C.; Nelson, T.A.; Davito, A.M.

    1977-01-01

    This material was generated as part of a seismic case review of the NFS Reprocessing Plant. This study is documented in UCRL-52266. The material is divided into two parts: mathematical model information, and ultimate load calculations and comparisons

  16. 50 CFR 23.19 - What CITES documents are required to export Appendix-I plants?

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 6 2010-10-01 2010-10-01 false What CITES documents are required to... ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Prohibitions, Exemptions, and Requirements § 23.19 What CITES documents are required to export Appendix-I plants? Answer the questions in the following decision...

  17. Design and analysis of new prestressed concrete containment and its passive cooling system for nuclear power plants

    International Nuclear Information System (INIS)

    Tan Xiaoshi; Li Xiaowei; Li Xiaotian; He Shuyan

    2014-01-01

    A new nuclear power plant prestressed concrete containment and its passive cooling system design were proposed for CAP1700 nuclear power plant as an example. The thermal-hydraulic calculation method for the new passive containment cooling system of CAP1700 was introduced and the operating parameters in accident condition were obtained. The result shows that the design of passive containment cooling system for CAP1700 is feasible and can meet the cooling demand in accident condition. Reservoir capacity of tank has a big margin and can be further optimized by calculation. (authors)

  18. Strepsicrates smithiana Walsingham (Lepidoptera, Tortricidae: first record from Chile and a newly documented host plant

    Directory of Open Access Journals (Sweden)

    Héctor A. Vargas

    2012-09-01

    Full Text Available Strepsicrates smithiana Walsingham (Lepidoptera, Tortricidae: first record from Chile and a newly documented host plant. Strepsicrates smithiana Walsingham, 1892 (Lepidoptera, Tortricidae is recorded for the first time from Chile. Male and female adults were reared from leaf-tying larvae collected on Myrica pavonis (Myricaceae, which is a new host plant record for S. smithiana.

  19. Ways to integrate document management systems with industrial plant configuration management systems

    International Nuclear Information System (INIS)

    Munoz, M.

    1995-01-01

    Based on experience gained from tasks carried out for Almaraz Nuclear Power Plant, this paper describes computer platforms used both at the power plant and in the main offices of the engineering company. Subsequently, a description is given of the procedure followed for the continuous up-dating of plant documentation, in order to maintain consistency with other information stored in data bases in the Operation Management System, Maintenance System, Modification Management System, etc. The work method used for the unitary updating of all information (document images and attributes corresponding to the different data bases), following refuelling procedures is also described. Lastly, the paper describes the functions and the user interface of the system used in the power plant for document management. (Author)

  20. High-inertia hermetically sealed main coolant pump for next generation passive nuclear power plants

    International Nuclear Information System (INIS)

    Kujawski, Joseph M.; Nair, Bala R.; Vijuk, Ronald P.

    2003-01-01

    The main coolant pump for the Westinghouse AP1000 advanced passive nuclear power plant represents a significant scale-up in power, flow capacity, and physical size from its predecessor designed for the smaller AP600 power plant. More importantly, the AP1000 pump incorporates several innovative features that contribute to improved efficiency, operational reliability, and plant safety. The features include an internals design which provides the highest hydraulic efficiency achieved in commercial nuclear power plant applications. Another feature is the use of a distributed inertial mass system in the rotating assembly to develop the high rotational inertia to meet the extended system flow coastdown requirement for core heat removal in the event of loss of power to the pumps. This advanced canned motor pump also incorporates the latest development in higher operating voltage, providing plant designers with the ability to eliminate plant transformers and operate directly on the site electrical bus in many cases. The salient features of the pump design and performance data are presented in this paper. (author)

  1. Applied reliability assessment for the passive safety systems of nuclear power plants (NPPs) using system dynamics (SD)

    International Nuclear Information System (INIS)

    Kim, Yun Il; Woo, Tae Ho

    2018-01-01

    The passive system by the free-fall is investigated in the accident of nuclear power plants (NPPs). The complex algorithm of the system dynamics (SD) modeling is done in the passive cooling system. The nuclear passive system by free-fall is successfully modeled for the loss of coolant accident (LOCA). Conventional passive system of gravity or natural circulation is working only when the piping systems is in the good condition. The external coolant supply system is introduced in the case of the piping system failure. The water is poured into the reactor through the guiding piping or tube. If the explosion happens, the coolants could be showering into the reactor core and its building. New kind of passive system is expected successfully in the on-site black out where the drone could be operated by battery or engine.

  2. Computerized documentation systems for nuclear power plants: A vision for the future

    International Nuclear Information System (INIS)

    Jakobsson, S.; Tommila, T.

    1998-01-01

    Systematic management of different plant systems throughout their whole lifetime is a crucial ingredient in safe and economic operation of a nuclear power plant. Documentation is one of the key issues in this activity, both on a strategic and on an operational level. Present nuclear power plants were designed and built during the seventies and early eighties. At that time it was natural to base the plant documentation on paper. However, managing the large amount of information is a difficult task. Even a simple plant modification may introduce the need for a change in dozens of documents, and it is often very difficult to be sure that all changes have been done correctly. The rapid development of information technology has increased the number of modifications needed in plant computers and instrumentation and control systems. On the other hand, it has provided some means to tackle the information management problem. Computers are now used to produce also the simplest piece of paper, and records are often kept with an electronically readable master copy. Efficient utilisation of intelligent databases can provide valuable support to ensure a timely and correct modification of plant documentation. In all operating modes there would also be a benefit of an easy access to plant documentation, e.g. in the control room. This would be still enhanced if it can be presented in a way which is adapted to users' needs. The paper goes through some recent development trends in information technology with the intent to point to some of the most promising ideas. (author)

  3. The european passive plant (EPP) design: compliance with the european utilities requirements (EUR)

    International Nuclear Information System (INIS)

    Noviello, L.; Oyarzabal, M.

    1996-01-01

    Back 1986, most of the European firms have participated to the American program called the Advanced Light Water Reactors (ALWR) including the development of the Utilities Requirements as well as four projects as for instance AP600. Later, in the year 1990, seven European firms have begun to develop the European Utilities Requirements. This development is justified by the fact that the lessons learned by the nuclear power plants designs programs of the years 1980 can be incorporated and the European specific conditions can be taken into consideration. Thus, in 1994, eight European firms - Westinghouse and their industrial partners - have decided to launch a multiphase program in order to check the AP600 compliance with the European Utilities Requirements (EUR) and to develop the required alterations. Today, the phase I of the EPP (European Passive Plant) program has been completed. In this phase, the main important objectives have been reached. (O.M.)

  4. Passive Flora? Reconsidering Nature’s Agency through Human-Plant Studies (HPS

    Directory of Open Access Journals (Sweden)

    John Charles Ryan

    2012-08-01

    Full Text Available Plants have been—and, for reasons of human sustenance and creative inspiration, will continue to be—centrally important to societies globally. Yet, plants—including herbs, shrubs, and trees—are commonly characterized in Western thought as passive, sessile, and silent automatons lacking a brain, as accessories or backdrops to human affairs. Paradoxically, the qualities considered absent in plants are those employed by biologists to argue for intelligence in animals. Yet an emerging body of research in the sciences and humanities challenges animal-centred biases in determining consciousness, intelligence, volition, and complex communication capacities amongst living beings. In light of recent theoretical developments in our understandings of plants, this article proposes an interdisciplinary framework for researching flora: human-plant studies (HPS. Building upon the conceptual formations of the humanities, social sciences, and plant sciences as advanced by Val Plumwood, Deborah Bird Rose, Libby Robin, and most importantly Matthew Hall and Anthony Trewavas, as well as precedents in the emerging areas of human-animal studies (HAS, I will sketch the conceptual basis for the further consideration and exploration of this interdisciplinary framework.

  5. Condition Based Prognostics of Passive Components - A New Era for Nuclear Power Plant Life Management

    International Nuclear Information System (INIS)

    Bakhtiari, S.; Mohanty, S.; Prokofiev, I.; Tregoning, R.

    2012-01-01

    As part of a research project sponsored by the U.S. NRC, Argonne National Laboratory (ANL) conducted scoping studies to identify viable and promising sensors and techniques for in-situ inspection and real-time monitoring of degradation in nuclear power plant (NPP) systems, structures, and components (SSC). Significant advances have been made over the past two decades toward development of online monitoring (OLM) techniques for detection, diagnostics, and prognostics of degradation in active nuclear power plant (NPP) components (e.g., pumps, valves). However, early detection of damage and degradation in safety-critical passive components, (e.g. piping, tubing pressure vessel), is challenging, and will likely remain so for the foreseeable future. Ensuring the structural integrity of the reactor pressure vessel (RPV) and piping systems in particular is a prerequisite to long term safe operation of NPPs. The current practice is to implement inservice inspection (ISI) and preventive maintenance programs. While these programs have generally been successful, they are limited in that information is only obtained during plant outages. Additionally, these inspections, often the critical path in the outage schedule, are costly, time consuming, and involve potentially high dose to nondestructive examination/evaluation (NDE) personnel. A viable plant-wide on-line structural health monitoring program for continuous and automatic monitoring of critical SSCs could be a more effective approach for guarding against unexpected failures. Specifically, OLM information about the current condition of the SSCs could be input to an online prognostics (OLP) system to forecast their remaining useful life in real time. This paper provides an overview of scoping studies performed at ANL on assessing the viability of OLM and OLP systems for real time and automated monitoring and remaining of condition and the remaining useful life of passive components in NPPs. (author)

  6. Hanford Waste Vitrification Plant technical background document for toxics best available control technology demonstration

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-10-01

    This document provides information on toxic air pollutant emissions to support the Notice of Construction for the proposed Hanford Waste Vitrification Plant (HWVP) to be built at the the Department of Energy Hanford Site near Richland, Washington. Because approval must be received prior to initiating construction of the facility, state and federal Clean Air Act Notices of construction are being prepared along with necessary support documentation.

  7. Hanford Waste Vitrification Plant technical background document for toxics best available control technology demonstration

    International Nuclear Information System (INIS)

    1992-10-01

    This document provides information on toxic air pollutant emissions to support the Notice of Construction for the proposed Hanford Waste Vitrification Plant (HWVP) to be built at the the Department of Energy Hanford Site near Richland, Washington. Because approval must be received prior to initiating construction of the facility, state and federal Clean Air Act Notices of construction are being prepared along with necessary support documentation

  8. Role of Passive Safety Features in Prevention And Mitigation of Severe Plant Conditions in Indian Advanced Heavy Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jain, Vikas; Nayak, A.; Dhiman, M.; Kulkarni, P. P.; Vijayan, P. K.; Vaze, K. K. [Bhabha Atomic Research Centre, Mumbai (India)

    2013-10-15

    Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor technologies. Indian innovative reactor 'AHWR' is a pressure-tube type natural circulation based boiling water reactor that is designed to meet such requirements, which essentially reflect the needs of next generation reactors. The reactor employs various passive features to prevent and mitigate accidental conditions, like a slightly negative void reactivity coefficient, passive poison injection to scram the reactor in event of failure of the wired shutdown systems, a large elevated pool of water as a heat sink inside the containment, passive decay heat removal based on natural circulation and passive valves, passive ECC injection, etc. It is designed to meet the fundamental safety requirements of safe shutdown, safe decay heat removal and confinement of activity with no impact in public domain, and hence, no need for emergency planning under all conceivable scenarios. This paper examines the role of the various passive safety systems in prevention and mitigation of severe plant conditions that may arise in event of multiple failures. For the purpose of demonstration of the effectiveness of its passive features, postulated scenarios on the lines of three major severe accidents in the history of nuclear power reactors are considered, namely; the Three Mile Island (TMI), Chernobyl and Fukushima accidents. Severe plant conditions along the lines of these scenarios are postulated to the extent conceivable in the reactor under consideration and analyzed using best estimate system thermal-hydraulics code RELAP5/Mod3.2. It is found that the various passive systems incorporated enable the reactor to tolerate the postulated accident conditions without causing severe plant conditions and core degradation.

  9. ROLE OF PASSIVE SAFETY FEATURES IN PREVENTION AND MITIGATION OF SEVERE PLANT CONDITIONS IN INDIAN ADVANCED HEAVY WATER REACTOR

    Directory of Open Access Journals (Sweden)

    VIKAS JAIN

    2013-10-01

    Full Text Available Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor technologies. Indian innovative reactor ‘AHWR’ is a pressure-tube type natural circulation based boiling water reactor that is designed to meet such requirements, which essentially reflect the needs of next generation reactors. The reactor employs various passive features to prevent and mitigate accidental conditions, like a slightly negative void reactivity coefficient, passive poison injection to scram the reactor in event of failure of the wired shutdown systems, a large elevated pool of water as a heat sink inside the containment, passive decay heat removal based on natural circulation and passive valves, passive ECC injection, etc. It is designed to meet the fundamental safety requirements of safe shutdown, safe decay heat removal and confinement of activity with no impact in public domain, and hence, no need for emergency planning under all conceivable scenarios. This paper examines the role of the various passive safety systems in prevention and mitigation of severe plant conditions that may arise in event of multiple failures. For the purpose of demonstration of the effectiveness of its passive features, postulated scenarios on the lines of three major severe accidents in the history of nuclear power reactors are considered, namely; the Three Mile Island (TMI, Chernobyl and Fukushima accidents. Severe plant conditions along the lines of these scenarios are postulated to the extent conceivable in the reactor under consideration and analyzed using best estimate system thermal-hydraulics code RELAP5/Mod3.2. It is found that the various passive systems incorporated enable the reactor to tolerate the postulated accident conditions without causing severe plant conditions and core degradation.

  10. Reactivity control in HTR power plants with respect to passive safety system. Summary

    Energy Technology Data Exchange (ETDEWEB)

    Barnert, H; Kugeler, K [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik

    1996-12-01

    The R and D and Demonstration of the High Temperature Reactor (HTR) is described in overview. The HTR-MODULE power plant, as the most advanced concept, is taken for the description of the reactivity control in general. The idea of the ``modularization of the core`` of the HTR has been developed as the answer on the experiences of the core melt accident at Three Miles Island. The HTR module has two shutdown systems: The ``6 rods``-system for hot shutdown at the ``18 small absorber pebbles units`` - system for cold shutdown. With respect to the definition of ``Passive Systems`` of IAEA-TECDOC-626 the total reactivity control system of the HTR-MODULE is a passive system of category D, because it is an emergency reactor shutdown system based on gravity driven rods, and devices, activated by fail-safe trip logic. But reactivity control of the HTR does not only consist of these engineered safety system but does have a self-acting stabilization by the negative temperature coefficient of the reactivity, being rather effective in reactivity control. Examples from computer calculations are presented, and, in addition, experimental results from the ``Stuck Rod Experiment`` at the AVR reactor in Juelich. On the basis of this the proposal is made that ``self-acting stabilization as a quality of the function`` should be discussed as a new category in addition to the active and passive engineered safety systems, structures and components of IAEA-TECDOC-626. The requirements for a future ``catastrophe-free`` nuclear technology are presented. In the appendix the 7th amendment of the atomic energy act of the Federal Republic of Germany, effective 28 July 94, is given. (author).

  11. Determination of Waste Isolation Pilot Plant (WIPP) management and institutional requirements documents for contact-handled (CH) critical systems

    International Nuclear Information System (INIS)

    1990-01-01

    This document lists the critical requirements documents applicable to the receipt of contact-handled waste at the Waste Isolation Pilot Plant. It also describes the processes used to determine the applicability of each document. This analysis is based on the applicable documents that were in effect in the February 1988 time frame. 2 refs

  12. 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.

  13. Application of passive auto catalytic recombiner (PAR) for BWR plants in Japan

    International Nuclear Information System (INIS)

    Kobayashi, K.; Murano, K.; Yamanari, S.; Yamamoto, Y.

    2001-01-01

    The passive auto-catalytic recombiner (PAR), which can recombine flammable gases such as hydrogen and oxygen with each other to avoid an explosion in case of a loss-of-coolant accident (LOCA), installed in the primary containment vessel does not require a power supply or dynamic equipment, while the existing flammability gas control system (FCS) of most BWRs as an outer loop of the primary containment vessel needs them to make flammable gases circulate through blowers and heaters in the system. PAR offers a number of advantages over existing FCS, such as high reliability, low cost due to much smaller amount of materials needed, good maintainability, good operability in case of a LOCA, and smaller space for installation. An experimental study has been carried out for the purpose of solving the problems of applying PAR to Japanese BWR plants instead of existing FCS, in which we grasped the basic characteristics of PAR. (author)

  14. A Methodology for Modeling Nuclear Power Plant Passive Component Aging in Probabilistic Risk Assessment under the Impact of Operating Conditions, Surveillance and Maintenance Activities

    Science.gov (United States)

    Guler Yigitoglu, Askin

    In the context of long operation of nuclear power plants (NPPs) (i.e., 60-80 years, and beyond), investigation of the aging of passive systems, structures and components (SSCs) is important to assess safety margins and to decide on reactor life extension as indicated within the U.S. Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) Program. In the traditional probabilistic risk assessment (PRA) methodology, evaluating the potential significance of aging of passive SSCs on plant risk is challenging. Although passive SSC failure rates can be added as initiating event frequencies or basic event failure rates in the traditional event-tree/fault-tree methodology, these failure rates are generally based on generic plant failure data which means that the true state of a specific plant is not reflected in a realistic manner on aging effects. Dynamic PRA methodologies have gained attention recently due to their capability to account for the plant state and thus address the difficulties in the traditional PRA modeling of aging effects of passive components using physics-based models (and also in the modeling of digital instrumentation and control systems). Physics-based models can capture the impact of complex aging processes (e.g., fatigue, stress corrosion cracking, flow-accelerated corrosion, etc.) on SSCs and can be utilized to estimate passive SSC failure rates using realistic NPP data from reactor simulation, as well as considering effects of surveillance and maintenance activities. The objectives of this dissertation are twofold: The development of a methodology for the incorporation of aging modeling of passive SSC into a reactor simulation environment to provide a framework for evaluation of their risk contribution in both the dynamic and traditional PRA; and the demonstration of the methodology through its application to pressurizer surge line pipe weld and steam generator tubes in commercial nuclear power plants. In the proposed methodology, a

  15. Use of color-change indicators to quantify passive films on the stainless steel valves of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, Cong Qian [School of Materials Science, Engineering, Dalian University of Technology, Dalian 116085 (China); Yang, Shu Kai [School of Materials Science, Engineering, Dalian University of Technology, Dalian 116085 (China); Suzhou Nuclear Power Research Institute, Suzhou 215004 (China); Zhao, Jie, E-mail: jiezhao@dlut.edu.cn [School of Materials Science, Engineering, Dalian University of Technology, Dalian 116085 (China)

    2016-02-15

    Highlights: • A facile method to evaluate passivation quality by color change indicator. • Two indicators were compared in lab and applied on vales in nuclear power plants. • It shows that the higher value of color change the worse quality of passivation. • Traditional ferroxyl solution is unstable and might impair the vale surface. • The new indicator is more practicable than the ferroxyl test for on-site inspection. - Abstract: The passive film on nuclear-grade stainless steels was evaluated by quantifying its color changes. Coloration reactions were compared by using ferroin and blue dot solutions as indicators on the basis of the measured results in a laboratory. The reactions were then applied on stainless steel valves in a nuclear power plant. The degree of color change indicates the degree of growth of a passive film. The ferroin solution exhibits higher accuracy and more stable than blue dot solution in determining passive film quality. The potentiodynamic polarization curves show that blue dot solution might cause surface damage compared with ferroin solution. The inspection result on stainless steel valves supports our laboratory result. However, stainless steel exhibited a dramatic decrease in sensitivity to blue dot because of the intrinsic instability and high acidity of this solution. Ferroin solution is superior to blue dot solution for stainless steel facilities in a nuclear power plant.

  16. Acceptable knowledge document for INEEL stored transuranic waste - Rocky Flats Plant waste. Revision 2

    International Nuclear Information System (INIS)

    1998-01-01

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems

  17. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

  18. Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V. (Ebasco Services, Inc., Bellevue, WA (USA))

    1990-10-01

    This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs.

  19. Hanford Waste Vitrification Plant technical background document for best available radionuclide control technology demonstration

    International Nuclear Information System (INIS)

    Carpenter, A.B.; Skone, S.S.; Rodenhizer, D.G.; Marusich, M.V.

    1990-10-01

    This report provides the background documentation to support applications for approval to construct and operate new radionuclide emission sources at the Hanford Waste Vitrification Plant (HWVP) near Richland, Washington. The HWVP is required to obtain permits under federal and state statutes for atmospheric discharges of radionuclides. Since these permits must be issued prior to construction of the facility, draft permit applications are being prepared, as well as documentation to support these permits. This report addresses the applicable requirements and demonstrates that the preferred design meets energy, environmental, and economic criteria for Best Available Radionuclide Control Technology (BARCT) at HWVP. 22 refs., 11 figs., 25 tabs

  20. Microbial Community Activity And Plant Biomass Are Insensitive To Passive Warming In A Semiarid Ecosystem

    Science.gov (United States)

    Espinosa, N. J.; Fehmi, J. S.; Rasmussen, C.; Gallery, R. E.

    2017-12-01

    Soil microorganisms drive biogeochemical and nutrient cycling through the production of extracellular enzymes that facilitate organic matter decomposition and the flux of large amounts of carbon dioxide to the atmosphere. Although dryland ecosystems occupy over 40% of land cover and are projected to expand due to climate change, much of our current understanding of these processes comes from mesic temperate ecosystems. Understanding the responses of these globally predominant dryland ecosystems is therefore important yet complicated by co-occurring environmental changes. For example, the widespread and pervasive transition from grass to woody dominated landscapes is changing the hydrology, fire regimes, and carbon storage potential of semiarid ecosystems. In this study, we used a novel passive method of warming to conduct a warming experiment with added plant debris as either woodchip or biochar, to simulate different long-term carbon additions that accompany woody plant encroachment in semiarid ecosystems. The response of heterotrophic respiration, plant biomass, and microbial activity was monitored bi-annually. We hypothesized that the temperature manipulations would have direct and indirect effects on microbial activity. Warmer soils directly reduce the activity of soil extracellular enzymes through denaturation and dehydration of soil pores and indirectly through reducing microbe-available substrates and plant inputs. Overall, reduction in extracellular enzyme activity may reduce decomposition of coarse woody debris and potentially enhance soil carbon storage in semiarid ecosystems. For all seven hydrolytic enzymes examined as well as heterotrophic respiration, there was no consistent or significant response to experimental warming, regardless of seasonal climatic and soil moisture variation. The enzyme results observed here are consistent with the few other experimental results for warming in semiarid ecosystems and indicate that the controls over soil

  1. Passive cooling applications for nuclear power plants using pulsating steam-water heat pipes

    International Nuclear Information System (INIS)

    Aparna, J.; Chandraker, D.K.

    2015-01-01

    Gen IV reactors incorporate passive principles in their system design as an important safety philosophy. Passive safety systems use inherent physical phenomena for delivering the desired safe action without any external inputs or intrusion. The accidents in Fukushima have renewed the focus on passive self-manageable systems capable of unattended operation, for long hours even in extended station blackout (SBO) and severe accident conditions. Generally, advanced reactors use water or atmospheric air as their ultimate heat sink and employ passive principles in design for enhanced safety. This paper would be discussing the experimental results on pulsating steam water heat-pipe devices and their applications in passive cooling. (author)

  2. Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S.

    1996-01-01

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  3. Plutonium Finishing Plant (PFP) Standards/Requirements Identification Document (S/RID)

    International Nuclear Information System (INIS)

    Maddox, B.S.

    1996-01-01

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ESH) standards/requirements for the Plutonium Finishing Plant (PFP). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment

  4. Performance evaluation recommendations of nuclear power plants outdoor significant civil structures earthquake resistance. Technical documentation

    International Nuclear Information System (INIS)

    2005-06-01

    The Japan Society of Civil Engineers has updated performance evaluation recommendations of nuclear power plants outdoor significant civil structures earthquake resistance in June 2005. Experimental and analytical considerations on the seismic effects evaluation criteria, such as analytical seismic models of soils for underground structures, effects of vertical motions on time-history dynamic analysis and shear fracture of reinforced concretes by cyclic loadings, were shown in this document and incorporated in new recommendations. (T. Tanaka)

  5. Sodium hydroxide injection passivation work for the reactor water clean-up system in a new ABWR plant

    International Nuclear Information System (INIS)

    Wen, Tung-Jen; Lu, Ju-Huang

    2012-09-01

    Several studies have identified that Co-58 and Co-60 as the primary source of radiation build up on out-of-core components in new BWR plants. The deposition rate of Co on stainless steel and carbon steel is shown to be controlled mainly by the thickness of oxide films and its morphology formed through pretreatment. The passivation treatment was implemented accordingly at Lungmen unit 1 in an ABWR plant in September 2010. It is determined that the passivation conditions should be maintained at the temperature of 180∼230 deg. C, pH of 8.0∼8.5 and dissolved oxygen content over 400 ppb. The films would provide effective protection against radioactive deposition. The application of the pre-filming process on piping before the pre-operation is done during the flow induced vibration test (FIV) period. The protectiveness of stable magnetite can be increased by the pH control under the specific condition. The pre-filming control process and evaluation of passivation effectiveness is discussed in detail based on the surface analysis of the passivated specimens. Many efforts have been devoted to sodium hydroxide injection method for pH control of the system through the filter demineralizer under smooth operation. A comparison of test specimens on the properties of oxide film formed between laboratory and in-plant tests through alkaline treatment are also shown in this report. (authors)

  6. 10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-25

    Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)

  7. COMSY- A Software Tool For Aging And Plant Life Management With An Integrated Documentation Tool

    International Nuclear Information System (INIS)

    Baier, Roman; Zander, Andre

    2008-01-01

    For the aging and plant life management the integrity of the mechanical components and structures is one of the key objectives. In order to ensure this integrity it is essential to implement a comprehensive aging management. This should be applied to all safety relevant mechanical systems or components, civil structures, electrical systems as well as instrumentation and control (I and C). The following aspects should be covered: - Identification and assessment of relevant degradation mechanisms; - Verification and evaluation of the quality status of all safety relevant systems, structures and components (SSC's); - Verification and modernization of I and C and electrical systems; - Reliable and up-to-date documentation. For the support of this issue AREVA NP GmbH has developed the computer program COMSY, which utilizes more than 30 years of experience resulting from research activities and operational experience. The program provides the option to perform a plant-wide screening for identifying system areas, which are sensitive to specific degradation mechanisms. Another object is the administration and evaluation of NDE measurements from different techniques. An integrated documentation tool makes the document management and maintenance fast, reliable and independent from staff service. (authors)

  8. Fate of As, Se, and Hg in a Passive Integrated System for Treatment of Fossil Plant Wastewater

    Energy Technology Data Exchange (ETDEWEB)

    Terry Yost; Paul Pier; Gregory Brodie

    2007-12-31

    TVA is collaborating with EPRI and DOE to demonstrate a passive treatment system for removing SCR-derived ammonia and trace elements from a coal-fired power plant wastewater stream. The components of the integrated system consist of trickling filters for ammonia oxidation, reaction cells containing zero-valent iron (ZVI) for trace contaminant removal, a settling basin for storage of iron hydroxide floc, and anaerobic vertical-flow wetlands for biological denitrification. The passive integrated treatment system will treat up to 0.25 million gallons per day (gpd) of flue gas desulfurization (FGD) pond effluent, with a configuration requiring only gravity flow to obviate the need for pumps. The design of the system will enable a comparative evaluation of two parallel treatment trains, with and without the ZVI extraction trench and settling/oxidation basin components. One of the main objectives is to gain a better understanding of the chemical transformations that species of trace elements such as arsenic, selenium, and mercury undergo as they are treated in passive treatment system components with differing environmental conditions. This progress report details the design criteria for the passive integrated system for treating fossil power plant wastewater as well as performance results from the first several months of operation. Engineering work on the project has been completed, and construction took place during the summer of 2005. Monitoring of the passive treatment system was initiated in October 2005 and continued until May 18 2006. The results to date indicate that the treatment system is effective in reducing levels of nitrogen compounds and trace metals. Concentrations of both ammonia and trace metals were lower than expected in the influent FGD water, and additions to increase these concentrations will be done in the future to further test the removal efficiency of the treatment system. In May 2006, the wetland cells were drained of FGD water, refilled with

  9. Documentation of hypoglycemic and wound healing plants in Kodiyampalayam coastal village (southeast coast of India

    Directory of Open Access Journals (Sweden)

    Satyavani Kaliamurthi

    2014-08-01

    Full Text Available Objective: To document the hypoglycemic and wound healing plant species especially halophytes and associates were carried out in the coastal village of Kodiyampalayam (Southeast coast of India. Methods: The data were collected during the month of December 2011 to November 2012 with personal interviews and group discussion of local coastal fisher women community and traditional practitioner. Results: The results indicated the traditional knowledge of 33 medicinal plant species, photographs, vernacular name, habit, active part and their mode of action. Among these, Citrullus colocynthis, Coccinia grandis, Rhizophora apiculata, Rhizophora mucronata, Bruguiera cylindrica, Excoecaria agallocha and Andrographis paniculata were discovered in huge number. Conclusions: This study concludes medicinal uses of halophytes and associates in the coastal area. It will be needed scientific validation for development of novel therapeutic agents.

  10. Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie,J.; Braverman, J.; Hofmayer, C.; Kim, M. K.; Choi, I-K.

    2009-04-27

    When performing seismic safety assessments of nuclear power plants (NPPs), the potential effects of age-related degradation on structures, systems, and components (SSCs) should be considered. To address the issue of aging degradation, the Korea Atomic Energy Research Institute (KAERI) has embarked on a five-year research project to develop a realistic seismic risk evaluation system which will include the consideration of aging of structures and components in NPPs. Three specific areas that are included in the KAERI research project, related to seismic probabilistic risk assessment (PRA), are probabilistic seismic hazard analysis, seismic fragility analysis including the effects of aging, and a plant seismic risk analysis. To support the development of seismic capability evaluation technology for degraded structures and components, KAERI entered into a collaboration agreement with Brookhaven National Laboratory (BNL) in 2007. The collaborative research effort is intended to continue over a five year period with the goal of developing seismic fragility analysis methods that consider the potential effects of age-related degradation of SSCs, and using these results as input to seismic PRAs. In the Year 1 scope of work BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations that will be performed in the subsequent evaluations in the years that follow. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. This report

  11. Application of digital field photographs as documents for tropical plant inventory1

    Science.gov (United States)

    LaFrankie, James V.; Chua, Anna I.

    2015-01-01

    Premise of the study: We tested the credibility and significance of digital field photographs as supplements or substitutes for conventional herbarium specimens with particular relevance to exploration of the tropics. Methods: We made 113 collections in triplicate at a species-rich mountain in the Philippines while we took 1238 digital photographs of the same plants. We then identified the plants from the photographs alone, categorized the confidence of the identification and the reason for failure to identify, and compared the results to identifications based on the dried specimens. Results: We identified 72.6% of the photographic sets with high confidence and 27.4% with low confidence or only to genus. In no case was a confident identification altered by subsequent examination of the dried specimen. The failure to identify photographic sets to species was due to the lack of a key feature in 67.8% of the cases and due to a poorly understood taxonomy in 32.2%. Discussion: We conclude that digital photographs cannot replace traditional herbarium specimens as the primary elements that document tropical plant diversity. However, photographs represent a new and important artifact that aids an expedient survey of tropical plant diversity while encouraging broad public participation. PMID:25995976

  12. Application of digital field photographs as documents for tropical plant inventory.

    Science.gov (United States)

    LaFrankie, James V; Chua, Anna I

    2015-05-01

    We tested the credibility and significance of digital field photographs as supplements or substitutes for conventional herbarium specimens with particular relevance to exploration of the tropics. We made 113 collections in triplicate at a species-rich mountain in the Philippines while we took 1238 digital photographs of the same plants. We then identified the plants from the photographs alone, categorized the confidence of the identification and the reason for failure to identify, and compared the results to identifications based on the dried specimens. We identified 72.6% of the photographic sets with high confidence and 27.4% with low confidence or only to genus. In no case was a confident identification altered by subsequent examination of the dried specimen. The failure to identify photographic sets to species was due to the lack of a key feature in 67.8% of the cases and due to a poorly understood taxonomy in 32.2%. We conclude that digital photographs cannot replace traditional herbarium specimens as the primary elements that document tropical plant diversity. However, photographs represent a new and important artifact that aids an expedient survey of tropical plant diversity while encouraging broad public participation.

  13. Operating correspondent documentation in power plants. Influence of modern control engineering and planning means. Proceedings. Betriebsgerechte Dokumentation in Kraftwerken. Einfluss der modernen Leittechnik und der Planungsmittel. Vortraege

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The proceedings contain 3 papers covering the aspect of documentation in power plants: Relevant documentation from the operator's view and the manufacturer's view, auxiliary means for documentation and its futural aspects.

  14. Soil Moisture Active Passive (SMAP) Project Algorithm Theoretical Basis Document SMAP L1B Radiometer Data Product: L1B_TB

    Science.gov (United States)

    Piepmeier, Jeffrey; Mohammed, Priscilla; De Amici, Giovanni; Kim, Edward; Peng, Jinzheng; Ruf, Christopher; Hanna, Maher; Yueh, Simon; Entekhabi, Dara

    2016-01-01

    The purpose of the Soil Moisture Active Passive (SMAP) radiometer calibration algorithm is to convert Level 0 (L0) radiometer digital counts data into calibrated estimates of brightness temperatures referenced to the Earth's surface within the main beam. The algorithm theory in most respects is similar to what has been developed and implemented for decades for other satellite radiometers; however, SMAP includes two key features heretofore absent from most satellite borne radiometers: radio frequency interference (RFI) detection and mitigation, and measurement of the third and fourth Stokes parameters using digital correlation. The purpose of this document is to describe the SMAP radiometer and forward model, explain the SMAP calibration algorithm, including approximations, errors, and biases, provide all necessary equations for implementing the calibration algorithm and detail the RFI detection and mitigation process. Section 2 provides a summary of algorithm objectives and driving requirements. Section 3 is a description of the instrument and Section 4 covers the forward models, upon which the algorithm is based. Section 5 gives the retrieval algorithm and theory. Section 6 describes the orbit simulator, which implements the forward model and is the key for deriving antenna pattern correction coefficients and testing the overall algorithm.

  15. EFSA Guidance Document on the risk assessment of plant protection products on bees (Apis mellifera, Bombus spp. and solitary bees)

    NARCIS (Netherlands)

    Arnold, G.; Boesten, J.J.T.I.; Clook, M.

    2013-01-01

    The Guidance Document is intended to provide guidance for notifiers and authorities in the context of the review of plant protection products (PPPs) and their active substances under Regulation (EC) 1107/2009. The scientific opinion on the science behind the development of a risk assessment of plant

  16. Documentation, User Support, and Verification of Wind Turbine and Plant Models

    Energy Technology Data Exchange (ETDEWEB)

    Robert Zavadil; Vadim Zheglov; Yuriy Kazachkov; Bo Gong; Juan Sanchez; Jun Li

    2012-09-18

    As part of the Utility Wind Energy Integration Group (UWIG) and EnerNex's Wind Turbine Modeling Project, EnerNex has received ARRA (federal stimulus) funding through the Department of Energy (DOE) to further the progress of wind turbine and wind plant models. Despite the large existing and planned wind generation deployment, industry-standard models for wind generation have not been formally adopted. Models commonly provided for interconnection studies are not adequate for use in general transmission planning studies, where public, non-proprietary, documented and validated models are needed. NERC MOD (North American Electric Reliability Corporation) reliability standards require that power flow and dynamics models be provided, in accordance with regional requirements and procedures. The goal of this project is to accelerate the appropriate use of generic wind turbine models for transmission network analysis by: (1) Defining proposed enhancements to the generic wind turbine model structures that would allow representation of more advanced; (2) Comparative testing of the generic models against more detailed (and sometimes proprietary) versions developed by turbine vendors; (3) Developing recommended parameters for the generic models to best mimic the performance of specific commercial wind turbines; (4) Documenting results of the comparative simulations in an application guide for users; (5) Conducting technology transfer activities in regional workshops for dissemination of knowledge and information gained, and to engage electric power and wind industry personnel in the project while underway; (6) Designing of a "living" homepage to establish an online resource for transmission planners.

  17. GCFR demonstration plant: conceptual design and status report. Briefing document and executive summary

    International Nuclear Information System (INIS)

    1980-12-01

    Helium Breeder Associates (HBA), a non-profit corporation, has been the program manager and technical integrator of the Gas-Cooled Fast Reactor (GCFR) development effort since 1977. When DOE discontinued support of the GCFR in 1980, the HBA members undertook the task of providing for an orderly termination and documentation of the program. HBA does not agree with the government's rational for withdrawing support for this promising technology and has directed its termination and documentation toward preserving the current state of its development. Toward that end, HBA has compiled a report of which this is a brief summary covering the conceptual design of the demonstration plant and status of the program as of the end of 1980. All the work in design, development, safety, and licensing which has been done to date, both in this country and in Europe, has given positive results and the prognosis for ultimately achieving the potential advantages of the GCFR is excellent. The report is intended to provide the reader with the design considerations that were current at the time of program termination. The report could be useful in restarting the program in the future by establishing the basis of the completed conceptual design and indicating a logical path for new design and development

  18. Profile of medicinal plants utilization through patent documents: the andiroba example

    Directory of Open Access Journals (Sweden)

    Luciene F. Gaspar Amaral

    2013-06-01

    Full Text Available Today, one of the trends of the pharmaceutical, cosmetic and food market is the development of products with components of natural origin, rationally exploiting biodiversity. Brazilian population makes secular use of medicinal plants including andiroba, whose oil is used in folk medicine as febrifuge, pain-relieving, anti-parasitic, anti-allergic as well as insect repellant. The present study attempts to evaluate the profile of utilization of andiroba by analyzing the patenting trends based on information collected on the databases of the World Intellectual Property Organization, European Patent Office and Brazilian National Institute of Industrial Property in the period from 1990 to 2011. The following parameters were analyzed: chronological aspect of the applications, countries of priority, international patent classification, technologies and actors in the technological platform. The temporal analysis of the applications shows an evident increase despite a discontinuous evolution of the number of applications. Pharmaceutical, chemical and cosmetic areas were identified as the main areas for commercial application of the plant. Brazil is the country with the largest number of applications even though the majority of the patent technologies are already in public domain, indicating that the technological information contained in these documents could be used for research and investment in several areas.

  19. 'Passive fire protection in nuclear power plants' - German technologies of the company svt Brandschutz in future as well in Korean NPPs? -

    International Nuclear Information System (INIS)

    Bremer, Joerg; Kim, Duill; Wendt, Ruediger

    2002-01-01

    Fires in NPPs are unfortunately not avoidable and to consider during the planning and operation period of the plants. The multitude of combustible materials which are used especially cables, oils and other building materials describe a potential source of danger. In Germany recently a new planning guideline for the fire protection field in NPPs has been adopted: the nuclear guideline KTA 1401. This document certainly is one of the most progressive guidelines for the fire protection field and has united · structural engineering elements of fire protection · electrotechnical and machine components · as well as questions of fire alarm and organisation measures. Passive and active fire protection measures are explained and layed down in their complexity within this document. Our group of companies has realised quit a lot of fire protection projects in Europe during the last years, especially within retrofitting measures for NPPs in Germany, Switzerland, Russia, the Ukraine and Lithuania, the Czech and Slovak Republic as well as within decommissioning projects of NPPs. We have carried out international fire protection projects of the EBRD, London, and within the framework of TACIS projects of the European Commission, i. a. linked with the working out of fire protection analyses for NPPs realised in close co-operation with the Germanischer Lloyd, Hamburg. We especially have wide experiences in improving the fire protection of cable installations where a 100% separation of the different safety systems is not any longer possible

  20. Development of digital library system on regulatory documents for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, K. H.; Kim, K. J.; Yoon, Y. H.; Kim, M. W.; Lee, J. I.

    2001-01-01

    The main objective of this study is to establish nuclear regulatory document retrieval system based on internet. With the advancement of internet and information processing technology, information management patterns are going through a new paradigm. Getting along the current of the time, it is general tendency to transfer paper-type documents into electronic-type documents through document scanning and indexing. This system consists of nuclear regulatory documents, nuclear safety documents, digital library, and information system with index and full text

  1. Plant Chlorophyll fluorescence: active and passive measurements at canopy and leaf scales with different nitrogen treatments

    Science.gov (United States)

    Most studies assessing chlorophyll fluorescence (ChlF) have examined leaf responses to environmental stress conditions using active techniques. Alternatively, passive techniques are able to measure ChlF at both leaf and canopy scales. However, although the measurement principles of both techniques a...

  2. Implementation of passive samplers for monitoring volatile organic compounds in ground water at the Kansas City Plant

    International Nuclear Information System (INIS)

    Gardner, F.G.; Korte, N.E.; Wilson-Nichols, M.J.; Baker, J.L.; Ramm, S.G.

    1998-06-01

    Passive sampling for monitoring volatile organic compounds (VOCs) has been suggested as a possible replacement to the traditional bailer method used at the Department of Energy Kansas City Plant (KCP) for routine groundwater monitoring. To compare methods, groundwater samples were collected from 19 KCP wells with VOC concentrations ranging from non-detectable to > 100,000 microg/L. Analysis of the data was conducted using means and medians of multiple measurements of TCE, 1,2-DCE, 1,1-DCE and VC. All 95% confidence intervals of these VOCs overlap, providing evidence that the two methods are similar. The study also suggests that elimination of purging and decontamination of sampling equipment reduces the labor required to sample by approximately 32%. Also, because the passive method generates no waste water, there are no associated disposal costs. The results suggest evidence to continue studies and efforts to replace traditional bailer methods with passive sampling at KCP based on cost and the similarity of the methods

  3. Use of an advanced document system in post-refuelling updating of nuclear power plant documentation; Utilizacion de un sistema documental avanzado en la actualizacion de documentacion post recarga

    Energy Technology Data Exchange (ETDEWEB)

    Puech Suanzes, P; Cortes Soler, M [Empresarios Agrupados, A.I.E., Madrid (Spain)

    1993-12-15

    This paper discusses the results of the extensive use of an advanced document system to update documentation prepared by traditional methods and affected by changes in the period between two plant refuellings. The implementation of a system for the capture, retrieval and storage of drawings using optical discs is part of a plan to modernize production and management tools and to thus achieve better control of document configuration. These processes are consequently optimized in that: 1. The deterioration of drawings is detained with the help of an identical, updated, legible, reliable support for all users. 2. The time required to update documentation is reduced. Given the large number of drawings, the implementation method should effectively combine costs and time. The document management tools ensure optical disc storage control so that from the moment a drawing resides in the system, any modification to it is made through the system utilities, thus ensuring quality and reducing schedules. The system described was used to update the electrical drawings of Almaraz Nuclear Power Plant. Changes made during the eighth refuelling of Unit I were incorporated and the time needed to issue the updated drawings was reduced by one month. (author)

  4. Information technology impact on nuclear power plant documentation. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    International Nuclear Information System (INIS)

    2002-04-01

    As the majority of the nuclear power plants (NPPs) in the world were designed and constructed about twenty to forty years ago, these older power plants may have shortcomings in documentation on construction, commissioning, operations, maintenance, or decommissioning. Therefore, facility documentation does not always reflect actual plant status after years of plant operation, modification, and maintenance. To deal with these shortcomings, computer and information technologies that provide sophisticated and modern design tools as well as information processing and storage facilities can offer dramatic innovation from paper-centric documentation towards data-centric documentation. This report addresses all aspects of documentation associated with various life-cycle phases of NPPs and the information technology (IT) that are relevant to the documentation process. It also provides a guide for planning, designing, and executing an IT documentation project. Examples are given to demonstrate successful implementations at plants. Finally, it discusses the issues related to the application of the IT in NPPs and the trends for applications of the IT at NPPs as well as the technology itself. It is recognized that this can also improve configuration management. reliability of data, quality of personnel work, and ultimately plant performance reliability and safety. The aspects of using the IT for NPP documentation are closely related to configuration management at NPPs. The report consists of nine sections, a reference section, and five additional appendices. The development of this report which was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is the result of a series of consultants meetings held by the IAEA in Vienna (October 1999, November 2000). It was prepared with the participation and contributions of experts from Canada, Germany, Norway, Sweden, and the United States of America. In addition, a

  5. Information technology impact on nuclear power plant documentation. Report prepared within the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-04-01

    As the majority of the nuclear power plants (NPPs) in the world were designed and constructed about twenty to forty years ago, these older power plants may have shortcomings in documentation on construction, commissioning, operations, maintenance, or decommissioning. Therefore, facility documentation does not always reflect actual plant status after years of plant operation, modification, and maintenance. To deal with these shortcomings, computer and information technologies that provide sophisticated and modern design tools as well as information processing and storage facilities can offer dramatic innovation from paper-centric documentation towards data-centric documentation. This report addresses all aspects of documentation associated with various life-cycle phases of NPPs and the information technology (IT) that are relevant to the documentation process. It also provides a guide for planning, designing, and executing an IT documentation project. Examples are given to demonstrate successful implementations at plants. Finally, it discusses the issues related to the application of the IT in NPPs and the trends for applications of the IT at NPPs as well as the technology itself. It is recognized that this can also improve configuration management. reliability of data, quality of personnel work, and ultimately plant performance reliability and safety. The aspects of using the IT for NPP documentation are closely related to configuration management at NPPs. The report consists of nine sections, a reference section, and five additional appendices. The development of this report which was initiated by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). It is the result of a series of consultants meetings held by the IAEA in Vienna (October 1999, November 2000). It was prepared with the participation and contributions of experts from Canada, Germany, Norway, Sweden, and the United States of America. In addition, a

  6. Exposure of Lima bean leaves to volatiles from herbivore-induced conspecific plants results in emission of carnivore attractants: active or passive process?

    NARCIS (Netherlands)

    Choh, Y.; Shimoda, T.; Ozawa, R.; Dicke, M.; Takabayashi, J.

    2004-01-01

    There is increasing evidence that volatiles emitted by herbivore-damaged plants can cause responses in downwind undamaged neighboring plants, such as the attraction of carnivorous enemies of herbivores. One of the open questions is whether this involves an active (production of volatiles) or passive

  7. Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

    International Nuclear Information System (INIS)

    1996-12-01

    The meeting provided an overview of the key issues on passive safety. Technical problems which may affect future deployment, and the operating experience of passive systems and components, as well as, definitions of passive safety terms, were discussed. Advantages and disadvantages of passive systems were also highlighted. The philosophy behind different passive safety systems was presented and the range of possibility between fully passive and fully active systems was discussed. Refs, figs, tabs

  8. Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The meeting provided an overview of the key issues on passive safety. Technical problems which may affect future deployment, and the operating experience of passive systems and components, as well as, definitions of passive safety terms, were discussed. Advantages and disadvantages of passive systems were also highlighted. The philosophy behind different passive safety systems was presented and the range of possibility between fully passive and fully active systems was discussed. Refs, figs, tabs.

  9. Plant Line Trial Evaluation of Viable Non-Chromium Passivation Systems for Electrolytin Tinplate, ETP (TRP 9911)

    Energy Technology Data Exchange (ETDEWEB)

    John A. Sinsel

    2003-06-30

    Plant trial evaluations have been completed for two zirconium-based, non-chromium passivation systems previously identified as possible alternatives to cathodic dichromate (CDC) passivation for electrolytic tinplate (ETP). These trials were done on a commercial electrolytic tin plating line at Weirton Steel and extensive evaluations of the materials resulting from these trials have been completed. All this was accomplished as a collaborative effort under the AISI Technology Roadmap Program and was executed by seven North American Tin Mill Products producers [Bethlehem Steel (now acquired by International Steel Group (ISG)), Dofasco Inc., National Steel (now acquired by U.S. Steel), U.S. Steel, USS-Posco, Weirton Steel, and Wheeling-Pittsburgh Steel] with funding partially from the Department of Energy (DOE) and partially on an equal cost sharing basis among project participants. The initial phases of this project involved optimization of application procedures for the non-chromium systems in the laboratories at Bethlehem Steel and Betz Dearborn followed by extensive testing with various lacquer formulations and food simulants in the laboratories at Valspar and PPG. Work was also completed at Dofasco and Weirton Steel to develop methods to prevent precipitation of insoluble solids as a function of time from the zirconate system. The results of this testing indicated that sulfide staining characteristics for the non-chromium passivation systems could be minimized but not totally eliminated and neither system was found to perform quite as good, in this respect, as the standard CDC system. As for the stability of zirconate treatment, a method was developed to stabilize this system for a sufficient period of time to conduct plant trial evaluations but, working with a major supplier of zirconium orthosulfate, a method for long term stabilization is still under development.

  10. Data management for the Clinch River Breeder Reactor Plant Project by use of document status and hold systems

    International Nuclear Information System (INIS)

    Hunt, C.S.; Beck, A.E.; Akhtar, M.S.

    1982-01-01

    This paper describes the development, framework, and scope of the Document Status System and the Document Hold System for the Clinch River Breeder Reactor Plant Project. It shows how data are generated at five locations and transmitted to a central computer for processing and storage. The resulting computerized data bank provides reports needed to perform day-to-day management and engineering planning. Those reports also partially satisfy the requirements of the Project's Quality Assurance Program

  11. Planning of solar heated plant for low-energy houses and passive houses. An introduction; Planlegging av solvarmeanlegg for lavenergiboliger og passivhus. En introduksjon

    Energy Technology Data Exchange (ETDEWEB)

    Andresen, Inger

    2008-07-01

    This guide gives an introduction to the most important principles in planning and projecting of solar heated plant in low-energy houses and passive houses. It is written mainly for architects and consultants involved in housing projects with ambitions to achieve low-energy or passive house standard, but will also be of value for builders and others interested in the topic. (AG). 35 refs., 27 figs

  12. Interface control document between PUREX/UO3 Plant Transition and Solid Waste Disposal Division

    International Nuclear Information System (INIS)

    Duncan, D.R.

    1994-01-01

    This interface control document (ICD) between PUREX/UO 3 Plant Transition (PPT) and Solid Waste Disposal Division (SWD) establishes at a top level the functional responsibilities of each division where interfaces exist between the two divisions. Since the PUREX Transition and Solid Waste Disposal divisions operate autonomously, it is important that each division has a clear understanding of the other division's expectations regarding these interfaces. This ICD primarily deals with solid wastes generated by the PPT. In addition to delineating functional responsibilities, the ICD includes a baseline description of those wastes that will require management as part of the interface between the divisions. The baseline description of wastes includes waste volumes and timing for use in planning the proper waste management capabilities: the primary purpose of this ICD is to ensure defensibility of expected waste stream volumes and Characteristics for future waste management facilities. Waste descriptions must be as complete as-possible to ensure adequate treatment, storage, and disposal capability will exist. The ICD also facilitates integration of existing or planned waste management capabilities of the PUREX. Transition and Solid Waste Disposal divisions. The ICD does not impact or affect the existing processes or procedures for shipping, packaging, or approval for shipping wastes by generators to the Solid Waste Division

  13. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant

    International Nuclear Information System (INIS)

    Zamora R, L.; Medina F, A.

    1999-01-01

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  14. Review of passive groundwater remediation systems: Lessons learned Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-08-01

    One of the proposed solutions for treatment of the contaminated groundwater in the Bear Creek Valley is the installation of a passive treatment system. Such a system would use a reactive media installed in a continuous trench or in a gate as part of a barrier wall and gate system. This report evaluates information on five similar systems [no information was available on two additional systems] and evaluates the shortcomings and the advantages of each. Section 5 provides a short summary of the findings and presents some recommendations on how to avoid some of the common problems encountered with the existing systems

  15. Concept research on general passive system

    International Nuclear Information System (INIS)

    Han Xu; Yang Yanhua; Zheng Mingguang

    2009-01-01

    This paper summarized the current passive techniques used in nuclear power plants. Through classification and analysis, the functional characteristics and inherent identification of passive systems were elucidated. By improving and extending the concept of passive system, the general passive concept was proposed, and space and time relativity was discussed and assumption of general passive system were illustrated. The function of idealized general passive system is equivalent with the current passive system, but the design of idealized general passive system is more flexible. (authors)

  16. Passivity Enhancement in Renewable Energy Source Based Power Plant With Paralleled Grid-Connected VSIs

    DEFF Research Database (Denmark)

    Bai, Haofeng; Wang, Xiongfei; Blaabjerg, Frede

    2017-01-01

    Harmonic instability is threatening the operation of renewable energy based power plants where multiple gridconnected VSIs are connected in parallel. To analyze and improve the stability of the grid-connected VSIs, the real part of the output admittance of the VSIs is first investigated......-connected VSIs can improve the stability of the renewable power plant....

  17. Carbon steel protection in G.S. (Girlder sulfide) heavy water fabrication plants. Control of iron content at the final stage of passivation. Pt. 10

    International Nuclear Information System (INIS)

    Rojo, E.A.

    1991-01-01

    This paper is part of a series which corresponds to the carbon steel behaviour as construction material for Girlder sulfide (G.S.) heavy water plants. The present work analyses the iron concentration study during passivation in the passivating fluid. At the beginning, during the formation of the most soluble sulfide -that is the mackinawite-, the iron concentration reaches more than 10 ppm. After some days, this iron concentration begins to decrease up to its stabilization under 0.1 ppm. This process, which occurs in the 9th. and 11th days, indicates that passivation is over, and that a pyrite and pyrrhotite-pyrite layer exists on the iron. Some differences exist between the results obtained and those previsible for the iron sulfides solubilities. In spite of these difficulties, the procedure is perfectly adequate to judge the passivation final stage. (Author) [es

  18. High-Throughput Phenotyping of Wheat and Barley Plants Grown in Single or Few Rows in Small Plots Using Active and Passive Spectral Proximal Sensing

    Directory of Open Access Journals (Sweden)

    Gero Barmeier

    2016-11-01

    Full Text Available In the early stages of plant breeding, breeders evaluate a large number of varieties. Due to limited availability of seeds and space, plot sizes may range from one to four rows. Spectral proximal sensors can be used in place of labour-intensive methods to estimate specific plant traits. The aim of this study was to test the performance of active and passive sensing to assess single and multiple rows in a breeding nursery. A field trial with single cultivars of winter barley and winter wheat with four plot designs (single-row, wide double-row, three rows, and four rows was conducted. A GreenSeeker RT100 and a passive bi-directional spectrometer were used to assess biomass fresh and dry weight, as well as aboveground nitrogen content and uptake. Generally, spectral passive sensing and active sensing performed comparably in both crops. Spectral passive sensing was enhanced by the availability of optimized ratio vegetation indices, as well as by an optimized field of view and by reduced distance dependence. Further improvements of both sensors in detecting the performance of plants in single rows can likely be obtained by optimization of sensor positioning or orientation. The results suggest that even in early selection cycles, enhanced high-throughput phenotyping might be able to assess plant performance within plots comprising single or multiple rows. This method has significant potential for advanced breeding.

  19. Numerical simulation of a passive scalar transport from thermal power plants

    Science.gov (United States)

    Issakhov, Alibek; Baitureyeva, Aiymzhan

    2017-06-01

    The active development of the industry leads to an increase in the number of factories, plants, thermal power plants, nuclear power plants, thereby increasing the amount of emissions into the atmosphere. Harmful chemicals are deposited on the soil surface, remain in the atmosphere, which leads to a variety of environmental problems which are harmful for human health and the environment, flora and fauna. Considering the above problems, it is very important to control the emissions to keep them at an acceptable level for the environment. In order to do that it is necessary to investigate the spread of harmful emissions. The best way to assess it is the creating numerical simulation of gaseous substances' motion. In the present work the numerical simulation of the spreading of emissions from the thermal power plant chimney is considered. The model takes into account the physical properties of the emitted substances and allows to calculate the distribution of the mass fractions, depending on the wind velocity and composition of emissions. The numerical results were performed using the ANSYS Fluent software package. As a result, the results of numerical simulations and the graphs are given.

  20. Magnetohydrodynamics (MHD) Engineering Test Facility (ETF) 200 MWe power plant. Design Requirements Document (DRD)

    Science.gov (United States)

    Rigo, H. S.; Bercaw, R. W.; Burkhart, J. A.; Mroz, T. S.; Bents, D. J.; Hatch, A. M.

    1981-01-01

    A description and the design requirements for the 200 MWe (nominal) net output MHD Engineering Test Facility (ETF) Conceptual Design, are presented. Performance requirements for the plant are identified and process conditions are indicated at interface stations between the major systems comprising the plant. Also included are the description, functions, interfaces and requirements for each of these major systems. The lastest information (1980-1981) from the MHD technology program are integrated with elements of a conventional steam electric power generating plant.

  1. Combined photogrammetry and 3-D CAD for plant documentation and planning of refits

    International Nuclear Information System (INIS)

    Fraas, K.C.; Giese, U.; Kamsties, K.D.

    1991-01-01

    Meticulous advance planning and erection studies using a three-dimensional computer-aided design model of the plant area concerned can reduce the problem that unexpected events during a plant refit will prolong the required inspection period. This presupposes that a 3-D CAD scale model of the running plant has been generated. A method is described with which the as-built condition of the plant area is converted into a 3-D CAD model by combining photogrammetry with 3-D CAD. The minimum amount of time required for in-plant surveying and the completeness and clarity of results are the special advantages of this method in comparison with other measurement techniques. Selected applications are presented. (orig.) [de

  2. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  3. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  4. Foliar Reflectance and Fluorescence Responses for Plants Under Nitrogen Stress Determined with Active and Passive Systems

    Science.gov (United States)

    Middleton, E. M.; McMurtrey, J. E.; Campbell, P. K. Entcheva; Corp, L. A.; Butcher, L. M.; Chappelle, E. W.

    2003-01-01

    Vegetation productivity is driven by nitrogen (N) availability in soils. Both excessive and low soil N induce physiological changes in plant foliage. In 2001, we examined the use of spectral fluorescence and reflectance measurements to discriminate among plants provided different N fertilizer application rates: 20%, 50%, 100% and 150% of optimal N levels. A suite of optical, fluorescence, and biophysical measurements were collected on leaves from field grown corn (Zea mays L.) and soybean plants (Glycine max L.) grown in pots (greenhouse + ambient sunlight daily). Three types of steady state laser-induced fluorescence measurements were made on adaxial and abaxial surfaces: 1) fluorescence images in four 10 nm bands (blue, green, red, far-red) resulting from broad irradiance excitation; 2) emission spectra (5 nm resolution) produced by excitation at single wavelengths (280,380 or 360, and 532 nm); and 3) excitation spectra (2 nm resolution), with emission wavelengths fixed at wavelengths centered on selected solar Fraunhofer lines (532,607,677 and 745 nm). Two complementary sets of high resolution (less than 2 nm) optical spectra were acquired for both adaxial and abaxial leaf surfaces: 1) optical properties (350-2500 nm) for reflectance, transmittance, and absorptance; and 2) reflectance spectra (500-1000 nm) acquired with and without a short pass filter at 665 nm to determine the fluorescence contribution to apparent reflectance in the 650-750 spectrum, especially at the 685 and 740 nm chlorophyll fluorescence (ChIF) peaks. The strongest relationships between foliar chemistry and optical properties were demonstrated for C/N content and two optical parameters associated with the red edge inflection point. Select optical properties and ChIF parameters were highly correlated for both species. A significant contribution of ChIF to apparent reflectance was observed, averaging 10-25% at 685 nm and 2 - 6% at 740 nm over all N treatments. Discrimination of N treatment

  5. Safety assessment for the passive system of the nuclear power plants (NPPs) using safety margin estimation

    International Nuclear Information System (INIS)

    Woo, Tae-Ho; Lee, Un-Chul

    2010-01-01

    The probabilistic safety assessment (PSA) for gas-cooled nuclear power plants has been investigated where the operational data are deficient, because there is not any commercial gas-cooled nuclear power plant. Therefore, it is necessary to use the statistical data for the basic event constructions. Several estimations for the safety margin are introduced for the quantification of the failure frequency in the basic event, which is made by the concept of the impact and affordability. Trend of probability of failure (TPF) and fuzzy converter (FC) are introduced using the safety margin, which shows the simplified and easy configurations for the event characteristics. The mass flow rate in the natural circulation is studied for the modeling. The potential energy in the gravity, the temperature and pressure in the heat conduction, and the heat transfer rate in the internal stored energy are also investigated. The values in the probability set are compared with those of the fuzzy set modeling. Non-linearity of the safety margin is expressed by the fuzziness of the membership function. This artificial intelligence analysis of the fuzzy set could enhance the reliability of the system comparing to the probabilistic analysis.

  6. Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    Di Maio, Francesco; Nicola, Giancarlo; Borgonovo, Emanuele; Zio, Enrico

    2016-01-01

    Sensitivity Analysis (SA) is performed to gain fundamental insights on a system behavior that is usually reproduced by a model and to identify the most relevant input variables whose variations affect the system model functional response. For the reliability analysis of passive safety systems of Nuclear Power Plants (NPPs), models are Best Estimate (BE) Thermal Hydraulic (TH) codes, that predict the system functional response in normal and accidental conditions and, in this paper, an ensemble of three alternative invariant SA methods is innovatively set up for a SA on the TH code input variables. The ensemble aggregates the input variables raking orders provided by Pearson correlation ratio, Delta method and Beta method. The capability of the ensemble is shown on a BE–TH code of the Passive Containment Cooling System (PCCS) of an Advanced Pressurized water reactor AP1000, during a Loss Of Coolant Accident (LOCA), whose output probability density function (pdf) is approximated by a Finite Mixture Model (FMM), on the basis of a limited number of simulations. - Highlights: • We perform the reliability analysis of a passive safety system of Nuclear Power Plant (NPP). • We use a Thermal Hydraulic (TH) code for predicting the NPP response to accidents. • We propose an ensemble of Invariant Methods for the sensitivity analysis of the TH code • The ensemble aggregates the rankings of Pearson correlation, Delta and Beta methods. • The approach is tested on a Passive Containment Cooling System of an AP1000 NPP.

  7. Passive safety; Passive Sicherheit

    Energy Technology Data Exchange (ETDEWEB)

    Rueckert, J. [Skoda Auto a.s., Mlada Boleslav (Czech Republic). Interieurentwicklung und Versuche; Hau, M. [Skoda Auto a.s., Mlada Boleslav (Czech Republic). Koordination der Fahrzeugsicherung

    2004-05-01

    The specifications for passive safety are partly based on the legal requirements for all export markets combined with the strict internal standards of Volkswagen Group. The Euro NCAP tests and their precisely defined testing methods using the new point assessment are very important. (orig.)

  8. CLASSIFICATION OF SYSTEMS FOR PASSIVE AFTERHEAT REMOVAL FROM REACTOR CONTAINMENT OF NUCLEAR POWER PLANT WITH WATER-COOLED POWER REACTOR

    Directory of Open Access Journals (Sweden)

    N. Khaled

    2014-01-01

    Full Text Available A classification on systems for passive afterheat removal from reactor containment has been developed in the paper.  The classification permits to make a detailed analysis of various concepts pertaining to systems for passive afterheat removal from reactor containment of new generation. The paper considers main classification features of the given systems.

  9. Monitoring and documentation of practice biogas plants; Monitoring und Dokumentation von Praxis-Biogasanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Ebertseder, Florian; Kissel, Rainer; Lehner, Andreas; Rivera Gracia, Eunice; Bachmaier, Hans; Effenberger, Mathias

    2012-09-15

    The aim of the project is to extend the data base for the evaluation of biogas plants in terms of functionality and reliability of the technical equipment, the stability and efficiency of the fermentation process as well as the energy utilization. For the presented studies six companies were selected as examples. [German] Ziel des Projektes ist die Erweiterung der Datengrundlage zur Bewertung von Biogasanlagen hinsichtlich der Funktionalitaet und Zuverlaessigkeit der technischen Einrichtungen, der Stabilitaet und Leistungsfaehigkeit des Gaerprozesses sowie der Energieverwertung. Fuer die in diesem Bericht vorgestellten Untersuchungen wurden sechs Betriebe beispielhaft ausgewaehlt.

  10. High-Throughput Phenotyping of Wheat and Barley Plants Grown in Single or Few Rows in Small Plots Using Active and Passive Spectral Proximal Sensing

    OpenAIRE

    Barmeier, Gero;Schmidhalter, Urs

    2017-01-01

    In the early stages of plant breeding, breeders evaluate a large number of varieties. Due to limited availability of seeds and space, plot sizes may range from one to four rows. Spectral proximal sensors can be used in place of labour-intensive methods to estimate specific plant traits. The aim of this study was to test the performance of active and passive sensing to assess single and multiple rows in a breeding nursery. A field trial with single cultivars of winter barley and winter wheat w...

  11. Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

    Energy Technology Data Exchange (ETDEWEB)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a

  12. Preliminary Feasibility Assessment of Integrating CCHP with NW Food Processing Plant #1: Modeling Documentation

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, Michael G.; Srivastava, Viraj; Wagner, Anne W.; Makhmalbaf, Atefe; Thornton, John

    2014-01-01

    The Pacific Northwest National Laboratory (PNNL) has launched a project funded by the Bonneville Power Association (BPA) to identify strategies for increasing industrial energy efficiency and reducing energy costs of Northwest Food Processors Association (NWFPA) plants through deployment of novel combinations and designs of variable-output combined heat and power (CHP) distributed generation (DG), combined cooling, heating and electric power (CCHP) DG and energy storage systems. Detailed evaluations and recommendations of CHP and CCHP DG systems will be performed for several Northwest (NW) food processing sites. The objective is to reduce the overall energy use intensity of NW food processors by 25% by 2020 and by 50% by 2030, as well as reducing emissions and understanding potential congestion reduction impacts on the transmission system in the Pacific Northwest.

  13. Estimation of geochemical parameters for assessing subsurface transport at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    Looney, B.B.; Grant, M.W.; King, C.M.

    1987-03-01

    Geochemical parameter estimates to be used in assessing the subsurface transport of chemicals from Savannah River Plant (SRP) waste sites are presented. Specifically, reference values for soil-solution distribution coefficients, solubility, leach rates, and retardation coefficients are estimated for 31 inorganic chemicals (assuming speciation is governed by reasonable assumptions about controlling variables such as Eh and pH) and 36 organic compounds. Additionally, facilitated transport (the association of chemicals with inorganic and organic ligands or colloids resulting in relatively high mobility) was estimated using field data to derive a fraction of the disposal mass which was assumed to be mobile. Hydrologic parameters such as dispersion coefficient, average moisture content in vadose zone, bulk density, and effective porosity are also presented. The estimates are based on site-specific studies when available, combined with technical literature

  14. Documents for designing the emergency system for the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Machek, J.; Fiser, V.

    1993-12-01

    The organizational structure of the emergency system at the Temelin nuclear power plant is described and the responsibilities, principal assignments and number of personnel and their qualification are outlined; these include the Emergency Staff, emergency organization of the operator shift, Technical Support Center, External Emergency Support Center, and Operating Support Center. The emergency information system to secure personnel activities in emergency situations is also described. This consists of a critical safety function display system, a post-accident monitoring system, and a post-accident sampling system. The performance of the emergency support centers, their equipment with communications and computer hardware, and the number and qualification of personnel are also dealt with. The emergency classification is as follows: anomaly, incident, accident, major accident. The information and warning system is briefly described. A decision flow-chart for the assessment of emergency situations and their classification, including the complete algorithm for classifying accidents in the accident classification system, is given in the annex. (J.B.)

  15. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    International Nuclear Information System (INIS)

    Herborn, D.I.

    1993-11-01

    Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals

  16. Computerising documentation

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The nuclear power generation industry is faced with public concern and government pressures over safety, efficiency and risk. Operators throughout the industry are addressing these issues with the aid of a new technology - technical document management systems (TDMS). Used for strategic and tactical advantage, the systems enable users to scan, archive, retrieve, store, edit, distribute worldwide and manage the huge volume of documentation (paper drawings, CAD data and film-based information) generated in building, maintaining and ensuring safety in the UK's power plants. The power generation industry has recognized that the management and modification of operation critical information is vital to the safety and efficiency of its power plants. Regulatory pressure from the Nuclear Installations Inspectorate (NII) to operate within strict safety margins or lose Site Licences has prompted the need for accurate, up-to-data documentation. A document capture and management retrieval system provides a powerful cost-effective solution, giving rapid access to documentation in a tightly controlled environment. The computerisation of documents and plans is discussed in this article. (Author)

  17. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Volume 3: Comment response document

    International Nuclear Information System (INIS)

    1997-09-01

    The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy''s (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE''s Environmental Management Program. This volume provides responses to public comments on the Draft SEIS-II. Comments are related to: Alternatives; TRU waste; DOE credibility; Editorial; Endorsement/opposition; Environmental justice; Facility accidents; Generator site operations; Health and safety; Legal and policy issues; NEPA process; WIPP facilities; WIPP waste isolation performance; Purpose and need; WIPP operations; Site characterization; Site selection; Socioeconomics; and Transportation

  18. Remote Methodology used at B Plant Hanford to Map High Radiation and Contamination Fields and Document Remaining Hazards

    Energy Technology Data Exchange (ETDEWEB)

    SIMMONS, F.M.

    2000-01-01

    A remote radiation mapping system using the Gammacam{trademark} (AIL Systems Inc. Trademark) with real-time response was used in deactivating the B Plant at Hanford to produce digitized images showing actual radiation fields and dose rates. Deployment of this technology has significantly reduced labor requirements, decreased personnel exposure, and increased the accuracy of the measurements. Personnel entries into the high radiation/contamination areas was minimized for a dose savings of 30 Rem (.3 Seivert) and a cost savings of $640K. In addition, the data gathered was utilized along with historical information to estimate the amount of remaining hazardous waste in the process cells. The B Plant facility is a canyon facility containing 40 process cells which were used to separate cesium and strontium from high level waste. The cells and vessels are contaminated with chemicals used in the separation and purification processes. Most of the contaminants have been removed but the residual contamination from spills in the cells and heels in the tanks contribute to the localized high radioactivity. The Gammacam{trademark} system consists of a high density terbium-activated scintillating glass detector coupled with a digitized video camera. Composite images generated by the system are presented in pseudo color over a black and white image. Exposure times can be set from 10 milliseconds to 1 hour depending on the field intensity. This information coupled with process knowledge is then used to document the hazardous waste remaining in each cell. Additional uses for this radiation mapping system would be in support of facilities stabilization and deactivation activities at Hanford or other DOE sites. The system is currently scheduled for installation and mapping of the U Plant in 1999. This system is unique due to its portability and its suitability for use in high dose rate areas.

  19. Remote Methodology used at B Plant Hanford to Map High Radiation and Contamination Fields and Document Remaining Hazards

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    A remote radiation mapping system using the Gammacam(trademark) (AIL Systems Inc. Trademark) with real-time response was used in deactivating the B Plant at Hanford to produce digitized images showing actual radiation fields and dose rates. Deployment of this technology has significantly reduced labor requirements, decreased personnel exposure, and increased the accuracy of the measurements. Personnel entries into the high radiation/contamination areas was minimized for a dose savings of 30 Rem (.3 Seivert) and a cost savings of $640K. In addition, the data gathered was utilized along with historical information to estimate the amount of remaining hazardous waste in the process cells. The B Plant facility is a canyon facility containing 40 process cells which were used to separate cesium and strontium from high level waste. The cells and vessels are contaminated with chemicals used in the separation and purification processes. Most of the contaminants have been removed but the residual contamination from spills in the cells and heels in the tanks contribute to the localized high radioactivity. The Gammacam(trademark) system consists of a high density terbium-activated scintillating glass detector coupled with a digitized video camera. Composite images generated by the system are presented in pseudo color over a black and white image. Exposure times can be set from 10 milliseconds to 1 hour depending on the field intensity. This information coupled with process knowledge is then used to document the hazardous waste remaining in each cell. Additional uses for this radiation mapping system would be in support of facilities stabilization and deactivation activities at Hanford or other DOE sites. The system is currently scheduled for installation and mapping of the U Plant in 1999. This system is unique due to its portability and its suitability for use in high dose rate areas

  20. Passive radon daughter dosimeters

    International Nuclear Information System (INIS)

    McElroy, R.G.C.; Johnson, J.R.

    1986-03-01

    On the basis of an extensive review of the recent literature concerning passive radon daughter dosimeters, we have reached the following conclusions: 1) Passive dosimeters for measuring radon are available and reliable. 2) There does not presently exist an acceptable passive dosimeter for radon daughters. There is little if any hope for the development of such a device in the foreseeable future. 3) We are pessimistic about the potential of 'semi-passive dosimeters' but are less firm about stating categorically that these devices cannot be developed into a useful radon daughter dosimeter. This report documents and justifies these conclusions. It does not address the question of the worker's acceptance of these devices because at the present time, no device is sufficiently advanced for this question to be meaningful. 118 refs

  1. Fragility Analysis Methodology for Degraded Structures and Passive Components in Nuclear Power Plants - Illustrated using a Condensate Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y.; Kim, M.; Choi, I.

    2010-06-30

    The Korea Atomic Energy Research Institute (KAERI) is conducting a five-year research project to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). The KAERI research project includes three specific areas that are essential to seismic probabilistic risk assessment (PRA): (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. Since 2007, Brookhaven National Laboratory (BNL) has entered into a collaboration agreement with KAERI to support its development of seismic capability evaluation technology for degraded structures and components. The collaborative research effort is intended to continue over a five year period. The goal of this collaboration endeavor is to assist KAERI to develop seismic fragility analysis methods that consider the potential effects of age-related degradation of structures, systems, and components (SSCs). The research results of this multi-year collaboration will be utilized as input to seismic PRAs. In the Year 1 scope of work, BNL collected and reviewed degradation occurrences in US NPPs and identified important aging characteristics needed for the seismic capability evaluations. This information is presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and also designated as KAERI/RR-2931/2008. The report presents results of the statistical and trending analysis of this data and compares the results to prior aging studies. In addition, the report provides a description of U.S. current regulatory requirements, regulatory guidance documents, generic communications, industry standards and guidance, and past research related to aging degradation of SSCs. In the Year 2 scope of work, BNL carried out a research effort to identify and assess degradation models for the long-term behavior of dominant materials that are

  2. Preservation of FFTF Data Related to Passive Safety Testing

    International Nuclear Information System (INIS)

    Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.

    2010-01-01

    experience to a large-size LMR and obtain data for validating design analysis computer codes, and (3) to develop and test passive safety enhancements that might be used for future LMRs. These tests were designed to provide data sufficient to allow separation of fuel temperature effects from structural temperature effects. The data developed through this testing program were used to verify the predictive capability of passive safety analysis methods as well as provide a data base for calibrating design tools such as the SASSYS/SAS4A codes. These tests were instrumental in improving understanding of reactivity feedback mechanisms in LMRs and demonstrating passive safety margins available in an LMR. Knowledge preservation at the FFTF is focused on the areas of design, construction, startup, and operation of the reactor. This information may be of potential use for international exchanges with other LMR programs around the world. This information provides the basis for creating benchmarks for validating and testing large scale computer programs. All information preserved to date is now being stored and categorized consistent with the IAEA international standardized taxonomy. The test results information exists in several different formats depending upon the final stage of the test evaluation. Over 100 documents relevant to passive safety testing have been identified and are being recovered, scanned, and catalogued. Attempts to recover plant data tapes are also in progress. Documents related to passive safety testing are now being categorized consistent with internationally agreed upon IAEA standards. Documents are being converted to electronic format compatible with a general search engine being developed by INL. The data from the FFTF passive safety tests provides experimental verification of structural reactivity effects that should be very useful to innovative designers seeking to optimize passive safety in the design of new LMRs.

  3. Corrosion Inhibiting Mechanism of Nitrite Ion on the Passivation of Carbon Steel and Ductile Cast Iron for Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    K. T. Kim

    2015-01-01

    Full Text Available While NaNO2 addition can greatly inhibit the corrosion of carbon steel and ductile cast iron, in order to improve the similar corrosion resistance, ca. 100 times more NaNO2 addition is needed for ductile cast iron compared to carbon steel. A corrosion and inhibition mechanism is proposed whereby NO2- ion is added to oxidize. The NO2- ion can be reduced to nitrogen compounds and these compounds may be absorbed on the surface of graphite. Therefore, since nitrite ion needs to oxidize the surface of matrix and needs to passivate the galvanic corroded area and since it is absorbed on the surface of graphite, a greater amount of corrosion inhibitor needs to be added to ductile cast iron compared to carbon steel. The passive film of carbon steel and ductile cast iron, formed by NaNO2 addition showed N-type semiconductive properties and its resistance, is increased; the passive current density is thus decreased and the corrosion rate is then lowered. In addition, the film is mainly composed of iron oxide due to the oxidation by NO2- ion; however, regardless of the alloys, nitrogen compounds (not nitrite were detected at the outermost surface but were not incorporated in the inner oxide.

  4. Methodology for predictive modeling of environmental transport and health effects for waste sites at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    Stephensen, D.E.; King, C.M.; Looney, B.B.; Grant, M.W.

    1987-03-01

    This document provides information on the methods used to predict chemical transport and the associated health risk for various postulated closure activities at waste sites. The document was prepared as background documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the Savannah River Plant (SRP). The various mathematical formulations used in the environmental transport analysis, the exposure assessment, and the health risk assessment used in the analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (CFR, 1986) are presented in this document. The scenarios do not necessarily represent actual environmental conditions for every SRP waste site. This document was prepared in support of the National Environmental Policy Act process, but does not by itself satisfy federal or state regulatory requirements. 29 refs., 11 figs

  5. Measure Guideline: Passive Vents

    Energy Technology Data Exchange (ETDEWEB)

    Berger, David [Consortium for Advanced Residential Buildings, Norwalk, CT (United States); Neri, Robin [Consortium for Advanced Residential Buildings, Norwalk, CT (United States)

    2016-02-05

    This document addresses the use of passive vents as a source of outdoor air in multifamily buildings. The challenges associated with implementing passive vents and the factors affecting performance are outlined. A comprehensive design methodology and quantified performance metrics are provided. Two hypothetical design examples are provided to illustrate the process. This document is intended to be useful to designers, decision-makers, and contractors implementing passive ventilation strategies. It is also intended to be a resource for those responsible for setting high-performance building program requirements, especially pertaining to ventilation and outdoor air. To ensure good indoor air quality, a dedicated source of outdoor air is an integral part of high-performance buildings. Presently, there is a lack of guidance pertaining to the design and installation of passive vents, resulting in poor system performance. This report details the criteria necessary for designing, constructing, and testing passive vent systems to enable them to provide consistent and reliable levels of ventilation air from outdoors.

  6. Development and Validation of a SPME-GC-MS Method for In situ Passive Sampling of Root Volatiles from Glasshouse-Grown Broccoli Plants Undergoing Below-Ground Herbivory by Larvae of Cabbage Root Fly, Delia radicum L.

    Science.gov (United States)

    Deasy, William; Shepherd, Tom; Alexander, Colin J; Birch, A Nicholas E; Evans, K Andrew

    2016-11-01

    Research on plant root chemical ecology has benefited greatly from recent developments in analytical chemistry. Numerous reports document techniques for sampling root volatiles, although only a limited number describe in situ collection. To demonstrate a new method for non-invasive in situ passive sampling using solid phase micro extraction (SPME), from the immediate vicinity of growing roots. SPME fibres inserted into polyfluorotetrafluoroethylene (PTFE) sampling tubes located in situ which were either perforated, covered with stainless steel mesh or with microporous PTFE tubing, were used for non-invasive sub-surface sampling of root volatiles from glasshouse-grown broccoli. Sampling methods were compared with above surface headspace collection using Tenax TA. The roots were either mechanically damaged or infested with Delia radicum larvae. Principal component analysis (PCA) was used to investigate the effect of damage on the composition of volatiles released by broccoli roots. Analyses by gas chromatography-mass spectrometry (GC-MS) with SPME and automated thermal desorption (ATD) confirmed that sulphur compounds, showing characteristic temporal emission patterns, were the principal volatiles released by roots following insect larval damage. Use of SPME with in situ perforated PTFE sampling tubes was the most robust method for out-of-lab sampling. This study describes a new method for non-invasive passive sampling of volatiles in situ from intact and insect damaged roots using SPME. The method is highly suitable for remote sampling and has potential for wide application in chemical ecology/root/soil research. Copyright © 2016 John Wiley & Sons, Ltd. Copyright © 2016 John Wiley & Sons, Ltd.

  7. Passive Education

    Science.gov (United States)

    Bojesen, Emile

    2018-01-01

    This paper does not present an advocacy of a passive education as opposed to an active education nor does it propose that passive education is in any way 'better' or more important than active education. Through readings of Maurice Blanchot, Jacques Derrida and B.S. Johnson, and gentle critiques of Jacques Rancière and John Dewey, passive…

  8. HERMES: A tool to prepare documentation for access to plants; HERMES: Una Herramienta para la preparacion de la documentacion de acceso a las plantas

    Energy Technology Data Exchange (ETDEWEB)

    Serrano Vizcaino, J.; Rodriguez Montalban, J. R.; Garcia Valcarcel, M.

    2012-07-01

    The appearance of the IS-12 standard has marked a before and after in the entry requirements to the plants. Its impact, in companies like Tecnatom that mobilizing a large number of people to perform services during refueling stops, has forced the design of a tool to help prepare the personnel access documentation in an in a flexible and efficient.

  9. Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, In Kil; Kim, Min Kyu; Hofmayer, Charles; Braverman, Joseph; Nie, Jinsuo

    2009-03-01

    This report describes the research effort performed by BNL for the Year 2 scope of work. This research focused on methods that could be used to represent the long-term behavior of materials used at NPPs. To achieve this BNL reviewed time-dependent models which can approximate the degradation effects of the key materials used in the construction of structures and passive components determined to be of interest in the Year 1 effort. The intent was to review the degradation models that would cover the most common time-dependent changes in material properties for concrete and steel components

  10. Documentation and quantitative analysis of the local knowledge on medicinal plants in Kalrayan hills of Villupuram district, Tamil Nadu, India.

    Science.gov (United States)

    Prabhu, S; Vijayakumar, S; Yabesh, J E Morvin; Ravichandran, K; Sakthivel, B

    2014-11-18

    The aim of the present study was to document the medicinal plants by the traditional medical practitioners from Kalrayan hills of Villupuram district in Tamil Nadu, India. Quantitatively analyses of the data were made to acquire some useful leads for further studies. Successive free listing was the method adopted for the interview. In this study, 54 traditional healer medical practitioners were included and their knowledge on medicinal plants was gathered. The data were assessed with the help of two indices viz., informant consensus factor (Fic) and Informant Agreement on Remedies (IAR). The present survey is in accordance with some of the aspects of our previous surveys. Regarding the demography of the informants, it exhibited unevenness in male-female ratio and majority of the informants were poorly educated. Practicing this system of medicine as part time job by majority of the informants might indicate the reduced social status of this medicinal system. The present study had recorded the usage of 81 species, which in turn yielded 1073 use reports. The major illness category 'aphrodisiac, hair care and endocrinal disorders' hold a high Fic values. Among the other illness categories, gastro-intestinal ailments, genito-urinary ailments and dermatological infection ailments have a high percentage of use reports. Eye ailments, general health, kapha ailments, psychological ailments and skeleton muscular system ailments were the other illness categories with high Fic values. Some of the claims viz., Argyrolobium roseum (aphrodisiac ailments), Rosa brunonii (eye ailments) Hibiscus surattensis (dermatological infections ailments), Bauhinia variegata (neurology Ailments), Cotinus coggygria (circulatory system/cardiovascular ailments) and Uvaria narum (gastro-intestinal ailments) which have relatively high consensus can be taken up for further biomedical studies, since no substantial studies have been conducted on them. Based on the results of our present study, we have

  11. Administrative Reorganization, Modification And Enlargement The Personal Plant And The Functions Manual Of The Documentation Center And Nuclear Information Of The Institute Of Nuclear Matters

    International Nuclear Information System (INIS)

    De Escobar, Cecilia

    1991-01-01

    This document is a project of administrative reorganization, modification and amplification of the personal plant and the functions manual of of the Center of Documentation and Nuclear Information of the IAN. The methodology used to develop this work was constituted by an analysis of the statutes and objectives of the institution. A study of the objectives that the CDIN of the flowchart of the IAN should complete. Interview with the Boss of the CDIN to define necessities as soon as administrative organization, modification of the plant of personal and of the manual of functions of the Center, interview the officials of the Documentation Center, tending efficiently to gather information on the current conditions of work and their proposals for the benefit of the more services. Surveys of the Center users to diagnose like they are come lending the services and their recommendations for the improvement of the same ones

  12. Preliminary analysis of the inclusion of security passive systems to reduce the impact of accidents in nuclear power plants

    International Nuclear Information System (INIS)

    Sanchez J, J.; Morales S, J. B.; Espinosa P, G.

    2011-11-01

    In this work is presented a conceptual analysis of possible benefits and limitations that potentially represents the introduction of security passive systems to reduce the events impact of very low probability and high risk to the systems of radioactive material confinement of a light water reactor. These events are related with the possibility that a hydrogen explosion is presented as consequence of the accumulation of the same hydrogen in the contention of the reactor, in a scenario of severe accident. This accumulated hydrogen can be liberated in the reactor building or primary contention, where the conditions of their atmosphere make but prone the combustion. The catalytic recombination represents a viable option for the hydrogen concentrations decrease and because this recombination is highly exothermic, is important to analyze and to know if the recombined vapor to high temperature can be used in combination with vapor injectors that in turn, they are passive systems. In the following sections an explanation is presented about the use of the mentioned systems, as well as some results on the behavior of the vapor injectors. (Author)

  13. Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II

    International Nuclear Information System (INIS)

    Jarvio C, G.; Fernandez S, G.

    2008-01-01

    Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

  14. Annual report on the environmental radiation monitoring around Tokai Reprocessing Plant. FY 2001. Document on present state of affairs

    International Nuclear Information System (INIS)

    Shinohara, Kunihiko; Takeishi, Minoru; Miyagawa, Naoto

    2002-06-01

    Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed since 1975, based on ''Safety Regulations for the Tokai Reprocessing Plant, Chapter IV - Environmental Monitoring''. This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant during April 2001 to March 2002. Appendices present comprehensive information, such as monitoring program, monitoring results, meteorological data and annual discharges from the plant. (author)

  15. 78 FR 47805 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Science.gov (United States)

    2013-08-06

    ... Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Revision... Used in Safety Systems of Nuclear Power Plants.'' This RG endorses the Institute of Electrical and... nuclear power plants. ADDRESSES: Please refer to Docket ID NRC-2012-0195 when contacting the NRC about the...

  16. 77 FR 50720 - Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

    Science.gov (United States)

    2012-08-22

    ... Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft... Computer Software used in Safety Systems of Nuclear Power Plants.'' The DG-1207 is proposed Revision 1 of... for Digital Computer Software Used in Safety Systems of Nuclear Power Plants'' is temporarily...

  17. Passive containment system

    International Nuclear Information System (INIS)

    Kleimola, F.W.

    1977-01-01

    Disclosed is a containment system that provides complete protection entirely by passive means for the loss of coolant accident in a nuclear power plant and wherein all stored energy released in the coolant blowdown is contained and absorbed while the nuclear fuel is prevented from over-heating by a high containment back-pressure and a reactor vessel refill system. The primary containment vessel is restored to a high sub-atmospheric pressure within a few minutes after accident initiation and the decay heat is safely transferred to the environment while radiolytic hydrogen is contained by passive means. 20 claims, 14 figures

  18. Operator-centered technical documentation of the power plant control system. Betreibergerechte, betriebstechnische Dokumentation der Kraftwerks-Leittechnik

    Energy Technology Data Exchange (ETDEWEB)

    Welfonder, E

    1986-01-01

    The report - starting with an overview of the general structure of documentation - includes in chapter 3 an assortment of the main expectations to be had by the technical staff towards control system documentation. These are divided into: general basic requirements; testable compulsory requirements; practical recommendations and information for the manufacturer. In chapter 4 these documentation requirements are reflected to the present state of technical documentation. The main emphasis of the report however is laid on the sample documentation for one control system area presented in chapter 5. This sample documentation is based on a hierarchically structured and function related documentary method developed by the University of Stuttgart on the basis of the derived requirements and the present usual control system documentation. This function-related documentary method proves to be useful, not only for the technical staff in his rapid search for control system disturbances, but also offers - due to its clear and homogeneous meshed structure - considerable advantages for control system planning, projecting and initial start ups. As the presented documentation method is furthermore independent of the control system manufacturers, it is important that all participants try to use it uniformly.

  19. Creating and Evaluating a Hypertext System of Documenting Analytical Test Methods in a Chemical Plant Quality Assurance Laboratory.

    Science.gov (United States)

    White, Charles E., Jr.

    The purpose of this study was to develop and implement a hypertext documentation system in an industrial laboratory and to evaluate its usefulness by participative observation and a questionnaire. Existing word-processing test method documentation was converted directly into a hypertext format or "hyperdocument." The hyperdocument was designed and…

  20. 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

  1. Performance Evaluation of the Concept of Hybrid Heat Pipe as Passive In-core Cooling Systems for Advanced Nuclear Power Plant

    International Nuclear Information System (INIS)

    Jeong, Yeong Shin; Kim, Kyung Mo; Kim, In Guk; Bang, In Cheol

    2015-01-01

    As an arising issue for inherent safety of nuclear power plant, the concept of hybrid heat pipe as passive in-core cooling systems was introduced. Hybrid heat pipe has unique features that it is inserted in core directly to remove decay heat from nuclear fuel without any changes of structures of existing facilities of nuclear power plant, substituting conventional control rod. Hybrid heat pipe consists of metal cladding, working fluid, wick structure, and neutron absorber. Same with working principle of the heat pipe, heat is transported by phase change of working fluid inside metal cask. Figure 1 shows the systematic design of the hybrid heat pipe cooling system. In this study, the concept of a hybrid heat pipe was introduced as a Passive IN-core Cooling Systems (PINCs) and demonstrated for internal design features of heat pipe containing neutron absorber. Using a commercial CFD code, single hybrid heat pipe model was analyzed to evaluate thermal performance in designated operating condition. Also, 1-dimensional reactor transient analysis was done by calculating temperature change of the coolant inside reactor pressure vessel using MATLAB. As a passive decay heat removal device, hybrid heat pipe was suggested with a concept of combination of heat pipe and control rod. Hybrid heat pipe has distinct feature that it can be a unique solution to cool the reactor when depressurization process is impossible so that refueling water cannot be injected into RPV by conventional ECCS. It contains neutron absorber material inside heat pipe, so it can stop the reactor and at the same time, remove decay heat in core. For evaluating the concept of hybrid heat pipe, its thermal performance was analyzed using CFD and one-dimensional transient analysis. From single hybrid heat pipe simulation, the hybrid heat pipe can transport heat from the core inside to outside about 18.20 kW, and total thermal resistance of hybrid heat pipe is 0.015 .deg. C/W. Due to unique features of long heat

  2. A Procedure for Determination of Degradation Acceptance Criteria for Structures and Passive Components in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Nie, J.; Braverman, J.; Hofmayer, C.; Choun, Y-S.; Hahm, D.; Choi, I-K.

    2012-01-30

    The Korea Atomic Energy Research Institute (KAERI) has been collaborating with Brookhaven National Laboratory since 2007 to develop a realistic seismic risk evaluation system which includes the consideration of aging of structures and components in nuclear power plants (NPPs). This collaboration program aims at providing technical support to a five-year KAERI research project, which includes three specific areas that are essential to seismic probabilistic risk assessment: (1) probabilistic seismic hazard analysis, (2) seismic fragility analysis including the effects of aging, and (3) a plant seismic risk analysis. The understanding and assessment of age-related degradations of structures, systems, and components and their impact on plant safety is the major goal of this KAERI-BNL collaboration. Four annual reports have been published before this report as a result of the collaboration research.

  3. Experimental Study of Hydraulic Control Rod Drive Mechanism for Passive IN-core Cooling System of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin; Bang, In Cheol [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    CAREM 25 (27 MWe safety systems using hydraulic control rod drives (CRD) studied critical issues that were rod drops with interrupted flow [3]. Hydraulic control rod drive suggested fast shutdown condition using a large gap between piston and cylinder in order to fast drop of neutron absorbing rods. A Passive IN-core Cooling system (PINCs) was suggested for safety enhancement of pressurized water reactors (PWR), small modular reactor (SMR), sodium fast reactor (SFR) in UNIST. PINCs consist of hydraulic control rod drive mechanism (Hydraulic CRDM) and hybrid control rod assembly with heat pipe combined with control rod. The schematic diagram of the hydraulic CRDM for PINCs is shown in Fig. 1. The experimental results show the steady state and transient behavior of the upper cylinder at a low pressure and low temperature. The influence of the working fluid temperature and cylinder mass are investigated. Finally, the heat removal between evaporator section and condenser section is compared with or without the hybrid control rod. Heat removal test of the hybrid heat pipe with hydraulic CRDM system showed the heat transfer coefficient of the bundle hybrid control rod and its effect on evaporator pool. The preliminary test both hydraulic CRDM and heat removal system was conducted, which showed the possibility of the in-core hydraulic drive system for application of PINCs.

  4. New Low-Level Radioactive Waste Storage/Disposal Facilities at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    Cook, J.R.; Grant, M.W.; Towler, O.O.

    1987-04-01

    Site selection, alternative facilities, and alternative operations are described for a new low-level solid radioactive waste storage/disposal operation at the Savannah River Plant. Performance assessments and cost estimates for the alternatives are presented. Appendix G contains an intensive archaeological survey of alternative waste disposal areas in the Savannah River Plant area. 117 refs., 99 figs., 128 tabs

  5. WIPP documentation plan

    International Nuclear Information System (INIS)

    Plung, D.L.; Montgomery, T.T.; Glasstetter, S.R.

    1986-01-01

    In support of the programs at the Waste Isolation Pilot Plant (WIPP), the Publications and Procedures Section developed a documentation plan that provides an integrated document hierarchy; further, this plan affords several unique features: 1) the format for procedures minimizes the writing responsibilities of the technical staff and maximizes use of the writing and editing staff; 2) review cycles have been structured to expedite the processing of documents; and 3) the numbers of documents needed to support the program have been appreciably reduced

  6. ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

    International Nuclear Information System (INIS)

    2000-01-01

    The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

  7. Environmental information document: New hazardous and mixed waste storage/disposal facilities at the Savannah River Plant

    International Nuclear Information System (INIS)

    Cook, J.R.; Grant, M.W.; Towler, O.O.

    1987-04-01

    Site selection, alternative facilities and alternative operations are described for new hazardous and mixed waste storage/disposal facilities at the Savannah River Plant. Performance assessments and cost estimates for the alternatives are presented

  8. Hood River Passive House

    Energy Technology Data Exchange (ETDEWEB)

    Hales, David [BA-PIRC, Spokane, WA (United States)

    2014-01-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to "reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project. The design includes high R-Value assemblies, extremely tight construction, high performance doors and windows, solar thermal DHW, heat recovery ventilation, moveable external shutters and a high performance ductless mini-split heat pump. Cost analysis indicates that many of the measures implemented in this project did not meet the BA standard for cost neutrality. The ductless mini-split heat pump, lighting and advanced air leakage control were the most cost effective measures. The future challenge will be to value engineer the performance levels indicated here in modeling using production based practices at a significantly lower cost.

  9. In-plant measurements of gamma-ray transmissions for precise K-edge and passive assay of plutonium concentration and isotopic abundance in product solutions at the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Asakura, Y.; Kondo, I.; Masui, J.; Shoji, K.; Russo, P.A.; Hsue, S.T.; Sprinkle, J.K. Jr.; Johnson, S.S.

    1982-01-01

    A field test has been carried out for more than 2 years for determination of plutonium concentration by K-edge absorption densitometry and for determination of plutonium isotopic abundance by transmission-corrected passive gamma-ray spectrometry. This system was designed and built at Los Alamos National Laboratory and installed at the Tokai reprocessing plant of the Power Reactor and Nuclear Fuel Development Corporation as a part of the Tokai Advanced Safeguards Technology Exercise (TASTEX). For K-edge measurement of plutonium concentration, the transmissions at two discrete gamma-ray energies are measured using the 121.1- and 122.1-keV gamma rays from 75 Se and 57 Co. Intensities of the plutonium passive gamma rays in the energy regions between 38 and 51 keV and between 129 and 153 keV are used for determination of the isotopic abundances. More than 200 product solution samples have been measured in a timely fashion during these 2 years. The relative precisions and accuracies of the plutonium concentration measurement are shown to be within 0.6% (1 sigma) in these applications, and those for plutonium isotopic abundances are within 3% for 238 Pu, 0.4% for 239 Pu, 1.2% for 240 Pu, 1.3% for 241 Pu, and 7% for 242 Pu. The time required is 10 min for the concentration assay, 10 min for the isotopics assay, and about 15 min for handling procedures in the laboratory

  10. Model of dispersion of a passive species in a reservoir with application to radionuclides discharged from the Browns Ferry Nuclear Plant

    International Nuclear Information System (INIS)

    Almquist, C.W.; Harper, W.L.; Ungate, C.D.; Ferrick, M.G.

    1977-04-01

    An accidental release of a quantity of radioactive material took place from the Browns Ferry Nuclear Plant RHRS into Wheeler Reservoir from 1945 CST on January 4, 1977, until 0200 CST on January 5. The Water Systems Development Branch was requested to predict both the location of the effluent patch as it progressed down Wheeler Reservoir and the concentration distribution within the patch. Of particular interest were the time of arrival and concentrations expected at the nearest downstream public water supply, located on the left bank at TRM 282.2. Preliminary calculations indicated that a two-dimensional (horizontal plane), unsteady model was required to adequately model the diffusion and advection processes. A Gaussian Puff type model was developed for this purpose, employing the existing TVA Simulated Open Channel Hydraulic Model for the calculation of the unsteady reservoir flows. Major results from this model were as follows: (1) the effluent patch was predicted to reach the nearest downstream public water supply at 1800 CST on January 6, approximately 46 hours after the start of the release; (2) the maximum radionuclide concentration in the reservoir at this time was predicted to be approximately 10 -4 of the initial concentration; this would occur at the right bank; and because of the relatively slow transverse mixing, it was predicted that, for practical purposes, the effluent would not have reached the left bank by the time it reached TRM 282.2. In addition, hourly predictions for the location of the effluent patch were made. It was felt that the concentration predictions were somewhat conservative, but were realistic. The model presented in this report is applicable to any passive species and will be further refined to provide more accurate mixing estimates in future applications

  11. SGHWR - quality assurance documentation

    International Nuclear Information System (INIS)

    Garrard, R.S.; Caulfield, J.

    1976-01-01

    The quality assurance program for a modern power station such as an SGHWR type reactor plant must include a record of quality achievement. The case history record which is evidence of the actual quality of the plant and is a data bank of design, manufacture, and results of inspections and tests, is described. Documentation distribution, which keeps all key areas informed of plant item quality status, and the retrieval and storage of information, are briefly discussed. (U.K.)

  12. Passive heat removal in CANDU

    International Nuclear Information System (INIS)

    Hart, R.S.

    1997-01-01

    CANDU has a tradition of incorporating passive systems and passive components whenever they are shown to offer performance that is equal to or better than that of active systems, and to be economic. Examples include the two independent shutdown systems that employ gravity and stored energy respectively, the dousing subsystem of the CANDU 6 containment system, and the ability of the moderator to cool the fuel in the event that all coolant is lost from the fuel channels. CANDU 9 continues this tradition, incorporating a reserve water system (RWS) that increases the inventory of water in the reactor building and profiles a passive source of makeup water and/or heat sinks to various key process systems. The key component of the CANDU 9 reserve water system is a large (2500 cubic metres) water tank located at a high elevation in the reactor building. The reserve water system, while incorporating the recovery system functions, and the non-dousing functions of the dousing tank in CANDU 6, embraces other key systems to significantly extend the passive makeup/heat sink capability. The capabilities of the reserve water system include makeup to the steam generators secondary side if all other sources of water are lost; makeup to the heat transport system in the event of a leak in excess of the D 2 O makeup system capability; makeup to the moderator in the event of a moderator leak when the moderator heat sink is required; makeup to the emergency core cooling (ECC) system to assure NPSH to the ECC pumps during a loss of coolant accident (LOCA), and provision of a passive heat sink for the shield cooling system. Other passive designs are now being developed by AECL. These will be incorporated in future CANDU plants when their performance has been fully proven. This paper reviews the passive heat removal systems and features of current CANDU plants and the CANDU 9, and briefly reviews some of the passive heat removal concepts now being developed. (author)

  13. Methodology and parameters for assessing human health effects for waste sites at the Savannah River Plant: Environmental information document

    International Nuclear Information System (INIS)

    King, C.M.; Marter, W.L.; Looney, B.B.; Pickett, J.B.

    1987-03-01

    This report provides a summary of the components of risk assessment and presents the technical basis for application of the risk evaluation process to the principal pollutants at SRP: radionuclides, toxic chemicals, and carcinogenic compounds. An extensive technical data base from the fields of radiation health physics, toxicology, and environmental sciences is required to accomplish this task. The origin and meaning of this data base is summarized for each class of contaminant and parameter values provided for use in numerical analysis of risk. The process of risk assessment is associated with uncertainties, a fact which is frequently stated in the technical literature addressing this subject. A review of risk assessment uncertainties and the limitations of predictive risk assessment are summarized. Risk estimators for each class of contaminants at the SRP have been tabulated for radionuclides, toxic chemicals, and carcinogens from the technical literature. Estimation of human health risk is not an additive process for radiation effects and chemical carcinogenesis since their respective dosimetric models are distinctly different even though the induction of cancer is reported to be the common end result. It is recommended in this report that risk estimation for radionuclides and chemical carcinogens should be tabulated separately and this recommendation has been applied in all environmental information documentation published by the Savannah River Laboratory. Impacts due to toxic chemicals in the biosphere should also be estimated as a separate entity since toxic chemical risk estimators are uniquely different and do not reflect the probability of a detrimental health effect. 23 refs., 4 figs., 13 tabs

  14. Nuclear Power Plant with VK-300 Reactor. Simplicity and Passivity as a Way to Provide Enhanced Safety and Economic Competitive Ability

    International Nuclear Information System (INIS)

    Kuznetsov, Y. N.; Lisitsa, F. D.; Tokarev, Y. I.; Glazkov, O. M.

    1998-01-01

    NPP with simplified boiling reactors with coolant natural circulation is developed by RDIPE. removal of residual heat releases under any emergency conditions is supposed to be put into effect with maximum application of passive systems and devices. (author)

  15. Compositional properties of passivity

    NARCIS (Netherlands)

    Kerber, Florian; van der Schaft, Arjan

    2011-01-01

    The classical passivity theorem states that the negative feedback interconnection of passive systems is again passive. The converse statement, - passivity of the interconnected system implies passivity of the subsystems -, turns out to be equally valid. This result implies that among all feasible

  16. Standardization Documents

    Science.gov (United States)

    2011-08-01

    Specifications and Standards; Guide Specifications; CIDs; and NGSs . Learn. Perform. Succeed. STANDARDIZATION DOCUMENTS Federal Specifications Commercial...national or international standardization document developed by a private sector association, organization, or technical society that plans ...Maintain lessons learned • Examples: Guidance for application of a technology; Lists of options Learn. Perform. Succeed. DEFENSE HANDBOOK

  17. Passive containment system in high earthquake motion

    International Nuclear Information System (INIS)

    Kleimola, F.W.; Falls, O.B. Jr.

    1977-01-01

    High earthquake motion necessitates major design modifications in the complex of plant structures, systems and components in a nuclear power plant. Distinctive features imposed by seismic category, safety class and quality classification requirements for the high seismic ground acceleration loadings significantly reflect in plant costs. The design features in the Passive Containment System (PCS) responding to high earthquake ground motion are described

  18. MIDAS documentation

    International Nuclear Information System (INIS)

    Seeman, S.E.

    1981-09-01

    MIDAS, the Master Information and Data Acquisition System, is a computerized system being implemented on FFTF to control the work released to the plant. The purpose of this system is to demonstrate the safety enhancement provided for LMFBRs when the operator has instant recall to the status of all work released to the plant, the interrelationships between functional equipment groups in the plant, and the relationships of equipment to safety functions

  19. Maury Documentation

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Supporting documentation for the Maury Collection of marine observations. Includes explanations from Maury himself, as well as guides and descriptions by the U.S....

  20. Documentation Service

    International Nuclear Information System (INIS)

    Charnay, J.; Chosson, L.; Croize, M.; Ducloux, A.; Flores, S.; Jarroux, D.; Melka, J.; Morgue, D.; Mottin, C.

    1998-01-01

    This service assures the treatment and diffusion of the scientific information and the management of the scientific production of the institute as well as the secretariat operation for the groups and services of the institute. The report on documentation-library section mentions: the management of the documentation funds, search in international databases (INIS, Current Contents, Inspects), Pret-Inter service which allows accessing documents through DEMOCRITE network of IN2P3. As realizations also mentioned are: the setup of a video, photo database, the Web home page of the institute's library, follow-up of digitizing the document funds by integrating the CD-ROMs and diskettes, electronic archiving of the scientific production, etc

  1. Passive solar technology

    Energy Technology Data Exchange (ETDEWEB)

    Watson, D

    1981-04-01

    The present status of passive solar technology is summarized, including passive solar heating, cooling and daylighting. The key roles of the passive solar system designer and of innovation in the building industry are described. After definitions of passive design and a summary of passive design principles are given, performance and costs of passive solar technology are discussed. Passive energy design concepts or methods are then considered in the context of the overall process by which building decisions are made to achieve the integration of new techniques into conventional design. (LEW).

  2. Passive Safety Features for Small Modular Reactors

    International Nuclear Information System (INIS)

    Ingersoll, Daniel T.

    2010-01-01

    The rapid growth in the size and complexity of commercial nuclear power plants in the 1970s spawned an interest in smaller, simpler designs that are inherently or intrinsically safe through the use of passive design features. Several designs were developed, but none were ever built, although some of their passive safety features were incorporated into large commercial plant designs that are being planned or built today. In recent years, several reactor vendors are actively redeveloping small modular reactor (SMR) designs with even greater use of passive features. Several designs incorporate the ultimate in passive safety they completely eliminate specific accident initiators from the design. Other design features help to reduce the likelihood of an accident or help to mitigate the accidents consequences, should one occur. While some passive safety features are common to most SMR designs, irrespective of the coolant technology, other features are specific to water, gas, or liquid-metal cooled SMR designs. The extensive use of passive safety features in SMRs promise to make these plants highly robust, protecting both the general public and the owner/investor. Once demonstrated, these plants should allow nuclear power to be used confidently for a broader range of customers and applications than will be possible with large plants alone.

  3. Active and passive cooling methods for dwellings

    DEFF Research Database (Denmark)

    Oropeza-Perez, Ivan; Østergaard, Poul Alberg

    2018-01-01

    In this document a review of three active as well as ten passive cooling methods suitable for residential buildings is carried out. The review firstly addresses how the various technologies cool the space according to the terms of the building heat balance, under what technical conditions...... ventilation, controlled ventilation, roof coating and eco-evaporative cooling are the most suitable passive methods for an extensive use in this country....

  4. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant; Analisis de documentos de los materiales de la envolvente del nucleo del reactor nuclear de la CLV U-1

    Energy Technology Data Exchange (ETDEWEB)

    Zamora R, L.; Medina F, A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  5. Fundamental studies of passivity and passivity breakdown

    International Nuclear Information System (INIS)

    Macdonald, D.D.; Urquidi-Macdonald, M.; Song, H.; Biaggio-Rocha, S.; Searson, P.

    1991-11-01

    This report summarizes the findings of our fundamental research program on passivity and passivity breakdown. During the past three and one half years in this program (including the three year incrementally-funded grant prior to the present grant), we developed and experimentally tested various physical models for the growth and breakdown of passive films on metal surfaces. These models belong to a general class termed ''point defects models'' (PDMs), in which the growth and breakdown of passive films are described in terms of the movement of anion and cation vacancies

  6. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted.   CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat a...

  7. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the natu...

  8. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the natur...

  9. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ Management- CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management - CB - MB - FB Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2007 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of employment and ...

  10. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ Management- CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management - CB - MB - FB Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2007 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of em¬pl...

  11. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the iCMS Web site. The following items can be found on: http://cms.cern.ch/iCMS/ General - CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. LHC Symposiums Management - CB - MB - FB - FMC Agendas and minutes are accessible to CMS members through their AFS account (ZH). However some linked documents are restricted to the Board Members. FB documents are only accessible to FB members. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2006 Annual reviews are posted. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral students upon completion of their theses. Therefore it is requested that Ph.D students inform the CMS Secretariat about the na...

  12. Passive systems for light water reactors

    International Nuclear Information System (INIS)

    Adinolfi, R.; Noviello, L.

    1990-01-01

    The paper reviews the most original concepts that have been considered in Italy for the back-fitting of the nuclear power plants in order to reduce the probability and the importance of the release to the environment in case of a core melt. With reference either to BWR or PWR, passive concepts have been considered for back-fitting in the following areas: pump seals damage prevention and ECCS passive operation; reactor passive depressurization; molten reactor core passive cooling; metal containment passive water cooling through a water tank located at high level; containment isolation improvement through a sealing system; containment leaks control and limitation of environmental release. In addition some considerations will be made on the protection against external events introduced from the beginning on the PUN design either on building and equipment lay-out either on structure design. (author). 5 figs

  13. Assessment of ALWR passive safety system reliability. Phase 1: Methodology development and component failure quantification

    International Nuclear Information System (INIS)

    Hake, T.M.; Heger, A.S.

    1995-04-01

    Many advanced light water reactor (ALWR) concepts proposed for the next generation of nuclear power plants rely on passive systems to perform safety functions, rather than active systems as in current reactor designs. These passive systems depend to a great extent on physical processes such as natural circulation for their driving force, and not on active components, such as pumps. An NRC-sponsored study was begun at Sandia National Laboratories to develop and implement a methodology for evaluating ALWR passive system reliability in the context of probabilistic risk assessment (PRA). This report documents the first of three phases of this study, including methodology development, system-level qualitative analysis, and sequence-level component failure quantification. The methodology developed addresses both the component (e.g. valve) failure aspect of passive system failure, and uncertainties in system success criteria arising from uncertainties in the system's underlying physical processes. Traditional PRA methods, such as fault and event tree modeling, are applied to the component failure aspect. Thermal-hydraulic calculations are incorporated into a formal expert judgment process to address uncertainties in selected natural processes and success criteria. The first phase of the program has emphasized the component failure element of passive system reliability, rather than the natural process uncertainties. Although cursory evaluation of the natural processes has been performed as part of Phase 1, detailed assessment of these processes will take place during Phases 2 and 3 of the program

  14. Tracing early breccia pipe studies, Waste Isolation Pilot Plant, southeastern New Mexico: A study of the documentation available and decision-making during the early years of WIPP

    International Nuclear Information System (INIS)

    Power, D.W.

    1996-01-01

    Breccia pipes in southeastern New Mexico are local dissolution-collapse features that formed over the Capitan reef more than 500,000 years ago. During early site studies for the Waste Isolation Pilot Plant (WIPP), the threat to isolation by these features was undetermined. Geophysical techniques, drilling, and field mapping were used beginning in 1976 to study breccia pipes. None were found at the WIPP site, and they are considered unlikely to be a significant threat even if undetected. WIPP documents related to breccia pipe studies were assembled, inspected, and analyzed, partly to present a history of these studies. The main objective is to assess how well the record reflects the purposes, results, and conclusions of the studies from concept to decision-making. The main record source was the Sandia WIPP Central File (SWCF). Early records (about 1975 to 1977) are very limited, however, about details of objectives and plans predating any investigation. Drilling programs from about 1977 were covered by a broadly standardized statement of work, field operations plan, drilling history, and basic data report. Generally standardized procedures for peer, management, and quality assurance review were developed during this time. Agencies such as the USGS conducted projects according to internal standards. Records of detailed actions for individual programs may not be available, though a variety of such records were found in the SWCF. A complete written record cannot be reconstructed. With persistence, a professional geologist can follow individual programs, relate data to objectives (even if implied), and determine how conclusions were used in decision-making. 83 refs

  15. K-BREF(Korean BAT reference document) development : BAT and BAT-AELs for large combustion plants and waste incinerators in Korea.

    Science.gov (United States)

    Yoo, Heungmin; Lee, Daegyun; Park, Jaehong

    2017-04-01

    Since the initial environmental policy namely "Regulation on assigning license for environmental pollutant emission facilities" was introduced in 1971, the previous environmental policy that assign licenses on emission facilities of each pollutant has been implementing in Korea. From this, economic standard and environmental quality of Korea are recognized as level of developed countries, even though various development activities for industrialization. However, amount of pollutant, emission route and emission source are increasing with development of various industries, and citizens recognition for environment have been changed as well. Thus, ministry of environment of Korea needs systematic policy based on scientific grounds for conversion of paradigm. For this, ministry of environment was introduced new policy namely "integrated pollution prevention and control(IPPC)", and it will be implemented from 2017 in Korea. IPPC is established for considering environment, economic and efficiency: 10 licenses on each pollutant emission will be integrated to one license, and it can be expected simplification for business licensing process. As well, this policy can be upgraded and processed while considering characteristics on location and industry types, in the future. However, to conduct this system harmoniously, policy demanders have to apply integrated control system to their facilities. Especially, the first applied industries by IPPC are two industries, such as large combustion plants for power generation and waste incineration facilities. Therefore, ministry of environment has to publish technical guideline books firstly for those industries, and they were named to "BAT reference document(BREF)". In this study, essential information for BREFs publishment, that is including emission levels, best available technique(BAT) and so on was investigated. In addition, the BAT-associated emission levels (BAT-AELs) of each industry were set using emission data obtained from

  16. Tracing early breccia pipe studies, Waste Isolation Pilot Plant, southeastern New Mexico: A study of the documentation available and decision-making during the early years of WIPP

    Energy Technology Data Exchange (ETDEWEB)

    Power, D.W. [HC 12, Anthony, TX (United States)

    1996-01-01

    Breccia pipes in southeastern New Mexico are local dissolution-collapse features that formed over the Capitan reef more than 500,000 years ago. During early site studies for the Waste Isolation Pilot Plant (WIPP), the threat to isolation by these features was undetermined. Geophysical techniques, drilling, and field mapping were used beginning in 1976 to study breccia pipes. None were found at the WIPP site, and they are considered unlikely to be a significant threat even if undetected. WIPP documents related to breccia pipe studies were assembled, inspected, and analyzed, partly to present a history of these studies. The main objective is to assess how well the record reflects the purposes, results, and conclusions of the studies from concept to decision-making. The main record source was the Sandia WIPP Central File (SWCF). Early records (about 1975 to 1977) are very limited, however, about details of objectives and plans predating any investigation. Drilling programs from about 1977 were covered by a broadly standardized statement of work, field operations plan, drilling history, and basic data report. Generally standardized procedures for peer, management, and quality assurance review were developed during this time. Agencies such as the USGS conducted projects according to internal standards. Records of detailed actions for individual programs may not be available, though a variety of such records were found in the SWCF. A complete written record cannot be reconstructed. With persistence, a professional geologist can follow individual programs, relate data to objectives (even if implied), and determine how conclusions were used in decision-making. 83 refs.

  17. Active and passive measurements of radon/thoron exhalation from coal and flyash samples collected from various thermal power plants of Delhi, India

    International Nuclear Information System (INIS)

    Singh, Lalit Mohan; Kumar, Rajesh; Sahoo, B.K.; Sapra, B.K.; Rajendra Prasad

    2013-01-01

    Measurement of radon ( 222 Rn) exhalation from coal, flyash and soil samples was carried out using active (Scintillation based Smart Radon Monitor) as well as passive technique (SSNTD based Can technique). In addition, thoron ( 220 Rn) exhalation measurements were also made for the above samples using Scintillation based Smart Thoron Monitor. To the best of our knowledge, thoron exhalation measurement is first of its kind in India. In this study, a total of 26 samples collected from Badarpur Thermal Power Station, Badarpur and Rajghat Power Station, Rajghat, Delhi were analysed. Thoron surface exhalation rate measured by Scintillation based Thoron Monitor for Badarpur Thermal Power Station varied from 327.8 Bq/m 2 /h to 874.2 Bq/m 2 /h and for Rajghat Thermal Power Station it varied from 176.0 Bq/m 2 /h to 781.1 Bq/m 2 /h. Similarly, the radon mass exhalation rate measured by active technique varied from 12.13 mBq/Kg/h to 118.08 mBq/Kg/h for the samples collected from Badarpur Thermal Power Station; while it varied from 15.00 Bq/Kg/h to 168.07 mBq/Kg/h for the samples collected from Rajghat Thermal Power station. On the other hand, result of measurements made by the conventional Can technique were significantly lower varying from 0.44 mBq/Kg/h to 2.34 mBq/Kg/h for Rajghat Thermal Power Station and from 0.78 mBq/Kg/h to 2.88 mBq/Kg/h for Badarpur Thermal Power Station. This vast variation in the results obtained by active and passive techniques is due to the fact that the active technique accounts for the effect of back-diffusion and possible leakage from the chamber in the process of least square fitting of exponential model while it is not so in the case of SSNTD based Can technique. In view of this, results of active technique are more reliable as compared to the passive technique. More importantly, there was no thoron interference in the radon measurement by the active technique. Further experiments are being carried out using controlled radon and thoron

  18. Immunizations: Active vs. Passive

    Science.gov (United States)

    ... Issues Health Issues Health Issues Conditions Injuries & Emergencies Vaccine Preventable Diseases ... Children > Safety & Prevention > Immunizations > Immunizations: Active vs. Passive Safety & ...

  19. Document Models

    Directory of Open Access Journals (Sweden)

    A.A. Malykh

    2017-08-01

    Full Text Available In this paper, the concept of locally simple models is considered. Locally simple models are arbitrarily complex models built from relatively simple components. A lot of practically important domains of discourse can be described as locally simple models, for example, business models of enterprises and companies. Up to now, research in human reasoning automation has been mainly concentrated around the most intellectually intensive activities, such as automated theorem proving. On the other hand, the retailer business model is formed from ”jobs”, and each ”job” can be modelled and automated more or less easily. At the same time, the whole retailer model as an integrated system is extremely complex. In this paper, we offer a variant of the mathematical definition of a locally simple model. This definition is intended for modelling a wide range of domains. Therefore, we also must take into account the perceptual and psychological issues. Logic is elitist, and if we want to attract to our models as many people as possible, we need to hide this elitism behind some metaphor, to which ’ordinary’ people are accustomed. As such a metaphor, we use the concept of a document, so our locally simple models are called document models. Document models are built in the paradigm of semantic programming. This allows us to achieve another important goal - to make the documentary models executable. Executable models are models that can act as practical information systems in the described domain of discourse. Thus, if our model is executable, then programming becomes redundant. The direct use of a model, instead of its programming coding, brings important advantages, for example, a drastic cost reduction for development and maintenance. Moreover, since the model is well and sound, and not dissolved within programming modules, we can directly apply AI tools, in particular, machine learning. This significantly expands the possibilities for automation and

  20. Hydrogenation of passivated contacts

    Energy Technology Data Exchange (ETDEWEB)

    Nemeth, William; Yuan, Hao-Chih; LaSalvia, Vincenzo; Stradins, Pauls; Page, Matthew R.

    2018-03-06

    Methods of hydrogenation of passivated contacts using materials having hydrogen impurities are provided. An example method includes applying, to a passivated contact, a layer of a material, the material containing hydrogen impurities. The method further includes subsequently annealing the material and subsequently removing the material from the passivated contact.

  1. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L.; Moyer, R.A.

    1989-12-01

    This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)

  2. Orbitmpi Documentation

    International Nuclear Information System (INIS)

    Lowe, Lisa L.

    2000-01-01

    Orbitmpi is a parallelized version of Roscoe White's Orbit code. The code has been parallelized using MPI, which makes it portable to many types of machines. The guidelines used for the parallelization were to increase code performance with minimal changes to the code's original structure. This document gives a general description of how the parallel sections of the code run. It discusses the changes made to the original code and comments on the general procedure for future additions to Orbitmpi, as well as describing the effects of a parallelized random number generator on the code's output. Finally, the scaling results from Hecate and from Puffin are presented. Hecate is a 64-processor Origin 2000 machine, with MIPS R12000 processors and 16GB of memory, and Puffin is a PC cluster with 9 dual-processor 450 MHz Pentium III (18 processors max.), with 100Mbits ethernet communication

  3. CMS DOCUMENTATION

    CERN Multimedia

    CMS TALKS AT MAJOR MEETINGS The agenda and talks from major CMS meetings can now be electronically accessed from the ICMS Web site. The following items can be found on: http://cms.cern.ch/iCMS Management – CMS Weeks (Collaboration Meetings), CMS Weeks Agendas The talks presented at the Plenary Sessions. Management – CB – MB – FB Agendas and minutes are accessible to CMS members through Indico. LHCC The talks presented at the ‘CMS Meetings with LHCC Referees’ are available on request from the PM or MB Country Representative. Annual Reviews The talks presented at the 2008 Annual Reviews are posted in Indico. CMS DOCUMENTS It is considered useful to establish information on the first employment of CMS doctoral student upon completion of their theses.  Therefore it is requested that Ph.D students inform the CMS Secretariat about the nature of employment and name of their first employer. The Notes, Conference Reports and Theses published si...

  4. Honeywell modular automation system computer software documentation

    International Nuclear Information System (INIS)

    Cunningham, L.T.

    1997-01-01

    This document provides a Computer Software Documentation for a new Honeywell Modular Automation System (MAS) being installed in the Plutonium Finishing Plant (PFP). This system will be used to control new thermal stabilization furnaces in HA-21I

  5. Omega documentation

    Energy Technology Data Exchange (ETDEWEB)

    Howerton, R.J.; Dye, R.E.; Giles, P.C.; Kimlinger, J.R.; Perkins, S.T.; Plechaty, E.F.

    1983-08-01

    OMEGA is a CRAY I computer program that controls nine codes used by LLNL Physical Data Group for: 1) updating the libraries of evaluated data maintained by the group (UPDATE); 2) calculating average values of energy deposited in secondary particles and residual nuclei (ENDEP); 3) checking the libraries for internal consistency, especially for energy conservation (GAMCHK); 4) producing listings, indexes and plots of the library data (UTILITY); 5) producing calculational constants such as group averaged cross sections and transfer matrices for diffusion and Sn transport codes (CLYDE); 6) producing and updating standard files of the calculational constants used by LLNL Sn and diffusion transport codes (NDFL); 7) producing calculational constants for Monte Carlo transport codes that use group-averaged cross sections and continuous energy for particles (CTART); 8) producing and updating standard files used by the LLNL Monte Carlo transport codes (TRTL); and 9) producing standard files used by the LANL pointwise Monte Carlo transport code MCNP (MCPOINT). The first four of these functions and codes deal with the libraries of evaluated data and the last five with various aspects of producing calculational constants for use by transport codes. In 1970 a series, called PD memos, of internal and informal memoranda was begun. These were intended to be circulated among the group for comment and then to provide documentation for later reference whenever questions arose about the subject matter of the memos. They have served this purpose and now will be drawn upon as source material for this more comprehensive report that deals with most of the matters covered in those memos.

  6. Omega documentation

    International Nuclear Information System (INIS)

    Howerton, R.J.; Dye, R.E.; Giles, P.C.; Kimlinger, J.R.; Perkins, S.T.; Plechaty, E.F.

    1983-08-01

    OMEGA is a CRAY I computer program that controls nine codes used by LLNL Physical Data Group for: 1) updating the libraries of evaluated data maintained by the group (UPDATE); 2) calculating average values of energy deposited in secondary particles and residual nuclei (ENDEP); 3) checking the libraries for internal consistency, especially for energy conservation (GAMCHK); 4) producing listings, indexes and plots of the library data (UTILITY); 5) producing calculational constants such as group averaged cross sections and transfer matrices for diffusion and Sn transport codes (CLYDE); 6) producing and updating standard files of the calculational constants used by LLNL Sn and diffusion transport codes (NDFL); 7) producing calculational constants for Monte Carlo transport codes that use group-averaged cross sections and continuous energy for particles (CTART); 8) producing and updating standard files used by the LLNL Monte Carlo transport codes (TRTL); and 9) producing standard files used by the LANL pointwise Monte Carlo transport code MCNP (MCPOINT). The first four of these functions and codes deal with the libraries of evaluated data and the last five with various aspects of producing calculational constants for use by transport codes. In 1970 a series, called PD memos, of internal and informal memoranda was begun. These were intended to be circulated among the group for comment and then to provide documentation for later reference whenever questions arose about the subject matter of the memos. They have served this purpose and now will be drawn upon as source material for this more comprehensive report that deals with most of the matters covered in those memos

  7. Electropotential measurements of passivation and corrosion of steel coupons

    International Nuclear Information System (INIS)

    Petit, G.S.; Wright, R.R.

    1977-02-01

    There is considerable interest at the Oak Ridge Gaseous Diffusion Plant (ORGDP) in the preparation of mild steel to resist corrosion (passivation) both in moist air and uranium hexafluoride (UF 6 ) environments. Steel prepared by the usual procedures to prevent rusting, such as oiling, plastic coating, painting, or phosphating, cannot be used in the presence of UF 6 . Tests have shown that a chromate treatment or an ammoniacal citrate treatment for passivation are effective. The electropotential behavior of these two passivation treatments is described. The initial electropotential measurement, when compared to that of an unpassivated coupon, gives the electropotential degree in volts of passivation. Continual exposure in the test, when compared to the unpassivated coupon, gives a profile of the durability of the passivation film. The chromate passivation treatment was slightly superior to the citrate passivation

  8. Implications of passive safety based on historical industrial experience

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1988-01-01

    In the past decade, there have been multiple proposals for applying different technologies to achieve passively safe light water reactors (LWRs). A key question for all such concepts is, ''What are the gains in safety, costs, and reliability for passive safety systems.'' Using several types of historical data, estimates have been made of gains from passive safety and operating systems, which are independent of technology. Proposals for passive safety in reactors usually have three characteristics: (1) Passive systems with no moving mechanical parts, (2) systems with far fewer components and (3) more stringent design criteria for safety-related and process systems. Each characteristic reduces the potential for an accident and may increase plant reliability. This paper addresses gains from items (1) and (2). Passive systems often allow adoption of more rigorous design criteria which would be either impossible or economically unfeasible for active systems. This important characteristic of passive safety systems cannot be easily addressed using historical industrial experience

  9. Documentation of the status of international geothermal power plants and a list by country of selected geothermally active governmental and private sector entities

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    This report includes the printouts from the International Geothermal Power Plant Data Base and the Geothermally Active Entity Data Base. Also included are the explanation of the abbreviations used in the power plant data base, maps of geothermal installations by country, and data base questionnaires and mailing lists.

  10. Documentation of the status of international geothermal power plants and a list by country of selected geothermally active governmental and private sector entities

    International Nuclear Information System (INIS)

    1992-10-01

    This report includes the printouts from the International Geothermal Power Plant Data Base and the Geothermally Active Entity Data Base. Also included are the explanation of the abbreviations used in the power plant data base, maps of geothermal installations by country, and data base questionnaires and mailing lists

  11. Balancing passive and active systems for evolutionary water cooled reactors

    International Nuclear Information System (INIS)

    Fil, N.S.; Allen, P.J.; Kirmse, R.E.; Kurihara, M.; Oh, S.J.; Sinha, R.K.

    1999-01-01

    Advanced concepts of the water-cooled reactors are intended to improve safety, economics and public perception of nuclear power. The potential inclusion of new passive means in addition or instead of traditional active systems is being considered by nuclear plant designers to reach these goals. With respect to plant safety, application of the passive means is mainly intended to simplify the safety systems and to improve their reliability, to mitigate the effect of human errors and equipment malfunction. However, some clear drawbacks and the limited experience and testing of passive systems may raise additional questions that have to be addressed in the design process for each advanced reactor. Therefore the plant designer should find a reasonable balance of active and passive means to effectively use their advantages and compensate their drawbacks. Some considerations that have to be taken into account when balancing active/passive means in advanced water-cooled reactors are discussed in this paper. (author)

  12. Areva - 2011 Reference document

    International Nuclear Information System (INIS)

    2011-01-01

    After having indicated the person responsible of this document and the legal account auditors, and provided some financial information, this document gives an overview of the different risk factors existing in the company: law risks, industrial and environmental risks, operational risks, risks related to large projects, market and liquidity risks. Then, after having recalled the history and evolution of the company and the evolution of its investments over the last five years, it proposes an overview of Areva's activities on the markets of nuclear energy and renewable energies, of its clients and suppliers, of its strategy, of the activities of its different departments. Other information are provided: company's flow chart, estate properties (plants, equipment), an analysis of its financial situation, its research and development policy, the present context, profit previsions or estimations, management organization and operation

  13. Passive magnetic bearing configurations

    Science.gov (United States)

    Post, Richard F [Walnut Creek, CA

    2011-01-25

    A journal bearing provides vertical and radial stability to a rotor of a passive magnetic bearing system when the rotor is not rotating and when it is rotating. In the passive magnetic bearing system, the rotor has a vertical axis of rotation. Without the journal bearing, the rotor is vertically and radially unstable when stationary, and is vertically stable and radially unstable when rotating.

  14. Early Site Permit Demonstration Program: Plant parameters envelope report

    International Nuclear Information System (INIS)

    1993-03-01

    The Early Site Permit (ESP) Demonstration Program is the nuclear industry's initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants

  15. SBO simulations for Integrated Passive Safety System (IPSS) using MARS

    International Nuclear Information System (INIS)

    Kim, Sang Ho; Jeong, Sung Yeop; Chang, Soon Heung

    2012-01-01

    The current nuclear power plants have lots of active safety systems with some passive safety systems. The safety of current and future nuclear power plants can be enhanced by the application of additional passive safety systems for the ultimate safety. It is helpful to install the passive safety systems on current nuclear power plants without the design change for the licensibility. For solving the problem about the system complexity shown in the Fukushima accidents, the current nuclear power plants are needed to be enhanced by an additional integrated and simplified system. As a previous research, the integrated passive safety system (IPSS) was proposed to solve the safety issues related with the decay heat removal, containment integrity and radiation release. It could be operated by natural phenomena like gravity, natural circulation and pressure difference without AC power. The five main functions of IPSS are: (a) Passive decay heat removal, (b) Passive emergency core cooling, (c) Passive containment cooling, (d) Passive in vessel retention and ex-vessel cooling, and (e) Filtered venting and pressure control. The purpose of this research is to analyze the performances of each function by using MARS code. The simulated accident scenarios were station black out (SBO) and the additional accidents accompanied by SBO

  16. Passive solar construction handbook

    Energy Technology Data Exchange (ETDEWEB)

    Levy, E.; Evans, D.; Gardstein, C.

    1981-08-01

    Many of the basic elements of passive solar design are reviewed. The unique design constraints presented in passive homes are introduced and many of the salient issues influencing design decisions are described briefly. Passive solar construction is described for each passive system type: direct gain, thermal storage wall, attached sunspace, thermal storage roof, and convective loop. For each system type, important design and construction issues are discussed and case studies illustrating designed and built examples of the system type are presented. Construction details are given and construction and thermal performance information is given for the materials used in collector components, storage components, and control components. Included are glazing materials, framing systems, caulking and sealants, concrete masonry, concrete, brick, shading, reflectors, and insulators. The Load Collector Ratio method for estimating passive system performance is appended, and other analysis methods are briefly summarized. (LEW)

  17. Neutralization of wastewater from nitrite passivation

    International Nuclear Information System (INIS)

    Pawlowski, L.; Mientki, B.; Wasag, H.

    1982-01-01

    A method for neutralization of wastewater formed in nitrite passivation has been presented. The method consists of introducing urea into wastewater and acidifying it with sulphuric acid. Wastewater is neutralized with lime. After clarification, wastewater can be drained outside the plant

  18. Passivity and Evolutionary Game Dynamics

    KAUST Repository

    Park, Shinkyu; Shamma, Jeff S.; Martins, Nuno C.

    2018-01-01

    This paper investigates an energy conservation and dissipation -- passivity -- aspect of dynamic models in evolutionary game theory. We define a notion of passivity using the state-space representation of the models, and we devise systematic methods to examine passivity and to identify properties of passive dynamic models. Based on the methods, we describe how passivity is connected to stability in population games and illustrate stability of passive dynamic models using numerical simulations.

  19. Passivity and Evolutionary Game Dynamics

    KAUST Repository

    Park, Shinkyu

    2018-03-21

    This paper investigates an energy conservation and dissipation -- passivity -- aspect of dynamic models in evolutionary game theory. We define a notion of passivity using the state-space representation of the models, and we devise systematic methods to examine passivity and to identify properties of passive dynamic models. Based on the methods, we describe how passivity is connected to stability in population games and illustrate stability of passive dynamic models using numerical simulations.

  20. Active versus passive screening for entrance control

    International Nuclear Information System (INIS)

    McCormick, N.J.

    1976-01-01

    The benefits of different entrance control actions are quantitatively assessed by defining a relative improvement index for the screening activity. Three classes of entrance control measures are investigated: the use of a purely active screening measure (such as a portal monitor), the use of a purely passive screening measure (such as personality typing), and the combined use of active and passive measures. Active entrance control measures have been studied previously [McCormick and Erdmann, Nucl. Mat. Manag. 4, (1975)] where it was determined that the relative improvement index is approximately related to the nondetection probability factor r for the protective system by (1-r + r ln r). It is shown here that the relative improvement index for a purely passive screening system also can be approximately expressed in a convenient manner. Because the probability is very small that a sabotage or diversion action would be attempted, the result for passive screening, multiplied by r, may be combined with the factor (1-r + r ln r) to give the relative improvement index for a combined, active-and-passive entrance control system. Results from simple example calculations indicate that passive screening of nuclear plant personnel or applicants for such positions is orders-of-magnitude less effective than portal monitors or reasonable improvements in them. 5 tables

  1. Aktiv kontra passiv forvaltning

    DEFF Research Database (Denmark)

    Bechmann, Ken L.; Pedersen, Lasse Heje

    2017-01-01

    Fordele og ulemper ved aktiv og passiv forvaltning har fået fornyet opmærksomhed blandt andet i forbindelse med den forestående implementering af MiFID II. Som bidrag til denne diskussion indeholder dette nummer af Finans/Invest tre artikler, der behandler aktiv og passiv forvaltning fra...... forskellige vinkler. Denne leder forklarer, hvorfor valget mellem aktiv og passiv forvaltning er mere kompliceret, end hvad man kunne tro ved første øjekast, og konkluderer, at der vil være plads til - og behov for - begge typer forvaltning....

  2. Most energetic passive states.

    Science.gov (United States)

    Perarnau-Llobet, Martí; Hovhannisyan, Karen V; Huber, Marcus; Skrzypczyk, Paul; Tura, Jordi; Acín, Antonio

    2015-10-01

    Passive states are defined as those states that do not allow for work extraction in a cyclic (unitary) process. Within the set of passive states, thermal states are the most stable ones: they maximize the entropy for a given energy, and similarly they minimize the energy for a given entropy. Here we find the passive states lying in the other extreme, i.e., those that maximize the energy for a given entropy, which we show also minimize the entropy when the energy is fixed. These extremal properties make these states useful to obtain fundamental bounds for the thermodynamics of finite-dimensional quantum systems, which we show in several scenarios.

  3. Public comments on the proposed 10 CFR Part 51 rule for renewal of nuclear power plant operating licenses and supporting documents: Review of concerns and NRC staff response. Volume 1

    International Nuclear Information System (INIS)

    1996-05-01

    This report documents the Nuclear Regulatory Commission (NRC) staff review of public comments provided in response to the NRC's proposed amendments to 10 Code of Federal Regulations (CFR) Part 51, which establish new requirements for the environmental review of applications for the renewal of operating licenses of nuclear power plants. The public comments include those submitted in writing, as well as those provided at public meetings that were held with other Federal agencies, State agencies, nuclear industry representatives, public interest groups, and the general public. This report also contains the NRC staff response to the various concerns raised, and highlights the changes made to the final rule and the supporting documents in response to these concerns

  4. AREVA - 2013 Reference document

    International Nuclear Information System (INIS)

    2014-01-01

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies, as well as estimates of the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the Reference Document; 2 - Statutory auditors; 3 - Selected financial information; 4 - Description of major risks confronting the company; 5 - Information about the issuer; 6 - Business overview; 7 - Organizational structure; 8 - Property, plant and equipment; 9 - Situation and activities of the company and its subsidiaries; 10 - Capital resources; 11 - Research and development programs, patents and licenses; 12 - Trend information; 13 - Profit forecasts or estimates; 14 - Management and supervisory bodies; 15 - Compensation and benefits; 16 - Functioning of the management and supervisory bodies; 17 - Human resources information; 18 - Principal shareholders; 19 - Transactions with related parties; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information; 22 - Major contracts; 23 - Third party information, statements by experts and declarations of interest; 24 - Documents on display; 25 - Information on holdings; Appendix 1: report of the supervisory board chairman on the preparation and organization of the board's activities and internal control procedures; Appendix 2: statutory auditors' reports; Appendix 3: environmental report; Appendix 4: non-financial reporting methodology and independent third-party report on social, environmental and societal data; Appendix 5: ordinary and extraordinary general shareholders' meeting; Appendix 6: values charter; Appendix 7: table of concordance of the management report; glossaries

  5. Deep influence of passive low energy consumption multi-storey residential building in cold region

    Science.gov (United States)

    Shuai, Zhang; Lihua, Zhao; Rong, Jin; Dong, Junyan

    2018-02-01

    The example of passive architecture demonstration building in Jilin Province, China, based on the practical experience of this project, the control index of passive and low energy consumption residential buildings in cold and passive buildings is referenced by reference to the German construction standard and the Chinese residence construction document, “passive ultra-low energy consumption green Building Technology Guide (Trial)”. The requirement of passive low energy residential buildings on the ground heat transfer coefficient limits is determined, and the performance requirements of passive residential buildings are discussed. This paper analyzes the requirement of the passive low energy residential building on the ground heat transfer coefficient limit, and probes into the influence factors of the ground thermal insulation of the passive low energy consumption residential building. The construction method of passive low energy consumption residential building is proposed.

  6. Preliminary investigation on reliability assessment of passive safety system

    International Nuclear Information System (INIS)

    Huang Changfan; Kuang Bo

    2012-01-01

    The reliability evaluation of passive safety system plays an important part in probabilistic safety assessment (PSA) of nuclear power plant applying passive safety design, which depends quantitatively on reliabilities of passive safety system. According to the object of reliability assessment of passive safety system, relevant parameters are identified. Then passive system behavior during accident scenarios are studied. A practical example of this method is given for the case of reliability assessment of AP1000 passive heat removal system in loss of normal feedwater accident. Key and design parameters of PRHRS are identified and functional failure criteria are established. Parameter combinations acquired by Latin hyper~ cube sampling (LHS) in possible parametric ranges are input and calculations of uncertainty propagation through RELAP5/MOD3 code are carried out. Based on the calculations, sensitivity assessment on PRHRS functional criteria and reliability evaluation of the system are presented, which might provide further PSA with PRHR system reliability. (authors)

  7. EFSA Panel on Plant Protection Products and their Residues (PPR); EFSA Scientific Opinion on the science behind the revision of the guidance document on dermal absorption

    DEFF Research Database (Denmark)

    Petersen, Annette

    will be finalised and published only after adoption and publication of this opinion. This opinion has been developed after a public consultation of EFSA on the current guidance document and an outsourced project carried out by the UK Chemicals Regulation Directorate (CRD, 2010). It is not intended...... that have an impact on absorption, a description of important elements in the design of experimental studies and an analysis of available data on dermal absorption of PPPs. The PPR Panel concludes that assessment of dermal absorption in the absence of specific studies can be performed based on default...

  8. Piping reliability improvement through passive seismic supports

    International Nuclear Information System (INIS)

    Baltus, R.; Rubbers, A.

    1999-01-01

    The nuclear plants designed in the 1970's were equipped with large quantities of snubbers in auxiliary piping systems. The experience revealed a poor performance of snubbers during periodic inspection, while non-nuclear facility piping survived through strong earthquakes. Consequently, seismic design rules evolved towards more realistic criteria and passive dynamic supports were developed to reduce snubber quantities. These solutions improve the pipe reliability during normal operation while reducing the radiation exposure in a sample line is presented with the impact on pipe stresses compared to the results obtained with passive supports named Limit Stops. (author)

  9. Passive containment system for a nuclear reactor

    International Nuclear Information System (INIS)

    Kleimola, F.W.

    1976-01-01

    A containment system is described that provides complete protection entirely by passive means for the loss of coolant accident in a nuclear power plant and wherein all stored energy released in the coolant blowdown is contained and absorbed while the nuclear fuel is continuously maintained submerged in liquid. The primary containment vessel is restored to a high subatmospheric pressure within a few minutes after accident initiation and the decay heat is safely transferred to the environment while radiolytic hydrogen is contained by passive means

  10. Techniques for active passivation

    Science.gov (United States)

    Roscioli, Joseph R.; Herndon, Scott C.; Nelson, Jr., David D.

    2016-12-20

    In one embodiment, active (continuous or intermittent) passivation may be employed to prevent interaction of sticky molecules with interfaces inside of an instrument (e.g., an infrared absorption spectrometer) and thereby improve response time. A passivation species may be continuously or intermittently applied to an inlet of the instrument while a sample gas stream is being applied. The passivation species may have a highly polar functional group that strongly binds to either water or polar groups of the interfaces, and once bound presents a non-polar group to the gas phase in order to prevent further binding of polar molecules. The instrument may be actively used to detect the sticky molecules while the passivation species is being applied.

  11. Passive Mixing inside Microdroplets

    Directory of Open Access Journals (Sweden)

    Chengmin Chen

    2018-04-01

    Full Text Available Droplet-based micromixers are essential units in many microfluidic devices for widespread applications, such as diagnostics and synthesis. The mixers can be either passive or active. When compared to active methods, the passive mixer is widely used because it does not require extra energy input apart from the pump drive. In recent years, several passive droplet-based mixers were developed, where mixing was characterized by both experiments and simulation. A unified physical understanding of both experimental processes and simulation models is beneficial for effectively developing new and efficient mixing techniques. This review covers the state-of-the-art passive droplet-based micromixers in microfluidics, which mainly focuses on three aspects: (1 Mixing parameters and analysis method; (2 Typical mixing element designs and the mixing characters in experiments; and, (3 Comprehensive introduction of numerical models used in microfluidic flow and diffusion.

  12. First record of folivory on a newly documented host plant for the little known geometrid moth Eupithecia yubitzae Vargas & Parra (Lepidoptera, Geometridae in northern Chile

    Directory of Open Access Journals (Sweden)

    Héctor A. Vargas

    2015-06-01

    Full Text Available The native tree Schinus molle (Anacardiacae is reported for the first time as a host plant for larvae of the little known geometrid moth Eupithecia yubitzae Vargas & Parra (Lepidoptera, Geometridae in the Atacama Desert of northern Chile, based on morphology and DNA barcodes. This discovery importantly expands the host range of E. yubitzae, as previous records were restricted to Fabaceae trees. Larvae were previously known as florivorous, while these were found to be folivorous on S. molle. Furthermore, host-associated cryptic larval polychromatism was detected, as larvae collected on S. molle were found to be mostly pale green, contrasting with the dark yellow ground color of the larvae typically collected on fabaceous host plants.

  13. Environmental summary document for the Republic Geothermal, Inc. application for a geothermal loan guaranty project: 64 MW well field and 48 MW (net) geothermal power plant

    Energy Technology Data Exchange (ETDEWEB)

    Layton, D.W.; Powers, D.J.; Leitner, P.; Crow, N.B.; Gudiksen, P.H.; Ricker, Y.E.

    1979-07-01

    A comprehensive review and analysis is provided of the environmental consequences of (1) guaranteeing a load for the completion of the 64 MW well field and the 48 MW (net) power plant or (2) denying a guaranteed load that is needed to finish the project. Mitigation measures are discussed. Alternatives and their impacts are compared and some discussion is included on unavoidable adverse impacts. (MHR)

  14. CANDU passive shutdown systems

    Energy Technology Data Exchange (ETDEWEB)

    Hart, R S; Olmstead, R A [AECL CANDU, Sheridan Park Research Community, Mississauga, ON (Canada)

    1996-12-01

    CANDU incorporates two diverse, passive shutdown systems, independent of each other and from the reactor regulating system. Both shutdown systems function in the low pressure, low temperature, moderator which surrounds the fuel channels. The shutdown systems are functionally different, physically separate, and passive since the driving force for SDS1 is gravity and the driving force for SDS2 is stored energy. The physics of the reactor core itself ensures a degree of passive safety in that the relatively long prompt neutron generation time inherent in the design of CANDU reactors tend to retard power excursions and reduces the speed required for shutdown action, even for large postulated reactivity increases. All passive systems include a number of active components or initiators. Hence, an important aspect of passive systems is the inclusion of fail safe (activated by active component failure) operation. The mechanisms that achieve the fail safe action should be passive. Consequently the passive performance of the CANDU shutdown systems extends beyond their basic modes of operation to include fail safe operation based on natural phenomenon or stored energy. For example, loss of power to the SDS1 clutches results in the drop of the shutdown rods by gravity, loss of power or instrument air to the injection valves of SDS2 results in valve opening via spring action, and rigorous self checking of logic, data and timing by the shutdown systems computers assures a fail safe reactor trip through the collapse of a fluctuating magnetic field or the discharge of a capacitor. Event statistics from operating CANDU stations indicate a significant decrease in protection system faults that could lead to loss of production and elimination of protection system faults that could lead to loss of protection. This paper provides a comprehensive description of the passive shutdown systems employed by CANDU. (author). 4 figs, 3 tabs.

  15. Active or passive systems? The EPR approach

    International Nuclear Information System (INIS)

    Bonhomme, N.; Py, J.P.

    1996-01-01

    In attempting to review how EPR is contemplated to meet requirements applicable to future nuclear power plants, the authors indicate where they see the markets and the corresponding unit sizes for the EPR which is a generic key factor for competitiveness. There are no reason in industrialized countries, other than USA (where the investment and amortizing practices under control by Public Utility Commission are quite particular), not to build future plants in the 1000 to 1500 MWe range. Standardization, which has been actively applied all along the French program and for the Konvoi plants, does not prevent evolution and allows to concentrate large engineering effort in smooth realization of plants and achieve actual construction and commissioning without significant delays. In order to contribute to public trust renewal, a next generation of power reactors should be fundamentally less likely to incur serious accidents. To reach this goal the best of passive and active systems must be considered without forgetting that the most important source of knowledge is construction and operating experience. Criteria to assess passive systems investigated for possible implementation in the EPR, such as simplicity of design, impact on plant operation, safety and cost, are discussed. Examples of the principal passive systems investigated are described and reasons why they have been dropped after screening through the criteria are given. (author). 11 figs

  16. Active or passive systems? The EPR approach

    Energy Technology Data Exchange (ETDEWEB)

    Bonhomme, N [Nuclear Power International, Cedex (France); Py, J P [FRAMATOME, Cedex (France)

    1996-12-01

    In attempting to review how EPR is contemplated to meet requirements applicable to future nuclear power plants, the authors indicate where they see the markets and the corresponding unit sizes for the EPR which is a generic key factor for competitiveness. There are no reason in industrialized countries, other than USA (where the investment and amortizing practices under control by Public Utility Commission are quite particular), not to build future plants in the 1000 to 1500 MWe range. Standardization, which has been actively applied all along the French program and for the Konvoi plants, does not prevent evolution and allows to concentrate large engineering effort in smooth realization of plants and achieve actual construction and commissioning without significant delays. In order to contribute to public trust renewal, a next generation of power reactors should be fundamentally less likely to incur serious accidents. To reach this goal the best of passive and active systems must be considered without forgetting that the most important source of knowledge is construction and operating experience. Criteria to assess passive systems investigated for possible implementation in the EPR, such as simplicity of design, impact on plant operation, safety and cost, are discussed. Examples of the principal passive systems investigated are described and reasons why they have been dropped after screening through the criteria are given. (author). 11 figs.

  17. Melter Disposal Strategic Planning Document

    Energy Technology Data Exchange (ETDEWEB)

    BURBANK, D.A.

    2000-09-25

    This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

  18. Passive House Solutions

    Energy Technology Data Exchange (ETDEWEB)

    Strom, I.; Joosten, L.; Boonstra, C. [DHV Sustainability Consultants, Eindhoiven (Netherlands)

    2006-05-15

    PEP stands for 'Promotion of European Passive Houses' and is a consortium of European partners, supported by the European Commission, Directorate General for Energy and Transport. In this working paper an overview is given of Passive House solutions. An inventory has been made of Passive House solutions for new build residences applied in each country. Based on this, the most common basic solutions have been identified and described in further detail, including the extent to which solutions are applied in common and best practice and expected barriers for the implementation in each country. An inventory per country is included in the appendix. The analysis of Passive House solutions in partner countries shows high priority with regard to the performance of the thermal envelope, such as high insulation of walls, roofs, floors and windows/ doors, thermal bridge-free construction and air tightness. Due to the required air tightness, special attention must be paid to indoor air quality through proper ventilation. Finally, efficient ((semi-)solar) heating systems for combined space and DHW heating still require a significant amount of attention in most partner countries. Other basic Passive House solutions show a smaller discrepancy with common practice and fewer barriers have been encountered in partner countries. In the next section, the general barriers in partner countries have been inventoried. For each type of barrier a suggested approach has been given. Most frequently encountered barriers in partner countries are: limited know-how; limited contractor skills; and acceptation of Passive Houses in the market. Based on the suggested approaches to overcoming barriers, this means that a great deal of attention must be paid to providing practical information and solutions to building professionals, providing practical training to installers and contractors and communication about the Passive House concept to the market.

  19. Development of a procedure for qualitative and quantitative evaluation of human factors as a part of probabilistic safety assessments of nuclear power plants. Part B. Technical documentation

    International Nuclear Information System (INIS)

    Richei, A.

    1998-01-01

    As international studies have shown, accidents in plants are increasingly caused by combinations of technical failures and human errors. Therefore careful investigations of man-machine-interactions to determine human reliability are gaining importance worldwide. Regarding nuclear power plants such investigations are usually carried out within the scope of probabilistic safety assessments. A great number of procedures to evaluate human factors has been developed up to now. However, none of them is able to take into account the whole spectrum of requirements - as for instance transferability of date to other plants, analysis of weak points, and evaluation of cognitive tasks - for a complete and reliable probabilistic safety assessment. Based on an advanced model for a man-machine-system, the Human Error Rate Assessment and Optimizing System (HEROS) and a corresponding expert system of the same name are introduced. This expert system enables the quantification of human error probabilities for plant operator actions on the one hand and is also capable of providing quantitative statements regarding the optimization of man-machine-system in terms of human error probability minimization on the other one. Three relevant evaluation levels, i.e. 'Management Structure', 'Working Environment' and 'Man-Machine-Interface', are derived from a model of the man-machine-system. Linguistic variables are assigned to all performance shaping factors at these levels. These variables are used to establish a rule-based expert system. The knowledge bases of this system are represented by rules. Processing of these rules is carried out by means of the fuzzy set theory, after provision of relevant data for a particular personal action to be evaluated. This procedure enables a simple and effective use of ergonomic studies as the relevant database, which is also transferable to other plants with any design. The expert system consist in total of 16 rule bases in which all ascertainable and

  20. Preliminary statement concerning the expert opinion and other documents relating to the Wackersdorf fuel reprocessing plant, laid open between June 18 and July 15, 1985 by the Bavarian Ministry of State for Regional Development and Environmental Affairs

    International Nuclear Information System (INIS)

    1985-01-01

    The conclusion drawn in the statement is that the expert opinions and documents available do not justify the granting of a first partial licence for the erection of the fuel reprocessing plant. Such a first partial licence would include the site approval, the outline design approval, and part-construction permits, in this case for instance for the fuel element receiving store. The site approval would be a premature decision according to this statement, as some decisive expert opinions (on meteorological, hydrological, and radioecological site conditions) are not yet completed. The documents available for evaluation of the design concept are said to have been insufficient in many regards, so that all the authors can state at the present time is that 'there may be technically feasible solutions by now'. This is judged to be an insufficient basis for an outline design approval in accordance with the Atomic Energy Act. The reasons brought forward against licensing the fuel element receiving store are similar. For lack of appropriate documents, the authors of the statement found themselves unable to assess the safety of a major component, the fuel element storage tank. (orig./HSCH) [de

  1. On the Modern History of Passive Solar Architecture

    DEFF Research Database (Denmark)

    Marsh, Rob

    2017-01-01

    This article examines the paradox of passive solar architecture within the Nordic context of Denmark, Norway and Sweden. Regulative developments to reduce space heating demand since the 1970s oil crisis are explored, highlighting architectural responses and the rise in prom-inence of passive solar...... design. An empirical study of passive solar housing schemes docu-ments architectural strategy, energy savings and extensive problems with overheating. A theo-retical study examines how passive solar was seen as advantageous when viewed with the 1985-2005 space heating paradigm, but actually resulted...... of Nordic modernism meant that passive solar architecture became the de-facto visual, aesthetic and functional expression of environmental design at that time. The article concludes by explor-ing the implications of the environmental paradigm for the architectural profession. By positing the architectural...

  2. Documents and legal texts

    International Nuclear Information System (INIS)

    2013-01-01

    This section reprints a selection of recently published legislative texts and documents: - Russian Federation: Federal Law No.170 of 21 November 1995 on the use of atomic energy, Adopted by the State Duma on 20 October 1995; - Uruguay: Law No.19.056 On the Radiological Protection and Safety of Persons, Property and the Environment (4 January 2013); - Japan: Third Supplement to Interim Guidelines on Determination of the Scope of Nuclear Damage resulting from the Accident at the Tokyo Electric Power Company Fukushima Daiichi and Daini Nuclear Power Plants (concerning Damages related to Rumour-Related Damage in the Agriculture, Forestry, Fishery and Food Industries), 30 January 2013; - France and the United States: Joint Statement on Liability for Nuclear Damage (Aug 2013); - Franco-Russian Nuclear Power Declaration (1 November 2013)

  3. Interactions between industrial organic pollutants and rhizosphere components and documentation of material streams in plant-based wastewater treatment plants - laboratory experiments; Wechselwirkungen industrieller organischer Schadstoffe mit Rhizosphaerenkomponenten und Bilanzierung von Stoffstroemen in Pflanzenklaeranlagen - Laborversuche

    Energy Technology Data Exchange (ETDEWEB)

    Plugge, J.

    2001-07-01

    The purpose of the present study was to examine the suitability of plant/soil systems for cleaning organically polluted effluents and to assess the influence of plant growth and dissolved humic substances on processes leading to the elimination of organic pollutants. This involved an examination of sorption interactions between selected pollutants on the one hand and sand and root material on the other, use of vertically irrigated plant-bearing sand columns for simulating real plant-based wastewater treatment plants, assessment of the cleaning efficiency of these systems with respect to the employed model pollutants and determination of the contamination of the filter material and plants with pollutants. Radiotracer techniques were used to determine pollution paths of phenanthrene and its microbial degradation in the model system. [German] In der vorliegenden Arbeit wurde die Eignung von Pflanze/Boden-Systemen zur Reinigung carbochemisch belasteter Abwaesser untersucht und der Einfluss eines Pflanzenbewuchses sowie geloester Huminstoffe auf die Prozesse, die zur Entfernung organischer Schadstoffe fuehren, bewertet. Die Bearbeitung dieses Themas umfasste Untersuchungen zu Sorptionswechselwirkungen ausgewaehlter Schadstoffe mit Sand- und Wurzelmaterial, die Anwendung vertikal durchstroemter, bepflanzter Sandsaeulen zur Nachbildung realer Pflanzenklaeranlagen, die Erfassung der Reinigungseffizienz dieser Systeme fuer die Modellschadstoffe sowie die Bestimmung der Schadstoffkontamination des Filtermaterials und der Pflanzen. Unter Anwendung der Radiotracertechnik erfolgte darueber hinaus die Bestimmung der Schadstoffpfade von Phenanthren einschliesslich des mikrobiellen Abbaus im Modellsystem. (orig.)

  4. Report on the Regulatory Experience of Risk-Informed In-service Inspection of Nuclear Power Plant Components and Common Views (consensus document)

    International Nuclear Information System (INIS)

    2004-08-01

    The present report represents the work product of the activities conducted by the Task Force. The TF performed a review and inventory of the existing approaches to risk-informed inservice inspection and testing, and completed its work in 1999 with a Current Practices Document 2, titled Report on risk-informed in-service inspection and in-service testing (EUR 19153 EN). In November 2001, the NRWG held a Special session on risk-informed applications, with emphasis on risk-informed inservice inspection, where results and experiences from pilot studies on risk-informed inservice inspection (RI-ISI), performed in several European countries, were presented and discussed. As a follow-up in May 2002, the TF was reconvened with the objectives to analyse from the regulatory point of view key aspects associated with the application of risk-informed inservice inspection, and to go beyond a state of the art report, presenting a series of recommendations of good practices or common positions reached by the regulators represented in the Task Force. (author)

  5. Decision document for performing a long-term pumping test at the S-3 Site, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-02-01

    One of the principal problems confronting the remediation of Bear Creek Valley is the cleanup of contaminated groundwater. The S-3 Site is one of the locations in the valley where groundwater is most contaminated, and contamination from the S-3 Site has also caused extensive contamination of downgradient groundwater. This groundwater plume, therefore, has a high priority in the Bear Creek Valley remedial process. Pumping and treating groundwater was identified early in the feasibility study as a likely remedial alternative for the S-3 Site groundwater plume. The hydrology and geochemistry of the plume are extremely complex. There is a high degree of uncertainty in the current understanding of how the aquifer will react physically and chemically to pumping, making evaluation of a pump-and-treat alternative impractical at the present time. Before a pump-and-treat alternative can be evaluated, its technical practicability, effectiveness, and projected cost must be determined. A long-term pumping test (LTPT) at the S-3 Site has been proposed so that the information necessary to carry out this evaluation can be collected. This document constitutes the first phase in the planning process for this test

  6. AVLIS documentation overview and tables of contents

    International Nuclear Information System (INIS)

    1984-01-01

    Three documents constitute the executive summary series in Data Package III: this document (Documentation Overview and Tables of Contents (E001)) plus the AVLIS Production Plant Executive Summary (E010) and the AVLIS Production Plant Overall Design Report (E020). They provide progressively greater detail on the key information and conclusions contained within the data package. The Executive Summary and Overall Design Report present summaries of each Data Package III document. They are intended to provide a global overview of AVLIS Production Plant deployment including program planning, project management, schedules, engineering design, production, operations, capital cost, and operating cost. The purpose of Overview and Tables of Contents is threefold: to briefly review AVLIS goals for Data Package III documentation, to present an overview of the contents of the data package, and to provide a useful guide to information contained in the numerous documents comprising the package

  7. AREVA - 2012 Reference document

    International Nuclear Information System (INIS)

    2013-03-01

    After a presentation of the person responsible for this Reference Document, of statutory auditors, and of a summary of financial information, this report address the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risk related to major projects, liquidity and market risk, and other risks (related to political and economic conditions, to Group's structure, and to human resources). The next parts propose information about the issuer, a business overview (markets for nuclear power and renewable energies, customers and suppliers, group's strategy, operations), a brief presentation of the organizational structure, a presentation of properties, plants and equipment (principal sites, environmental issues which may affect these items), analysis and comments on the group's financial position and performance, a presentation of capital resources, a presentation of research and development activities (programs, patents and licenses), a brief description of financial objectives and profit forecasts or estimates, a presentation of administration, management and supervision bodies, a description of the operation of corporate bodies, an overview of personnel, of principal shareholders, and of transactions with related parties, a more detailed presentation of financial information concerning assets, financial positions and financial performance. Addition information regarding share capital is given, as well as an indication of major contracts, third party information, available documents, and information on holdings

  8. AREVA 2010 Reference document

    International Nuclear Information System (INIS)

    2010-01-01

    After a presentation of the person responsible for this document, and of statutory auditors, this report proposes some selected financial information. Then, it addresses, presents and comments the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risks related to major projects, liquidity and market risk, and other risk. Then, after a presentation of the issuer, it proposes a business overview (markets for nuclear and renewable energies, AREVA customers and suppliers, strategy, activities), a presentation of the organizational structure, a presentation of AREVA properties, plants and equipment (sites, environmental issues), an analysis and comment of the group's financial position and performance, a presentation of its capital resources, an overview of its research and development activities, programs, patents and licenses. It indicates profit forecast and estimates, presents the administrative, management and supervisory bodies, and compensation and benefits amounts, reports of the functioning of corporate bodies. It describes the human resource company policy, indicates the main shareholders and transactions with related parties. It proposes financial information concerning assets, financial positions and financial performance. This document contains its French and its English versions

  9. Constructing passive houses

    Energy Technology Data Exchange (ETDEWEB)

    Oehler, S. [Oehler Faigle Archkom Solar Architektur, Bretten (Germany)

    2005-07-01

    Everybody can learn to build energy-efficient. It needs theoretical and practical experience. 1997 we built the first freestanding Passive House in Europe, the Passive House Oehler. There had been a lot of questions, starting with the insecurity, whether the calculation program of the Passive House Institute, the PHPP, is working properly in our case. Nobody knew at that time because nobody tried it out before. It took us a lot of time to find out and every detail of the construction hat to be invented to meet the very high demand of thermal quality. All the following houses needed less time and had fewer open questions, adding one piece of experience with every building. 2002 we realised the biggest Passive House, the office building Energon Ulm with 420 working spaces. In the meantime we have learned a lot like how to produce prefabricated timber elements for the facades, providing good insulation, air tightness and avoiding serious thermal bridges. We have proofed, that any kind of building type can be a Passive House. And with increasing experience the freedom of design and construction is growing. Even the economical efficiency increased. The Energon Ulm is providing a much better indoor climate than any other office building and was build 10 % cheaper than an average German office building. At present the Passive House Standard is the most efficient solution for the user to live in the desired comfort zone between 20 C and 25 C. This zone of individual feeling-well can be described with the term ''operative temperature''. This term is defined by factors like air temperature, radiation temperature of warm and cold surfaces, air speed and humidity. The result of all these factors has to be within 18 C to 25 C without accepting one of the factors getting extreme.

  10. Wireless passive radiation sensor

    Science.gov (United States)

    Pfeifer, Kent B; Rumpf, Arthur N; Yelton, William G; Limmer, Steven J

    2013-12-03

    A novel measurement technique is employed using surface acoustic wave (SAW) devices, passive RF, and radiation-sensitive films to provide a wireless passive radiation sensor that requires no batteries, outside wiring, or regular maintenance. The sensor is small (<1 cm.sup.2), physically robust, and will operate unattended for decades. In addition, the sensor can be insensitive to measurement position and read distance due to a novel self-referencing technique eliminating the need to measure absolute responses that are dependent on RF transmitter location and power.

  11. Documents and legal texts

    International Nuclear Information System (INIS)

    2014-01-01

    This section of the Bulletin presents the recently published documents and legal texts sorted by country: - Brazil: Resolution No. 169 of 30 April 2014. - Japan: Act Concerning Exceptions to Interruption of Prescription Pertaining to Use of Settlement Mediation Procedures by the Dispute Reconciliation Committee for Nuclear Damage Compensation in relation to Nuclear Damage Compensation Disputes Pertaining to the Great East Japan Earthquake (Act No. 32 of 5 June 2013); Act Concerning Measures to Achieve Prompt and Assured Compensation for Nuclear Damage Arising from the Nuclear Plant Accident following the Great East Japan Earthquake and Exceptions to the Extinctive Prescription, etc. of the Right to Claim Compensation for Nuclear Damage (Act No. 97 of 11 December 2013); Fourth Supplement to Interim Guidelines on Determination of the Scope of Nuclear Damage Resulting from the Accident at the Tokyo Electric Power Company Fukushima Daiichi and Daini Nuclear Power Plants (Concerning Damages Associated with the Prolongation of Evacuation Orders, etc.); Outline of 'Fourth Supplement to Interim Guidelines (Concerning Damages Associated with the Prolongation of Evacuation Orders, etc.)'. - OECD Nuclear Energy Agency: Decision and Recommendation of the Steering Committee Concerning the Application of the Paris Convention to Nuclear Installations in the Process of Being Decommissioned; Joint Declaration on the Security of Supply of Medical Radioisotopes. - United Arab Emirates: Federal Decree No. (51) of 2014 Ratifying the Convention on Supplementary Compensation for Nuclear Damage; Ratification of the Federal Supreme Council of Federal Decree No. (51) of 2014 Ratifying the Convention on Supplementary Compensation for Nuclear Damage

  12. European Embedding of Passive Houses. www.europeanpassivehouses.org

    Energy Technology Data Exchange (ETDEWEB)

    Elswijk, M.; Kaan, H. (eds.) [and others

    2008-05-15

    The passive house concept has become a European wide accepted solution to reach a significant energy demand reduction in the built environment. The European Commission has published the ambition to construct newly built ho uses in 2015 accordingly to the passive ho use standard. In most project participating countries this ambition is shared. With the support of the Intelligent Energy Europe program this project 'Promotion of European Passive Houses' (PEP-project) contributed to achieve this ambition to clear the first market barriers internationally to reach the status 'Business As Usual' for passive houses in 2015. The PEP project aimed at the development of easy accessible web based documentation for stakeholders in the building process to solve national market introduction barriers regarding the passive house concept. The project also aimed at the distribution of this information via international and national workshops, seminars and conferences. It can be concluded that the PEP-project has been successful. All participating countries made significant progress in the societal embedding process of passive houses and in most countries the passive house concept is on the brink of breaking through nationally. Further, the PEP-project contributed successfully in the internationalisation of the Internal Passive House Conference and fixed the definition of a passive house for three geographical European regions. Finally, the PEP website with its wealth of information was a powerful tool for promotion of passive houses in Europe. In order to increase the implementation efficiency of the passive house concept it is recommended to develop additional information packages concerning passive house solutions for offices, schools and social homes (e.g. architectural examples, organisational issues); passive house renovations; financial schemes for passive houses; performance oriented quality approach for the design and construction process; industrial

  13. Generic safety documentation model

    International Nuclear Information System (INIS)

    Mahn, J.A.

    1994-04-01

    This document is intended to be a resource for preparers of safety documentation for Sandia National Laboratories, New Mexico facilities. It provides standardized discussions of some topics that are generic to most, if not all, Sandia/NM facilities safety documents. The material provides a ''core'' upon which to develop facility-specific safety documentation. The use of the information in this document will reduce the cost of safety document preparation and improve consistency of information

  14. AREVA 2009 reference document

    International Nuclear Information System (INIS)

    2009-01-01

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies. It contains information on the markets, market shares and competitive position of the AREVA group. This information provides an adequate picture of the size of these markets and of the AREVA group's competitive position. Content: 1 - Person responsible for the Reference Document and Attestation by the person responsible for the Reference Document; 2 - Statutory and Deputy Auditors; 3 - Selected financial information; 4 - Risks: Risk management and coverage, Legal risk, Industrial and environmental risk, Operating risk, Risk related to major projects, Liquidity and market risk, Other risk; 5 - Information about the issuer: History and development, Investments; 6 - Business overview: Markets for nuclear power and renewable energies, AREVA customers and suppliers, Overview and strategy of the group, Business divisions, Discontinued operations: AREVA Transmission and Distribution; 7 - Organizational structure; 8 - Property, plant and equipment: Principal sites of the AREVA group, Environmental issues that may affect the issuer's; 9 - Analysis of and comments on the group's financial position and performance: Overview, Financial position, Cash flow, Statement of financial position, Events subsequent to year-end closing for 2009; 10 - Capital Resources; 11 - Research and development programs, patents and licenses; 12 -trend information: Current situation, Financial objectives; 13 - Profit forecasts or estimates; 14 - Administrative, management and supervisory bodies and senior management; 15 - Compensation and benefits; 16 - Functioning of corporate bodies; 17 - Employees; 18 - Principal shareholders; 19 - Transactions with related parties: French state, CEA, EDF group; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information: Share capital, Certificate of incorporation and by-laws; 22 - Major

  15. Passive low energy cooling of buildings

    CERN Document Server

    Givoni, Baruch

    1994-01-01

    A practical sourcebook for building designers, providing comprehensive discussion of the impact of basic architectural choices on cooling efficiency, including the layout and orientation of the structure, window size and shading, exterior color, and even the use of plantings around the site. All major varieties of passive cooling systems are presented, with extensive analysis of performance in different types of buildings and in different climates: ventilation; radiant cooling; evaporative cooling; soil cooling; and cooling of outdoor spaces.

  16. Passiv-Sammler

    OpenAIRE

    Fritsche, U.

    1991-01-01

    The invention relates to a passive collector for air pollution for the determination of emission rates for dry and wet deposits on construction materials such as natural stone, whereby the collector has a surrogate surface of the stone under investigation, the surrogate surface being linked to a collecting vessel such that any dry or wet contamination occurring can be collected.

  17. Passive houses in Norway

    Energy Technology Data Exchange (ETDEWEB)

    Halse, Andreas

    2008-12-15

    The paper analyzes the introduction of passive houses in the Norwegian house market. Passive houses are houses with extremely low levels of energy consumption for heating, and have not yet been built in Norway, but have started to enter the market in Germany and some other countries. The construction sector is analyzed as a sectoral innovation system. The different elements of the innovation system are studied. This includes government agencies, producers, consumers, finance and education. The analysis shows that passive and low-energy houses are on the verge of market breakthrough. This can partly be explained by economic calculations, and partly by processes of learning and change in the institutional set-up of the sector. The construction sector is a sector characterized by low innovative intensity and little interaction between different agents. Those working to promote passive houses have to some extent managed to cope with these challenges. This has happened by breaking away from the traditional focus of Norwegian energy efficiency policies on technology and the economically rational agents, by instead focusing on knowledge and institutional change at the level of the producers. (Author)

  18. Passive THz metamaterials

    DEFF Research Database (Denmark)

    Lavrinenko, Andrei; Malureanu, Radu; Zalkovskij, Maksim

    2012-01-01

    In this work we present our activities in the fabrication and characterization of passive THz metamaterials. We use two fabrication processes to develop metamaterials either as free-standing metallic membranes or patterned metallic multi-layers on the substrates to achieve different functionalities...

  19. AP1000{sup R} nuclear power plant safety overview for spent fuel cooling

    Energy Technology Data Exchange (ETDEWEB)

    Gorgemans, J.; Mulhollem, L.; Glavin, J.; Pfister, A.; Conway, L.; Schulz, T.; Oriani, L.; Cummins, E.; Winters, J. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and costs. The AP1000 design uses passive features to mitigate design basis accidents. The passive safety systems are designed to function without safety-grade support systems such as AC power, component cooling water, service water or HVAC. Furthermore, these passive features 'fail safe' during a non-LOCA event such that DC power and instrumentation are not required. The AP1000 also has simple, active, defense-in-depth systems to support normal plant operations. These active systems provide the first level of defense against more probable events and they provide investment protection, reduce the demands on the passive features and support the probabilistic risk assessment. The AP1000 passive safety approach allows the plant to achieve and maintain safe shutdown in case of an accident for 72 hours without operator action, meeting the expectations provided in the U.S. Utility Requirement Document and the European Utility Requirements for passive plants. Limited operator actions are required to maintain safe conditions in the spent fuel pool via passive means. In line with the AP1000 approach to safety described above, the AP1000 plant design features multiple, diverse lines of defense to ensure spent fuel cooling can be maintained for design-basis events and beyond design-basis accidents. During normal and abnormal conditions, defense-in-depth and other systems provide highly reliable spent fuel pool cooling. They rely on off-site AC power or the on-site standby diesel generators. For unlikely design basis events with an extended loss of AC power (i.e., station blackout) or loss of heat sink or both, spent fuel cooling can still be provided indefinitely: - Passive systems, requiring minimal or no operator actions, are sufficient for at least 72 hours under all

  20. Dose Modeling Evaluations and Technical Support Document For the Authorized Limits Request for the DOE-Owned Property Outside the Limited Area, Paducah Gaseous Diffusion Plant Paducah, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    Boerner, A. J. [Oak Ridge Institute for Science and Education (ORISE), Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program; Maldonado, D. G. [Oak Ridge Institute for Science and Education (ORISE), Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program; Hansen, Tom [Ameriphysics, LLC (United States)

    2012-09-01

    Environmental assessments and remediation activities are being conducted by the U.S. Department of Energy (DOE) at the Paducah Gaseous Diffusion Plant (PGDP), Paducah, Kentucky. The Oak Ridge Institute for Science and Education (ORISE), a DOE prime contractor, was contracted by the DOE Portsmouth/Paducah Project Office (DOE-PPPO) to conduct radiation dose modeling analyses and derive single radionuclide soil guidelines (soil guidelines) in support of the derivation of Authorized Limits (ALs) for 'DOE-Owned Property Outside the Limited Area' ('Property') at the PGDP. The ORISE evaluation specifically included the area identified by DOE restricted area postings (public use access restrictions) and areas licensed by DOE to the West Kentucky Wildlife Management Area (WKWMA). The licensed areas are available without restriction to the general public for a variety of (primarily) recreational uses. Relevant receptors impacting current and reasonably anticipated future use activities were evaluated. In support of soil guideline derivation, a Conceptual Site Model (CSM) was developed. The CSM listed radiation and contamination sources, release mechanisms, transport media, representative exposure pathways from residual radioactivity, and a total of three receptors (under present and future use scenarios). Plausible receptors included a Resident Farmer, Recreational User, and Wildlife Worker. single radionuclide soil guidelines (outputs specified by the software modeling code) were generated for three receptors and thirteen targeted radionuclides. These soil guidelines were based on satisfying the project dose constraints. For comparison, soil guidelines applicable to the basic radiation public dose limit of 100 mrem/yr were generated. Single radionuclide soil guidelines from the most limiting (restrictive) receptor based on a target dose constraint of 25 mrem/yr were then rounded and identified as the derived soil guidelines. An additional evaluation using the derived soil

  1. Dose Modeling Evaluations and Technical Support Document For the Authorized Limits Request for the DOE-Owned Property Outside the Limited Area, Paducah Gaseous Diffusion Plant Paducah, Kentucky

    International Nuclear Information System (INIS)

    Boerner, A. J.

    2012-01-01

    Environmental assessments and remediation activities are being conducted by the U.S. Department of Energy (DOE) at the Paducah Gaseous Diffusion Plant (PGDP), Paducah, Kentucky. The Oak Ridge Institute for Science and Education (ORISE), a DOE prime contractor, was contracted by the DOE Portsmouth/Paducah Project Office (DOE-PPPO) to conduct radiation dose modeling analyses and derive single radionuclide soil guidelines (soil guidelines) in support of the derivation of Authorized Limits (ALs) for 'DOE-Owned Property Outside the Limited Area' ('Property') at the PGDP. The ORISE evaluation specifically included the area identified by DOE restricted area postings (public use access restrictions) and areas licensed by DOE to the West Kentucky Wildlife Management Area (WKWMA). The licensed areas are available without restriction to the general public for a variety of (primarily) recreational uses. Relevant receptors impacting current and reasonably anticipated future use activities were evaluated. In support of soil guideline derivation, a Conceptual Site Model (CSM) was developed. The CSM listed radiation and contamination sources, release mechanisms, transport media, representative exposure pathways from residual radioactivity, and a total of three receptors (under present and future use scenarios). Plausible receptors included a Resident Farmer, Recreational User, and Wildlife Worker. single radionuclide soil guidelines (outputs specified by the software modeling code) were generated for three receptors and thirteen targeted radionuclides. These soil guidelines were based on satisfying the project dose constraints. For comparison, soil guidelines applicable to the basic radiation public dose limit of 100 mrem/yr were generated. Single radionuclide soil guidelines from the most limiting (restrictive) receptor based on a target dose constraint of 25 mrem/yr were then rounded and identified as the derived soil guidelines. An additional evaluation using the derived soil

  2. Early Site Permit Demonstration Program: Plant parameters envelope report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    The Early Site Permit (ESP) Demonstration Program is the nuclear industry`s initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants.

  3. PUREX Deactivation Health and Safety documentation

    International Nuclear Information System (INIS)

    Dodd, E.N. III.

    1995-01-01

    The purpose of the PUREX Deactivation Project is to establish a passively safe and environmentally secure configuration of PUREX at the Hanford Site, and to preserve that configuration for a 10-year horizon. The 10-year horizon is used to predict future maintenance requirements and represents they typical time duration expended to define, authorize, and initiate the follow-on Decontamination and Decommissioning (D ampersand D) activities. This document was prepared to increase attention to worker safety issues during the deactivation project and, as such, identifies the documentation and programs associated with PUREX Deactivation Health and Safety

  4. PUREX Deactivation Health and Safety documentation

    Energy Technology Data Exchange (ETDEWEB)

    Dodd, E.N. III

    1995-01-01

    The purpose of the PUREX Deactivation Project is to establish a passively safe and environmentally secure configuration of PUREX at the Hanford Site, and to preserve that configuration for a 10-year horizon. The 10-year horizon is used to predict future maintenance requirements and represents they typical time duration expended to define, authorize, and initiate the follow-on Decontamination and Decommissioning (D&D) activities. This document was prepared to increase attention to worker safety issues during the deactivation project and, as such, identifies the documentation and programs associated with PUREX Deactivation Health and Safety.

  5. Intrinsically Passive Handling and Grasping

    NARCIS (Netherlands)

    Stramigioli, Stefano; Scherpen, Jacquelien M.A.; Khodabandehloo, Koorosh

    2000-01-01

    The paper presents a control philosophy called Intrinsically Passive Control, which has the feature to properly behave during interaction with any passive objects. The controlled robot will never become unstable due to the physical structure of the controller.

  6. Areva - 2014 Reference document

    International Nuclear Information System (INIS)

    2015-01-01

    Areva supplies high added-value products and services to support the operation of the global nuclear fleet. The company is present throughout the entire nuclear cycle, from uranium mining to used fuel recycling, including nuclear reactor design and operating services. Areva is recognized by utilities around the world for its expertise, its skills in cutting-edge technologies and its dedication to the highest level of safety. Areva's 44,000 employees are helping build tomorrow's energy model: supplying ever safer, cleaner and more economical energy to the greatest number of people. This Reference Document contains information on Areva's objectives, prospects and development strategies. It contains estimates of the markets, market shares and competitive position of Areva. Contents: 1 - Person responsible; 2 - Statutory auditors; 3 - Selected financial information; 4 - Risk factors; 5 - Information about the issuer; 6 - Business overview; 7 - Organizational structure; 8 - Property, plant and equipment; 9 - Analysis of and comments on the group's financial position and performance; 10 - Capital resources; 11 - Research and development programs, patents and licenses; 12 - Trend information; 13 - Profit forecasts; 14 - Administrative, management and supervisory bodies and senior management; 15 - Compensation and benefits; 16 - Functioning of administrative, management and supervisory bodies and senior management; 17 - Employees; 18 - Principal shareholders; 19 - Transactions with related parties; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information; 22 - Major contracts; 23 - Third party information, statements by experts and declarations of interest; 24 - Documents on display; 25 - information on holdings; appendix: Report of the Chairman of the Board of Directors on governance, internal control procedures and risk management, Statutory Auditors' report, Corporate social

  7. Advances in passive cooling design and performance analysis

    International Nuclear Information System (INIS)

    Woodcock, J.

    1994-01-01

    The Third International Conference on Containment Design and Operation continues the trend of rapidly extending the state of the art in containment methodology, joining other conferences, OECD-sponsored International Standard Problem exercises, and vendor licensing submittals. Methodology developed for use on plants with passive features is under increasing scrutiny for advanced designs, since the passive features are often the only deviation from existing operating base of the past 30 years of commercial nuclear power. This session, 'Containment Passive Safety Systems Design and Operation,' offers papers on a wide range of topics, with authors from six organizations from around the world, dealing with general passive containments, Westinghouse AP600, large (>1400 MWe) passive plants, and the AECL advanced CANDU reactor. This level and variety of participation underscores the high interest and accelerated methods development associated with advanced passive containment heat removal. The papers presented in this session demonstrate that significant contributions are being made to the advancement of technology necessary for building a new generation of safer, more economical nuclear plants. (author)

  8. An approach for assessing ALWR passive safety system reliability

    International Nuclear Information System (INIS)

    Hake, T.M.

    1991-01-01

    Many of the advanced light water reactor (ALWR) concepts proposed for the next generation of nuclear power plants rely on passive rather than active systems to perform safety functions. Despite the reduced redundancy of the passive systems as compared to active systems in current plants, the assertion is that the overall safety of the plant is enhanced due to the much higher expected reliability of the passive systems. In order to investigate this assertion, a study is being conducted at Sandia National Laboratories to evaluate the reliability of ALWR passive safety features in the context of probabilistic risk assessment (PRA). The purpose of this paper is to provide a brief overview of the approach to this study. The quantification of passive system reliability is not as straightforward as for active systems, due to the lack of operating experience, and to the greater uncertainty in the governing physical phenomena. Thus, the adequacy of current methods for evaluating system reliability must be assessed, and alternatives proposed if necessary. For this study, the Westinghouse Advanced Passive 600 MWe reactor (AP600) was chosen as the advanced reactor for analysis, because of the availability of AP600 design information. This study compares the reliability of AP600 emergency cooling system with that of corresponding systems in a current generation reactor

  9. Passive solar heating

    Energy Technology Data Exchange (ETDEWEB)

    Wiberg, K

    1981-11-10

    The present work treats the possibilities for heating according to the passive solar heating method. Problems of 'spatial organization in an energy-saving society' are distinguished from among other social problems. The final delimination of the actual problems under investigation consists of the use of passive solar heating and especially the 'consequences of such solar heating exploitation upon the form and structures' of planning and construction. In the concluding chapter an applied example shows how this method can be used in designing an urban area and what are its limitations. The results indicate the possibilities and difficulties in attempting to transfer this ideal and general method into models and directives for form and structure from which examples of the actual possibilities in practical planning can be given.

  10. PFP MICON DCS computer software documentation

    Energy Technology Data Exchange (ETDEWEB)

    Silvan, G.R.

    1996-03-26

    This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs.

  11. PFP MICON DCS computer software documentation

    International Nuclear Information System (INIS)

    Silvan, G.R.

    1996-01-01

    This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs

  12. Honeywell Modular Automation System Computer Software Documentation

    International Nuclear Information System (INIS)

    CUNNINGHAM, L.T.

    1999-01-01

    This document provides a Computer Software Documentation for a new Honeywell Modular Automation System (MAS) being installed in the Plutonium Finishing Plant (PFP). This system will be used to control new thermal stabilization furnaces in HA-211 and vertical denitration calciner in HC-230C-2

  13. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  14. Safety related terms for advanced nuclear plants

    International Nuclear Information System (INIS)

    1991-09-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety

  15. Qademah Fault Passive Data

    KAUST Repository

    Hanafy, Sherif M.

    2014-01-01

    OBJECTIVE: In this field trip we collect passive data to 1. Convert passive to surface waves 2. Locate Qademah fault using surface wave migration INTRODUCTION: In this field trip we collected passive data for several days. This data will be used to find the surface waves using interferometry and then compared to active-source seismic data collected at the same location. A total of 288 receivers are used. A 3D layout with 5 m inline intervals and 10 m cross line intervals is used, where we used 12 lines with 24 receivers at each line. You will need to download the file (rec_times.mat), it contains important information about 1. Field record no 2. Record day 3. Record month 4. Record hour 5. Record minute 6. Record second 7. Record length P.S. 1. All files are converted from original format (SEG-2) to matlab format P.S. 2. Overlaps between records (10 to 1.5 sec.) are already removed from these files

  16. Results of a Demonstration Assessment of Passive System Reliability Utilizing the Reliability Method for Passive Systems (RMPS)

    Energy Technology Data Exchange (ETDEWEB)

    Bucknor, Matthew; Grabaskas, David; Brunett, Acacia; Grelle, Austin

    2015-04-26

    Advanced small modular reactor designs include many advantageous design features such as passively driven safety systems that are arguably more reliable and cost effective relative to conventional active systems. Despite their attractiveness, a reliability assessment of passive systems can be difficult using conventional reliability methods due to the nature of passive systems. Simple deviations in boundary conditions can induce functional failures in a passive system, and intermediate or unexpected operating modes can also occur. As part of an ongoing project, Argonne National Laboratory is investigating various methodologies to address passive system reliability. The Reliability Method for Passive Systems (RMPS), a systematic approach for examining reliability, is one technique chosen for this analysis. This methodology is combined with the Risk-Informed Safety Margin Characterization (RISMC) approach to assess the reliability of a passive system and the impact of its associated uncertainties. For this demonstration problem, an integrated plant model of an advanced small modular pool-type sodium fast reactor with a passive reactor cavity cooling system is subjected to a station blackout using RELAP5-3D. This paper discusses important aspects of the reliability assessment, including deployment of the methodology, the uncertainty identification and quantification process, and identification of key risk metrics.

  17. Registration document 2005; Document de reference 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This reference document of Gaz de France provides information and data on the Group activities in 2005: financial informations, business, activities, equipments factories and real estate, trade, capital, organization charts, employment, contracts and research programs. (A.L.B.)

  18. 2002 reference document; Document de reference 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    This 2002 reference document of the group Areva, provides information on the society. Organized in seven chapters, it presents the persons responsible for the reference document and for auditing the financial statements, information pertaining to the transaction, general information on the company and share capital, information on company operation, changes and future prospects, assets, financial position, financial performance, information on company management and executive board and supervisory board, recent developments and future prospects. (A.L.B.)

  19. Can passive house be the solution to our energy problems, and particularly with solar energy?

    OpenAIRE

    Merciadri, Luca

    2007-01-01

    A description about the main characteristics of the passive house concept. The aim of this document is to answer to the question ``Can passive house be the solution to our energy problems, and particularly with solar energy ?'' in an objective way.

  20. Web document engineering

    International Nuclear Information System (INIS)

    White, B.

    1996-05-01

    This tutorial provides an overview of several document engineering techniques which are applicable to the authoring of World Wide Web documents. It illustrates how pre-WWW hypertext research is applicable to the development of WWW information resources

  1. Enterprise Document Management

    Data.gov (United States)

    US Agency for International Development — The function of the operation is to provide e-Signature and document management support for Acquisition and Assisitance (A&A) documents including vouchers in...

  2. Experimental research progress on passive safety systems of Chinese advanced PWR

    International Nuclear Information System (INIS)

    Xiao Zejun; Zhuo Wenbin; Zheng Hua; Chen Bingde; Zong Guifang; Jia Dounan

    2003-01-01

    TMI and Chernobyl accidents, having pronounced impact on nuclear industries, triggered the governments as well as interested institutions to devote much attention to the safety of nuclear power plant and public's requirements on nuclear power plant safety were also going to be stricter and stricter. It is obvious that safety level of an ordinary light water reactor is no longer satisfactory to these requirements. Recently, the safety authorities have recommended the implementation of passive system to improve the safety of nuclear reactors. Passive safety system is one of the main differences between Chinese advanced PWR and other conventional PWR. The working principle of passive safety system is to utilize the gravity, natural convection (natural circulation) and stored energy to implement the system's safety function. Reactors with passive safety systems are not only safer, but also more economical. The passive safety system of Chinese advanced PWR is composed of three independent systems, i.e. passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system. This paper is a summary of experimental research progress on passive containment cooling system, passive residual heat removal system and passive core makeup tank injection system

  3. Tank Waste Remediation System Projects Document Control Plan

    International Nuclear Information System (INIS)

    Slater, G.D.; Halverson, T.G.

    1994-01-01

    The purpose of this Tank Waste Remediation System Projects Document Control Plan is to provide requirements and responsibilities for document control for the Hanford Waste Vitrification Plant (HWVP) Project and the Initial Pretreatment Module (IPM) Project

  4. Documenting Employee Conduct

    Science.gov (United States)

    Dalton, Jason

    2009-01-01

    One of the best ways for a child care program to lose an employment-related lawsuit is failure to document the performance of its employees. Documentation of an employee's performance can provide evidence of an employment-related decision such as discipline, promotion, or discharge. When properly implemented, documentation of employee performance…

  5. Documents preparation and review

    International Nuclear Information System (INIS)

    1999-01-01

    Ignalina Safety Analysis Group takes active role in assisting regulatory body VATESI to prepare various regulatory documents and reviewing safety reports and other documentation presented by Ignalina NPP in the process of licensing of unit 1. The list of main documents prepared and reviewed is presented

  6. Passive appendages generate drift through symmetry breaking

    Science.gov (United States)

    Lācis, U.; Brosse, N.; Ingremeau, F.; Mazzino, A.; Lundell, F.; Kellay, H.; Bagheri, S.

    2014-10-01

    Plants and animals use plumes, barbs, tails, feathers, hairs and fins to aid locomotion. Many of these appendages are not actively controlled, instead they have to interact passively with the surrounding fluid to generate motion. Here, we use theory, experiments and numerical simulations to show that an object with a protrusion in a separated flow drifts sideways by exploiting a symmetry-breaking instability similar to the instability of an inverted pendulum. Our model explains why the straight position of an appendage in a fluid flow is unstable and how it stabilizes either to the left or right of the incoming flow direction. It is plausible that organisms with appendages in a separated flow use this newly discovered mechanism for locomotion; examples include the drift of plumed seeds without wind and the passive reorientation of motile animals.

  7. Passive appendages aid locomotion through symmetry breaking

    Science.gov (United States)

    Bagheri, Shervin; Lacis, Ugis; Mazzino, Andrea; Kellay, Hamid; Brosse, Nicolas; Lundell, Fredrik; Ingremeau, Francois

    2014-11-01

    Plants and animals use plumes, barbs, tails, feathers, hairs, fins, and other types of appendages to aid locomotion. Despite their enormous variation, passive appendages may contribute to locomotion by exploiting the same physical mechanism. We present a new mechanism that applies to body appendages surrounded by a separated flow, which often develops behind moving bodies larger than a few millimeters. We use theory, experiments, and numerical simulations to show that bodies with protrusions turn and drift by exploiting a symmetry-breaking instability similar to the instability of an inverted pendulum. Our model explains why the straight position of an appendage in flowing fluid is unstable and how it stabilizes either to the left or right of the incoming fluid flow direction. The discovery suggests a new mechanism of locomotion that may be relevant for certain organisms; for example, how plumed seeds may drift without wind and how motile animals may passively reorient themselves.

  8. Passive cooling of control rod drive mechanisms

    International Nuclear Information System (INIS)

    Hankinson, M.F.; Schwirian, R.E.

    1992-01-01

    A method and apparatus are provided for passively cooling the control rod drive mechanisms (CRDMs) in the reactor vessel of a nuclear power plant. Passive cooling is achieved by dispersing a plurality of chimneys within the CRDM array in positions where a control rod is not required. The chimneys induce convective air currents which cause ambient air from within the containment to flow over the CRDM coils. The air heated by the coils is guided into inlets in the chimneys by baffles. The chimney is insulated and extends through the seismic support platform and missile shield disposed above the closure head. A collar of adjustable height mates with plate elements formed at the distal end of the CRDM pressure housings by an interlocking arrangement so that the seismic support platform provides lateral restraint for the chimneys. (Author)

  9. Incorporation of passive components aging into PRAs

    International Nuclear Information System (INIS)

    Phillips, J.H.; Roesener, W.S.; Magleby, H.L.; Geidl, V.

    1993-01-01

    The probabilistic risk assessments being developed at most nuclear power plants to calculate the risk of core damage generally focus on the possible failure of active components. The possible failure of passive components is given little consideration. We are developing a method for selecting risk-significant passive components and including them in probabilistic risk assessments. We demonstrated the method by selecting a weld in the auxiliary feedwater system. The selection of this component was based on expert judgement of the likelihood of failure and on an estimate of the consequence of component failure to plant safety. We then used the PRAISE computer code to perform a probabilistic structural analysis to calculate the probability that crack growth due to aging would cause the weld to fail. The calculation included the effects of mechanical loads and thermal transients considered in the design and the effects of thermal cycling caused by a leaking check valve. We modified an existing probabilistic risk assessment (NUREG-1150 plant) to include the possible failure of the auxiliary feedwater weld, and then we used the weld failure probability as input to the modified probabilistic risk assessment to calculate the change in plant risk with time. The results showed that if the failure probability of the selected weld is high, the effect on plant risk is significant. However, this particular calculation showed a very low weld failure probability and no change in plant risk for the 48 years of service analyzed. The success of this demonstration shows that this method could be applied to nuclear power plants. (orig.)

  10. Guidelines for the review of accident management programmes in nuclear power plants. Reference document for the IAEA safety service missions on review of accident management programmes in nuclear power plants

    International Nuclear Information System (INIS)

    2003-01-01

    Similarly as for other IAEA safety services, the objectives of accident management safety service are to assist the Member States in ensuring and enhancing the safety of NPPs. In particular, the objective is to assist at the utility and NPP (i.e. licensee) level in effective plant specific AMP preparation, development and implementation. However, assistance can also be provided to the regulatory body in its reviewing of AMPs. Objectives of the safety service can be summarized as follows: To explain to licensee personnel principles and possible approaches in effective implementation of AMP based on experience world-wide; To give opportunities to experts from the host plant to broaden their experience and knowledge in the field; To perform an objective assessment of the status in various phases of AMP implementation, compared with international experience and practices; To provide the licensee with suggestions and assistance for improvements in various stages of AMP implementation. The objective of the IAEA safety services is to offer two options to respond to individual requirements. These options include missions to review accident analysis needed for accident management and missions to review the whole AMP. Review of accident analysis for accident management (RAAAM): this review is intended to check completeness and quality of accident analysis covering BDBA and severe accidents. The review should be typically performed prior to use of accident analysis for development of AMP. It is considered that 2 experts and 1 IAEA team leader in one-week mission can perform the review. Detailed guidelines for review of analysis are provided in Section 2. Reference is also made to another IAEA Safety Report (Safety Standards Series No. NS-R-1) which is devoted to guidance for accident analysis of nuclear power plants (NPPs). Review of AMP (RAMP): this review of AMP, which is in particular appropriate prior to its implementation, is intended to check its quality, consistency

  11. Passive Power Filters

    CERN Document Server

    Künzi, R.

    2015-06-15

    Power converters require passive low-pass filters which are capable of reducing voltage ripples effectively. In contrast to signal filters, the components of power filters must carry large currents or withstand large voltages, respectively. In this paper, three different suitable filter struc tures for d.c./d.c. power converters with inductive load are introduced. The formulas needed to calculate the filter components are derived step by step and practical examples are given. The behaviour of the three discussed filters is compared by means of the examples. P ractical aspects for the realization of power filters are also discussed.

  12. Old TNX Seepage Basin: Environmental information document

    International Nuclear Information System (INIS)

    Dunaway, J.K.; Johnson, W.F.; Kingley, L.E.; Simmons, R.V.; Bledsoe, H.W.; Smith, J.A.

    1986-12-01

    This document provides environmental information on postulated closure options for the Old TNX Seepage Basin at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1500-1508). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a regulatory closure plan or other regulatory document to comply with required federal or state environmental regulations

  13. Starlink Document Styles

    Science.gov (United States)

    Lawden, M. D.

    This document describes the various styles which are recommended for Starlink documents. It also explains how to use the templates which are provided by Starlink to help authors create documents in a standard style. This paper is concerned mainly with conveying the ``look and feel" of the various styles of Starlink document rather than describing the technical details of how to produce them. Other Starlink papers give recommendations for the detailed aspects of document production, design, layout, and typography. The only style that is likely to be used by most Starlink authors is the Standard style.

  14. Subject (of documents)

    DEFF Research Database (Denmark)

    Hjørland, Birger

    2017-01-01

    This article presents and discuss the concept “subject” or subject matter (of documents) as it has been examined in library and information science (LIS) for more than 100 years. Different theoretical positions are outlined and it is found that the most important distinction is between document......-oriented views versus request-oriented views. The document-oriented view conceive subject as something inherent in documents, whereas the request-oriented view (or the policy based view) understand subject as an attribution made to documents in order to facilitate certain uses of them. Related concepts...

  15. Expansion of passive safety function

    International Nuclear Information System (INIS)

    Inai, Nobuhiko; Nei, Hiromichi; Kumada, Toshiaki.

    1995-01-01

    Expansion of the use of passive safety functions is proposed. Two notions are presented. One is that, in the design of passive safety nuclear reactors where aversion of active components is stressed, some active components are purposely introduced, by which a system is built in such a way that it behaves in an apparently passive manner. The second notion is that, instead of using a passive safety function alone, a passive safety function is combined with some active components, relating the passivity in the safety function with enhanced controllability in normal operation. The nondormant system which the authors propose is one example of the first notion. This is a system in which a standby safety system is a portion of the normal operation system. An interpretation of the nondormant system via synergetics is made. As an example of the second notion, a PIUS density lock aided with active components is proposed and is discussed

  16. Passive cooling containment study

    International Nuclear Information System (INIS)

    Shin, J.J.; Iotti, R.C.; Wright, R.F.

    1993-01-01

    Pressure and temperature transients of nuclear reactor containment following postulated loss of coolant accident with a coincident station blackout due to total loss of all alternating current power are studied analytically and experimentally for the full scale NPR (New Production Reactor). All the reactor and containment cooling under this condition would rely on the passive cooling system which removes reactor decay heat and provides emergency core and containment cooling. Containment passive cooling for this study takes place in the annulus between containment steel shell and concrete shield building by natural convection air flow and thermal radiation. Various heat transfer coefficients inside annular air space were investigated by running the modified CONTEMPT code CONTEMPT-NPR. In order to verify proper heat transfer coefficient, temperature, heat flux, and velocity profiles were measured inside annular air space of the test facility which is a 24 foot (7.3m) high, steam heated inner cylinder of three foot (.91m) diameter and five and half foot (1.7m) diameter outer cylinder. Comparison of CONTEMPT-NPR and WGOTHIC was done for reduced scale NPR

  17. Fly ash carbon passivation

    Science.gov (United States)

    La Count, Robert B; Baltrus, John P; Kern, Douglas G

    2013-05-14

    A thermal method to passivate the carbon and/or other components in fly ash significantly decreases adsorption. The passivated carbon remains in the fly ash. Heating the fly ash to about 500 and 800 degrees C. under inert gas conditions sharply decreases the amount of surfactant adsorbed by the fly ash recovered after thermal treatment despite the fact that the carbon content remains in the fly ash. Using oxygen and inert gas mixtures, the present invention shows that a thermal treatment to about 500 degrees C. also sharply decreases the surfactant adsorption of the recovered fly ash even though most of the carbon remains intact. Also, thermal treatment to about 800 degrees C. under these same oxidative conditions shows a sharp decrease in surfactant adsorption of the recovered fly ash due to the fact that the carbon has been removed. This experiment simulates the various "carbon burnout" methods and is not a claim in this method. The present invention provides a thermal method of deactivating high carbon fly ash toward adsorption of AEAs while retaining the fly ash carbon. The fly ash can be used, for example, as a partial Portland cement replacement in air-entrained concrete, in conductive and other concretes, and for other applications.

  18. Field demonstrations of passive detectors for screening of alpha contaminated soils

    International Nuclear Information System (INIS)

    Meyer, K.E.; Gammage, R.B.; Dudney, C.S.

    1994-01-01

    There are numerous sites around the country, DOE and otherwise, that are faced with the daunting task of remediating radiologically contaminated soils and groundwaters. Some of these sites, such as the Nevada Test Site and the Rocky Flats Plant, have contaminants that have been dispersed over wide areas. The costs of the characterization phase alone for such remediation programs can be prohibitive. Therefore there are pressing needs for testing and evaluation of new technologies for screening for radiological contaminants that may offer significant advantages in capital costs, ease of use, sensitivity, ruggedness, and/or reliability. This work reports on laboratory and Field tests of two types of passive alpha detectors, electret ionization chambers (EIC's) and alpha track detectors (ATD's), that have been commercially developed for indoor radon measurements. Previous work documented calibration and measurement protocols developed for these detectors for indoor surface contamination measurements

  19. Areva - 2011 Reference document; Areva - Document de reference 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    After having indicated the person responsible of this document and the legal account auditors, and provided some financial information, this document gives an overview of the different risk factors existing in the company: law risks, industrial and environmental risks, operational risks, risks related to large projects, market and liquidity risks. Then, after having recalled the history and evolution of the company and the evolution of its investments over the last five years, it proposes an overview of Areva's activities on the markets of nuclear energy and renewable energies, of its clients and suppliers, of its strategy, of the activities of its different departments. Other information are provided: company's flow chart, estate properties (plants, equipment), an analysis of its financial situation, its research and development policy, the present context, profit previsions or estimations, management organization and operation

  20. Surface Passivation in Empirical Tight Binding

    OpenAIRE

    He, Yu; Tan, Yaohua; Jiang, Zhengping; Povolotskyi, Michael; Klimeck, Gerhard; Kubis, Tillmann

    2015-01-01

    Empirical Tight Binding (TB) methods are widely used in atomistic device simulations. Existing TB methods to passivate dangling bonds fall into two categories: 1) Method that explicitly includes passivation atoms is limited to passivation with atoms and small molecules only. 2) Method that implicitly incorporates passivation does not distinguish passivation atom types. This work introduces an implicit passivation method that is applicable to any passivation scenario with appropriate parameter...

  1. Passive components used in power converters

    CERN Document Server

    Rufer, A; Barrade, P

    2006-01-01

    In power converters, passive components play an important role, and have in general specific nature and properties. The goal of this tutorial is to give an overview, first on inductive components for power conversion, and second on dedicated power capacitors. In a third part, new components— supercapacitors—will be presented. Generally, inductors for power applications must be custom designed. In this tutorial, the most important effects encountered when realising inductive components will be presented in the first part, without entering into the detailed design of such components. For that purpose, the referenced documents that have served as a base for this tutorial must be consulted [1], [2], and mainly [3]. The second part of this tutorial (Capacitors used in power electronics) is dedicated to power capacitors. Unlike inductors, capacitors cannot be specifically designed, but must be selected from a manufacturer’s list of components. Here, the documentation corresponds to a subset of Ref. [4] that h...

  2. Passive-solar construction handbook

    Energy Technology Data Exchange (ETDEWEB)

    Levy, E.; Evans, D.; Gardstein, C.

    1981-02-01

    Many of the basic elements of passive solar design are reviewed. Passive solar construction is covered according to system type, each system type discussion including a general discussion of the important design and construction issues which apply to the particular system and case studies illustrating designed and built examples of the system type. The three basic types of passive solar systems discussed are direct gain, thermal storage wall, and attached sunspace. Thermal performance and construction information is presented for typical materials used in passive solar collector components, storage components, and control components. Appended are an overview of analysis methods and a technique for estimating performance. (LEW)

  3. The passive safety systems of the Swr 1000

    International Nuclear Information System (INIS)

    Neumann, D.

    2001-01-01

    In recent years, a new boiling water reactor (BWR) plant called the SWR 1000 has been developed by Siemens on behalf of Germany's electric utilities. This new plant design concept incorporates the wide range of operating experience gained with German BWRs. The main objective behind developing the SWR 1000 was to design a plant with a rated electric output of approximately 1000 MW which would not only have a lower capital cost and lower power generating costs but would also provide a much higher level of nuclear safety compared to plants currently in operation. This safety-related goal has been met through, for example, the use of passive safety equipment. Passive systems make a significant contribution towards increasing the over-all level of plant safety due to the way in which they operate. They function solely accord-ing to basic laws of nature, such as gravity, and perform their designated functions with-out any need for electric power or other sources of external energy, or signals from instrumentation and control (I and C) equipment. The passive safety systems have been designed such that design basis accidents can be controlled using just these systems alone. However, the design concept of the SWR 1000 is nevertheless still based on the provision of active safety systems in addition to passive systems. (author)

  4. Age-Related Degradation of Nuclear Power Plant Structures and Components

    International Nuclear Information System (INIS)

    Braverman, J.; Chang, T.-Y.; Chokshi, N.; Hofmayer, C.; Morante, R.; Shteyngart, S.

    1999-01-01

    This paper summarizes and highlights the results of the initial phase of a research project on the assessment of aged and degraded structures and components important to the safe operation of nuclear power plants (NPPs). A review of age-related degradation of structures and passive components at NPPs was performed. Instances of age-related degradation have been collected and reviewed. Data were collected from plant generated documents such as Licensing Event Reports, NRC generic communications, NUREGs and industry reports. Applicable cases of degradation occurrences were reviewed and then entered into a computerized database. The results obtained from the review of degradation occurrences are summarized and discussed. Various trending analyses were performed to identify which structures and components are most affected, whether degradation occurrences are worsening, and what was the most common aging mechanisms. The paper also discusses potential aging issues and degradation-susceptible structures and passive components which would have the greatest impact on plant risk

  5. A fully updated version of the European utility requirement (EUR) documents is to be available

    International Nuclear Information System (INIS)

    Chatry, J.P.; Berbey, P.

    2001-01-01

    The major European electricity producers have worked on a common requirement document for future LWR plants since 1992 to get specifications acceptable together by the owners, the public and the authorities. Thus the designers can develop standard LWR designs that could be acceptable everywhere in Europe and the utilities can open their consultations to vendors on common bases. Public and authority's acceptance should be improved as well. Significant savings are expected in development and construction costs. Since the release of the last versions of the EUR texts in 1996, a lot of work has been carried out: reviews by the regulators and other external organisations, comparisons, assessment of compliance of designs vs. EUR and clarification works on the controversial topics that deserved changes or clarification. At the beginning of 1999 enough material was available to start a complete revision of the EUR document. Volumes 1 and 2 of the EUR document list generic nuclear island requirements. The main NPP vendors are developing advanced LWR designs for the European market, with reference to the EUR document. Volume 3 deals with the application of EUR to those designs. The EUR utilities -with contributions of the vendors- are writing specific parts of the EUR document that address some of these designs. Each part includes a plant description and an assessment of its level of compliance with EUR. The first three parts deal with EPR (1500 MW PWR developed by NPI, Framatome and Siemens), EPP (1000 MW PWR with passive safety features developed by Westinghouse and Ansaldo) and BWR 90 (1300 MW BWR developed by ABB Atom). Two other subsets are: one for ABWR (1300 MW BWR developed by GE), the other one for SWR 1000 (1000 MW BWR with passive safety features developed by Siemens). This large and diverse set of designs actually gives the EUR document a very strong base. Revision B of Volume 4 incorporates responses to the comments collected on revision A. Considering all that

  6. Engineered safeguards and passive safety features (safety analysis detailed report no. 6)

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-15

    The Safety-Analysis Summary lists the reactor's safety aspects for passive and active prevention of severe accidents and mitigation of accident consequences, i.e., intrinsic and passive protections of the plant; intrinsic and passive protections of the core; inherent decay-heat removal systems; rapid-shutdown systems; four physical containment barriers. This report goes into further details regarding some of this aspects.

  7. Scheme Program Documentation Tools

    DEFF Research Database (Denmark)

    Nørmark, Kurt

    2004-01-01

    are separate and intended for different documentation purposes they are related to each other in several ways. Both tools are based on XML languages for tool setup and for documentation authoring. In addition, both tools rely on the LAML framework which---in a systematic way---makes an XML language available...... as named functions in Scheme. Finally, the Scheme Elucidator is able to integrate SchemeDoc resources as part of an internal documentation resource....

  8. Get It Right First Time: A Beginner's Guide to Document Management.

    Science.gov (United States)

    Hayes, Mike

    1997-01-01

    Document management (DM) systems capture, store, index, retrieve, route, distribute, and archive information in organizations. Discusses "passive" electronic libraries and "active" systems; characteristics of effective systems; implementing a system; fitting a new system to an existing infrastructure; budgets; system…

  9. Health physics documentation

    International Nuclear Information System (INIS)

    Stablein, G.

    1980-01-01

    When dealing with radioactive material the health physicist receives innumerable papers and documents within the fields of researching, prosecuting, organizing and justifying radiation protection. Some of these papers are requested by the health physicist and some are required by law. The scope, quantity and deposit periods of the health physics documentation at the Karlsruhe Nuclear Research Center are presented and rationalizing methods discussed. The aim of this documentation should be the application of physics to accident prevention, i.e. documentation should protect those concerned and not the health physicist. (H.K.)

  10. CAED Document Repository

    Data.gov (United States)

    U.S. Environmental Protection Agency — Compliance Assurance and Enforcement Division Document Repository (CAEDDOCRESP) provides internal and external access of Inspection Records, Enforcement Actions, and...

  11. CFO Payment Document Management

    Data.gov (United States)

    US Agency for International Development — Paperless management will enable the CFO to create, store, and access various financial documents electronically. This capability will reduce time looking for...

  12. Passive magnetic bearing system

    Science.gov (United States)

    Post, Richard F.

    2014-09-02

    An axial stabilizer for the rotor of a magnetic bearing provides external control of stiffness through switching in external inductances. External control also allows the stabilizer to become a part of a passive/active magnetic bearing system that requires no external source of power and no position sensor. Stabilizers for displacements transverse to the axis of rotation are provided that require only a single cylindrical Halbach array in its operation, and thus are especially suited for use in high rotation speed applications, such as flywheel energy storage systems. The elimination of the need of an inner cylindrical array solves the difficult mechanical problem of supplying support against centrifugal forces for the magnets of that array. Compensation is provided for the temperature variation of the strength of the magnetic fields of the permanent magnets in the levitating magnet arrays.

  13. Passive safety systems for integral reactors

    International Nuclear Information System (INIS)

    Kuul, V.S.; Samoilov, O.B.

    1996-01-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs

  14. Passive safety systems for integral reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kuul, V S; Samoilov, O B [OKB Mechanical Engineering (Russian Federation)

    1996-12-01

    In this paper, a wide range of passive safety systems intended for use on integral reactors is considered. The operation of these systems relies on natural processes and does not require external power supplies. Using these systems, there is the possibility of preventing serious consequences for all classes of accidents including reactivity, loss-of-coolant and loss of heat sink as well as severe accidents. Enhancement of safety system reliability has been achieved through the use of self-actuating devices, capable of providing passive initiation of protective and isolation systems, which respond immediately to variations in the physical parameters of the fluid in the reactor or in a guard vessel. For beyond design base accidents accompanied by complete loss of heat removal capability, autonomous self-actuated ERHR trains have been proposed. These trains are completely independent of the secondary loops and need no action to isolate them from the steam turbine plant. Passive safety principles have been consistently implemented in AST-500, ATETS-200 and VPBER 600 which are new generation NPPs developed by OKBM. Their main characteristic is enhanced stability over a wide range of internal and external emergency initiators. (author). 10 figs.

  15. European vehicle passive safety network

    NARCIS (Netherlands)

    Wismans, J.S.H.M.; Janssen, E.G.

    1999-01-01

    The general objective of the European Vehicle Passive Safety Network is to contribute to the reduction of the number of road traffic victims in Europe by passive safety measures. The aim of the road safety policy of the European Commission is to reduce the annual total of fatalities to 18000 in

  16. Passive films at the nanoscale

    International Nuclear Information System (INIS)

    Maurice, Vincent; Marcus, Philippe

    2012-01-01

    Highlights: ► Nanoscale data on growth, structure and local properties of passive films reviewed. ► Preferential role of defects of passive films on the corrosion resistance emphasized. ► Effect of grain boundaries on local electronic properties shown by new data. ► Use of atomistic modeling to test mechanistic hypotheses illustrated. - Abstract: The nanometer scale chemical and structural aspects of ultrathin oxide passive films providing self-protection against corrosion to metals and alloys in aqueous environments are reviewed. Data on the nucleation and growth of 2D anodic oxide films, details on the atomic structure and nanostructure of 3D passive films, the preferential role of surface step edges in dissolution in the passive state and the preferential role of grain boundaries of the passive films in passivity breakdown are presented. Future perspectives are discussed, and exemplified by new data obtained on the relationship between the nanostructure of oxide passive films and their local electronic properties. Atomistic corrosion modeling by ab initio density functional theory (DFT) is illustrated by the example of interactions of chloride ions with hydroxylated oxide surfaces, including the role of surface step edges. Data obtained on well-defined substrate surfaces with surface analytical techniques are emphasized.

  17. Udviklingen i bilers passive sikkerhed

    DEFF Research Database (Denmark)

    Hels, Tove; Lyckegaard, Allan; Prato, Carlo Giacomo

    man mellem aktiv og passiv sikkerhed, det vil sige faktorer, der nedsætter • risikoen for, at der sker et uheld (aktiv sikkerhed), henholdsvis • graden af alvorlighed, givet at uheldet er sket (passiv sikkerhed). Rapporten begrænser sig til at undersøge, om der kan påvises en generel sammenhæng mellem...

  18. The Passive in Singapore English.

    Science.gov (United States)

    Bao, Zhiming; Wee, Lionel

    1999-01-01

    Presents an analysis of the two passive (or passive-like) constructions in Singapore English which exhibit substrate influence from Malay and Chinese. The paper shows that while substrate languages contribute to the grammar of Singapore English, the continued prestige of standard English exerts normative pressure and mitigates the effect of…

  19. IDC System Specification Document.

    Energy Technology Data Exchange (ETDEWEB)

    Clifford, David J.

    2014-12-01

    This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Reengineering Phase 2 project. Revisions Version Date Author/Team Revision Description Authorized by V1.0 12/2014 IDC Reengineering Project Team Initial delivery M. Harris

  20. INFCE plenary conference documents

    International Nuclear Information System (INIS)

    This document consists of the reports to the First INFCE Plenary Conference (November 1978) by the Working Groups a Plenary Conference of its actions and decisions, the Communique of the Final INFCE Plenary Conference (February 1980), and a list of all documents in the IAEA depository for INFCE

  1. Human Document Project

    NARCIS (Netherlands)

    de Vries, Jeroen; Abelmann, Leon; Manz, A; Elwenspoek, Michael Curt

    2012-01-01

    “The Human Document Project‿ is a project which tries to answer all of the questions related to preserving information about the human race for tens of generations of humans to come or maybe even for a future intelligence which can emerge in the coming thousands of years. This document mainly

  2. Reactive documentation system

    Science.gov (United States)

    Boehnlein, Thomas R.; Kramb, Victoria

    2018-04-01

    Proper formal documentation of computer acquired NDE experimental data generated during research is critical to the longevity and usefulness of the data. Without documentation describing how and why the data was acquired, NDE research teams lose capability such as their ability to generate new information from previously collected data or provide adequate information so that their work can be replicated by others seeking to validate their research. Despite the critical nature of this issue, NDE data is still being generated in research labs without appropriate documentation. By generating documentation in series with data, equal priority is given to both activities during the research process. One way to achieve this is to use a reactive documentation system (RDS). RDS prompts an operator to document the data as it is generated rather than relying on the operator to decide when and what to document. This paper discusses how such a system can be implemented in a dynamic environment made up of in-house and third party NDE data acquisition systems without creating additional burden on the operator. The reactive documentation approach presented here is agnostic enough that the principles can be applied to any operator controlled, computer based, data acquisition system.

  3. Documentation: Records and Reports.

    Science.gov (United States)

    Akers, Michael J

    2017-01-01

    This article deals with documentation to include the beginning of documentation, the requirements of Good Manufacturing Practice reports and records, and the steps that can be taken to minimize Good Manufacturing Practice documentation problems. It is important to remember that documentation for 503a compounding involves the Formulation Record, Compounding Record, Standard Operating Procedures, Safety Data Sheets, etc. For 503b outsourcing facilities, compliance with Current Good Manufacturing Practices is required, so this article is applicable to them. For 503a pharmacies, one can see the development and modification of Good Manufacturing Practice and even observe changes as they are occurring in 503a documentation requirements and anticipate that changes will probably continue to occur. Copyright© by International Journal of Pharmaceutical Compounding, Inc.

  4. Natural circulating passive cooling system for nuclear reactor containment structure

    Science.gov (United States)

    Gou, Perng-Fei; Wade, Gentry E.

    1990-01-01

    A passive cooling system for the contaminant structure of a nuclear reactor plant providing protection against overpressure within the containment attributable to inadvertent leakage or rupture of the system components. The cooling system utilizes natural convection for transferring heat imbalances and enables the discharge of irradiation free thermal energy to the atmosphere for heat disposal from the system.

  5. Passive cooling system for nuclear reactor containment structure

    Science.gov (United States)

    Gou, Perng-Fei; Wade, Gentry E.

    1989-01-01

    A passive cooling system for the contaminant structure of a nuclear reactor plant providing protection against overpressure within the containment attributable to inadvertent leakage or rupture of the system components. The cooling system utilizes natural convection for transferring heat imbalances and enables the discharge of irradiation free thermal energy to the atmosphere for heat disposal from the system.

  6. Passive sensor systems for nuclear material monitoring

    International Nuclear Information System (INIS)

    Simpson, M.L.; Boatner, L.A.; Holcomb, D.E.; McElhaney, S.A.; Mihalczo, J.T.; Muhs, J.D.; Roberts, M.R.; Hill, N.W.

    1993-01-01

    Passive fiber optic sensor systems capable of confirming the presence of special nuclear materials in storage or process facilities are being developed at Oak Ridge National Laboratory (ORNL). These sensors provide completely passive, remote measurement capability. No power supplies, amplifiers, or other active components that could degrade system reliability are required at the sensor location. ORNL, through its research programs in scintillator materials, has developed a variety of materials for use in alpha-, beta-, gamma-, and neutron-sensitive scintillator detectors. In addition to sensors for measuring radiation flux, new sensor materials have been developed which are capable of measuring weight, temperature, and source location. An example of a passive sensor for temperature measurement is the combination of a thermophosphor (e.g., rare-earth activated Y 2 O 3 ) with 6 LiF (95% 6 Li). This combination results in a new class of scintillators for thermal neutrons that absorb energy from the radiation particles and remit the energy as a light pulse, the decay rate of which, over a specified temperature range, is temperature dependent. Other passive sensors being developed include pressure-sensitive triboluminescent materials, weight-sensitive silicone rubber fibers, scintillating fibers, and other materials for gamma and neutron detection. The light from the scintillator materials of each sensor would be sent through optical fibers to a monitoring station, where the attribute quantity could be measured and compared with previously recorded emission levels. Confirmatory measurement applications of these technologies are being evaluated to reduce the effort, costs, and employee exposures associated with inventorying stockpiles of highly enriched uranium at the Oak Ridge Y-12 Plant

  7. Local public document room directory. Revision 7

    International Nuclear Information System (INIS)

    1998-04-01

    This directory (NUREG/BR-0088, Revision 7) lists local public document rooms (LPDRs) for commercial nuclear power plants with operating or possession-only licenses or under construction, plus the LPDRs for potential high-level radioactive waste repository sites, gaseous diffusion plants, certain fuel cycle facilities, certain low-level waste disposal facilities, and any temporary LPDRs established for the duration of licensing proceedings. In some instances, the LPDR libraries maintain document collections for more than one licensed facility. The library staff members listed are the persons most familiar with the LPDR collections. Reference librarians in the NRC Headquarters Public Document Room (PDR) are also available to assist the public in locating NRC documents

  8. CNEA's quality system documentation

    International Nuclear Information System (INIS)

    Mazzini, M.M.; Garonis, O.H.

    1998-01-01

    Full text: To obtain an effective and coherent documentation system suitable for CNEA's Quality Management Program, we decided to organize the CNEA's quality documentation with : a- Level 1. Quality manual. b- Level 2. Procedures. c-Level 3. Qualities plans. d- Level 4: Instructions. e- Level 5. Records and other documents. The objective of this work is to present a standardization of the documentation of the CNEA's quality system of facilities, laboratories, services, and R and D activities. Considering the diversity of criteria and formats for elaboration the documentation by different departments, and since ultimately each of them generally includes the same quality management policy, we proposed the elaboration of a system in order to improve the documentation, avoiding unnecessary time wasting and costs. This will aloud each sector to focus on their specific documentation. The quality manuals of the atomic centers fulfill the rule 3.6.1 of the Nuclear Regulatory Authority, and the Safety Series 50-C/SG-Q of the International Atomic Energy Agency. They are designed by groups of competent and highly trained people of different departments. The normative procedures are elaborated with the same methodology as the quality manuals. The quality plans which describe the organizational structure of working group and the appropriate documentation, will asses the quality manuals of facilities, laboratories, services, and research and development activities of atomic centers. The responsibilities for approval of the normative documentation are assigned to the management in charge of the administration of economic and human resources in order to fulfill the institutional objectives. Another improvement aimed to eliminate unnecessary invaluable processes is the inclusion of all quality system's normative documentation in the CNEA intranet. (author) [es

  9. PSA applications. Good practices and documentation

    International Nuclear Information System (INIS)

    Dewailly, J.; Magne, L.

    1997-10-01

    In this paper, it is shown what the condensed documentation of the main strategic choices and technical assumptions related to a PSA could contain: how to select the internal and external initiating events, how the detail the plant configuration and the general organization of the plant and operating staff, how to highlight the assumptions related to physical models, etc. The proposals in this documentation are based on the R and D D's experience with PSA (construction of PSA models, use of PSA models for operation or maintenance, PSA tools). This document also presents different types of rules or recommendations related to PSA modelling for various applications involved in nuclear power plant operating. Finally, the paper stresses the main difficulties encountered (appropriate use of uncertainties, communication of PSA results to non-specialist users) and it also outlines some prospects for the future. (author)

  10. Administrative Reorganization, Modification And Enlargement The Personal Plant And The Functions Manual Of The Documentation Center And Nuclear Information Of The Institute Of Nuclear Matters; Reorganizacion administrativa, Modificacion y Amipliacion de la planta de personal y del Manual de Funciones del Centro de Documentacion e Informacion Nuclear del Instituto de Asuntos Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    De Escobar, Cecilia

    1991-07-01

    This document is a project of administrative reorganization, modification and amplification of the personal plant and the functions manual of of the Center of Documentation and Nuclear Information of the IAN. The methodology used to develop this work was constituted by an analysis of the statutes and objectives of the institution. A study of the objectives that the CDIN of the flowchart of the IAN should complete. Interview with the Boss of the CDIN to define necessities as soon as administrative organization, modification of the plant of personal and of the manual of functions of the Center, interview the officials of the Documentation Center, tending efficiently to gather information on the current conditions of work and their proposals for the benefit of the more services. Surveys of the Center users to diagnose like they are come lending the services and their recommendations for the improvement of the same ones.

  11. Antireflection/Passivation Step For Silicon Cell

    Science.gov (United States)

    Crotty, Gerald T.; Kachare, Akaram H.; Daud, Taher

    1988-01-01

    New process excludes usual silicon oxide passivation. Changes in principal electrical parameters during two kinds of processing suggest antireflection treatment almost as effective as oxide treatment in passivating cells. Does so without disadvantages of SiOx passivation.

  12. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1990-04-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference to Principal Documents

  13. Westinghouse AP600 advanced nuclear plant design

    International Nuclear Information System (INIS)

    Gangloff, W.

    1999-01-01

    As part of the cooperative US Department of Energy (DOE) Advanced Light Water Reactor (ALWR) Program and the Electric Power Research Institute (EPRI), the Westinghouse AP600 team has developed a simplified, safe, and economic 600-megawatt plant to enter into a new era of nuclear power generation. Designed to satisfy the standards set by DOE and defined in the ALWR Utility Requirements Document (URD), the Westinghouse AP600 is an elegant combination of innovative safety systems that rely on dependable natural forces and proven technologies. The Westinghouse AP600 design simplifies plant systems and significant operation, inspections, maintenance, and quality assurance requirements by greatly reducing the amount of valves, pumps, piping, HVAC ducting, and other complex components. The AP600 safety systems are predominantly passive, depending on the reliable natural forces of gravity, circulation, convection, evaporation, and condensation, instead of AC power supplies and motor-driven components. The AP600 provides a high degree of public safety and licensing certainty. It draws upon 40 years of experience in light water reactor components and technology, so no demonstration plant is required. During the AP600 design program, a comprehensive test program was carried out to verify plant components, passive safety systems components, and containment behavior. When the test program was completed at the end of 1994, the AP600 became the most thoroughly tested advanced reactor design ever reviewed by the US Nuclear Regulatory Commission (NRC). The test results confirmed the exceptional behavior of the passive systems and have been instrumental in facilitating code validations. Westinghouse received Final Design Approval from the NRC in September 1998. (author)

  14. Revision of documents guide to obtain the renovation of licence of the nuclear power plant of Laguna Verde, Units I and II; Revision de documentos guia para obtener la renovacion de licencia de la Central Nuclear Laguna Verde Unidades 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G. [ININ 52750 La Marquesa, Estado de Mexico (Mexico); Fernandez S, G. [CFE, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin s/n (Km. 7.5), Dos Bocas, 54270 Veracruz (Mexico)]. e-mail: giarvio@yahoo.com.mx

    2008-07-01

    Unquestionably the renovation of license of the nuclear power plants , it this converting in a promising option to be able to gather in sure, reliable form and economic those requests about future energy in the countries with facilities of this type. This work it analyzes four documents guide and their application for the determination of the renovation of it licenses in nuclear plants that will serve of base for their aplication in the Nuclear Power Plant of Laguna Verde Units I and 2. The four documents in question are: the one Inform Generic of Learned Lessons on the Aging (NUREG - 1801), the Standard Revision Plan for the Renovation of License (NUREG - 1800), the Regulatory Guide for Renovation of License (GR-1.188), and the NEI 95-10, developed by the Institute of Nuclear Energy that is an Industrial Guide to Implement the Requirements of the 1OCFR Part 54-the Rule of Renovation of It licenses. (Author)

  15. NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Levin, A.E.

    1995-09-01

    New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

  16. Technical document characterization by data analysis

    International Nuclear Information System (INIS)

    Mauget, A.

    1993-05-01

    Nuclear power plants possess documents analyzing all the plant systems, which represents a vast quantity of paper. Analysis of textual data can enable a document to be classified by grouping the texts containing the same words. These methods are used on system manuals for feasibility studies. The system manual is then analyzed by LEXTER and the terms it has selected are examined. We first classify according to style (sentences containing general words, technical sentences, etc.), and then according to terms. However, it will not be possible to continue in this fashion for the 100 system manuals existing, because of lack of sufficient storage capacity. Another solution is being developed. (author)

  17. TRANSPORTATION SYSTEM REQUIREMENTS DOCUMENT

    International Nuclear Information System (INIS)

    2004-01-01

    This document establishes the Transportation system requirements for the U.S. Department of Energy's (DOE's) Civilian Radioactive Waste Management System (CRWMS). These requirements are derived from the Civilian Radioactive Waste Management System Requirements Document (CRD). The Transportation System Requirements Document (TSRD) was developed in accordance with LP-3.1Q-OCRWM, Preparation, Review, and Approval of Office of National Transportation Level-2 Baseline Requirements. As illustrated in Figure 1, the TSRD forms a part of the DOE Office of Civilian Radioactive Waste Management (OCRWM) Technical Baseline

  18. Environmental impact of passive house nursery

    Energy Technology Data Exchange (ETDEWEB)

    Vares, S., Email: sirje.vares@vtt.fi

    2012-06-15

    It is often believed that reduction in energy use automatically leads to the total reduction of the carbon footprint and other emissions. To achieve better energy efficiency more raw materials may be needed not only for insulation and better windows but also for heating systems like ground source heat and solar panels. The use of advanced building systems increase the use of electricity and in winter where electricity production is already inadequate the additional stand-by power plants must be taken in use. These are not as effective as CHP plants for heat production. Moreover also the passive house structures can be produced in dozens ways and from many different materials which all have different service life, different need for maintenance and also different effect on the overall carbon footprint. Finally as the nursery is the overall concept, besides the building structures outdoor playgrounds and specific operations requiring day care trips, personnel commuting and waste treatment must be taken into account. (orig.)

  19. EDF group - Reference Document 2007

    International Nuclear Information System (INIS)

    2008-01-01

    The EDF Group is a leading player in the European energy industry, active in all areas of the electricity value chain, from generation to trading and network management. The leader in the French electricity market, the Group also has solid positions in the United Kingdom, Germany and Italy, with a portfolio of 38.5 million European customers and a generation fleet which is unique in the world. It intends to play a major role in the global revival of nuclear and is increasingly active in the gas chain. The Group has a sound business model, evenly balanced between regulated and deregulated activities. Given its R and D capability, its track record and expertise in nuclear, fossil-fired and hydro generation and in renewable energies, together with its energy eco-efficiency offers, EDF is well placed to deliver competitive solutions to reconcile sustainable economic growth and climate preservation. This document is EDF Group's Reference Document and Annual Financial Report for the year 2007. It contains information about Group profile, governance, business, investments, property, plant and equipment, management, financial position, human resources, shareholders, etc. The document includes the 2008 half-year financial report and consolidated financial statements, and the report drafted by the Statutory Auditors

  20. Mixed waste characterization reference document

    International Nuclear Information System (INIS)

    1997-09-01

    Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization

  1. Electronic document management at Sizewell B

    International Nuclear Information System (INIS)

    Rippon, Simon.

    1996-01-01

    Sizewell ''B'', Britain's first PWR, officially opened on March 25 1996, will now rely for its document management on a sophisticated computer-based system. One of the largest single engineering projects ever to be commissioned on one site in Britain, Sizewell ''B'' accommodates more than 300,000 documents, including over 200,000 drawings. The electronic document management system will provide a number of important benefits, including a more direct method of maintaining the station's Configuration Management and hence maintaining high safety standards; improved turnaround in plant modification proposals (PMP); significant time and cost savings in managing vital records; and increased productivity. (Author)

  2. Evaluation of the reliability of a passive system

    International Nuclear Information System (INIS)

    Bianchi, F.; Burgazzi, L.; D'Auria, F.; Galassi, G.M.; Ricotti, M.E.; Oriani, L.

    2001-01-01

    A passive system should be theoretically more reliable than an active one. In fact its operation is independent by any external input or energy and is relied only upon natural physical laws (e.g., gravity, natural circulation, etc.) and/or 'intelligent' use of the energy inherently available in the system (e.g., chemical reaction, decay heat, etc.). Nevertheless the passive system may fail its mission as consequences of component failures, deviation of physical phenomena, boundary and/or initial conditions from the expectation. This document describes at first the methodology developed by ENEA, in collaboration of University of Pisa and Polytechnic of Milano, allowing the evaluation of the reliability for a passive system, which operation is based on moving working fluids (type B and C, cf. IAEA). It reports the results of an exercise performed on a system, which operation is based on Natural Circulation.(author)

  3. Passive hygrothermal control of a museum storage building in Vejle

    DEFF Research Database (Denmark)

    Christensen, Jørgen Erik; Janssen, Hans

    2010-01-01

    and maintenance costs are currently motivating a paradigm change toward passive control. Passive control, via the thermal and hygric inertia of the building, is gaining a foothold in the museum conservation and building physical community. In this report we document the hygrothermal performance optimisation...... of a museum storage building, related to an existing storage centre in Vejle (Denmark). The current building design already incorporates passive control concepts: thermal inertia is provided by the thick walls, the ground floor and its underlying soil volume, while hygric inertia is provided by the thick...... with the thermal inertia of the ground and thus a higher temperature variation; For those reasons, more heavily insulated walls and roofs could be considered. Their effects on the interior climate and dehumidification load are however not that large. For the floor, no insulation should be added, and it could...

  4. Applications for electronic documents

    International Nuclear Information System (INIS)

    Beitel, G.A.

    1995-01-01

    This paper discusses the application of electronic media to documents, specifically Safety Analysis Reports (SARs), prepared for Environmental Restoration and Waste Management (ER ampersand WM) programs being conducted for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). Efforts are underway to upgrade our document system using electronic format. To satisfy external requirements (DOE, State, and Federal), ER ampersand WM programs generate a complement of internal requirements documents including a SAR and Technical Safety Requirements along with procedures and training materials. Of interest, is the volume of information and the difficulty in handling it. A recently prepared ER ampersand WM SAR consists of 1,000 pages of text and graphics; supporting references add 10,000 pages. Other programmatic requirements documents consist of an estimated 5,000 pages plus references

  5. Informational system. Documents management

    Directory of Open Access Journals (Sweden)

    Vladut Iacob

    2009-12-01

    Full Text Available Productivity growing, as well as reducing of operational costs in a company can be achieved by adopting a document management solutions. Such application will allow management and structured and efficient transmission of information within the organization.

  6. Transportation System Requirements Document

    International Nuclear Information System (INIS)

    1993-09-01

    This Transportation System Requirements Document (Trans-SRD) describes the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of this document is to define the system-level requirements for Transportation consistent with the CRWMS Requirement Document (CRD). These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presents an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. The interface identification and description are published in the CRWMS Interface Specification

  7. Integrated Criteria Document Chromium

    NARCIS (Netherlands)

    Slooff W; Cleven RFMJ; Janus JA; van der Poel P; van Beelen P; Boumans LJM; Canton JH; Eerens HC; Krajnc EI; de Leeuw FAAM; Matthijsen AJCM; van de Meent D; van der Meulen A; Mohn GR; Wijland GC; de Bruijn PJ; van Keulen A; Verburgh JJ; van der Woerd KF

    1990-01-01

    Betreft de engelse versie van rapport 758701001
    Bij dit rapport behoort een appendix onder hetzelfde nummer getiteld: "Integrated Criteria Document Chromium: Effects" Auteurs: Janus JA; Krajnc EI
    (appendix: see 710401002A)

  8. NCDC Archive Documentation Manuals

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The National Climatic Data Center Tape Deck Documentation library is a collection of over 400 manuals describing NCDC's digital holdings (both historic and current)....

  9. Registration document 2005

    International Nuclear Information System (INIS)

    2005-01-01

    This reference document of Gaz de France provides information and data on the Group activities in 2005: financial informations, business, activities, equipments factories and real estate, trade, capital, organization charts, employment, contracts and research programs. (A.L.B.)

  10. Performance Analysis of AP1000 Passive Systems during Direct Vessel Injection (DVI Line Break

    Directory of Open Access Journals (Sweden)

    A.S. Ekariansyah

    2016-08-01

    Full Text Available Generation II Nuclear Power Plants (NPPs have a design weakness as shown by the Fukushima accident. Therefore, Generation III+ NPPs are developed with focus on improvements of fuel technology and thermal efficiency, standardized design, and the use of passive safety system. One type of Generation III+ NPP is the AP1000 that is a pressurized water reactor (PWR type that has received the final design acceptance from US-NRC and is already under construction at several sites in China as of 2015. The aim of this study is to investigate the behavior and performance of the passive safety system in the AP1000 and to verify the safety margin during the direct vessel injection (DVI line break as selected event. This event was simulated using RELAP5/SCDAP/Mod3.4 as a best-estimate code developed for transient simulation of light water reactors during postulated accidents. This event is also described in the AP1000 design control document as one of several postulated accidents simulated using the NOTRUMP code. The results obtained from RELAP5 calculation was then compared with the results of simulations using the NOTRUMP code. The results show relatively good agreements in terms of time sequences and characteristics of some injected flow from the passive safety system. The simulation results show that the break of one of the two available DVI lines can be mitigated by the injected coolant flowing, which is operated effectively by gravity and density difference in the cooling system and does not lead to core uncovery. Despite the substantial effort to obtain an apropriate AP1000 model due to lack of detailed geometrical data, the present model can be used as a platform model for other initiating event considered in the AP1000 accident analysis.

  11. Are PDF Documents Accessible?

    Directory of Open Access Journals (Sweden)

    Mireia Ribera Turró

    2008-09-01

    Full Text Available Adobe PDF is one of the most widely used formats in scientific communications and in administrative documents. In its latest versions it has incorporated structural tags and improvements that increase its level of accessibility. This article reviews the concept of accessibility in the reading of digital documents and evaluates the accessibility of PDF according to the most widely established standards.

  12. 2002 reference document

    International Nuclear Information System (INIS)

    2002-01-01

    This 2002 reference document of the group Areva, provides information on the society. Organized in seven chapters, it presents the persons responsible for the reference document and for auditing the financial statements, information pertaining to the transaction, general information on the company and share capital, information on company operation, changes and future prospects, assets, financial position, financial performance, information on company management and executive board and supervisory board, recent developments and future prospects. (A.L.B.)

  13. LCS Content Document Application

    Science.gov (United States)

    Hochstadt, Jake

    2011-01-01

    My project at KSC during my spring 2011 internship was to develop a Ruby on Rails application to manage Content Documents..A Content Document is a collection of documents and information that describes what software is installed on a Launch Control System Computer. It's important for us to make sure the tools we use everyday are secure, up-to-date, and properly licensed. Previously, keeping track of the information was done by Excel and Word files between different personnel. The goal of the new application is to be able to manage and access the Content Documents through a single database backed web application. Our LCS team will benefit greatly with this app. Admin's will be able to login securely to keep track and update the software installed on each computer in a timely manner. We also included exportability such as attaching additional documents that can be downloaded from the web application. The finished application will ease the process of managing Content Documents while streamlining the procedure. Ruby on Rails is a very powerful programming language and I am grateful to have the opportunity to build this application.

  14. Documentation of spectrom-32

    International Nuclear Information System (INIS)

    Callahan, G.D.; Fossum, A.F.; Svalstad, D.K.

    1989-01-01

    SPECTROM-32 is a finite element program for analyzing two-dimensional and axisymmetric inelastic thermomechanical problems related to the geological disposal of nuclear waste. The code is part of the SPECTROM series of special-purpose computer programs that are being developed by RE/SPEC Inc. to address many unique rock mechanics problems encountered in analyzing radioactive wastes stored in geologic formations. This document presents the theoretical basis for the mathematical models, the finite element formulation and solution procedure of the program, a description of the input data for the program, verification problems, and details about program support and continuing documentation. The computer code documentation is intended to satisfy the requirements and guidelines outlined in the document entitled Final Technical Position on Documentation of Computer Codes for High-Level Waste Management. The principal component models used in the program involve thermoelastic, thermoviscoelastic, thermoelastic-plastic, and thermoviscoplastic types of material behavior. Special material considerations provide for the incorporation of limited-tension material behavior and consideration of jointed material behavior. Numerous program options provide the capabilities for various boundary conditions, sliding interfaces, excavation, backfill, arbitrary initial stresses, multiple material domains, load incrementation, plotting database storage and access of results, and other features unique to the geologic disposal of radioactive wastes. Numerous verification problems that exercise many of the program options and illustrate the required data input and printed results are included in the documentation

  15. Technical approach document

    International Nuclear Information System (INIS)

    1988-04-01

    This document describes the general technical approaches and design criteria adopted by the US Department of Energy (DOE) in order to implement Remedial Action Plans (RAPs) and final designs that comply with EPS standards. This document is a revision to the original document. Major revisions were made to the sections in riprap selection and sizing, and ground-water; only minor revisions were made to the remainder of the document. The US Nuclear Regulatory Commission (NRC) has prepared a Standard Review Plan (NRC-SRP) which describes factors to be considered by the NRC in approving the RAP. Sections 3.0, 4.0, 5.0, and 7.0 of this document are arranged under the same headings as those used in the NRC-SRP. This approach is adopted in order to facilitate joint use of the documents. Section 2.0 (not included in the NRC-SRP) discusses design considerations; Section 3.0 describes surface-water hydrology and erosion control; Section 4.0 describes geotechnical aspects of pile design; Section 5.0 discusses the Alternate Site Selection Process; Section 6.0 deals with radiological issues (in particular, the design of the radon barrier); Section 7.0 discusses protection of groundwater resources; and Section 8.0 discusses site design criteria for the RAC

  16. Preliminary analysis of the inclusion of security passive systems to reduce the impact of accidents in nuclear power plants; Analisis preliminar de la inclusion de sistemas pasivos de seguridad para reducir el impacto de accidentes en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez J, J.; Morales S, J. B. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Espinosa P, G., E-mail: jersonsanchez@gmail.com [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico D. F. (MX)

    2011-11-15

    In this work is presented a conceptual analysis of possible benefits and limitations that potentially represents the introduction of security passive systems to reduce the events impact of very low probability and high risk to the systems of radioactive material confinement of a light water reactor. These events are related with the possibility that a hydrogen explosion is presented as consequence of the accumulation of the same hydrogen in the contention of the reactor, in a scenario of severe accident. This accumulated hydrogen can be liberated in the reactor building or primary contention, where the conditions of their atmosphere make but prone the combustion. The catalytic recombination represents a viable option for the hydrogen concentrations decrease and because this recombination is highly exothermic, is important to analyze and to know if the recombined vapor to high temperature can be used in combination with vapor injectors that in turn, they are passive systems. In the following sections an explanation is presented about the use of the mentioned systems, as well as some results on the behavior of the vapor injectors. (Author)

  17. Association between passive smoking and Mycobacterium tuberculosis infection in children with household TB contact

    Directory of Open Access Journals (Sweden)

    Novaily Zuliartha

    2015-03-01

    Full Text Available Background Tuberculosis (TB and cigarette consumption are relatively high in Indonesia. Passive smoking may increase the risk of infection and disease in adults and children exposed to TB. An association between passive smoking and Mycobacterium tuberculosis infection in children has not been well documented. Objective To assess for an association between passive smoking and M. tuberculosis infection in children who had household contact with a TB patient. Methods This cross-sectional study was conducted in February and March 2011. Children aged 5 to 18 years who had household contact with a TB patient underwent tuberculin testing for M. tuberculosis infection. Subjects were divided into two groups: those exposed to passive smoke and those not exposed to passive smoke. Chi-square test was used to assess for an association between passive smoking and M. tuberculosis infection. Results There were 140 children enrolled in this study, with 70 exposed to passive smoke and 70 not exposed to passive smoke. Prevalence of M. tuberculosis infection was significantly higher in the passive smoking group than in those not exposed to passive smoke [81.4% and 52.9%, respectively, (P= 0.0001]. In the passive smoking group there were significant associations between nutritional state, paternal and maternal education, and M. tuberculosis infection. But no associations were found between M. tuberculosis infection and familial income or BCG vaccination. Conclusion Among children who had household contact with a TB patient, they who exposed to passive smoke are more likely to have M. tuberculosis infection compared to they who not exposed to passive smoke.

  18. Issues in risk analysis of passive LWR designs

    International Nuclear Information System (INIS)

    Youngblood, R.W.; Pratt, W.T.; Amico, P.J.; Gallagher, D.

    1992-01-01

    This paper discusses issues which bear on the question of how safety is to be demonstrated for ''simplified passive'' light water reactor (LWR) designs. First, a very simplified comparison is made between certain systems in today's plants. comparable systems in evolutionary designs, and comparable systems in the simplified passives. in order to introduce the issues. This discussion is not intended to describe the designs comprehensively, but is offered only to show why certain issues seem to be important in these particular designs. Next, an important class of accident sequences is described; finally, based on this discussion, some priorities in risk analysis are presented and discussed

  19. Utility requirements for safety in the passive advanced light-water reactor

    International Nuclear Information System (INIS)

    Marston, T.U.; Layman, W.H.; Bockhold, G. Jr.

    1993-01-01

    The objective of the passive plant design is to use passive systems to replace all the active engineered safety systems presently used in light-water reactors. The benefits derived from such an approach to safety design are multiple. First, it is expected that a passive design approach will significantly simplify the overall plant design, including a reduction in the number of components, and reduce the operation and maintenance burden. Second, it is expected that the overall safety and reliability of the passive systems will be improved over active systems, which will result in extremely low risk to public health and safety. Third, challenges to the operating staff will be minimized during transient and emergency conditions, which will reduce the uncertainty associated with human behavior. Finally, it is expected that reliance on passive safety features will lead to a better understanding by the general public and recognition that a major improvement in public safety has been achieved

  20. French concepts of ''passive safety''

    International Nuclear Information System (INIS)

    Dennielou, Y.; Serret, M.

    1990-01-01

    N 4 model, the French 1400 MW PWR of the 90's, exhibits many advanced features. As far as safety is concerned, the fully computerized control room design takes advantage of the operating experience feedback and largely improves the man machine interface. New post-accident procedures have been developed (the so-called ''physical states oriented procedures''). A complete consistent set of ''Fundamental Safety Rules'' have been issued. This however doesn't imply any significant modification of standard PWR with regard to the passive aspects of safety systems or functions. Nevertheless, traditional PWR safety systems largely use passive aspects: natural circulation, reactivity coefficients, gravity driven control rods, injection accumulators, so on. Moreover, probability calculations allow for comparison between the respective contributions of passive and of active failures. In the near future, eventual options of future French PWRs to be commissioned after 2000 will be evaluated; simplification, passive and forgiving aspects of safety systems will be thoroughly considered. (author)

  1. Effectiveness of passive alcohol sensors

    Science.gov (United States)

    1996-03-01

    Author's abstract: The purpose of this study was to evaluate the effectiveness of passive alcohol sensors for youth alcohol enforcement conducted as part of normal or typical police operations. Three municipal police departments of 100 or more sworn ...

  2. Thermal-hydraulic modeling needs for passive reactors

    International Nuclear Information System (INIS)

    Kelly, J.M.

    1997-01-01

    The U.S. Nuclear Regulatory Commission has received an application for design certification from the Westinghouse Electric Corporation for an Advanced Light Water Reactor design known as the AP600. As part of the design certification process, the USNRC uses its thermal-hydraulic system analysis codes to independently audit the vendor calculations. The focus of this effort has been the small break LOCA transients that rely upon the passive safety features of the design to depressurize the primary system sufficiently so that gravity driven injection can provide a stable source for long term cooling. Of course, large break LOCAs have also been considered, but as the involved phenomena do not appear to be appreciably different from those of current plants, they were not discussed in this paper. Although the SBLOCA scenario does not appear to threaten core coolability - indeed, heatup is not even expected to occur - there have been concerns as to the performance of the passive safety systems. For example, the passive systems drive flows with small heads, consequently requiring more precision in the analysis compared to active systems methods for passive plants as compared to current plants with active systems. For the analysis of SBLOCAs and operating transients, the USNRC uses the RELAP5 thermal-hydraulic system analysis code. To assure the applicability of RELAP5 to the analysis of these transients for the AP600 design, a four year long program of code development and assessment has been undertaken

  3. Thermal-hydraulic modeling needs for passive reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, J.M. [Nuclear Regulatory Commission, Washington, DC (United States)

    1997-07-01

    The U.S. Nuclear Regulatory Commission has received an application for design certification from the Westinghouse Electric Corporation for an Advanced Light Water Reactor design known as the AP600. As part of the design certification process, the USNRC uses its thermal-hydraulic system analysis codes to independently audit the vendor calculations. The focus of this effort has been the small break LOCA transients that rely upon the passive safety features of the design to depressurize the primary system sufficiently so that gravity driven injection can provide a stable source for long term cooling. Of course, large break LOCAs have also been considered, but as the involved phenomena do not appear to be appreciably different from those of current plants, they were not discussed in this paper. Although the SBLOCA scenario does not appear to threaten core coolability - indeed, heatup is not even expected to occur - there have been concerns as to the performance of the passive safety systems. For example, the passive systems drive flows with small heads, consequently requiring more precision in the analysis compared to active systems methods for passive plants as compared to current plants with active systems. For the analysis of SBLOCAs and operating transients, the USNRC uses the RELAP5 thermal-hydraulic system analysis code. To assure the applicability of RELAP5 to the analysis of these transients for the AP600 design, a four year long program of code development and assessment has been undertaken.

  4. SNL evaluation of Gigabit Passive Optical Networks (GPON).

    Energy Technology Data Exchange (ETDEWEB)

    Heckart, David G.; Roybal, Glen B.; Walker, Betty R.; Pratt, Thomas Joseph; Gossage, Steven Allen; Trujillo, Sandra M.; Fischer, Bob; Brenkosh, Joseph Peter; Rudolfo, Gerald F.; Dirks, David H.; Schutt, James Alan

    2009-08-01

    Gigabit Passive Optical Networks (GPON) is a networking technology which offers the potential to provide significant cost savings to Sandia National Laboratories in the area of network operations. However, a large scale GPON deployment requires a significant investment in equipment and infrastructure. Before a large scale GPON system was acquired and built, a small GPON system manufactured by Motorola was acquired and tested. The testing performed was to determine the suitability of GPON for use at SNL. This report documents that testing. This report presents test results of GPON system consisting of Motorola and Juniper equipment. The GPON system was tested in areas of data throughput, video conferencing, VOIP, security, and operations and management. The GPON system performed well in almost all areas. GPON will not meet the needs of the low percentage of users requiring a true 1-10 Gbps network connection. GPON will also most likely not meet the need of some servers requiring dedicated throughput of 1-10 Gbps. Because of that, there will be some legacy network connections that must remain. If these legacy network connections can not be reduced to a bare minimum and possibly consolidated to a few locations, any cost savings gained by switching to GPON will be negated by maintaining two networks. A contract has been recently awarded for new GPON equipment with larger buffers. This equipment should improve performance and further reduce the need for legacy network connections. Because GPON has fewer components than a typical hierarchical network, it should be easier to manage. For the system tested, the management was performed by using the AXSVison client. Access to the client must be tightly controlled, because if client/server communications are compromised, security will be an issue. As with any network, the reliability of individual components will determine overall system reliability. There were no failures with the routers, OLT, or Sun Workstation Management

  5. Key issues for passive safety

    International Nuclear Information System (INIS)

    Hayns, M.R.

    1996-01-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ''review paper'' as such and only record the highlights. (author)

  6. Key issues for passive safety

    Energy Technology Data Exchange (ETDEWEB)

    Hayns, M R [AEA Technology, Harwell, Didcot (United Kingdom). European Institutions; Hicken, E F [Forschungszentrum Juelich GmbH (Germany)

    1996-12-01

    The paper represents a summary of the introductory presentation made at this Advisory Group Meeting on the Technical Feasibility and Reliability of Passive Safety Systems. It was intended as an overview of our views on what are the key issues and what are the technical problems which might dominate any future developments of passive safety systems. It is, therefore, not a ``review paper`` as such and only record the highlights. (author).

  7. B Plant hazards assessment

    International Nuclear Information System (INIS)

    Broz, R.E.

    1994-01-01

    This document establishes the technical basis in support of Emergency Planning Activities for B Plant on the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE Order 5500.3A. Through this document, the technical basis for the development of facility specific , Emergency Action Levels and the Emergency Planning Zone is demonstrated

  8. T Plant hazards assessment

    International Nuclear Information System (INIS)

    Broz, R.E.

    1994-01-01

    This document establishes the technical basis in support of Emergency Planning activities for the T Plant on the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

  9. Preliminary assessment of a combined passive safety system for typical 3-loop PWR CPR1000

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Zijiang; Shan, Jianqiang, E-mail: jqshan@mail.xjtu.edu.cn; Gou, Junli

    2017-03-15

    Highlights: • A combined passive safety system was placed on a typical 3-loop PWR CPR1000. • Three accident analyses show the three different accident mitigation methods of the passive safety system. • The three mitigation methods were proved to be useful. - Abstract: As the development of the nuclear industry, passive technology turns out to be a remarkable characteristic of advanced nuclear power plants. Since the 20th century, much effort has been given to the passive technology, and a number of evolutionary passive systems have developed. Thoughts have been given to upgrade the existing reactors with passive systems to meet stricter safety demands. In this paper, the CPR1000 plant, which is one kind of mature pressurized water reactor plants in China, is improved with some passive systems to enhance safety. The passive systems selected are as follows: (1) the reactor makeup tank (RMT); (2) the advanced accumulator (A-ACC); (3) the in-containment refueling water storage tank (IRWST); (4) the passive emergency feed water system (PEFS), which is installed on the secondary side of SGs; (5) the passive depressurization system (PDS). Although these passive components is based on the passive technology of some advanced reactors, their structural and trip designs are adjusted specifically so that it could be able to mitigate accidents of the CPR1000. Utilizing the RELAP5/MOD3.3 code, accident analyses (small break loss of coolant accident, large break loss of coolant accident, main feed water line break accident) of this improved CPR1000 plant were presented to demonstrate three different accident mitigation methods of the safety system and to test whether the passive safety system preformed its function well. In the SBLOCA, all components of the passive safety system were put into work sequentially, which prevented the core uncover. The LBLOCA analysis illustrates the contribution of the A-ACCs whose small-flow-rate injection can control the maximum cladding

  10. Passive vapor extraction feasibility study

    International Nuclear Information System (INIS)

    Rohay, V.J.

    1994-01-01

    Demonstration of a passive vapor extraction remediation system is planned for sites in the 200 West Area used in the past for the disposal of waste liquids containing carbon tetrachloride. The passive vapor extraction units will consist of a 4-in.-diameter pipe, a check valve, a canister filled with granular activated carbon, and a wind turbine. The check valve will prevent inflow of air that otherwise would dilute the soil gas and make its subsequent extraction less efficient. The granular activated carbon is used to adsorb the carbon tetrachloride from the air. The wind turbine enhances extraction rates on windy days. Passive vapor extraction units will be designed and operated to meet all applicable or relevant and appropriate requirements. Based on a cost analysis, passive vapor extraction was found to be a cost-effective method for remediation of soils containing lower concentrations of volatile contaminants. Passive vapor extraction used on wells that average 10-stdft 3 /min air flow rates was found to be more cost effective than active vapor extraction for concentrations below 500 parts per million by volume (ppm) of carbon tetrachloride. For wells that average 5-stdft 3 /min air flow rates, passive vapor extraction is more cost effective below 100 ppm

  11. Securing XML Documents

    Directory of Open Access Journals (Sweden)

    Charles Shoniregun

    2004-11-01

    Full Text Available XML (extensible markup language is becoming the current standard for establishing interoperability on the Web. XML data are self-descriptive and syntax-extensible; this makes it very suitable for representation and exchange of semi-structured data, and allows users to define new elements for their specific applications. As a result, the number of documents incorporating this standard is continuously increasing over the Web. The processing of XML documents may require a traversal of all document structure and therefore, the cost could be very high. A strong demand for a means of efficient and effective XML processing has posed a new challenge for the database world. This paper discusses a fast and efficient indexing technique for XML documents, and introduces the XML graph numbering scheme. It can be used for indexing and securing graph structure of XML documents. This technique provides an efficient method to speed up XML data processing. Furthermore, the paper explores the classification of existing methods impact of query processing, and indexing.

  12. Two types of a passive safety containment for a near future BWR with active and passive safety systems

    International Nuclear Information System (INIS)

    Sato, Takashi; Akinaga, Makoto; Kojima, Yoshihiro

    2009-01-01

    The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

  13. Two types of a passive safety containment for a near future BWR with active and passive safety systems

    Energy Technology Data Exchange (ETDEWEB)

    Sato, Takashi [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)], E-mail: takashi44.sato@glb.toshiba.co.jp; Akinaga, Makoto; Kojima, Yoshihiro [Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)

    2009-09-15

    The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.

  14. Segmentation of complex document

    Directory of Open Access Journals (Sweden)

    Souad Oudjemia

    2014-06-01

    Full Text Available In this paper we present a method for segmentation of documents image with complex structure. This technique based on GLCM (Grey Level Co-occurrence Matrix used to segment this type of document in three regions namely, 'graphics', 'background' and 'text'. Very briefly, this method is to divide the document image, in block size chosen after a series of tests and then applying the co-occurrence matrix to each block in order to extract five textural parameters which are energy, entropy, the sum entropy, difference entropy and standard deviation. These parameters are then used to classify the image into three regions using the k-means algorithm; the last step of segmentation is obtained by grouping connected pixels. Two performance measurements are performed for both graphics and text zones; we have obtained a classification rate of 98.3% and a Misclassification rate of 1.79%.

  15. Plant Host Finding by Parasitic Plants: A New Perspective on Plant to Plant Communication

    OpenAIRE

    Mescher, Mark C; Runyon, Justin B; De Moraes, Consuelo M

    2006-01-01

    Plants release airborne chemicals that can convey ecologically relevant information to other organisms. These plant volatiles are known to mediate a large array of, often complex, interactions between plants and insects. It has been suggested that plant volatiles may have similar importance in mediating interactions among plant species, but there are few well-documented examples of plant-to-plant communication via volatiles, and the ecological significance of such interactions has been much d...

  16. 225-B ion exchange piping design documentation

    International Nuclear Information System (INIS)

    Prather, M.C.

    1996-02-01

    This document describes the interface between the planned permanent ion exchange piping system and the planned portable ion exchange system. This is part of the Waste Encapsulation and Storage Facility (WESF). In order to decouple this WESF from B-Plant and to improve recovery from a capsule leak, contaminated pool cell water will be recirculated through a portable ion exchange resin system

  17. La Documentation photographique

    Directory of Open Access Journals (Sweden)

    Magali Hamm

    2009-03-01

    Full Text Available La Documentation photographique, revue destinée aux enseignants et étudiants en histoire-géographie, place l’image au cœur de sa ligne éditoriale. Afin de suivre les évolutions actuelles de la géographie, la collection propose une iconographie de plus en plus diversifiée : cartes, photographies, mais aussi caricatures, une de journal ou publicité, toutes étant considérées comme un document géographique à part entière. Car l’image peut se faire synthèse ; elle peut au contraire montrer les différentes facettes d’un objet ; souvent elle permet d’incarner des phénomènes géographiques. Associées à d’autres documents, les images aident les enseignants à initier leurs élèves à des raisonnements géographiques complexes. Mais pour apprendre à les lire, il est fondamental de les contextualiser, de les commenter et d’interroger leur rapport au réel.The Documentation photographique, magazine dedicated to teachers and students in History - Geography, places the image at the heart of its editorial line. In order to follow the evolutions of Geography, the collection presents a more and more diversified iconography: maps, photographs, but also drawings or advertisements, all this documents being considered as geographical ones. Because image can be a synthesis; on the contrary it can present the different facets of a same object; often it enables to portray geographical phenomena. Related to other documents, images assist the teachers in the students’ initiation to complex geographical reasoning. But in order to learn how to read them, it is fundamental to contextualize them, comment them and question their relations with reality.

  18. Customer Communication Document

    Science.gov (United States)

    2009-01-01

    This procedure communicates to the Customers of the Automation, Robotics and Simulation Division (AR&SD) Dynamics Systems Test Branch (DSTB) how to obtain services of the Six-Degrees-Of-Freedom Dynamic Test System (SDTS). The scope includes the major communication documents between the SDTS and its Customer. It established the initial communication and contact points as well as provides the initial documentation in electronic media for the customer. Contact the SDTS Manager (SM) for the names of numbers of the current contact points.

  19. Thermal limits for passive safety of fusion reactors

    International Nuclear Information System (INIS)

    Kazimi, M.S.; Massidda, J.E.; Oshima, M.

    1989-01-01

    The thermal response of the first wall and blanket due to power/cooling mismatch in the absence of operation action is examined. The analyses of coolant and power transients are carried out on six reference blanket designs representing a broad range of fusion first wall and blanket technology. It is concluded that the requirement of plant protection will impose sufficiently stringent peak neutron wall loading limits to avoid a serious threat to the public. It is found that for the D-T design,s the operating wall loading may have to be limited to 3 - 8 MW/m/sup 2/ for passive plant protection, depending on the plant design

  20. PSA in design of passive/active safety reactors

    International Nuclear Information System (INIS)

    Sato, T.; Tanabe, A.; Kondo, S.

    1995-01-01

    PSAs in the design of advanced reactors are applied mainly in level 1 PSA areas. However, even in level 1 PSA, there are certain areas where special care must be taken depending on plant design concepts. This paper identifies these areas both for passive and active safety reactor concepts. For example, 'long-term PSA' and shutdown PSA are very important for a passive safety reactor concept from the standpoint of effectiveness of a grace period and passive safety systems. External events are also important for an active safety reactor concept. These kinds of special PSAs are difficult to conduct precisely in a conceptual design stage. This paper shows methods of conducting these kinds of special PSAs simply and conveniently and the use of acquired insights for the design of advanced reactors. This paper also clarifies the meaning or definition of a grace period from the standpoint of PSA

  1. Coupled analysis of passive safety injection and containment filtered venting for passive decay heat removal - 15140

    International Nuclear Information System (INIS)

    Kim, S.H.; Ham, J.H.; Jeong, Y.H.; Chang, S.H.

    2015-01-01

    Lots of interests for the safety of nuclear power plants have risen these days. The safety has to be continuously reviewed and enhanced in nuclear power plants currently operating as well as those designed and constructed in future. After the Fukushima accidents, many additional safety systems which can be applied to nuclear power plants in operation have been proposed. Those include alternating power source such as movable diesel generators and DC batteries in non-safety grade. Also, emergency preparedness for the prevention of a core damage accident was proposed to cope with the extended-SBO (station blackout) by using fire protection systems. In order to prevent the release of radioactive materials, safety systems for preserving the integrity of containment were proposed in two views of cooling and venting containment. Two approaches are effective for mitigating a severe accident. The design concept installing big water tanks besides containment at high level was proposed for various safety functions. One of the functions in the system is to inject the coolant from the elevated tank into a reactor vessel in the case of loss of coolant accident. When the pressure in reactor coolant system is sufficiently low, the coolant can be injected by gravity. If not, the depressurization in reactor vessel would be needed considering the containment pressure. Containment cooling in conventional pressurized water reactors is dependent on containment cooling pumps and sprays. Additional containment cooling systems cannot be simply and easily applied in the current nuclear power plants without major modifications. Therefore, for the operation of passive safety injection system, containment filtered venting system can be adopted for the depressurization of containment. In the design and operation of the passive safety injection system and the containment filtered venting system, main operating points related with open and close pressures in the filtered venting system were

  2. Documents on Disarmament.

    Science.gov (United States)

    Arms Control and Disarmament Agency, Washington, DC.

    This publication, latest in a series of volumes issued annually since 1960, contains primary source documents on arms control and disarmament developments during 1969. The main chronological arrangement is supplemented by both chronological and topical lists of contents. Other reference aids include a subject/author index, and lists of…

  3. ROOT Reference Documentation

    CERN Document Server

    Fuakye, Eric Gyabeng

    2017-01-01

    A ROOT Reference Documentation has been implemented to generate all the lists of libraries needed for each ROOT class. Doxygen has no option to generate or add the lists of libraries for each ROOT class. Therefore shell scripting and a basic C++ program was employed to import the lists of libraries needed by each ROOT class.

  4. Client Oriented Management Documents.

    Science.gov (United States)

    Limaye, Mohan R.; Hightower, Rick

    Noting that accounting reports, including management advisory service (MAS) studies, reports on internal control, and tax memoranda, often appear rather dense and heavy in style--partly because of the legal environment's demand for careful expression and partly because such documents convey very complex information--this paper presents four…

  5. Using Primary Source Documents.

    Science.gov (United States)

    Mintz, Steven

    2003-01-01

    Explores the use of primary sources when teaching about U.S. slavery. Includes primary sources from the Gilder Lehrman Documents Collection (New York Historical Society) to teach about the role of slaves in the Revolutionary War, such as a proclamation from Lord Dunmore offering freedom to slaves who joined his army. (CMK)

  6. QA programme documentation

    International Nuclear Information System (INIS)

    Scheibelt, L.

    1980-01-01

    The present paper deals with the following topics: The need for a documented Q.A. program; Establishing a Q.A. program; Q.A. activities; Fundamental policies; Q.A. policies; Quality objectives Q.A. manual. (orig./RW)

  7. Student Problems with Documentation.

    Science.gov (United States)

    Freimer, Gloria R.; Perry, Margaret M.

    1986-01-01

    Interviews with faculty, a survey of 20 students, and examination of style manuals revealed that students are confused by inconsistencies in and multiplicity of styles when confronted with writing and documenting a research paper. Librarians are urged to teach various citation formats and work for adoption of standardization. (17 references) (EJS)

  8. Documentation of spectrom-41

    International Nuclear Information System (INIS)

    Svalstad, D.K.

    1989-01-01

    SPECTROM-41 is a finite element heat transfer computer program developed to analyze thermal problems related to nuclear waste disposal. The code is part of the SPECTROM (Special Purpose Engineering Codes for Thermal/ROck Mechanics) series of special purpose finite element programs that are continually being developed by RE/SPEC Inc. (RSI) to address the many unique formations. This document presents the theoretical basis for the mathematical model, the finite element formulation of the program, and a description of the input data for the program, along with details about program support and continuing documentation. The documentation is intended to satisfy the requirements and guidelines outlined in NUREG-0856. The principal component model used in the programs based on Fourier's law of conductance. Numerous program options provide the capability of considering various boundary conditions, material stratification and anisotropy, and time-dependent heat generation that are characteristic of problems involving the disposal of nuclear waste in geologic formation. Numerous verification problems are included in the documentation in addition to highlights of past and ongoing verification and validation efforts. A typical repository problem is solving using SPECTROM-41 to demonstrate the use of the program in addressing problems related to the disposal of nuclear waste

  9. Text document classification

    Czech Academy of Sciences Publication Activity Database

    Novovičová, Jana

    č. 62 (2005), s. 53-54 ISSN 0926-4981 R&D Projects: GA AV ČR IAA2075302; GA AV ČR KSK1019101; GA MŠk 1M0572 Institutional research plan: CEZ:AV0Z10750506 Keywords : document representation * categorization * classification Subject RIV: BD - Theory of Information

  10. Course documentation report

    DEFF Research Database (Denmark)

    Buus, Lillian; Bygholm, Ann; Walther, Tina Dyngby Lyng

    A documentation report on the three pedagogical courses developed during the MVU project period. The report describes the three processes taking departure in the structure and material avaiable at the virtual learning environment. Also the report describes the way the two of the courses developed...

  11. Extremely secure identification documents

    International Nuclear Information System (INIS)

    Tolk, K.M.; Bell, M.

    1997-09-01

    The technology developed in this project uses biometric information printed on the document and public key cryptography to ensure that an adversary cannot issue identification documents to unauthorized individuals or alter existing documents to allow their use by unauthorized individuals. This process can be used to produce many types of identification documents with much higher security than any currently in use. The system is demonstrated using a security badge as an example. This project focused on the technologies requiring development in order to make the approach viable with existing badge printing and laminating technologies. By far the most difficult was the image processing required to verify that the picture on the badge had not been altered. Another area that required considerable work was the high density printed data storage required to get sufficient data on the badge for verification of the picture. The image processing process was successfully tested, and recommendations are included to refine the badge system to ensure high reliability. A two dimensional data array suitable for printing the required data on the badge was proposed, but testing of the readability of the array had to be abandoned due to reallocation of the budgeted funds by the LDRD office

  12. Documents and legal texts

    International Nuclear Information System (INIS)

    2017-01-01

    This section treats of the following documents and legal texts: 1 - Belgium 29 June 2014 - Act amending the Act of 22 July 1985 on Third-Party Liability in the Field of Nuclear Energy; 2 - Belgium, 7 December 2016. - Act amending the Act of 22 July 1985 on Third-Party Liability in the Field of Nuclear Energy

  13. The European Utility Requirement Document

    International Nuclear Information System (INIS)

    Roche, I.I.

    1999-01-01

    The major European electricity producers work on a common requirement document for future LWR plants since 1992. They aim at requirements acceptable together by the owners, the public and the authorities. Thus the designers can develop standard LWR designs acceptable everywhere in Europe and the utilities can open their consultations to vendors on common bases. Such a standardisation promotes an improvement of generation costs and of safety : public and authorities acceptance should be improved as well ; significant savings are expected in development and construction costs. Since the early stages of the project, the EUR group has grown significantly. It now includes utilities from nine European countries. Utilities from two other European countries are joining the group. Specific cooperation agreements are also in progress with a few extra-European partners

  14. Plant host finding by parasitic plants: a new perspective on plant to plant communication.

    Science.gov (United States)

    Mescher, Mark C; Runyon, Justin B; De Moraes, Consuelo M

    2006-11-01

    Plants release airborne chemicals that can convey ecologically relevant information to other organisms. These plant volatiles are known to mediate a large array of, often complex, interactions between plants and insects. It has been suggested that plant volatiles may have similar importance in mediating interactions among plant species, but there are few well-documented examples of plant-to-plant communication via volatiles, and the ecological significance of such interactions has been much debated. To date, nearly all studies of volatile-mediated interactions among plant species have focused on the reception of herbivore-induced volatiles by neighboring plants. We recently documented volatile effects in another system, demonstrating that the parasitic plant Cuscuta pentagona uses volatile cues to locate its hosts. This finding may broaden the discussion regarding plant-to-plant communication, and suggests that new classes of volatile-meditated interactions among plant species await discovery.

  15. Document clustering methods, document cluster label disambiguation methods, document clustering apparatuses, and articles of manufacture

    Science.gov (United States)

    Sanfilippo, Antonio [Richland, WA; Calapristi, Augustin J [West Richland, WA; Crow, Vernon L [Richland, WA; Hetzler, Elizabeth G [Kennewick, WA; Turner, Alan E [Kennewick, WA

    2009-12-22

    Document clustering methods, document cluster label disambiguation methods, document clustering apparatuses, and articles of manufacture are described. In one aspect, a document clustering method includes providing a document set comprising a plurality of documents, providing a cluster comprising a subset of the documents of the document set, using a plurality of terms of the documents, providing a cluster label indicative of subject matter content of the documents of the cluster, wherein the cluster label comprises a plurality of word senses, and selecting one of the word senses of the cluster label.

  16. Bechtel automated control of design document data

    International Nuclear Information System (INIS)

    Hollingshaus, H.

    1986-01-01

    Concern for nuclear power plant safety has resulted in many design features that complicate the licensing, operation, and maintenance of nuclear plants. To manage and control the design effectively, Bechtel has developed an integrated design document data base that provides efficient support of the plant during all phases of its life. The program runs on the IBM System 38, but can also be downloaded to an IBM PC to save storage and connect time. It is interactive and can accommodate multiple users at various locations. Although primarily developed to manage design changes resulting from the regulatory process and use of a fast track construction schedule, the data base will provide operations and maintenance personnel with qualifications status and pertinent data for each piece of equipment, including all electrical devices and a list of all associated design documents

  17. Technical approach document

    International Nuclear Information System (INIS)

    1989-12-01

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

  18. Materials for passively safe reactors

    International Nuclear Information System (INIS)

    Simnad, T.

    1993-01-01

    Future nuclear power capacity will be based on reactor designs that include passive safety features if recent progress in advanced nuclear power developments is realized. There is a high potential for nuclear systems that are smaller and easier to operate than the current generation of reactors, especially when passive or intrinsic characteristics are applied to provide inherent stability of the chain reaction and to minimize the burden on equipment and operating personnel. Taylor, has listed the following common generic technical features as the most important goals for the principal reactor development systems: passive stability, simplification, ruggedness, case of operation, and modularity. Economic competitiveness also depends on standardization and assurance of licensing. The performance of passively safe reactors will be greatly influenced by the successful development of advanced fuels and materials that will provide lower fuel-cycle costs. A dozen new designs of advanced power reactors have been described recently, covering a wide spectrum of reactor types, including pressurized water reactors, boiling water reactors, heavy-water reactors, modular high-temperature gas-cooled reactors (MHTGRs), and fast breeder reactors. These new designs address the need for passive safety features as well as the requirement of economic competitiveness

  19. New reactor programs from passive to pebble bed

    Energy Technology Data Exchange (ETDEWEB)

    Bruschi, H.J. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    2002-07-01

    The market for new nuclear power plants is small and challenged by alternative means of electric power generation. Customers and countries may vary in their requirements for a new nuclear plant; but all have a common theme of seeking a design that possesses favorable economics. This paper sets forth the economic challenges a new nuclear plant must overcome. In particular, it delineates the capital cost, construction time, and generation cost required to compete with combined cycle gas electric power generation. The U.S. power generation market is used as a point of comparison. Following this, the portfolio of BNFL/ Westinghouse plant designs are described and the methods by which they will meet the economic challenges previously delineated will be discussed. The portfolio includes the family of passive plants originated by the AP600 Design Certification process in the U.S. These plants are marked by a high degree of safety and simplicity, short construction times, and superior economics. In addition, the effort to meet European requirements for passive plants will be described. Lastly, the paper explores some advanced nuclear designs that are not yet licensed, and the hope that they hold for meeting the industry challenge ahead. (author)

  20. New reactor programs from passive to pebble bed

    International Nuclear Information System (INIS)

    Bruschi, H.J.

    2002-01-01

    The market for new nuclear power plants is small and challenged by alternative means of electric power generation. Customers and countries may vary in their requirements for a new nuclear plant; but all have a common theme of seeking a design that possesses favorable economics. This paper sets forth the economic challenges a new nuclear plant must overcome. In particular, it delineates the capital cost, construction time, and generation cost required to compete with combined cycle gas electric power generation. The U.S. power generation market is used as a point of comparison. Following this, the portfolio of BNFL/ Westinghouse plant designs are described and the methods by which they will meet the economic challenges previously delineated will be discussed. The portfolio includes the family of passive plants originated by the AP600 Design Certification process in the U.S. These plants are marked by a high degree of safety and simplicity, short construction times, and superior economics. In addition, the effort to meet European requirements for passive plants will be described. Lastly, the paper explores some advanced nuclear designs that are not yet licensed, and the hope that they hold for meeting the industry challenge ahead. (author)

  1. EDF group - Reference Document 2005

    International Nuclear Information System (INIS)

    2006-01-01

    The EDF Group is an integrated energy supplier operating in a wide range of electricity-related businesses: generation, transmission, distribution, sale and trading of energy. It is the main operator in the French electricity market and one of the leading electricity groups in Europe. With an installed capacity of 130.8 GW (123.9 GW in Europe), it contributes to the supply of energy and services to more than 40 million customers throughout the world (with approximately 36.7 million customers in Europe, more than 28 million of whom are in France). The EDF Group has built a business model balanced between deregulated and regulated operations in France and an international presence. In 2005, the Group recorded consolidated sales of euros 51,051 million, net income (Group share) of euros 3,242 million, and it achieved earnings before interests, taxes, depreciation and amortization of euros 13,010 million. This document is EDF Group's Reference Document for the year 2005. It contains information about: the Group activities, risk factors, Business Overview, Organizational Structure, Property, Plants and Equipment, Operating and Financial Review, Capital Resources, Research and Development, Patents and Licences, Trend Information, Financial Prospects, Administrative, Management, and Supervisory Bodies and Senior Management, Remuneration and Benefits, Board Practices, Employees/Human Resources, Major Shareholders, Related Party Transactions, Financial Information Concerning the Company's Assets and Liabilities, Financial Position and Profits and Losses, Material Contracts, Information on Holdings etc

  2. SRS ECOLOGY ENVIRONMENTAL INFORMATION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    Wike, L; Doug Martin, D; Eric Nelson, E; Nancy Halverson, N; John Mayer, J; Michael Paller, M; Rodney Riley, R; Michael Serrato, M

    2006-03-01

    The SRS Ecology Environmental Information Document (EEID) provides a source of information on the ecology of Savannah River Site (SRS). The SRS is a U.S. Department of Energy (DOE)--owned property on the upper Atlantic Coastal Plain of South Carolina, centered approximately 40 kilometers (25 miles) southeast of Augusta, Georgia. The entire site was designated a National Environmental Research Park in 1972 by the Atomic Energy Commission, the predecessor of DOE. This document summarizes and synthesizes ecological research and monitoring conducted on the three main types of ecosystems found at SRS: terrestrial, wetland and aquatic. It also summarizes the available information on the threatened and endangered species found on the Savannah River Site. SRS is located along the Savannah River and encompasses an area of 80,267 hectares (310 square miles) in three South Carolina counties. It contains diverse habitats, flora, and fauna. Habitats include upland terrestrial areas, wetlands, streams, reservoirs, and the adjacent Savannah River. These diverse habitats support a variety of plants and animals, including many commercially or recreationally valuable species and several rare, threatened, or endangered species. Soils are the basic terrestrial resource, influencing the development of terrestrial biological communities. Many different soils exist on the SRS, from hydric to well-drained, and from sand to clay. In general, SRS soils are predominantly well-drained loamy sands.

  3. EDF group - Reference Document 2004

    International Nuclear Information System (INIS)

    2005-01-01

    The EDF Group is an integrated energy supplier operating in a wide range of electricity-related businesses: generation, transmission, distribution, sale and trading of energy. It is the main operator in the French electricity market and one of the leading electricity groups in Europe. With an installed capacity of 125,4 GW, it contributes to the supply of energy and services to more than 42 million customers throughout the world (with approximately 36 million customers in Europe, more than 28 million of whom are in France). The EDF Group has built a business model balanced between deregulated and regulated operations in France and an international presence. In 2004, the Group recorded consolidated sales of euros 46,928 million, net income (Group share) of euros 1,341 million, and it achieved earnings before interests, taxes, depreciation and amortization of euros 12,127 million. This document is EDF Group's Reference Document for the year 2004. It contains information about: the Group activities, capital, relations with Gaz de France utility, strategy, industrial environment, history, activity in France, international activity, transverse activities and functions, disputes, arbitration and risk factors, Property, Plants and Equipment, Operating and Financial Review, Administrative, Management, and Supervisory Bodies and Senior Management, Remuneration and Benefits, recent trends and perspectives

  4. Plant walkdown

    International Nuclear Information System (INIS)

    Kostov, M.

    2000-01-01

    This report covers the following: preparatory steps for performing plant walk-down; the objective of the first plant walk-down; plant walk-down procedures; earthquake screening evaluation; walk-down documentation; second plant walk-down. The following objectives concerning the plant walk-down(s) were achieved. The plant system configuration is verified in order to proceed with event tree and fault tree analyses. Systems interactions, other types of dependencies or plant unique features are identified. he safety related components that are judged to generically possess high capacities (i.e., larger than the earthquake review level) have been verified to contain no weaknesses. Further analyses needed to establish the capacities of remaining safety-related components are identified and necessary field data are obtained. Information on components is obtained to assist in HCLPF (fragility) evaluation and peer review of the seismic margin study

  5. Use of passive solar architecture design in energy saving, Morena tourist village

    Energy Technology Data Exchange (ETDEWEB)

    Mina, M.B.

    1993-12-31

    This document deals with energy saving in buildings,more precisely in the Morena tourist village. The concept of passive solar technology is developed in villas. The first prototype enabled to have measurements of temperatures and thermal graphs. A comparison between the initial architectural design and this prototype shows the efficiency of the use of passive solar energy (energy and money saving). (TEC). 5 figs., 1 tab.

  6. Use of passive solar architecture design in energy saving, Morena tourist village

    Energy Technology Data Exchange (ETDEWEB)

    Mina, M B

    1994-12-31

    This document deals with energy saving in buildings,more precisely in the Morena tourist village. The concept of passive solar technology is developed in villas. The first prototype enabled to have measurements of temperatures and thermal graphs. A comparison between the initial architectural design and this prototype shows the efficiency of the use of passive solar energy (energy and money saving). (TEC). 5 figs., 1 tab.

  7. AREVA 2009 reference document; AREVA document de reference 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies. It contains information on the markets, market shares and competitive position of the AREVA group. This information provides an adequate picture of the size of these markets and of the AREVA group's competitive position. Content: 1 - Person responsible for the Reference Document and Attestation by the person responsible for the Reference Document; 2 - Statutory and Deputy Auditors; 3 - Selected financial information; 4 - Risks: Risk management and coverage, Legal risk, Industrial and environmental risk, Operating risk, Risk related to major projects, Liquidity and market risk, Other risk; 5 - Information about the issuer: History and development, Investments; 6 - Business overview: Markets for nuclear power and renewable energies, AREVA customers and suppliers, Overview and strategy of the group, Business divisions, Discontinued operations: AREVA Transmission and Distribution; 7 - Organizational structure; 8 - Property, plant and equipment: Principal sites of the AREVA group, Environmental issues that may affect the issuer's; 9 - Analysis of and comments on the group's financial position and performance: Overview, Financial position, Cash flow, Statement of financial position, Events subsequent to year-end closing for 2009; 10 - Capital Resources; 11 - Research and development programs, patents and licenses; 12 -trend information: Current situation, Financial objectives; 13 - Profit forecasts or estimates; 14 - Administrative, management and supervisory bodies and senior management; 15 - Compensation and benefits; 16 - Functioning of corporate bodies; 17 - Employees; 18 - Principal shareholders; 19 - Transactions with related parties: French state, CEA, EDF group; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information: Share capital, Certificate of incorporation and

  8. Passive inhalation of cannabis smoke

    Energy Technology Data Exchange (ETDEWEB)

    Law, B; Mason, P A; Moffat, A C; King, L J; Marks, V

    1984-09-01

    Six volunteers each smoked simultaneously, in a small unventilated room (volume 27 950 liter), a cannabis cigarette containing 17.1 mg delta 9-tetrahydrocannabinol (THC). A further four subjects - passive inhalers - remained in the room during smoking and afterwards for a total of 3 h. Blood and urine samples were taken from all ten subjects and analyzed by radioimmunoassay for THC metabolites. The blood samples from the passive subjects taken up to 3 h after the start of exposure to cannabis smoke showed a complete absence of cannabinoids. In contrast, their urine samples taken up to 6 h after exposure showed significant concentrations of cannabinoid metabolites (less than or equal to 6.8 ng ml-1). These data, taken with the results of other workers, show passive inhalation of cannabis smoke to be possible. These results have important implications for forensic toxicologists who are frequently called upon to interpret cannabinoid levels in body fluids.

  9. Active Versus Passive Academic Networking

    DEFF Research Database (Denmark)

    Goel, Rajeev K.; Grimpe, Christoph

    2013-01-01

    This paper examines determinants of networking by academics. Using information from a unique large survey of German researchers, the key contribution focuses on the active versus passive networking distinction. Is active networking by researchers a substitute or a complement to passive networking......? Other contributions include examining the role of geographic factors in networking and whether research bottlenecks affect a researcher's propensity to network. Are the determinants of European conference participation by German researchers different from conferences in rest of the world? Results show...... that some types of passive academic networking are complementary to active networking, while others are substitute. Further, we find differences in factors promoting participation in European conferences versus conferences in rest of the world. Finally, publishing bottlenecks as a group generally do...

  10. Protocol Monitoring Passive Solar Energy

    International Nuclear Information System (INIS)

    Van den Ham, E.R.; Bosselaar, L.

    1998-01-01

    A method has been developed by means of which the contribution of passive solar energy to the Dutch energy balance can be quantified univocally. The contribution was 57 PJ in 1990 and also 57 PJ in 1995. The efficiency of passive solar energy systems increased from -31.5% to -28.1% in the period 1990-1995, mainly as a result of the use of extra insulating glazing. As a result of the reduction of energy consumption for heating in houses it is expected that the extra contribution of 2 PJ will not be realized in the year 2010. It is suggested that the method to determine the absolute contribution of passive solar energy to the energy demand of dwellings is to be included in the protocol monitoring renewable energy. For the method to be included in the energy statistics of Statistics Netherlands (CBS) it can be considered only to take into account the difference compared to 1990. 11 refs

  11. Evaluation of Yield and Drought Using Active and Passive Spectral Sensing Systems at the Reproductive Stage in Wheat

    OpenAIRE

    Becker, Elisabeth; Schmidhalter, Urs

    2017-01-01

    Active and passive sensors are available for ground-based, high-throughput phenotyping in the field. However, these sensor systems have seldom been compared with respect to their determination of plant water status and water use efficiency related parameters under drought conditions. In this study, five passive and active reflectance sensors, including a hyperspectral passive sensor, an active flash sensor (AFS), the Crop Circle, and the GreenSeeker, were evaluated to assess drought-related d...

  12. Documentation of Concurrent programs.

    Science.gov (United States)

    1983-07-01

    preparing the documentation formats, and Tom McDonald for preparing the supplemental materials and statistical analyses. 16 [ 1 -16- I j REFERENCES I Boehm...34*h (eeeeeotop to enter h, to IAmlOCSot land ,uoMXM to R&’T- kfC ’Cod At 1*1 ,lgo: 0) 4 O ~ en ttR .I SA’ tgOhegl that ’t to 40n. .hi &ren a ~ O toll s

  13. SANSMIC design document.

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Paula D. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Rudeen, David Keith [GRAM, Inc., Albuquerque, NM (United States)

    2015-07-01

    The United States Strategic Petroleum Reserve (SPR) maintains an underground storage system consisting of caverns that were leached or solution mined in four salt domes located near the Gulf of Mexico in Texas and Louisiana. The SPR comprises more than 60 active caverns containing approximately 700 million barrels of crude oil. Sandia National Labo- ratories (SNL) is the geotechnical advisor to the SPR. As the most pressing need at the inception of the SPR was to create and fill storage volume with oil, the decision was made to leach the caverns and fill them simultaneously (leach-fill). Therefore, A.J. Russo developed SANSMIC in the early 1980s which allows for a transient oil-brine interface (OBI) making it possible to model leach-fill and withdrawal operations. As the majority of caverns are currently filled to storage capacity, the primary uses of SANSMIC at this time are related to the effects of small and large withdrawals, expansion of existing caverns, and projecting future pillar to diameter ratios. SANSMIC was identified by SNL as a priority candidate for qualification. This report continues the quality assurance (QA) process by documenting the "as built" mathematical and numerical models that comprise this document. The pro- gram flow is outlined and the models are discussed in detail. Code features that were added later or were not documented previously have been expounded. No changes in the code's physics have occurred since the original documentation (Russo, 1981, 1983) although recent experiments may yield improvements to the temperature and plume methods in the future.

  14. Electronic Braille Document Reader

    OpenAIRE

    Arif, Shahab; Holmes, Violeta

    2013-01-01

    This paper presents an investigation into developing a portable Braille device which would allow visually impaired individuals to read electronic documents by actuating Braille text on a finger. Braille books tend to be bulky in size due to the minimum size requirements for each Braille cell. E-books can be read in Braille using refreshable Braille displays connected to a computer. However, the refreshable Braille displays are expensive, bulky and are not portable. These factors restrict blin...

  15. Electronic Braille Document Reader

    OpenAIRE

    Arif, S.

    2012-01-01

    An investigation was conducted into developing a portable Braille device which would allow visually impaired individuals to read electronic documents by actuating Braille text on a finger. Braille books tend to be bulky in size due to the minimum size requirements for each Braille cell. E-books can be read in Braille using refreshable Braille displays connected to a computer. However, the refreshable Braille displays are expensive, bulky and are not portable. These factors restrict blind and ...

  16. AUDIT plan documenting method

    International Nuclear Information System (INIS)

    Cornecsu, M.

    1995-01-01

    The work describes a method of documenting the AUDIT plan upon the basis of two quantitative elements resulting from quality assurance program appraisal system function implementation degree as established from the latest AUDIT performed an system function weight in QAP, respectively, appraised by taking into account their significance for the activities that are to be performed in the period for which the AUDITs are planned. (Author) 3 Figs., 2 Refs

  17. Content Documents Management

    Science.gov (United States)

    Muniz, R.; Hochstadt, J.; Boelke J.; Dalton, A.

    2011-01-01

    The Content Documents are created and managed under the System Software group with. Launch Control System (LCS) project. The System Software product group is lead by NASA Engineering Control and Data Systems branch (NEC3) at Kennedy Space Center. The team is working on creating Operating System Images (OSI) for different platforms (i.e. AIX, Linux, Solaris and Windows). Before the OSI can be created, the team must create a Content Document which provides the information of a workstation or server, with the list of all the software that is to be installed on it and also the set where the hardware belongs. This can be for example in the LDS, the ADS or the FR-l. The objective of this project is to create a User Interface Web application that can manage the information of the Content Documents, with all the correct validations and filters for administrator purposes. For this project we used one of the most excellent tools in agile development applications called Ruby on Rails. This tool helps pragmatic programmers develop Web applications with Rails framework and Ruby programming language. It is very amazing to see how a student can learn about OOP features with the Ruby language, manage the user interface with HTML and CSS, create associations and queries with gems, manage databases and run a server with MYSQL, run shell commands with command prompt and create Web frameworks with Rails. All of this in a real world project and in just fifteen weeks!

  18. Passivation of high temperature superconductors

    Science.gov (United States)

    Vasquez, Richard P. (Inventor)

    1991-01-01

    The surface of high temperature superconductors such as YBa2Cu3O(7-x) are passivated by reacting the native Y, Ba and Cu metal ions with an anion such as sulfate or oxalate to form a surface film that is impervious to water and has a solubility in water of no more than 10(exp -3) M. The passivating treatment is preferably conducted by immersing the surface in dilute aqueous acid solution since more soluble species dissolve into the solution. The treatment does not degrade the superconducting properties of the bulk material.

  19. Investigations on passive containment cooling

    International Nuclear Information System (INIS)

    Knebel, J.U.; Cheng, X.; Neitzel, H.J.; Erbacher, F.J.; Hofmann, F.

    1997-01-01

    The composite containment design for advanced LWRs that has been examined under the PASCO project is a promising design concept for purely passive decay heat removal after a severe accident. The passive cooling processes applied are natural convection and radiative heat transfer. Heat transfer through the latter process removes at an emission coefficient of 0.9 about 50% of the total heat removed via the steel containment, and thus is an essential factor. The heat transferring surfaces must have a high emission coefficient. The sump cooling concept examined under the SUCO project achieves a steady, natural convection-driven flow from the heat source to the heat sink. (orig./CB) [de

  20. Passive solar offices: integrated design

    Energy Technology Data Exchange (ETDEWEB)

    Evans, B

    1992-05-06

    Passive solar design in out-of-town offices can remove the need for air-conditioning by making greater use of daylight and natural ventilation. To promote the use of passive solar energy a series of design studies are being run by the Energy Technology Support Unit on behalf of the Department of Energy. The three reported here are designs for out-of-town business buildings. Each is a hypothetical building designed to a realistic brief for an organisation taking the role of real client. (author).

  1. The Danish Reportive Passive as a Non-Canonical Passive

    DEFF Research Database (Denmark)

    Ørsnes, Bjarne

    2013-01-01

    Danish passive utterance and cognitive verbs allow a construction where the subject of an infinitival complement is raised: Peter siges at være bortrejst (‘Peter is said to be out of town’). Contrary to English, these verbs are not ECM-verbs or subject-to-object raising verbs in the active...

  2. Toward Documentation of Program Evolution

    DEFF Research Database (Denmark)

    Vestdam, Thomas; Nørmark, Kurt

    2005-01-01

    The documentation of a program often falls behind the evolution of the program source files. When this happens it may be attractive to shift the documentation mode from updating the documentation to documenting the evolution of the program. This paper describes tools that support the documentatio....... It is concluded that our approach can help revitalize older documentation, and that discovery of the fine grained program evolution steps help the programmer in documenting the evolution of the program....

  3. Passive fire protection role and evolutions

    Energy Technology Data Exchange (ETDEWEB)

    Cerosky, Tristan [NUVIA (France); Perdrix, Johan [NUVIA Protection (France)

    2015-12-15

    Major incidents associated with nuclear power plants often invoke a re-examination of key safety barriers. Fire hazard, in particular, is a key concern for safe operation of nuclear power plants given its propensity to damage safety systems which could ultimately lead to radioactive release into the atmosphere. In the recent past, events such as the Fukushima disaster have led to an industry-wide push to improve nuclear safety arrangements. As part of these measures, upgrading of fire safety systems has received significant attention. In addition to the inherent intricacies associated with such a complex undertaking, factors such as frequent changes in the national and European fire regulations also require due attention while formulating a fire protection strategy. This paper will highlight some salient aspects underpinning an effective fire protection strategy. This will involve: A) A comprehensive introduction to the different aspects of fire safety (namely prevention, containment and mitigation) supported by a review of the development of the RCC-I from 1993 to 1997 editions and the ETC-F (AFCEN codes used by EDF in France). B) Development of the fire risk analysis methodology and the different functions of passive fire protection within this method involving confinement and protection of safety-related equipment. C) A review of the benefits of an effective passive fire protection strategy, alongside other arrangements (such as active fire protection) to a nuclear operator in term of safety and cost savings. It is expected that the paper will provide nuclear operators useful guidelines for strengthening existing fire protection systems.

  4. Passive decay heat removal from the core region

    International Nuclear Information System (INIS)

    Hichen, E.F.; Jaegers, H.

    2002-01-01

    The decay heat in commercial Light Water Reactors is commonly removed by active and redundant safety systems supported by emergency power. For advanced power plant designs passive safety systems using a natural circulation mode are proposed: several designs are discussed. New experimental data gained with the NOKO and PANDA facilities as well as operational data from the Dodewaard Nuclear Power Plant are presented and compared with new calculations by different codes. In summary, the effectiveness of these passive decay heat removal systems have been demonstrated: original geometries and materials and for the NOKO facility and the Dodewaard Reactor typical thermal-hydraulic inlet and boundary conditions have been used. With several codes a good agreement between calculations and experimental data was achieved. (author)

  5. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1994-06-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  6. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1982-03-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  7. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1991-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued though the Department of Energy publication Power Reactor Docket Information, last published in January 1979

  8. Title List of documents made publicly available

    International Nuclear Information System (INIS)

    1982-05-01

    This document contains descriptions of the information received and generated by the US NRC. This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  9. Viviendo el documental

    OpenAIRE

    Álvarez Moreno, Víctor

    2017-01-01

    En el siguiente trabajo se recoge el proceso de realización y elaboración de un documental en 360 grados sobre la catedral de Valladolid bajo el título Reconstruyendo la catedral. El trabajo une realidad virtual con narrativa periodística. La realidad virtual es una herramienta que permite transformar al espectador en un testigo de la historia. En este caso, se muestra lo que pudo ser la catedral de Valladolid, cuyo objetivo era convertirse en la catedral más grande del territorio europeo. ...

  10. Documents and legal texts

    International Nuclear Information System (INIS)

    2016-01-01

    This section treats of the following documents and legal texts: 1 - Brazil: Law No. 13,260 of 16 March 2016 (To regulate the provisions of item XLIII of Article 5 of the Federal Constitution on terrorism, dealing with investigative and procedural provisions and redefining the concept of a terrorist organisation; and amends Laws No. 7,960 of 21 December 1989 and No. 12,850 of 2 August 2013); 2 - India: The Atomic Energy (Amendment) Act, 2015; Department Of Atomic Energy Notification (Civil Liability for Nuclear Damage); 3 - Japan: Act on Subsidisation, etc. for Nuclear Damage Compensation Funds following the implementation of the Convention on Supplementary Compensation for Nuclear Damage

  11. Databases in the documentation management for big industrial projects

    International Nuclear Information System (INIS)

    Cauchet, A.; Chevillard, F.; Parisot, Y.; Tirefort, C.

    1990-05-01

    The documentation management of a big industrial project involves a continuous update of information, both in the study and realization phase or in the operation phase. The organization of the technical documentation for big industrial projects requests complex information systems. In the first part of this paper are presented the methods appropriate for the analysis of documentation management procedures and in the second part are presented the tools by the combination of which a documentation system for the user is provided. The case of the documentation centres for the Hague reprocessing plant is described

  12. Antenna for passive RFID tags

    Science.gov (United States)

    Schiopu, Paul; Manea, Adrian; Cristea, Ionica; Grosu, Neculai; Vladescu, Marian; Craciun, Anca-Ileana; Craciun, Alexandru

    2015-02-01

    Minuscule devices, called RFID tags are attached to objects and persons and emit information which positioned readers may capture wirelessly. Many methods of identification have been used, but that of most common is to use a unique serial number for identification of person or object. RFID tags can be characterized as either active or passive [1,2]. Traditional passive tags are typically in "sleep" state until awakened by the reader's emitted field. In passive tags, the reader's field acts to charge the capacitor that powers the badge and this can be a combination of antenna and barcodes obtained with SAW( Surface Acoustic Wave) devices [1,2,3] . The antenna in an RFID tag is a conductive element that permits the tag to exchange data with the reader. The paper contribution are targeted to antenna for passive RFID tags. The electromagnetic field generated by the reader is somehow oriented by the reader antenna and power is induced in the tag only if the orientation of the tag antenna is appropriate. A tag placed orthogonal to the reader yield field will not be read. This is the reason that guided manufacturers to build circular polarized antenna capable of propagating a field that is alternatively polarized on all planes passing on the diffusion axis. Passive RFID tags are operated at the UHF frequencies of 868MHz (Europe) and 915MHz (USA) and at the microwave frequencies of 2,45 GHz and 5,8 GHz . Because the tags are small dimensions, in paper, we present the possibility to use circular polarization microstrip antenna with fractal edge [2].

  13. ExactPack Documentation

    Energy Technology Data Exchange (ETDEWEB)

    Singleton, Robert Jr. [Los Alamos National Laboratory; Israel, Daniel M. [Los Alamos National Laboratory; Doebling, Scott William [Los Alamos National Laboratory; Woods, Charles Nathan [Los Alamos National Laboratory; Kaul, Ann [Los Alamos National Laboratory; Walter, John William Jr [Los Alamos National Laboratory; Rogers, Michael Lloyd [Los Alamos National Laboratory

    2016-05-09

    For code verification, one compares the code output against known exact solutions. There are many standard test problems used in this capacity, such as the Noh and Sedov problems. ExactPack is a utility that integrates many of these exact solution codes into a common API (application program interface), and can be used as a stand-alone code or as a python package. ExactPack consists of python driver scripts that access a library of exact solutions written in Fortran or Python. The spatial profiles of the relevant physical quantities, such as the density, fluid velocity, sound speed, or internal energy, are returned at a time specified by the user. The solution profiles can be viewed and examined by a command line interface or a graphical user interface, and a number of analysis tools and unit tests are also provided. We have documented the physics of each problem in the solution library, and provided complete documentation on how to extend the library to include additional exact solutions. ExactPack’s code architecture makes it easy to extend the solution-code library to include additional exact solutions in a robust, reliable, and maintainable manner.

  14. Regulatory guidance document

    International Nuclear Information System (INIS)

    1994-05-01

    The Office of Civilian Radioactive Waste Management (OCRWM) Program Management System Manual requires preparation of the OCRWM Regulatory Guidance Document (RGD) that addresses licensing, environmental compliance, and safety and health compliance. The document provides: regulatory compliance policy; guidance to OCRWM organizational elements to ensure a consistent approach when complying with regulatory requirements; strategies to achieve policy objectives; organizational responsibilities for regulatory compliance; guidance with regard to Program compliance oversight; and guidance on the contents of a project-level Regulatory Compliance Plan. The scope of the RGD includes site suitability evaluation, licensing, environmental compliance, and safety and health compliance, in accordance with the direction provided by Section 4.6.3 of the PMS Manual. Site suitability evaluation and regulatory compliance during site characterization are significant activities, particularly with regard to the YW MSA. OCRWM's evaluation of whether the Yucca Mountain site is suitable for repository development must precede its submittal of a license application to the Nuclear Regulatory Commission (NRC). Accordingly, site suitability evaluation is discussed in Chapter 4, and the general statements of policy regarding site suitability evaluation are discussed in Section 2.1. Although much of the data and analyses may initially be similar, the licensing process is discussed separately in Chapter 5. Environmental compliance is discussed in Chapter 6. Safety and Health compliance is discussed in Chapter 7

  15. Strategy for Passivating Char Efficiently at the Pilot Scale

    Energy Technology Data Exchange (ETDEWEB)

    Dunning, Timothy C [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

    2018-01-18

    Fast pyrolysis is a promising pathway for the commercialization of liquid transportation fuels from biomass. Fast pyrolysis is performed at moderate heat (450-600 degrees Celcius) in an oxygen-deficient environment. One of the products of fast pyrolysis is biochar, which is often used as a heat source or as a soil amendment. Biochar is a partially reacted solid that is created in the production of bio-oil during fast pyrolysis. Biochar produced at these conditions contains significant quantities of carbon that adsorb oxygen when exposed to air. Biochar adsorption of oxygen is an exothermic process that may generate sufficient heat for combustion in ambient air. Biochar is also a self-insulating material which compounds the effects of heat generated internally. These factors lead to safety concerns and material handling difficulties. The Thermochemical Process Development Unit at the National Renewable Energy Laboratory operates a pilot plant that may be configured for fast pyrolysis, gasification, and will be introducing catalytic fast pyrolysis capabilities in 2018. The TCPDU designed and installed a system to introduce oxygen to collected biochar systematically for a controlled passivation. Biochar is collected and cooled in an oxygen deficient environment during fast pyrolysis. Oxygen is then introduced to the biochar on a mass flow basis. A sparger imbedded within the biochar sample near the bottom of the bed flows air diluted with nitrogen into the char bed, and excess gasses are removed from the top of the collection drum, above the char bed. Pressure within the collection drum is measured indicating adequate flow through filters. Sample weight is recorded before and after passivation. During passivation, temperature is measured at 18 points within the char bed. Oxygen content and temperature are measured leaving the char bed. Maximum temperature parameters were established to ensure operator safety during biochar passivation. Extensive passivation data was

  16. Surface Passivation in Empirical Tight Binding

    Science.gov (United States)

    He, Yu; Tan, Yaohua; Jiang, Zhengping; Povolotskyi, Michael; Klimeck, Gerhard; Kubis, Tillmann

    2016-03-01

    Empirical Tight Binding (TB) methods are widely used in atomistic device simulations. Existing TB methods to passivate dangling bonds fall into two categories: 1) Method that explicitly includes passivation atoms is limited to passivation with atoms and small molecules only. 2) Method that implicitly incorporates passivation does not distinguish passivation atom types. This work introduces an implicit passivation method that is applicable to any passivation scenario with appropriate parameters. This method is applied to a Si quantum well and a Si ultra-thin body transistor oxidized with SiO2 in several oxidation configurations. Comparison with ab-initio results and experiments verifies the presented method. Oxidation configurations that severely hamper the transistor performance are identified. It is also shown that the commonly used implicit H atom passivation overestimates the transistor performance.

  17. European BWR R and D cluster for innovative passive safety systems

    International Nuclear Information System (INIS)

    Hicken, E.F.; Lensa, W. von

    1996-01-01

    The main technological innovation trends for future nuclear power plants tend towards a broader use of passive safety systems for the prevention, mitigation and managing of severe accident scenarios. Several approaches have been undertaken in a number of European countries to study and demonstrate the feasibility and charateristics of innovative passive safety systems. The European BWR R and D Cluster combines those experimental and analytical efforts that are mainly directed to the introduction of passive safety systems into boiling water reactor technology. The Cluster is grouped around thermohydraulic test facilities in Europe for the qualification of innovative BWR safety systems, also taking into account especially the operating experience of the nuclear power plant Dodewaard and other BWRs, which already incorporated some passive safety features. The background, the objectives, the structure of the project and the work programme are presented in this paper as well as an outline of the significance of the expected results. (orig.) [de

  18. EDF group - Reference Document 2006

    International Nuclear Information System (INIS)

    2007-01-01

    The EDF Group is an integrated energy supplier operating in a wide range of electricity-related businesses: generation, transmission, distribution, sale and trading of energy. It is the main operator in the French electricity market and holds strong positions in the other three principal European markets (Germany, the United Kingdom, Italy) making it one of the leading electricity groups in Europe, and a recognized actor in the gas market. With an installed capacity of 123.7 GW in Europe (128.2 GW worldwide) it holds, among the major European energy specialists, the largest production fleet and the one emitting the least CO 2 , owing to the share of nuclear technology and hydropower in its generation mix. The EDF group supplies electricity, gas and associated services to more than 37.8 million customers throughout the world and in Europe (more than 28 million of whom are in France). The EDF Group has built a business model balanced between France and the international markets, and between deregulated and regulated operations. In 2006, the Group recorded consolidated sales of euros 58,932 million, net income (Group share) of euros 5,605 million, and it achieved earnings before interest, taxes, depreciation and amortization of euros 13,930 million. From July 1, 2007, the EDF group will carry out its trading activities in a European energy market fully open to competition. This document is EDF Group's Reference Document for the year 2006. It contains information about: the Group activities, risk factors, Business overview, Organizational structure, Property, plants and equipment, Operating and financial review, Capital resources and cash flows, Research and Development, Patents and Licenses, Trend information, Financial forecasts or estimates, Administrative, management and supervisory bodies and senior management, Remuneration and benefits, Board practices, Employees/Human resources, Major shareholders, Related party transactions, Financial information

  19. Passive Strategy with Integrated Passive Safety System (IPSS) for DBAs in SBO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sang Ho; Kim, Jihee; Choi, Jae Young; Jeon, Inseop; Chang, Soon Heung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2013-10-15

    In this paper, the strategies of coping with DBAs in SBO were proposed by the design with IPSS. Current nuclear power plants adopt emergency strategies using fire truck as a provision of steam generator cooling. However, it has a lot of limitation like water inventory, preparedness and accessibility. In the case of passive strategy by the application of IPSS, faster actions and more efficient performances can be achieved. The application of IPSS implies the preparedness of big water tank which can be used as water supplier, heat sink and filtering medium. The proposed strategies are set under the conservative conditions without AC power. In order to set more realistic and acceptable strategy, the proposed passive strategy has to be combined with the current strategies. The combined strategies can avoid the reiteration and complexity in accidents. Accordingly, the set of operation mode considering action priority with estimating specific conditions is the further work of this research. Removing decay heat is one of the most important issues in safety of nuclear engineering. In the Fukushima accidents, the initial problem was an occurrence of tsunami. It was connected into a station black out (SBO) which lost AC power in site. Finally, SBO with human error induced the failure of decay heat removal. The occurrence of SBO and the failure of decay heat removal imply the questions for solving them. In order to prevent and mitigate SBO, some solutions have been proposed after the Fukushima accident. First of all, physical protection is enhanced to prevent external risks. For example, the tsunami barrier was modified to be higher from 7.5 m to 10 m. The second is to add electrical redundancy to prevent a total loss of electrical power. AAC diesel generators and movable diesel generators are examples for emergency conditions to supply AC power in site. Bunker concept which was proposed in Europe is a representative example. The bunker concept was analyzed to be applied in

  20. Passivation Of High-Temperature Superconductors

    Science.gov (United States)

    Vasquez, Richard P.

    1991-01-01

    Surfaces of high-temperature superconductors passivated with native iodides, sulfides, or sulfates formed by chemical treatments after superconductors grown. Passivating compounds nearly insoluble in and unreactive with water and protect underlying superconductors from effects of moisture. Layers of cuprous iodide and of barium sulfate grown. Other candidate passivating surface films: iodides and sulfides of bismuth, strontium, and thallium. Other proposed techniques for formation of passivating layers include deposition and gas-phase reaction.

  1. Passive Scalar Evolution in Peripheral Region

    OpenAIRE

    Lebedev, V. V.; Turitsyn, K. S.

    2003-01-01

    We consider evolution of a passive scalar (concentration of pollutants or temperature) in a chaotic (turbulent) flow. A universal asymptotic behavior of the passive scalar decay (homogenization) related to peripheral regions (near walls) is established. The passive scalar moments and its pair correlation function in the peripheral region are analyzed. A special case investigated in our paper is the passive scalar decay along a pipe.

  2. Specialists' meeting on passive and active safety features of LMFRs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics.

  3. Specialists' meeting on passive and active safety features of LMFRs

    International Nuclear Information System (INIS)

    1991-01-01

    The objective of the meeting was to discuss and exchange information on passive and active safety concepts and to find some reasonable coupling of these concept, aiming at firmer establishment of plant safety and at the same time of plant cost reduction. The following main topical areas were discussed by delegates: (1) Overview - review of national status on the safety design approaches of LMFRs (2) Safety characteristics of decay heat removal system (DHRS) (3) Safety characteristics of reactor protection system (RPS) and reactor shutdown system (RSS) (4) Core safety characteristics

  4. Documentation of TRU biological transport model (BIOTRAN)

    Energy Technology Data Exchange (ETDEWEB)

    Gallegos, A.F.; Garcia, B.J.; Sutton, C.M.

    1980-01-01

    Inclusive of Appendices, this document describes the purpose, rationale, construction, and operation of a biological transport model (BIOTRAN). This model is used to predict the flow of transuranic elements (TRU) through specified plant and animal environments using biomass as a vector. The appendices are: (A) Flows of moisture, biomass, and TRU; (B) Intermediate variables affecting flows; (C) Mnemonic equivalents (code) for variables; (D) Variable library (code); (E) BIOTRAN code (Fortran); (F) Plants simulated; (G) BIOTRAN code documentation; (H) Operating instructions for BIOTRAN code. The main text is presented with a specific format which uses a minimum of space, yet is adequate for tracking most relationships from their first appearance to their formulation in the code. Because relationships are treated individually in this manner, and rely heavily on Appendix material for understanding, it is advised that the reader familiarize himself with these materials before proceeding with the main text.

  5. Documentation of TRU biological transport model (BIOTRAN)

    International Nuclear Information System (INIS)

    Gallegos, A.F.; Garcia, B.J.; Sutton, C.M.

    1980-01-01

    Inclusive of Appendices, this document describes the purpose, rationale, construction, and operation of a biological transport model (BIOTRAN). This model is used to predict the flow of transuranic elements (TRU) through specified plant and animal environments using biomass as a vector. The appendices are: (A) Flows of moisture, biomass, and TRU; (B) Intermediate variables affecting flows; (C) Mnemonic equivalents (code) for variables; (D) Variable library (code); (E) BIOTRAN code (Fortran); (F) Plants simulated; (G) BIOTRAN code documentation; (H) Operating instructions for BIOTRAN code. The main text is presented with a specific format which uses a minimum of space, yet is adequate for tracking most relationships from their first appearance to their formulation in the code. Because relationships are treated individually in this manner, and rely heavily on Appendix material for understanding, it is advised that the reader familiarize himself with these materials before proceeding with the main text

  6. Two or three decades of passive directions

    International Nuclear Information System (INIS)

    Cook, J.

    1995-01-01

    This paper presents an overview of the direction of passive solar architecture. The topics of the paper include design temperatures for buildings, active vs passive, fuel vs philosophy, engineering vs architecture, the thermal scale: heating vs cooling, fuel subsidies, divergent practices, sustainability, lighting, health, the place of passive technology

  7. Active house concept versus passive House

    NARCIS (Netherlands)

    Zeiler, W.; Boxem, G.; Vehler, R.; Verhoeven, M.; Fremouw, M.

    2009-01-01

    The passive house concept is the present trend in energy efficient sustainable dwellings. Within the passive house concept every effort is made to minimize the energy use. Substantial savings can be achieved by passive energy systems, especially natural ventilation, summer shading and winter solar

  8. Innovative solutions in passive house details

    NARCIS (Netherlands)

    Mlecnik, E.; Hilderson, W.

    2008-01-01

    For the realization of the first passive house demonstration projects in Belgium, passive houses were requested by convinced clients, designed by architects with experience in low energy building, and built by contractors with a feeling for working in building teams. These first passive house

  9. A Lexical Approach to Passive in ESL.

    Science.gov (United States)

    Marshall, Fred

    Dissatisfaction with the standard transformational grammar approach to teaching passive voice sentences gave rise to the method developed. It is based on the framework of a lexical-functional grammar, which claims that both active and passive sentences are base-generated, and that both active and passive verb forms occur in the lexicon. It would…

  10. Probable variations of a passive safety containment for a 1700 MWe class PWR with passive safety systems

    International Nuclear Information System (INIS)

    Sato, Takashi; Fujiki, Yasunobu; Oikawa, Hirohide; Ofstun, Richard P.

    2009-01-01

    The paper presents probable variations of a passive safety containment for a PWR. The passive safety containment is named Mark P containment tentatively. It is a pressure suppression type containment for a large scale PWR with a BWR type passive containment cooling system (PCCS). More than 3-day grace period can be achieved even for a 1700 MWe class large scale PWR owing to the PCCS. The containment is a reinforced concrete containment vessel (RCCV). The design pressure of the RCCV can be low owing to the suppression pool (S/P) and no prestressed tendon is necessary. It is a single barrier CV that can withstand a large airplane crash by itself. This simple configuration results in good economy and short construction term. The BWR type passive safety systems also include the Passive Cooling and Depressurization System (PCDS). The PCDS has 3-day grace period for the SBO induced by a giant earthquake and can practically eliminate the residual risk of a giant earthquake beyond the design basis earthquake of Ss. It also has a safety function to automatically depressurize the primary system at accidents such as SGTR and eliminate the need for operator actions. It is a large 1700 MWe passive safety PWR that has more than 3-day grace period for extremely severe natural disasters including a giant earthquake, a mega hurricane, tsunami and so on; no containment failure at a SA establishing a no evacuation plant; protection for a large airplane crash with the RCCV single barrier; good economy and short construction term. (author)

  11. Areva - 2016 Reference document

    International Nuclear Information System (INIS)

    2017-01-01

    Areva supplies high added-value products and services to support the operation of the global nuclear fleet. The company is present throughout the entire nuclear cycle, from uranium mining to used fuel recycling, including nuclear reactor design and operating services. Areva is recognized by utilities around the world for its expertise, its skills in cutting-edge technologies and its dedication to the highest level of safety. Areva's 36,000 employees are helping build tomorrow's energy model: supplying ever safer, cleaner and more economical energy to the greatest number of people. This Reference Document contains information on Areva's objectives, prospects and development strategies. It contains estimates of the markets, market shares and competitive position of Areva

  12. Working document dispersion models

    International Nuclear Information System (INIS)

    Dop, H. van

    1988-01-01

    This report is a summary of the most important results from June 1985 of the collaboration of the RIVM (Dutch National Institute for Public Health and Environment Hygiene) and KNMI (Royal Dutch Meteorologic Institute) on the domain of dispersion models. It contains a short description of the actual SO x /NO x -model. Furthermore it contains recommendations for modifications of some numerical-mathematical aspects and an impulse to a more complete description of chemical processes in the atmosphere and the (wet) deposition process. A separate chapter is devoted to the preparation of meteorologic data which are relevant for dispersion as well as atmospheric chemistry and deposition. This report serves as working document for the final formulation of a acidifying- and oxidant-model. (H.W.). 69 refs.; 51 figs.; 13 tabs.; 3 schemes

  13. Integrated criteria document mercury

    International Nuclear Information System (INIS)

    Sloof, W.; Beelan, P. van; Annema, J.A.; Janus, J.A.

    1995-01-01

    The document contains a systematic review and a critical evaluation of the most relevant data on the priority substance mercury for the purpose of effect-oriented environmental policy. Chapter headings are: properties and existing standards; production, application, sources and emissions (natural sources, industry, energy, households, agriculture, dental use, waste); distribution and transformation (cinnabar; Hg 2+ , Hg 2 2+ , elemental mercury, methylmercury, behavior in soil, water, air, biota); concentrations and fluxes in the environment and exposure levels (sampling and measuring methods, occurrence in soil, water, air etc.); effects (toxicity to humans and aquatic and terrestrial systems); emissions reduction (from industrial sources, energy, waste processing etc.); and evaluation (risks, standards, emission reduction objectives, measuring strategies). 395 refs

  14. Gaia DR1 documentation

    Science.gov (United States)

    van Leeuwen, F.; de Bruijne, J. H. J.; Arenou, F.; Comoretto, G.; Eyer, L.; Farras Casas, M.; Hambly, N.; Hobbs, D.; Salgado, J.; Utrilla Molina, E.; Vogt, S.; van Leeuwen, M.; Abreu, A.; Altmann, M.; Andrei, A.; Babusiaux, C.; Bastian, U.; Biermann, M.; Blanco-Cuaresma, S.; Bombrun, A.; Borrachero, R.; Brown, A. G. A.; Busonero, D.; Busso, G.; Butkevich, A.; Cantat-Gaudin, T.; Carrasco, J. M.; Castañeda, J.; Charnas, J.; Cheek, N.; Clementini, G.; Crowley, C.; Cuypers, J.; Davidson, M.; De Angeli, F.; De Ridder, J.; Evans, D.; Fabricius, C.; Findeisen, K.; Fleitas, J. M.; Gracia, G.; Guerra, R.; Guy, L.; Helmi, A.; Hernandez, J.; Holl, B.; Hutton, A.; Klioner, S.; Lammers, U.; Lecoeur-Taïbi, I.; Lindegren, L.; Luri, X.; Marinoni, S.; Marrese, P.; Messineo, R.; Michalik, D.; Mignard, F.; Montegriffo, P.; Mora, A.; Mowlavi, N.; Nienartowicz, K.; Pancino, E.; Panem, C.; Portell, J.; Rimoldini, L.; Riva, A.; Robin, A.; Siddiqui, H.; Smart, R.; Sordo, R.; Soria, S.; Turon, C.; Vallenari, A.; Voss, H.

    2017-12-01

    94000 Hipparcos stars in the primary data set, the proper motion standard errors are much smaller, at about 0.06 mas yr^-1. For the secondary astrometric data set, the typical standard error on the positions is 10 mas. The median standard errors on the mean G-band magnitudes range from the milli-magnitude level to 0.03 mag over the magnitude range 5 to 20.7. The DPAC undertook an extensive validation of Gaia DR1 which confirmed that this data release represents a major advance in the mapping of the skies and the availability of basic stellar data that form the foundation of observational astrophysics. However, as a consequence of the very preliminary nature of this first Gaia data release, there are a number of important limitations to the data quality. These limitations are documented in the Astronomy & Astrophysics papers that accompany Gaia DR1, with further information provided in this documentation. The reader is strongly encouraged to read about these limitations and to carefully consider them before drawing conclusions from the data. This Gaia DR1 documentation complements the peer-reviewed papers that accompany the release in a Special Issue of Astronomy & Astrophysics. The papers form the primary documentation for the data release and they are frequently referenced throughout the text.

  15. Wind system documentation

    Energy Technology Data Exchange (ETDEWEB)

    Froggatt, J.R.; Tatum, C.P.

    1993-01-15

    Atmospheric transport and diffusion models have been developed by the Environmental Technology Section (ETS) of the Savannah River Technology Center to calculate the location and concentration of toxic or radioactive materials during an accidental release at the Savannah River Site (SRS). The output from these models has been used to support initial on-site and off-site emergency response activities such as protective action decision making and field monitoring coordination. These atmospheric transport and diffusion models have been incorporated into an automated computer-based system called the (Weather Information and Display) System and linked to real-time meteorological and radiological monitoring instruments to provide timely information for these emergency response activities (Hunter, 1990). This report documents various aspects of the WIND system.

  16. ICRS Recommendation Document

    DEFF Research Database (Denmark)

    Roos, Ewa M.; Engelhart, Luella; Ranstam, Jonas

    2011-01-01

    and function evaluated for validity and psychometric properties in patients with articular cartilage lesions. Results: The knee-specific instruments, titled the International Knee Documentation Committee Subjective Knee Form and the Knee injury and Osteoarthritis and Outcome Score, both fulfill the basic......Abstract Objective: The purpose of this article is to describe and recommend patient-reported outcome instruments for use in patients with articular cartilage lesions undergoing cartilage repair interventions. Methods: Nonsystematic literature search identifying measures addressing pain...... constructs at all levels according to the International Classification of Functioning. Conclusions: Because there is no obvious superiority of either instrument at this time, both outcome measures are recommended for use in cartilage repair. Rescaling of the Lysholm Scoring Scale has been suggested...

  17. Environmental Information Document: L-reactor reactivation

    Energy Technology Data Exchange (ETDEWEB)

    Mackey, H.E. Jr. (comp.)

    1982-04-01

    Purpose of this Environmental Information Document is to provide background for assessing environmental impacts associated with the renovation, restartup, and operation of L Reactor at the Savannah River Plant (SRP). SRP is a major US Department of Energy installation for the production of nuclear materials for national defense. The purpose of the restart of L Reactor is to increase the production of nuclear weapons materials, such as plutonium and tritium, to meet projected needs in the nuclear weapons program.

  18. Environmental Information Document: L-reactor reactivation

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.

    1982-04-01

    Purpose of this Environmental Information Document is to provide background for assessing environmental impacts associated with the renovation, restartup, and operation of L Reactor at the Savannah River Plant (SRP). SRP is a major US Department of Energy installation for the production of nuclear materials for national defense. The purpose of the restart of L Reactor is to increase the production of nuclear weapons materials, such as plutonium and tritium, to meet projected needs in the nuclear weapons program

  19. Areva, reference document 2006

    International Nuclear Information System (INIS)

    2006-01-01

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains information on the markets, market shares and competitive position of the AREVA group. Content: - 1 Person responsible for the reference document and persons responsible for auditing the financial statements; - 2 Information pertaining to the transaction (Not applicable); - 3 General information on the company and its share capital: Information on AREVA, on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; - 4 Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts, The principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and development programs, intellectual property and trademarks, Risk and insurance; - 5 Assets - Financial position - Financial performance: Analysis of and comments on the group's financial position and performance, 2006 Human Resources Report, Environmental Report, Consolidated financial statements, Notes to the consolidated financial statements, AREVA SA financial statements, Notes to the corporate financial statements; 6 - Corporate Governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Combined General Meeting of Shareholders of May 3, 2007; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2006, Outlook; 8 - Glossary; 9 - Table of concordance

  20. Areva reference document 2007

    International Nuclear Information System (INIS)

    2008-01-01

    This reference document contains information on the AREVA group's objectives, prospects and development strategies, particularly in Chapters 4 and 7. It contains also information on the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the reference document and persons responsible for auditing the financial statements; 2 - Information pertaining to the transaction (not applicable); 3 - General information on the company and its share capital: Information on Areva, Information on share capital and voting rights, Investment certificate trading, Dividends, Organization chart of AREVA group companies, Equity interests, Shareholders' agreements; 4 - Information on company operations, new developments and future prospects: Overview and strategy of the AREVA group, The Nuclear Power and Transmission and Distribution markets, The energy businesses of the AREVA group, Front End division, Reactors and Services division, Back End division, Transmission and Distribution division, Major contracts 140 Principal sites of the AREVA group, AREVA's customers and suppliers, Sustainable Development and Continuous Improvement, Capital spending programs, Research and Development programs, Intellectual Property and Trademarks, Risk and insurance; 5 - Assets financial position financial performance: Analysis of and comments on the group's financial position and performance, Human Resources report, Environmental report, Consolidated financial statements 2007, Notes to the consolidated financial statements, Annual financial statements 2007, Notes to the corporate financial statements; 6 - Corporate governance: Composition and functioning of corporate bodies, Executive compensation, Profit-sharing plans, AREVA Values Charter, Annual Ordinary General Meeting of Shareholders of April 17, 2008; 7 - Recent developments and future prospects: Events subsequent to year-end closing for 2007, Outlook; Glossary; table of concordance

  1. Documenting and validating the indigenous knowledge on the use ...

    African Journals Online (AJOL)

    This article is based on research that focussed on the documentation and the validation of indigenous knowledge on the use of the Dwarf Sage plant in Namibia. The purpose of the study was four-fold: (a) to conduct a systematic recording of the body of indigenous knowledge of the Dwarf Sage; (b) to record and document ...

  2. A reliability assessment methodology for the VHTR passive safety system

    International Nuclear Information System (INIS)

    Lee, Hyungsuk; Jae, Moosung

    2014-01-01

    The passive safety system of a VHTR (Very High Temperature Reactor), which has recently attracted worldwide attention, is currently being considered for the design of safety improvements for the next generation of nuclear power plants in Korea. The functionality of the passive system does not rely on an external source of an electrical support system, but on the intelligent use of natural phenomena. Its function involves an ultimate heat sink for a passive secondary auxiliary cooling system, especially during a station blackout such as the case of the Fukushima Daiichi reactor accidents. However, it is not easy to quantitatively evaluate the reliability of passive safety for the purpose of risk analysis, considering the existing active system failure since the classical reliability assessment method cannot be applied. Therefore, we present a new methodology to quantify the reliability based on reliability physics models. This evaluation framework is then applied to of the conceptually designed VHTR in Korea. The Response Surface Method (RSM) is also utilized for evaluating the uncertainty of the maximum temperature of nuclear fuel. The proposed method could contribute to evaluating accident sequence frequency and designing new innovative nuclear systems, such as the reactor cavity cooling system (RCCS) in VHTR to be designed and constructed in Korea.

  3. Problems facing the use of passive safety systems

    International Nuclear Information System (INIS)

    Burgazzi, L.

    2012-01-01

    This study will analyze the current state of the art in the reliability of passive systems for extensive use in future nuclear power plants. This case study uncovers the insights on the technological issues associated with the reliability of the systems based on thermal-hydraulics, for which, methods are still in developing phase. The paper is organized as follows: at first the current available methodologies are illustrated and compared, the open issues coming out from their analysis are identified. Five open issues have been identified: 1) the assessment of the uncertainties related to passive system performance; 2) the dependencies among parameters in thermo-hydraulics; 3) the integration of the passive systems within an accident sequence in combination with active systems; 4) the development of dynamic event tree to incorporate the evolution upon time of the physical processes; and 5) the comparison between active and passive systems, mainly on a functional viewpoint. For each open issue the state of the art and the outlook is presented; the relative importance of each of them within the evaluation process is presented as well. (authors)

  4. Traffic classification with passive measurement

    OpenAIRE

    Pham, Hoang Phong

    2005-01-01

    Abstract This is a master thesis from a collaboration between Oslo University College and Uninett Research. Uninett have a passive monitoring device on a 2.5 Gbps backbone link between Trondheim and Narvik. They uses measurement with optical splitters and specialized measuring interfaces to trace traffic with Gigabit speed. We would like to investigate the structure and patterns in these data. It is of special interest to classify the traffic belonging to different services and protocols. ...

  5. Active and Passive Hybrid Sensor

    Science.gov (United States)

    Carswell, James R.

    2010-01-01

    A hybrid ocean wind sensor (HOWS) can map ocean vector wind in low to hurricane-level winds, and non-precipitating and precipitating conditions. It can acquire active and passive measurements through a single aperture at two wavelengths, two polarizations, and multiple incidence angles. Its low profile, compact geometry, and low power consumption permits installation on air craft platforms, including high-altitude unmanned aerial vehicles (UAVs).

  6. Alternative to Nitric Acid Passivation

    Science.gov (United States)

    Kessel, Kurt R.

    2016-01-01

    Corrosion is an extensive problem that affects the National Aeronautics and Space Administration (NASA) and European Space Agency (ESA). The deleterious effects of corrosion result in steep costs, asset downtime affecting mission readiness, and safety risks to personnel. It is vital to reduce corrosion costs and risks in a sustainable manner. The primary objective of this effort is to qualify citric acid as an environmentally-preferable alternative to nitric acid for passivation of stainless steel alloys.

  7. Interior design for passive solar homes

    Energy Technology Data Exchange (ETDEWEB)

    Breen, J. C.

    1981-07-01

    The increasing emphasis on refinement of passive solar systems has brought recognition to interior design as an integral part of passive solar architecture. Interior design can be used as a finetuning tool minimizing many of the problems associated with passive solar energy use in residential buildings. In addition, treatment of interior space in solar model homes may be a prime factor in determining sales success. A new style of interior design is evolving in response to changes in building form incorporating passive solar design features. The psychology behind passive solar architecture is reflected in interiors, and selection of interior components increasingly depends on the functional suitability of various interior elements.

  8. Interior design for passive solar homes

    Science.gov (United States)

    Breen, J. C.

    1981-07-01

    The increasing emphasis on refinement of passive solar systems brought recognition to interior design as an integral part of passive solar architecture. Interior design can be used as a finetuning tool minimizing many of the problems associated with passive solar energy use in residential buildings. In addition, treatment of interior space in solar model homes may be a prime factor in determining sales success. A new style of interior design is evolving in response to changes in building from incorporating passive solar design features. The psychology behind passive solar architecture is reflected in interiors, and selection of interior components increasingly depends on the functional suitably of various interior elements.

  9. Degradation of materials and passivity

    International Nuclear Information System (INIS)

    Meisel, W.

    1997-01-01

    Demanding for a reduction in materials degradation is a serious problem all over the world. Moessbauer spectroscopy (MS) is, among others, a very valuable tool to follow many degradation processes. Evidently, Fe is the most important Moessbauer element considering the overall presence of iron in everyday life. MS may contribute to our knowledge about nearly all fields of materials degradation, chemical, mechanical, thermal, irradiative, etc. Following some general lines, corrosion is considered in particular. MS is applicable to investigate the bulk of materials as well as their surface layers with an information depth of ca. 250 nm. In general, it has to be applied as a surface sensitive method in combination with other relevant methods in order to get a detailed insight into ongoing processes. Some examples have been selected to elucidate the application of MS in this field. Another class of examples concerns attempts to prevent corrosion, i.e., the application of coatings and transforming chemicals. A very effective and most natural way to reduce corrosion is the passivation of materials. The effect of passive layers and their destruction by environmental influences are discussed using results of MS and related methods. It is outlined that passivity is not restricted to chemically treated metals but can be considered as a general concept for preventing different kinds of materials from degradation. (orig.)

  10. Passive infrared motion sensing technology

    International Nuclear Information System (INIS)

    Doctor, A.P.

    1994-01-01

    In the last 10 years passive IR based (8--12 microns) motion sensing has matured to become the dominant method of volumetric space protection and surveillance. These systems currently cost less than $25 to produce and yet use traditionally expensive IR optics, filters, sensors and electronic circuitry. This IR application is quite interesting in that the volumes of systems produced and the costs and performance level required prove that there is potential for large scale commercial applications of IR technology. This paper will develop the basis and principles of operation of a staring motion sensor system using a technical approach. A model for the motion of the target is developed and compared to the background. The IR power difference between the target and the background as well as the optical requirements are determined from basic principles and used to determine the performance of the system. Low cost reflective and refractive IR optics and bandpass IR filters are discussed. The pyroelectric IR detector commonly used is fully discussed and characterized. Various schemes for ''false alarms'' have been developed and are also explained. This technology is also used in passive IR based motion sensors for other applications such as lighting control. These applications are also discussed. In addition the paper will discuss new developments in IR surveillance technology such as the use of linear motion sensing arrays. This presentation can be considered a ''primer'' on the art of Passive IR Motion Sensing as applied to Surveillance Technology

  11. Plant automation-application to SBWR project

    International Nuclear Information System (INIS)

    Rodriguez Rodriguez, C.

    1995-01-01

    In accordance with the requirements set out in the URD (Utility Requirements Document) issued by the EPRI (Electrical Power Research Institute), the design of new reactors, whether evolutionary or passive, shall taken into account the systematic automation of functions relating to normal plant operation. The objectives established are to: =2E Simplify operator-performed tasks =2E Reduce the risk of operator-error by considering human factors in the allocation of tasks =2E Improve man-machine reliability =2E Increase the availability of the plant In previous designs, automation has only been considered from the point of view of compliance with regulatory requirements for safety-related systems, or in isolated cases, as a method of protecting the investment where there is a risk of damage to main equipment. The use of digital technology has prevented the systematic pursuit of such objectives in the design of automated systems for processes associated with normal plant operation (startup, load follow, normal shutdown, etc) from being excessively complex and therefore costly to undertake. This paper describes how the automation of the aforementioned normal plant operation activities has been approached in General Electric's SBWR (Simplified Boiling Water Reactor) design. (Author)

  12. The passive of reflexive verbs in Icelandic

    Directory of Open Access Journals (Sweden)

    Hlíf Árnadóttir

    2011-10-01

    Full Text Available The Reflexive Passive in Icelandic is reminiscent of the so-called New Passive (or New Impersonal in that the oblique case of a passivized object NP is preserved. As is shown by recent surveys, however, speakers who accept the Reflexive Passive do not necessarily accept the New Passive, whereas conversely, speakers who accept the New Passive do also accept the Reflexive Passive. Based on these results we suggest that there is a hierarchy in the acceptance of passive sentences in Icelandic, termed the Passive Acceptability Hierarchy. The validity of this hierarchy is confirmed by our diachronic corpus study of open access digital library texts from Icelandic journals and newspapers dating from the 19th and 20th centuries (tímarit.is. Finally, we sketch an analysis of the Reflexive Passive, proposing that the different acceptability rates of the Reflexive and New Passives lie in the argument status of the object. Simplex reflexive pronouns are semantically dependent on the verbs which select them, and should therefore be analyzed as syntactic arguments only, and not as semantic arguments of these verbs.

  13. Documents and legal texts

    International Nuclear Information System (INIS)

    2015-01-01

    This section treats of the following Documents and legal texts: 1 - Canada: Nuclear Liability and Compensation Act (An Act respecting civil liability and compensation for damage in case of a nuclear incident, repealing the Nuclear Liability Act and making consequential amendments to other acts); 2 - Japan: Act on Compensation for Nuclear Damage (The purpose of this act is to protect persons suffering from nuclear damage and to contribute to the sound development of the nuclear industry by establishing a basic system regarding compensation in case of nuclear damage caused by reactor operation etc.); Act on Indemnity Agreements for Compensation of Nuclear Damage; 3 - Slovak Republic: Act on Civil Liability for Nuclear Damage and on its Financial Coverage and on Changes and Amendments to Certain Laws (This Act regulates: a) The civil liability for nuclear damage incurred in the causation of a nuclear incident, b) The scope of powers of the Nuclear Regulatory Authority (hereinafter only as the 'Authority') in relation to the application of this Act, c) The competence of the National Bank of Slovakia in relation to the supervised financial market entities in the financial coverage of liability for nuclear damage; and d) The penalties for violation of this Act)

  14. Survey and evaluation of inherent safety characteristics and passive safety systems for use in probabilistic safety analyses

    International Nuclear Information System (INIS)

    Wetzel, N.; Scharfe, A.

    1998-01-01

    The present report examines the possibilities and limits of a probabilistic safety analysis to evaluate passive safety systems and inherent safety characteristics. The inherent safety characteristics are based on physical principles, that together with the safety system lead to no damage. A probabilistic evaluation of the inherent safety characteristic is not made. An inventory of passive safety systems of accomplished nuclear power plant types in the Federal Republic of Germany was drawn up. The evaluation of the passive safety system in the analysis of the accomplished nuclear power plant types was examined. The analysis showed that the passive manner of working was always assumed to be successful. A probabilistic evaluation was not performed. The unavailability of the passive safety system was determined by the failure of active components which are necessary in order to activate the passive safety system. To evaluate the passive safety features in new concepts of nuclear power plants the AP600 from Westinghouse, the SBWR from General Electric and the SWR 600 from Siemens, were selected. Under these three reactor concepts, the SWR 600 is specially attractive because the safety features need no energy sources and instrumentation in this concept. First approaches for the assessment of the reliability of passively operating systems are summarized. Generally it can be established that the core melt frequency for the passive concepts AP600 and SBWR is advantageous in comparison to the probabilistic objectives from the European Pressurized Water Reactor (EPR). Under the passive concepts is the SWR 600 particularly interesting. In this concept the passive systems need no energy sources and instrumentation, and has active operational systems and active safety equipment. Siemens argues that with this concept the frequency of a core melt will be two orders of magnitude lower than for the conventional reactors. (orig.) [de

  15. Document image analysis: A primer

    Indian Academy of Sciences (India)

    R. Narasimhan (Krishtel eMaging) 1461 1996 Oct 15 13:05:22

    (1) Typical documents in today's office are computer-generated, but even so, inevitably by different computers and ... different sizes, from a business card to a large engineering drawing. Document analysis ... Whether global or adaptive ...

  16. Document management in engineering construction

    International Nuclear Information System (INIS)

    Liao Bing

    2008-01-01

    Document management is one important part of systematic quality management, which is one of the key factors to ensure the construction quality. In the engineering construction, quality management and document management shall interwork all the time, to ensure the construction quality. Quality management ensures that the document is correctly generated and adopted, and thus the completeness, accuracy and systematicness of the document satisfy the filing requirements. Document management ensures that the document is correctly transferred during the construction, and various testimonies such as files and records are kept for the engineering construction and its quality management. This paper addresses the document management in the engineering construction based on the interwork of the quality management and document management. (author)

  17. Recommended HSE-7 documents hierarchy

    International Nuclear Information System (INIS)

    Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

    1990-01-01

    This report recommends a hierarchy of waste management documents at Los Alamos National Laboratory (LANL or ''Laboratory''). The hierarchy addresses documents that are required to plan, implement, and document waste management programs at Los Alamos. These documents will enable the waste management group and the six sections contained within that group to satisfy requirements that are imposed upon them by the US Department of Energy (DOE), DOE Albuquerque Operations, US Environmental Protection Agency, various State of New Mexico agencies, and Laboratory management

  18. Safety related terms for advanced nuclear plants; Terminos relacionados con la seguridad para centrales nucleares avanzadas

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    The terms considered in this document are in widespread current use without a universal consensus as to their meaning. Other safety related terms are already defined in national or international codes and standards as well as in IAEA's Nuclear Safety Standards Series. Most of the terms in those codes and standards have been defined and used for regulatory purposes, generally for application to present reactor designs. There is no intention to duplicate the description of such regulatory terms here, but only to clarify the terms used for advanced nuclear plants. The following terms are described in this paper: Inherent safety characteristics, passive component, active component, passive systems, active system, fail-safe, grace period, foolproof, fault-/error-tolerant, simplified safety system, transparent safety.

  19. Passive film growth on carbon steel and its nanoscale features at various passivating potentials

    International Nuclear Information System (INIS)

    Li, Yuan; Cheng, Y. Frank

    2017-01-01

    Highlights: • Imaged the topography of passivated steel at various film-forming potentials. • Characterized the nanoscale features of passive films. • Determined the composition of passive films formed at various potentials. - Abstract: In this work, the passivation and topographic sub-structure of passive films on a carbon steel in a carbonate/bicarbonate solution was characterized by electrochemical measurements, atomic force microscopy and X-ray photoelectron spectroscopy. When passivating at a potential near the active-passive transition, the film contains the mixture of Fe_3O_4, Fe_2O_3 and FeOOH, with numerous nanoscale features. As the film-forming potential shifts positively, the passive film becomes more compact and the nanoscale features disappear. When the film is formed at a passive potential where the oxygen evolution is enabled, the content of FeOOH in the film increases, resulting in an amorphous topography and reduced corrosion resistance.

  20. Study on thermal-hydraulic phenomena identification of passive heat removal facilities

    International Nuclear Information System (INIS)

    Park, J. Y.

    2011-01-01

    Recently, passive heat removal facilities have been integral features of new generation or future reactor designs worldwide. This is because the passive heat removal facilities depending on a natural force such as buoyancy can give much higher operational reliability compared to active heat removal facilities depending on pumped fluid flow and as a result they can decrease core damage frequency of a nuclear power plant drastically ever achievable before. Keeping pace with this global trend, SMART and APR+ reactors also have introduced passive heat removal features such as a passive residual heat removal system (PRHRS) and a passive auxiliary feed water system (PAFS) in their designs. Since many thermal-hydraulic (T-H) phenomena including steam condensation are involved during operation of the passive heat removal facilities, they ought to be properly simulated by T-H codes such as MARS-KS and RELAP5 in order to guarantee reliable safety analysis by these codes. Unfortunately, however, these T-H codes are not well validated with respect to phenomena related to passive heat removal mechanism because previous focus on these codes validation was mainly on the LB LOCA and resulting phenomena. To resolve this gap, Korea Institute of Nuclear Safety has initiated a research program on the development of safety analysis technology for passive heat removal facilities. The main target of this program is PRHRS and PAFS in SMART and APR+ reactors and through this program, validation of capability of existing T-H codes and improvement of codes regarding passive facilities analysis are to be sought. In part of this research, T-H phenomena important to passive heat removal facilities (PRHRS and PAFS) are investigated in the present study