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Sample records for csni status summary

  1. CSNI Status summary on utilization of best-estimate methodology in safety analysis and licensing

    International Nuclear Information System (INIS)

    1996-10-01

    The PWG 2 Task Group on Thermal Hydraulic System Behavior has discussed the subject of the use of best-estimate codes in the licensing process (codes that model thermal hydraulic processes are important to assessing safety system performance). The Task Group set out to determine the prevailing practices in member countries, concerning safety assessment and safety review of transients affecting the reactor coolant system. A summary of information provided by member countries in response to eleven questions is given: Who is Responsible for Safety Analysis? Who is Responsible for Review and Evaluation of Safety Analysis? Do the Regulations Permit the use of Best-Estimate Codes? What are the Requirements for What Constitutes a Best Estimate Code? What are the Requirements Concerning Code Documentation? What are the Requirements for Review of Code Models and Correlations? What are the Requirements Concerning Code Assessment? What are the Requirements Concerning Initial and Boundary Conditions? What are the Requirements Concerning Operability of Active Equipment? What are the Requirements Concerning Operator Actions?

  2. CSNI/NEA Rasplav seminar 2000. Summary and conclusions

    International Nuclear Information System (INIS)

    2001-01-01

    various boundary conditions were investigated. The work involved a combination of integral and separate effect tests including molten-salt tests to investigate non-eutectic mixtures and the effects of stratification, extension of the material property database to allow interpretation and modelling of the experimental data. The CSNI decided to hold a seminar where the major outcome of the RASPLAV Project could be presented and discussed also in the context of other experienced activities on Severe Accidents. The objectives of the seminar are: - to review the experimental results of the RASPLAV Project; - to exchange information on complementary research; - to discuss the progress made on understanding severe accident progression; - to discuss the applicability to nuclear power plants and use of the results. The Seminar was intended to provide an in-depth review of the RASPLAV Project in terms of the technical capabilities, results and analyses produced during the project execution. The application of the results and their significance for power plant applications were addressed. Relevant results of the complementary research carried out at various laboratories were also presented. The seminar consisted of five sessions organised as follows: - Opening and overview; - Experimental results; - Theoretical Analyses; - Application and complementary research; - Conclusion

  3. CSNI/NEA Rasplav seminar 2000. Summary and conclusions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-15

    various boundary conditions were investigated. The work involved a combination of integral and separate effect tests including molten-salt tests to investigate non-eutectic mixtures and the effects of stratification, extension of the material property database to allow interpretation and modelling of the experimental data. The CSNI decided to hold a seminar where the major outcome of the RASPLAV Project could be presented and discussed also in the context of other experienced activities on Severe Accidents. The objectives of the seminar are: - to review the experimental results of the RASPLAV Project; - to exchange information on complementary research; - to discuss the progress made on understanding severe accident progression; - to discuss the applicability to nuclear power plants and use of the results. The Seminar was intended to provide an in-depth review of the RASPLAV Project in terms of the technical capabilities, results and analyses produced during the project execution. The application of the results and their significance for power plant applications were addressed. Relevant results of the complementary research carried out at various laboratories were also presented. The seminar consisted of five sessions organised as follows: - Opening and overview; - Experimental results; - Theoretical Analyses; - Application and complementary research; - Conclusion.

  4. Status of direct containment heating in CSNI member countries. Report of task group on ex-vessel thermal-hydraulics

    International Nuclear Information System (INIS)

    1989-03-01

    The status of activities on direct containment heating in the light water reactor program in OECD/CSNI countries is presented. Experimental and analytical studies are reviewed. Approaches or measures are discussed for accident management in relation to direct containment heating. A discussion is given of common and diverging views among the countries based, in part, on response to a questionnaire. The key issues are discussed and recommendations are provided for future CSNI work on direct containment heating

  5. OECD/CSNI specialist meeting on fuel coolant interactions: summary and conclusions

    International Nuclear Information System (INIS)

    1997-01-01

    Research activities and interest on fuel-coolant interaction (FCI) have been increased and broadened since the last CSNI Specialist Meeting held in January 1993. Significant experimental and analytical research has been performed in many OECD countries and others. The growing international interest is, in large part, due to the emphasis on broader aspects of FCI ranging from melt quenching and coolability to energetic explosions (both in- and ex-vessel), and their relevance and applications to next-generation reactor design as well as accident management strategies. The objectives of the meeting are to review the knowledge and to obtain consensus on the phenomenology of FCI and in predicting FCI behavior in LWRs severe accidents; to identify those areas of FCI phenomena and prediction which are important for reactor safety but still poorly understood and require further study with clear methodologies; to inform the community and the regulatory agencies of the status of FCI issues, especially in the application to accident management and future reactor designs. The various sessions are: reactor applications, pre-mixing, propagation / trigger, experiments

  6. OECD/NEA/CSNI Status Report on Filtered Containment Venting

    International Nuclear Information System (INIS)

    Jacquemain, D.; Guentay, S.; Basu, S.; Sonnenkalb, M.; Lebel, L.; Ball, J.; Allelein, H.J.; Liebana Martinez, B.; Eckardt, B.; Losch, N.; Ammirabile, L.; ); Gryffroy, D.; Sallus, L.; Kroes, A.; Rensonnet, T.; Anden, A.; Gyepi-Garbrah, S.; Viktorov, A.; Duspiva, J.; Routamo, T.; Guieu, S.; Hotta, A.; Nakamura, H.; Song, J.H.; Ha, K.S.; Filio, C.; Kuznetsov, M.V.; Kubisova, L.; Nemec, T.; Frid, W.; Loy, D.; Pellini, D.; Zieger, T.; Herranz Puebla, L.; Amri, A.; Kissane, M.; )

    2014-01-01

    This Status Report provides a comprehensive description of safety requirements associated with Filtered Containment Venting Systems (FCVSs) (Chapter 3) and of the status of FCVS implementation (Chapter 4) as provided by the various contributing countries. The different level of detail describing the accident management situation in different countries in relation to FCVS reflects in part the reality of the different levels of the current regulatory and/or technological appraisal of FCVS internationally. Further, the safety requirements differ in various countries being more-or-less prescriptive with FCVS not necessarily explicitly mandated or not considered as the primary measure to prevent containment over-pressurization. The following requirements may be prescribed for FCVS depending on venting strategies and objectives: vent capacity, vent opening and closing pressures, vent timing, venting system design requirements, consideration of possible hydrogen loads, radiological objectives, FCVS decontamination factors (DFs) for radioactive aerosols, for molecular iodine, etc. These are all discussed in detail in the report. A description of the FCV strategies for emergency operating procedures (EOPs) and SAM domains is provided in Chapter 5. FCVS are considered to be an additional system to protect the containment integrity. FCVSs are typically to be used in SAs as part of the overall applied SAM strategy for PWRs and BWRs, while they are also used in DBA for some PHWRs (CANDUs). Operation of a FCVS is also considered in some countries and for some reactor designs for accident management other than countering the long-term over-pressurization of the containment, e.g., for BWRs in the case of loss of heat sink to remove decay heat or to reduce the hydrogen inventory in the containment. Chapter 6 presents the well-known existing filtration technologies e.g., scrubbers, deep-bed filtration and different sorption systems. Details of systems for which information was

  7. OECD/CSNI Workshop on In-Vessel Core Debris Retention and Coolability - Summary and Conclusions

    International Nuclear Information System (INIS)

    Behbahani, Ali-Reza; Drozd, Andrzej; Kim, Sang-Baik; Micaelli, Jean-Claude; Okkonen, Timo; Sugimoto, Jun; Trambauer, Klaus; Tuomisto, Harri

    1999-01-01

    In the spring of 1994 an OECD Workshop on Large Pool Heat transfer was held in Grenoble. The scope of this workshop was the investigation of (1) molten pool heat transfer, (2) heat transfer to the surrounding water, and (3) the feasibility of in-vessel core debris cooling through external cooling of the vessel. Since this time, experimental test series have been completed (e.g., COPO, ULPU, CORVIS) and new experimental programs (e.g., BALI, SONATA, RASPLAV, debris and gap heat transfer) have been established to consolidate and expand the data base for further model development and to improve the understanding of in-vessel debris retention and coolability in a nuclear power plant. Discussions within the CSNI's PWG-2 and the Task Group on Degraded Core Cooling (TG-DCC) have led to the conclusion that the time was ripe for organizing a new international Workshop with the objectives: - to review the results of experimental research that has been conducted in this area; - to exchange information on the results of member countries experiments and model development on in-vessel core debris retention and coolability; - to discuss areas where additional experimental research is needed in order to provide an adequate data base for analytical model development for core debris retention and coolability. The scope of this workshop was limited to the phenomena connected to in-vessel core debris retention and coolability and did not include steam explosion and fission product issues. The workshop was structured into the following sessions: Key note papers; Experiments and model development; Debris bed heat transfer; Corium properties, molten pool convection and crust formation; Gap formation and gap cooling; Creep behaviour of reactor pressure vessel lower head; Ex-vessel boiling and critical heat flux phenomena; Scaling to reactor severe accident conditions and reactor applications. Compared to the previous workshop held in Grenoble in 1994, large progress has been made in the

  8. CSNI/NEA RASPLAV Seminar 2000, 14-15 November 2000, Munich, Germany - Executive Summary

    International Nuclear Information System (INIS)

    Asmolov, V.; Behbahani, A.; Hache, G.; Nakamura, H.; Raj Sehgal, B.; Strizhov, V.; Trambauer, K.; Tuomisto, H.; Vitanza, C.

    2000-11-01

    various boundary conditions were investigated. The work involved a combination of integral and separate effect tests including molten-salt tests to investigate non-eutectic mixtures and the effects of stratification, extension of the material property database to allow interpretation and modelling of the experimental data. The CSNI decided to hold a seminar where the major outcome of the RASPLAV Project could be presented and discussed also in the context of other experienced activities on Severe Accidents. The objectives of the seminar are: - to review the experimental results of the RASPLAV Project; - to exchange information on complementary research; - to discuss the progress made on understanding severe accident progression; - to discuss the applicability to nuclear power plants and use of the results. The Seminar was intended to provide an in-depth review of the RASPLAV Project in terms of the technical capabilities, results and analyses produced during the project execution. The application of the results and their significance for power plant applications were addressed. Relevant results of the complementary research carried out at various laboratories were also presented. The seminar consisted of five sessions. The abstracts of the presentations are given in the appendix, as well as the list of participants and the conference program

  9. CNRA/CSNI workshop on licensing and operating experience of computer-based I and C systems - Summary and conclusions

    International Nuclear Information System (INIS)

    2002-01-01

    The OECD Workshop on Licensing and Operating Experience of Computer-Based I and C Systems, was sponsored by both the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Czech State Office for Nuclear Safety (SUJB), the Czech Power Board CEZ a.s., I and C Energo a.s. and the Nuclear Research Institute, Rez near Prague. The objectives of the Workshop were to exchange the experience gained by both the regulators and the industry in different countries in the licensing and operation of computer-based I and C systems, to discuss the existing differences in their licensing approaches in various countries, to consider the safety aspects of their practical use, and to discuss the ways of promoting future international co-operation in the given area. The scope of the Workshop included: - review of the progress made since the CNRA/CSNI workshop which was held in 1996 - current and future regulatory needs and/or requirements for the computer-based I and C systems - progress made in software life cycle activities, including verification and validation, and safety/hazards analysis - benefits of applying the computer-based I and C systems to improve plant performance and safety. The Technical Sessions and Discussion Sessions covered the following topics: Opening Session: Advances made in the use and planning of computer-based I and C systems; Topic 1: National and international standards and guides for computer-based safety systems; Topic 2: Regulatory aspects; Topic 3: Analysis and assessment of digital I and C systems; Topic 4: Software life cycle activities; Topic 4: Experience with applications, system aspects, potential limits and future trends and needs; Final Session: Workshop summary. The workshop provided a unique opportunity for people with experience in licensing, developing, manufacturing, implementing, maintaining or

  10. Meeting summary of the second CSNI specialist meeting on simulators and plant analyzers - Current Issues in Nuclear Power Plant Simulation

    International Nuclear Information System (INIS)

    1998-01-01

    The Second CSNI Specialist Meeting on Simulators and Plant Analyzers: Current Issues in Nuclear Power Plant Simulation was held in Espoo, Finland, from September 29 through October 2, 1997. It was organised by CSNI Principal Working Group on Coolant System Behaviour (PWG2), Task Group on Thermal Hydraulic Applications (TG-THA), in co-operation with Technical Research Centre of Finland. The meeting in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. The previous meeting held in Lappeenranta, Finland, in 1992 collected some 85 participants from 12 countries, presenting a total of 40 papers. The meeting was structured into 6 sessions covering the important aspects of development and use of simulators and plant analyzers: Session I: New objectives, Requirements and Concepts. This session covered the progress experienced since the 1. simulator meeting and tried to address the changing role of simulators based on the changes in users' needs and developing possibilities. Session II: Trends in Simulation Technology. This session was reserved for studying the current trends in the simulation technology: software environments, visualisation, simulator configuration tools, programming languages and computer systems. Session III: Training and human factor studies using simulators. This session was created for studying the status of different uses of simulators such as educational simulators, human factor studies and integrated safety assessment in addition to traditional training. Regarding to the severe accidents, a question was raised whether the simulator use should be for training or education. Session IV: Modelling techniques. The session on modelling techniques was included to cover recent developments in the modelling techniques applicable to training

  11. Selected source term topics. Report to CSNI by an OECD/NEA Group of experts

    International Nuclear Information System (INIS)

    1987-04-01

    CSNI Report 136 summarizes the results of the work performed by the Group of Experts on the Source Term and Environmental Consequences (PWG4) during the period extending from 1983 and 1986. This report is complementary to Part 1, 'Technical Status of the Source Term' of CSNI Report 135, 'Report to CSNI on Source Term Assessment, Containment atmosphere control systems, and accident consequences'; it considers in detail a number of very specific issues thought to be important in the source term area. It consists of: an executive summary (prepared by the Chairman of the Group), a section on conclusions and recommendations, and five technical chapters (fission product chemistry in the primary circuit of a LWR during severe accidents; resuspension/re-entrainment of aerosols in LWRs following a meltdown accident; iodine chemistry under severe accident conditions; effects of combustion, steam explosions and pressurized melt ejection on fission product behaviour; radionuclide removal by pool scrubbing), a technical annex and two appendices

  12. Standards development status. Summary report

    International Nuclear Information System (INIS)

    1981-12-01

    The Standards Development Status Summary Report is designed for scheduling, monitoring, and controlling the process by which Regulatory Standards, Guides, Reports, Petitions, and Environmental Statements are written. It is a summary of the current schedule plans for development of the above products

  13. Product Operations Status Summary Metrics

    Science.gov (United States)

    Takagi, Atsuya; Toole, Nicholas

    2010-01-01

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

  14. Source term assessment, containment atmosphere control systems, and accident consequences. Report to CSNI by an OECD/NEA Group of experts

    International Nuclear Information System (INIS)

    1987-04-01

    CSNI Report 135 summarizes the results of the work performed by CSNI's Principal Working Group No. 4 on the Source Term and Environmental Consequences (PWG4) during the period extending from 1983 to 1986. This document contains the latest information on some important topics relating to source terms, accident consequence assessment, and containment atmospheric control systems. It consists of five parts: (1) a Foreword and Executive Summary prepared by PWG4's Chairman; (2) a Report on the Technical Status of the Source Term; (3) a Report on the Technical Status of Filtration and Containment Atmosphere Control Systems for Nuclear Reactors in the Event of a Severe Accident; (4) a Report on the Technical Status of Reactor Accident Consequence Assessment; (5) a list of members of PWG4

  15. Status report on developments and cooperation on risk-informed inservice-inspection and non-destructive testing (NDT) qualification in OECD-NEA member countries - CSNI integrity and ageing working group

    International Nuclear Information System (INIS)

    Skanberg, Lars

    2005-01-01

    During the last decades the nuclear industry has experienced service degradation of many components, both in primary systems and in secondary systems. Several inspection failures have also occurred over the years. This degradation and inspection history as well as the economical and political factors have consequently set up a pressure for more efficient and cost-effective in-service inspection programmes to ensure that there are adequate safety margins so that anticipated degradations of components do not lead to failures that cause accidents or even unplanned shutdowns with adverse effects on power production reliability. In this situation, nuclear regulators as well as nuclear utilities in many countries have developed and implement risk-informed inspection approaches together with more stringent requirements of demonstrating the performance of the NDT systems that are to be used for inspection of safety related components which are susceptible to different kind of degradation mechanisms. In December 2000, the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) agreed to prepare a state-of-the art report addressing the present situation and regulatory aspects in NEA member countries on: - Risk based / risk informed in-service inspections developments, - Qualification of NDT system to be used for the inspections. The CSNI gave mandate to the CSNI working group on the Integrity of Components and Structures (IAGE) to prepare the report. Practices and status in NEA member countries were collected in 2003 through a questionnaire. Results have been compiled in the report NEA/CSNI/R(2005)3. To complete the technical information, a CSNI Workshop was held from 13 to 14 April 2004 in Stockholm, Sweden hosted by the Swedish Nuclear Power Inspectorate. The Workshop gathered 54 participants from 17 countries including the EC, the IAEA and the main organisations worldwide developing RI-ISI methodologies. Papers

  16. Use and development of probabilistic safety assessment - CSNI WGRISK

    International Nuclear Information System (INIS)

    Siu, Nathan; Monninger, John; Gomez-Cobo, Ana; Kao, Tsu-Mu; Schoen, Gerhard; Gunsell, Lars; Nyman, Ralph; Jelinek, Tomas; Hultquist, Goeran; Rapp, Anders; Eriksson, Stefan; Lantaron, Alfredo; Vojnovic, Djordje; Husarcek, Jan; Kovacs, Zoltan; Versteeg, M.F.; Lopez Morones, Ramon; Lee, Chang-Ju; Fukuda, Mamoru; Burgazzi, Luciano; Caporali, Rino; RoeWEKAMP, Marina; MACSUGA, Geza; Bareith, Attila; Lanore, J.M.; Sorel, Vincent; Virolainen, Reino; Patrik, Milan; Mlady, Ondrej; Raducu, Gheorghe; De Gelder, Pieter; Hendrickx, Isabelle; Lanore, Jeanne-Marie; Murphy, Joseph A.; Shepherd, Charles; Pyy, Pekka T.; Mauny, Elisabeth

    2007-01-01

    The CSNI WGRISK produced a report in July 2002 on 'The Use and Development of Probabilistic Safety Assessment in NEA Member Countries'. This provides a description of the PSA programmes in the member countries at the time that the report was produced. However, there have been significant developments in PSA since 2002. Consequently, a decision was made at the WGRISK meeting in October 2005 to produce an updated version of the report. The aim was to produce an updated, stand alone version of the report that presents an analysis of the position on the use and development of PSA in the WGRISK member countries as of spring 2006. A detailed questionnaire was circulated to WGRISK members and to the IAEA to ascertain the state of the art in PSA use and development at the end of 2006. Detailed responses were prepared by 20 countries totalling several hundred pages of information. After first compilation of information, an updating round was organized by showing to the countries all the answers and the summary made of them by a small group of experts. The process led to some clarifications and more consistency in the report. The collected information was finally analyzed and summarized to reach the conclusions presented in this report. The set of section headings in the report is as follows: Executive summary. 1. Introduction. 2. PSA Framework and Environment. 3. Numerical Safety Criteria. 4. PSA Standards and Guidance. 5. Status and Scope of PSA Programmes. 6. PSA Methodology and Data. 7. PSA Applications. 8. Results and Insights from the PSAs. 9. Future Developments. Appendix A: Overview of the Status of PSA Programmes. Appendix B: Contact information. Appendix C: Questionnaire and Guidance to authors

  17. CSNI post-Fukushima activity on filtered containment venting systems: status in OECD countries and guidance for improvements and future designs - 15008

    International Nuclear Information System (INIS)

    Jacquemain, D.; Guentay, S.; Basu, S.; Sonnenkalb, M.; Lebel, L.; Allelein, H.J.; Liebana, B.; Eckardt, B.; Ammirabile, L.

    2015-01-01

    Stress tests performed after the Fukushima' s accident have led many countries to consider the implementation of Filtered Containment Venting Systems (FCVS) and strategies at their Nuclear Power Plants (NPP). Where not earlier applied, this could be considered as part of severe accident management (SAM) measures to enhance the response capability to severe accident (SA) situations. In addition, some countries are considering upgrading existing FCVS and their operation procedures for safe and reliable use in conditions which were not necessarily fully addressed at their design stage (e.g., robustness to hazards and hydrogen combustion loads, prolonged or repetitive use during a SA and manual operation without power supply). The CSNI report details safety design and qualification requirements for FCVS, FCV strategies for emergency operating procedures and SAM domains, implemented filtration technologies, performed source term evaluations in view of FCVS and provides guidance for the improvement of existing systems and for the design of future systems. Main outcomes of the report are presented in this paper

  18. Summary status of K Basins sludge characterization

    International Nuclear Information System (INIS)

    Baker, R.B.

    1995-01-01

    A number of activities are underway as part of the Spent Nuclear Fuels Project (SNFP) related to the processing and disposing of sludge in the 105-K Basins (K Basins). Efforts to rigorously define data requirements for these activities are being made using the Data Quality Objectives (DQO) process. Summaries of current sludge characterization data are required to both help support this DQO process and to allow continued progress with on-going engineering activities (e.g., evaluations of disposal alternatives). This document provides the status of K Basins sludge characterization data currently available to the Nuclear Fuel Evaluations group. This group is tasked by the SNFP to help develop and maintain the characterization baseline for the K Basins. The specific objectives of this document are to: (1) provide a current summary (and set of references) of sludge characterization data for use by SNFP initiatives, to avoid unnecessary duplication of effort and to support on-going initiatives; (2) submit these data to an open forum for review and comment, and identify additional sources of significant data that may be available; (3) provide a summary of current data to use as part of the basis to develop requirements for additional sludge characterization data through the DQO process; (4) provide an overview of the intended activities that will be used to develop and maintain the sludge characterization baseline

  19. Systematic evaluation program, status summary report

    International Nuclear Information System (INIS)

    1983-01-01

    Status reports are presented on the systematic evaluation program for the Big Rock Point reactor, Dresden-1 reactor, Dresden-2 reactor, Ginna-1 reactor, Connecticut Yankee reactor, LACBWR reactor, Millstone-1 reactor, Oyster Creek-1 reactor, Palisades-1 reactor, San Onofre-1 reactor, and Rowe Yankee reactor

  20. Systematic evaluation program. Status summary report

    International Nuclear Information System (INIS)

    1982-01-01

    Purpose of the SEP is to review the designs of ten older operating nuclear power plants to document their safety. The SEP topics, design basis event, and progress are discussed in the first section of this document. The topic numbers, reviewing branch, status, remarks, and dates are tabulated in the second section. In the third section, the topic number, title, SAR schedule, and SER schedule are tabulated

  1. Summary of CAMAC: status and outlook

    International Nuclear Information System (INIS)

    Wagner, L.J.

    1976-01-01

    CAMAC (Computer Automated Measurement And Control) is now a well established, mature, standard (IEEE 583) system for data bussing. Mature in the sense that, worldwide, research organizations and industrial process control users are taking advantage of this practical and cost effective, user developed, modular instrumentation system for data handling. But not staid; the CAMAC specification allows mobility with advancing technology (a tribute to the foresight of its originators). With much cooperation between parallel-functioning European and North American laboratory working groups and industrial users, advances have been made with assurance of upward compatibility; i.e., extensions and improvements to the specifications are made without preventing continued use of existing components. This paper is, accordingly, a review of the current status of CAMAC: factors having a high impact on present status and on future trends are discussed, numerous applications over recent years are described, and a projection is made of what to expect in the near future in view of related technological developments

  2. NRC Licensing Status Summary Report for NGNP

    Energy Technology Data Exchange (ETDEWEB)

    Moe, Wayne Leland [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kinsey, James Carl [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-11-01

    The Next Generation Nuclear Plant (NGNP) Project, initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy (DOE) pursuant to provisions of the Energy Policy Act of 2005, is based on research and development activities supported by the Department of Energy Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. The NGNP will be licensed for construction and operation by the Nuclear Regulatory Commission (NRC). However, not all elements of current regulations (and their related implementation guidance) can be applied to HTGR technology at this time. Certain policies established during past LWR licensing actions must be realigned to properly accommodate advanced HTGR technology. A strategy for licensing HTGR technology was developed and executed through the cooperative effort of DOE and the NRC through the NGNP Project. The purpose of this report is to provide a snapshot of the current status of the still evolving pre-license application regulatory framework relative to commercial HTGR technology deployment in the U.S. The following discussion focuses on (1) describing what has been accomplished by the NGNP Project up to the time of this report, and (2) providing observations and recommendations concerning actions that remain to be accomplished to enable the safe and timely licensing of a commercial HTGR facility in the U.S.

  3. Activities of OECD NEA CSNI PWG3

    International Nuclear Information System (INIS)

    Miller, A.

    1998-01-01

    Activities of OECD NEA are connected with IAEA-IWG LMNPP, IAEA Nuclear safety, CEC-JRC, CEC-DG XI, CEC-DG XII and utilities UNIPEDE and WANO. The Committee on the Safety of Nuclear Installations (CSNI) acts through working groups on Fuel Cycle safety; Operating Experiences and Human Factors; Coolant System Behaviour; Integrity of Components and Structures; Confinement of Accidental Radioactive Releases and Risk Assessment. Korea, Mexico, Hungary and Czech Republic are now members of OECD NEA, and the non OECD Countries like Russia, Ukraine, Slovakia, Lithuania can participate in workshops but not in regular committee meetings

  4. CSNI specialist meeting on simulators and plant analyzers

    International Nuclear Information System (INIS)

    Miettinen, J.; Holmstroem, H.

    1994-01-01

    The Specialist Meeting on Simulators and Plant Analyzers, held in June 9-12, 1992, in Lappeenranta, Finland, was sponsored by the Committee on the Safety on Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organized in collaboration with the Technical Research Centre of Finland (VTT) and the Lappeenranta Technical University of Technology (LTKK). All the presented papers were invited and devided into four sessions. In the first session the objectives, requirements and consepts of simulators were discussed against present standards and guidelines. The second session focused on the capabilities of current analytical models. The third session focused on the experiences gained so far from the applications. The final fourth session concentrated on simulators, which are currently under development, and future plans with regard to both development and utilization. At the end of the meeting topics of the meeting were discussed at the panel discussion. Summaries of the sessions and shortened version of the panel discussion are included into the proceeding. (orig.)

  5. Falsire: CSNI project for fracture analyses of large-scale international reference experiments (Phase 1). Comparison report

    International Nuclear Information System (INIS)

    1994-01-01

    A summary of the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE) is presented. Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the OECD/NEA Committee on the Safety of Nuclear Installations (CSNI), formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear vessel components. The aim of the Project FALSIRE was to assess various fracture methodologies through interpretive analyses of selected large-scale fracture experiments. The six experiments used in Project FALSIRE (performed in the Federal Republic of Germany, Japan, the United Kingdom, and the U.S.A.) were designed to examine various aspects of crack growth in reactor pressure vessel (RPV) steels under pressurized-thermal-shock (PTS) loading conditions. The analysis techniques employed by the participants included engineering and finite-element methods, which were combined with Jr fracture methodology and the French local approach. For each experiment, analysis results provided estimates of variables such as crack growth, crack-mouth-opening displacement, temperature, stress, strain, and applied J and K values. A comparative assessment and discussion of the analysis results are presented; also, the current status of the entire results data base is summarized. Some conclusions concerning predictive capabilities of selected ductile fracture methodologies, as applied to RPVs subjected to PTS loading, are given, and recommendations for future development of fracture methodologies are made

  6. In-vessel core degradation in LWR severe accidents: a state of the art report to CSNI january 1991

    International Nuclear Information System (INIS)

    1991-11-01

    This state of the art report on in-vessel core degradation has been produced at the request of CSNI Principal Working Group 2. The objective of the report is to present to CSNI member countries the status of research and related information on in-vessel degraded core behaviour in both Pressurised Water Reactors (PWR) and Boiling Water Reactors (BWR). Information on experiments, codes and comparisons of calculations with experiments up to january 1991 is summarised and reviewed. Integrated codes, which are wider in scope than just in-vessel degradation are covered as well as specialist, degraded core codes. Implications for PWR and BWR plant calculations are considered. Conclusions and recommendations for research, plant calculations and further CSNI activity in this area are the subject of the final chapter. A major conclusion of the report is that early phase core degradation is relatively well understood. However, codes need further development to bring them up to date with the experimental database, particularly to include low temperature liquefaction processes. These processes significantly affect early phase core degradation and their neglect could affect assessments of accident management actions (including recriticality in BWR severe accidents)

  7. The CSNI program: current priorities and future outlook

    International Nuclear Information System (INIS)

    Dircks, W.J.

    1986-01-01

    This paper gives a brief and general account of activities within the working groups of the CSNI. The five Principal Working groups cover the following areas: operating experience and human factors; reactor transients and primary circuit breaks; primary circuit integrity; reactor accident source term, and environmental consequences; and, risk assessment

  8. CSNI international standard problem procedures - CSNI Report No. 17 - Revision 4

    International Nuclear Information System (INIS)

    Micaelli, J.C.

    2004-01-01

    Assessing the safety of a nuclear installation requires the use of a number of highly specialised tools: computer codes, experimental facilities and their instrumentation, special measurement techniques, methods for testing materials and components and so on. These tools may vary to some extent in different countries and many of them are extremely complex and costly to produce and use. A highly effective way of increasing confidence in the validity and accuracy of such tools is provided by International Standard Problem (ISP) Exercises in which they are gauged against one another and/or against an agreed standard. For example, predictions of different computer codes for a given physical problem may be compared with each other and with the results of a carefully controlled experimental study which also could be a real plant transient. This kind of comparative exercise is clearly suitable for an international venture. CSNI is of the opinion that ISP exercises are useful and should be continued. ISPs are performed as 'open' or as 'blind' problems. In an open problem results of an experiment are available to participants before it is evaluated. In a blind problem results of the experiment are not made known to the participants until after delivery of the calculated results. Depending on the kind of experiment and its objectives, certain boundary and initial conditions of the experiment are communicated to the participants before they start the exercise. This is necessary where it is difficult to guarantee the reproducibility of experiments. For all ISPs the participants are provided with a complete description of the experimental facility. The Lead Country (proposing the ISP) must decide whether the data can be withheld temporarily (blind ISP) or whether the data will be published before the analysis of participating countries is completed (open ISP). It is recommended that ISPs be conducted blind, where possible. ISPs require a considerable expenditure of resources

  9. An analysis of CSNI standard problem, No. 8

    International Nuclear Information System (INIS)

    Sasaki, Shinobu; Araya, Fumimasa

    1980-03-01

    The CSNI International Standard Problem (ISP8), based on the Semiscale S-06-3 Test, was analyzed in the course of verification work of the computer code ALARM-P1. In this report, described was the result of the initial trial, which had been submitted to the CSNI. Due to the limitations of ALARM-P1 capability, only the blowdown portion of the transient was calculated. Though the hydraulic behavior before ECCS injection agreed with the test data, the ALARM-P1 could not continue calculation after 26 seconds due to severe predicted instability following the ECCS injection. The prediction of surface temperature of the heater rods was also unsatisfactory. Several problems to be improved have been identified both in the analytical model and the input data. (author)

  10. Contribution from twenty two years of CSNI International Standard Problems

    International Nuclear Information System (INIS)

    1998-03-01

    This report provides a brief overview on the contribution of some CSNI International Standard Problems (ISPs) to nuclear reactor safety issues (41 ISPs performed over the last 22 years). This CSNI activity on ISPs has been one of the major activities of the Principal Working Group no.2 on Coolant System Behaviour. Its domain extended from thermal-hydraulics to several other accident domains following the main concerns of nuclear reactor safety, e.g., LOCA predictions fuel behaviour, operator procedures, containment thermal-hydraulics severe accidents, VVERs, etc. ISPs are providing unique material and benefits for some safety related issues. Clearly, all the technical findings and benefits provided by ISPs are still needed and contribute to advancement of nuclear safety. The report provides some overview on the general objectives of ISPs, content and types of ISPs, and technical domains covered by ISPs, followed by a synthesis of technical findings and benefits to the scientific community

  11. CSNI International standard problems (ISP). Brief descriptions (1975-1999)

    International Nuclear Information System (INIS)

    2000-03-01

    Over the last twenty-five years the NEA Committee on the Safety of Nuclear Installations (CSNI) has sponsored a considerable number of international activities to promote the exchange of experience between its Member countries in the use of nuclear safety codes and testing materials. A primary goal of these activities is to increase confidence in the validity and accuracy of analytical tools or testing procedures which are needed in warranting the safety of nuclear installations, and to demonstrate the competence of involved institutions. International Standard Problems (ISPs) exercises are comparative exercises in which predictions or recalculations of a given physical problem with different best-estimate computer code are compared with each other and above all with the results of a carefully specified experimental study. ISP exercises are performed as 'open' or 'blind' problems. In an open Standard Problem exercise the results of the experiment are available to the participants before performing the calculations, while in a blind Standard Problem exercise the experimental results are locked until the calculation results are made available for comparison. The CSNI-promoted ISP activity started in the early 70's and is still underway. Parallel to other national and international programs the CSNI has sponsored over more than 25 years forty-seven International Standard Problem exercises. This program has been focused mainly on the applicability of large thermal-hydraulic code systems simulating the behaviour of nuclear coolant and containment systems, fuel behaviour under accident conditions, hydrogen distribution, core-concrete interactions and fission product release and transport. One ISP exercise was organised in connection with a seismic ultimate dynamic response test. ISP exercises have proven to be very valuable to participating countries. They have been fruitful to identify code application problems and to amplify the contacts between the experimental and

  12. IFT Scientific Status Summary 2008: Innovative Food Packaging Solutions

    Science.gov (United States)

    Food and beverage packaging comprises 55-65% of the $110 billion value of packaging in the United States. This review provides a summary of innovative technology developments in food packaging. The expanded role of food and beverage packaging is reviewed. Active and intelligent food packaging, ba...

  13. CSNI activities in knowledge management and knowledge transfer - An international dimension

    International Nuclear Information System (INIS)

    Reig, J.; Hrehor, M.

    2004-01-01

    The Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA) was set up in 1973 to develop and to co-ordinate the activities of the NEA concerning the technical aspects of the design, construction and operation of nuclear installations insofar as they affect the safety of such installations. Although there is currently no formal 'CSNI knowledge management strategy', i.e. defined CSNI approach and the appropriate resources for activities related to knowledge management as such, the CSNI has been actively involved during its 30 years of existence in a number of areas closely linked with knowledge management. The paper gives a number of specific examples of various CSNI activities which, all together, represent from an international perspective a significant contribution to knowledge management efforts at the national level of the OECD/NEA member countries. (author)

  14. Buff book 1: status summary report, water reactor safety research

    International Nuclear Information System (INIS)

    1980-01-01

    This Management Report, to provide information for monitoring and controlling the progress of LWR Safety Research Projects Associated with the Office of Nuclear Regulatory Research and other agencies and organizations engaged in nuclear safety research. It utilizes data pertaining to project schedules, cost, and status which have been integrated into a network-based management information system, The purpose of this publication is to provide a vehicle for review of the current status and overall progress of the safety Research Program from a managerial point of view

  15. Workshop summary of 'nuclear knowledge management: Present status and perspective'

    International Nuclear Information System (INIS)

    Yonezawa, Minoru

    2007-03-01

    The workshop on 'Nuclear Knowledge Management (NKM): Present Status and Perspective' was held at the Tokyo Institute of Technology (supported by the Japan Atomic Energy Agency), Tokyo, Japan on the 14th and 15th of December 2006. The purpose of the workshop is to introduce NKM activities inside and outside Japan so that concerned parties/professionals could share related information and enhance awareness of the issues on NKM. Participants from various sectors, such as authorities, industry, universities/research institutes, etc, made presentations. Issues on NKM are recognized and discussed. The workshop consisted of 18 oral lectures and a panel discussion. The 55 participants attended the workshop. Under permission of the Tokyo Institute of Technology which is the sponsor of the workshop, this report compiles these lecture's presentation materials which got permission of a lecturer and synopses which were submitted after the workshop. (author)

  16. ISP 33. OECD/NEA/CSNI International Standard Problem n. 33. Pactel natural circulation stepwise coolant inventory reduction experiment. Comparison report. Volume 1 + 2

    International Nuclear Information System (INIS)

    Purhonen, H.; Kouhia, J.; Holmstrom, H.

    1994-12-01

    This is the comparison report of the CSNI ISP n.33, which is based on a natural circulation experiment with various coolant inventories conducted in Pactel facility (Finland), a 1/305 volumetrically scaled, full-height simulator of a Russian type VVER-440 pressurized water reactor. It presents all submitted blind calculational results from different countries, using various codes (Athlet, Cathare2, etc.) and compares them with the experimental data. The Pactel facility and the ISP 33 experiment are described, and the summaries of the participants, the computer codes and the nodalizations used for the blind calculations are presented

  17. Load monitoring program: Status and results report. Volume 1: Summary

    International Nuclear Information System (INIS)

    1994-06-01

    British Columbia Hydro conducts a monitoring program to provide information on customer needs and values for planning; to measure customer response, energy savings impacts, and load shape impacts due to changes in rate level, rate restructuring, and Power Smart programs; to estimate end-use consumption and load shapes by customer class; and to provide load information for distribution and system load studies. To achieve these objectives, the monitoring program tracks the characteristics and energy use patterns of a sample of BC Hydro residential, commercial, and industrial customers over a period of several years. The entire sample will be surveyed periodically to obtain information on changes in building characteristics, equipment stocks, and energy-use behavior and attitudes. A report is provided on the status of monitoring program activities and some results obtained in 1993/94. For the residential sector, the results include typical load profiles, end-user demographics, and extent of electric space heating and water heating. In the commercial sector, customers were divided into two main groups. The large-building group was relatively well organized in terms of energy needs and participated in Power Smart programs. The small-building group was relatively energy-inefficient and relatively unaware of Power Smart programs. 43 figs., 15 tabs

  18. Dynamic Visualization of SNS Diagnostics Summary Report and System Status

    CERN Document Server

    Blokland, Willem; Long, Cary D; Murphy, Darryl J; Purcell, John D; Sundaram, Madhan

    2005-01-01

    The Spallation Neutron Source (SNS) accelerator systems will deliver a 1.0 GeV, 1.4 MW proton beam to a liquid mercury target for neutron scattering research. The accelerator complex consists of a 1 GeV linear accelerator, an accumulator ring and associated transport lines. The SNS diagnostics platform is PC-based running Embedded Windows XP and LabVIEW. The diagnostics instruments communicate with the control system using the Channel Access (CA) protocol of the Experimental Physics and Industrial Control System (EPICS). This paper describes the Diagnostics Group's approach to collecting data from the instruments, processing it, and presenting live in a summarized way over the web. Effectively, adding a supervisory level to the diagnostics instruments. One application of this data mining is the "Diagnostics Status Page" that summarizes the insert-able devices, transport efficiencies, and the mode of the accelerator in a compact webpage. The displays on the webpage change automatically to show the latest and/o...

  19. Proceedings of the third CSNI workshop on iodine chemistry in reactor safety

    International Nuclear Information System (INIS)

    Ishigure, Kenkichi; Saeki, Masakatsu; Soda, Kunihisa; Sugimoto, Jun

    1992-03-01

    This issue is the collection of the papers presented at the CSNI (Committee on the Safety of Nuclear Installations) workshop on iodine chemistry in reactor safety. The 31 of the presented papers are indexed individually. (J.P.N.)

  20. Proceedings of the OECD/CSNI specialists meeting on fuel-coolant interactions

    Energy Technology Data Exchange (ETDEWEB)

    Akiyama, Mamoru; Yamano, Norihiro; Sugimoto, Jun [eds.

    1998-01-01

    The OECD/CSNI Specialists Meeting on Fuel Coolant Interactions (FCI) was held at Tokai-mura in Japan on May 19 through 21, 1997, and attended by 80 participants from 14 countries and one international organizations. In the meeting 36 papers were presented followed by active discussions in six sessions on various aspects of FCI issues, such as reactor application, premixing, propagation/trigger, experiments and code/models. At the end of the Meeting, the participants have reached to the consensus on the summary and recommendations, which consists of the following items; (1) We find no new evidence that would change or violate the conclusion of SERG-2 (1996) that alpha-mode failure is not risk significant. (2) Significant progress has been made since the Santa Barbara meeting (1993). (3) Several areas have been identified, which need further investigations to understand the basic FCI phenomena, and to improve the modeling. (4) We recommend maximizing open communication between various research groups in order to accelerate the resolution of the remaining issues. (5) We recommend that the next specialist meeting be held within 3 to 5 years in order to synthesize the activities described above. (J.P.N.)

  1. Re-analysis of CSNI standard problem, 8

    International Nuclear Information System (INIS)

    Sasaki, Shinobu; Araya, Fumimasa

    1981-12-01

    This report presents the results of computer runs which carried out with the use of ALARM-Pl code. The object of analyses is the Semiscale S-06-3 experiment accepted as the CSNI International Standard Problem 8. According to the preliminary results reported before, the agreement between ALARM-Pl and this experiment was very poor for the key parameters such as the break flow or fuel cladding surface temperature. Hence, much effort has been made to improve the disagreement. Through the re-examination of both the code and input-data, the agreement between the calculated and measured results for key parameters has been much better than that gained in the foregoing test run. (author)

  2. Overview of CSNI separate effects tests validation matrix

    Energy Technology Data Exchange (ETDEWEB)

    Aksan, N. [Paul Scherrer Institute, Villigen (Switzerland); Auria, F.D. [Univ. of Pisa (Italy); Glaeser, H. [Gesellschaft fuer anlagen und Reaktorsicherheit, (GRS), Garching (Germany)] [and others

    1995-09-01

    An internationally agreed separate effects test (SET) Validation Matrix for thermal-hydraulic system codes has been established by a sub-group of the Task Group on Thermal Hydraulic System Behaviour as requested by the OECD/NEA Committee on Safety of Nuclear Installations (SCNI) Principal Working Group No. 2 on Coolant System Behaviour. The construction of such a Matrix is an attempt to collect together in a systematic way the best sets of openly available test data for code validation, assessment and improvement and also for quantitative code assessment with respect to quantification of uncertainties to the modeling of individual phenomena by the codes. The methodology, that has been developed during the process of establishing CSNI-SET validation matrix, was an important outcome of the work on SET matrix. In addition, all the choices which have been made from the 187 identified facilities covering the 67 phenomena will be investigated together with some discussions on the data base.

  3. FALSIRE. CSNI project for fracture analyses of large-scale international reference experiments. Phase 1

    International Nuclear Information System (INIS)

    Sievers, J.; Schulz, H.; Bass, B.R.; Pugh, C.E.; Keeney, J.

    1994-04-01

    The six experiments used in Project FALSIRE (performed in the Federal Republic of Germany, Japan, the United Kingdom, and the U.S.A.) were designed to examine various aspects of crack growth in reactor pressure vessel (RPV) steels under pressurized-thermal-shock (PTS) loading conditions. The CSNI/FAG established a common format for comprehensive statements of these experiments, including supporting information and available analysis results. For each experiment, analysis results provided estimates of variables such as crack growth, crack-mouth-opening displacement, temperature, stress, strain, and applied J and K values. A comparative assessment and discussion of the analysis results are presented; also, the current status of the entire results data base is summarized. Generally, these results highlight the importance of adequately modeling structural behavior of specimens before performing fracture mechanics evaluations. Applications of the various fracture methodologies were found to be partially successful in some cases but not in others. Based on these assessments, some conclusions concerning predictive capabilities of selected ductile fracture methodologies, as applied to RPVs subjected to PTS loading are given. (orig.)

  4. Report of a CSNI workshop on uncertainty analysis methods. Volume 1 + 2

    International Nuclear Information System (INIS)

    Wickett, A.J.; Yadigaroglu, G.

    1994-08-01

    The OECD NEA CSNI Principal Working Group 2 (PWG2) Task Group on Thermal Hydraulic System Behaviour (TGTHSB) has, in recent years, received presentations of a variety of different methods to analyze the uncertainty in the calculations of advanced unbiased (best estimate) codes. Proposals were also made for an International Standard Problem (ISP) to compare the uncertainty analysis methods. The objectives for the Workshop were to discuss and fully understand the principles of uncertainty analysis relevant to LOCA modelling and like problems, to examine the underlying issues from first principles, in preference to comparing and contrasting the currently proposed methods, to reach consensus on the issues identified as far as possible while not avoiding the controversial aspects, to identify as clearly as possible unreconciled differences, and to issue a Status Report. Eight uncertainty analysis methods were presented. A structured discussion of various aspects of uncertainty analysis followed - the need for uncertainty analysis, identification and ranking of uncertainties, characterisation, quantification and combination of uncertainties and applications, resources and future developments. As a result, the objectives set out above were, to a very large extent, achieved. Plans for the ISP were also discussed. Volume 1 contains a record of the discussions on uncertainty methods. Volume 2 is a compilation of descriptions of the eight uncertainty analysis methods presented at the workshop

  5. Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions

    International Nuclear Information System (INIS)

    1992-01-01

    The Second CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions was held at Kernforschungszentrum Karlsruhe, Germany on April 1-3, 1992. The status and progress in this field of severe reactor accidents were discussed from researchers around the world including participants from Russia and the Czech and Slovak Federal Republic. The contributions concentrated on two main topics. The first topic is the 'classical' core debris-concrete interaction, both experimental and theoretical. Integral effects and separate effects were addressed in thermal hydraulics and heat transfer, material interaction, and aerosol release during concrete erosion, with some applications to prototypical nuclear power plants. The second topic gaining more and more interest is the possibility of controlling and ending the erosion of the concrete by spreading of the core melt, and/or achieving coolability by the addition of water. In the final session it was concluded that considerable progress has been made in understanding and modelling the important phenomena. For the first topic a broad and generally sufficient experimental data base is existing, allowing further improvement qualification of the theoretical models which at present give reasonable agreement with the most important experimental data. A validation matrix is recommended for final validation of the codes. With respect to fission product release during MCCI measurements show that the releases are significantly less than previously estimated. The relatively new topic of melt coolability deserves further investigations which are already underway at different places or international coordinated efforts

  6. Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    The Second CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions was held at Kernforschungszentrum Karlsruhe, Germany on April 1-3, 1992. The status and progress in this field of severe reactor accidents were discussed from researchers around the world including participants from Russia and the Czech and Slovak Federal Republic. The contributions concentrated on two main topics. The first topic is the 'classical' core debris-concrete interaction, both experimental and theoretical. Integral effects and separate effects were addressed in thermal hydraulics and heat transfer, material interaction, and aerosol release during concrete erosion, with some applications to prototypical nuclear power plants. The second topic gaining more and more interest is the possibility of controlling and ending the erosion of the concrete by spreading of the core melt, and/or achieving coolability by the addition of water. In the final session it was concluded that considerable progress has been made in understanding and modelling the important phenomena. For the first topic a broad and generally sufficient experimental data base is existing, allowing further improvement qualification of the theoretical models which at present give reasonable agreement with the most important experimental data. A validation matrix is recommended for final validation of the codes. With respect to fission product release during MCCI measurements show that the releases are significantly less than previously estimated. The relatively new topic of melt coolability deserves further investigations which are already underway at different places or international coordinated efforts.

  7. Proceedings of the first OECD (NEA) CSNI-Specialist Meeting on Instrumentation to Manage Severe Accidents

    International Nuclear Information System (INIS)

    Sonnenkalb, Martin

    1992-07-01

    OECD member countries have adopted various accident management measures and procedures. To initiate these measures and control their effectiveness, information on the status of the plant and on accident symptoms is necessary. This information includes physical data (pressure, temperatures, hydrogen concentrations, etc.) but also data on the condition of components such as pumps, valves, power supplies, etc. In response to proposals made by the CSNI - PWG 4 Task Group on Containment Aspects of Severe Accident Management (CAM) and endorsed by PWG 4, CSNI has decided to sponsor a Specialist Meeting on Instrumentation to Manage Severe Accidents. The knowledge-basis for the Specialist Meeting was the paper on 'Instrumentation for Accident Management in Containment'. This technical document (NEA/CSNI/R(92)4) was prepared by the CSNI - Principle Working Group Number 4 of experts on January 1992. The Specialist Meeting was structured in the following sessions: I. Information Needs for Managing Severe Accidents, II. Capabilities and Limitations of Existing Instrumentation, III. Unconventional Use and Further Development of Instrumentation, IV. Operational Aids and Artificial Intelligence. The Specialist Meeting concentrated on existing instrumentation and its possible use under severe accident conditions; it also examined developments underway and planed. Desirable new instrumentation was discussed briefly. The interactions and discussions during the sessions were helpful to bring different perspectives to bear, thus sharpening the thinking of all. Questions were raised concerning the long-term viability of current (or added) instrumentation. It must be realized that the subject of instrumentation to manage severe accidents is very new, and that no international meeting on this topic was held previously. One of the objectives was to bring this important issue to the attention of both safety authorities and experts. It could be seen from several of the presentations and from

  8. CSNI International Standard Problems (ISP). Brief descriptions (1975-1994)

    International Nuclear Information System (INIS)

    1994-07-01

    Between 1975 and 1994 the NEA Committee on the Safety of Nuclear Installations (CSNI) has sponsored some forty International Standard Problems (ISPs) in the fields of in-vessel thermal-hydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermal-hydraulics. ISPs are comparative exercises in which predictions of different computer codes for a given physical problem are compared with each other or with the results of a carefully controlled experimental study. The main goal of ISP exercises is to increase confidence in the validity and accuracy of tools which are used in assessing the safety of nuclear installations. Moreover, they enable code users to gain experience and demonstrate their competence. ISPs are performed as 'open' or 'blind' problems. In an open Standard Problem the results of the experiment are available to the participants before performing the calculations, while in a blind Standard Problem the results are locked until the calculational results are made available for comparison. Experiments selected to support ISP exercises are exceptionally well documented; they provide the framework for several code validation matrices. This report briefly describes 36 ISPs and 3 containment analysis standard problems (CASP)

  9. Further evaluation of the CSNI separate effect test activity

    Energy Technology Data Exchange (ETDEWEB)

    D`Auria, F.; Aksan, S.N.; Glaeser, H. [and others

    1995-09-01

    An internationally agreed Separate Effect Test (SET) Validation Matrix for the thermalhydraulic system codes has been established by a subgroup of the Task Group on Thermalhydraulic System Behaviour as requested by OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) Principal Working Group No. 2 on Coolant System Behavior. The construction of such matrix constituted an attempt to collect together in a systematic way the best sets of openly available test data to select for code validation. As a final result, 67 phenomena have been identified and characterized, roughly 200 facilities have been considered and more than 1000 experiments have been selected as useful for the validation of the codes. The objective of the present paper is to provide additional evaluation of the obtained data base and to supply an a-posteriori judgement in relation to (a) the data base adequacy, (b) the phenomenon, and (c) the need for additional experiments. This has been provided independently by each of the authors. The main conclusions are that large amount of data are available for certain popular phenomena e.g. heat transfer, but data are severely lacking in more esoteric areas e.g. for characterizing phenomena such as parallel channel instability and boron mixing and transport.

  10. CSNI International standard problems (ISP): brief descriptions (1975-1997)

    International Nuclear Information System (INIS)

    1997-07-01

    Over the last twenty years (1975-1999) the NEA Committee on the Safety of Nuclear Installations (CSNI) has sponsored more than forty International Standard Problems (ISPs) in the fields of in-vessel thermal-hydraulic behaviour, fuel behaviour under accident conditions, fission product release and transport, core/concrete interactions, hydrogen distribution and mixing, containment thermal-hydraulic, and iodine behaviour in the containment. ISPs are comparative exercises in which predictions of different computer codes for a given physical problem are compared with each other or with the results of a carefully controlled experimental study. The main goal of ISP exercises is to increase confidence in the validity and accuracy of analytical tools or testing procedures which are needed in warranting the safety of nuclear installations, and to demonstrate the competence of involved institutions. ISP exercises are performed as 'open' or 'blind' problems. The main characteristics of 41 ISPs completed between 1975 and 1999, and 3 containment analysis standard problems (CASPs) are briefly presented

  11. Summary

    International Nuclear Information System (INIS)

    2004-01-01

    The fourth workshop of the OECD/NEA Forum on Stakeholder Confidence (FSC) was hosted by ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste Management and enriched fissile materials. The central theme of the workshop was ''Dealing with interests, values and knowledge in managing risk''within the Belgian context of local partnerships for the long term management of low-level, short-lived radioactive waste. The four-day workshop started with a half-day session in Brussels giving a general introduction on the Belgian context and the local partnership methodology. This was followed by community visits to three local partnerships, PaLoFF in Fleurus-Farciennes, MONA in Mol, and STOLA in Dessel. After the visits, the workshop continued with two full-day sessions in Brussels. One hundred and nineteen registered participants, representing 13 countries, attended the workshop or participated in the community visits. About two thirds were Belgian stakeholders; the remainder came from FSC member organisations. The participants included representatives of municipal governments, civil society organisations, government agencies, industrial companies, the media, and international organisations as well as private citizens, consultants and academics. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop and the community visits. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Executive Summary and also provided with this document, is a NEA Secretariat's reflection aiming to place the main lessons of the workshop into an international perspective. (author)

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

    International Nuclear Information System (INIS)

    1982-06-01

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

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

    International Nuclear Information System (INIS)

    1989-03-01

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

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

    International Nuclear Information System (INIS)

    Schwartz, I.

    1989-03-01

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

  15. Subseabed disposal program annual report, January-December 1979. Volume I. Summary and status

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1981-08-01

    This is the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program, which was begun in June 1973. The program was initiated by Sandia National Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world's oceans as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans. Summaries are presented in the following areas: systems analysis; barrier system characterization and assessment; environmental studies; emplacement; sampling and instrumentation development; and transportation studies

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

    International Nuclear Information System (INIS)

    1982-09-01

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

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

    International Nuclear Information System (INIS)

    1987-03-01

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

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

    International Nuclear Information System (INIS)

    1989-02-01

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

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

    International Nuclear Information System (INIS)

    1983-05-01

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

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

    International Nuclear Information System (INIS)

    1982-11-01

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

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

    International Nuclear Information System (INIS)

    1983-06-01

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

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

    International Nuclear Information System (INIS)

    1989-01-01

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

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

    International Nuclear Information System (INIS)

    1987-03-01

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

  4. Presentation on CSNI Activities and Introduction to the Seminar

    International Nuclear Information System (INIS)

    Amri, A.

    2008-01-01

    The standing committees of the OECD Nuclear Energy Agency (Nea) which consist of delegates from its Member countries, determine the Agency's programme of work. This paper explains how the Committee on the Safety of Nuclear Installations (CSNI) and its groups of experts function. Programmes of work are carried out in the areas of operating experience and human factors, thermal-hydraulics and coolant system behaviour, reactor component integrity and ageing, confinement of accidental radioactive releases, severe accident management, risk assessment, nuclear fuel safety, nuclear fuel cycle safety, and safety margins. Some of these activities are open to countries who are not Members of the OECD. Selected programmes of work are described briefly. The objectives and the methods of work of the OECD and the Nea are outlined in the first part of the paper. Nea's nuclear reactor safety programme is a varied and evolving patch-work of studies, tasks and projects, interspersed with specialist meetings and workshops. It provides a efficient forum for delegates and experts of Member countries to discuss issues of mutual concern and to arrive at consensus views and conclusions. Because of the nature of its membership, its flexibility, and its methods of working, Nea is in a unique position to provide the international community, quickly and efficiently, with advanced views and complete up-to-date information on a broad range of nuclear safety and regulation issues. Nea's programme is performed in close collaboration with other international organisations, in particular the International Atomic Energy Agency and the Commission of the European Communities.

  5. CSNI collective statement on support facilities for existing and advanced reactors. The function of OECD/Nea joint projects Nea committee on the safety of nuclear installations (CSNI)

    International Nuclear Information System (INIS)

    2008-01-01

    The NEA Committee on the Safety of Nuclear Installations (CSNI) has recently completed a study on the availability and utilisation of facilities supporting safety studies for current and advanced nuclear power reactors. The study showed that significant steps had been undertaken in the past several years in support of safety test facilities, mainly by conducting multinational joint projects centered on the capability of unique test facilities worldwide. Given the positive experience of the safety research projects, it has been recommended that efforts be made to prioritize technical issues associated with advanced (Generation IV) reactor designs and to develop options on how to efficiently obtain the necessary data through internationally co-ordinated research, preparing a gradual extension of safety research beyond the needs set by currently operating reactors. This statement constitutes a reference for future CSNI activities and for safety authorities, R and D centres and industry for internationally co-ordinated research initiatives in the nuclear safety research area. (author)

  6. CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE)

    International Nuclear Information System (INIS)

    Bass, B.R.; Pugh, C.E.; Keeney-Walker, J.; Schulz, H.; Sievers, J.

    1993-06-01

    This report summarizes the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE). Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the Organization for Economic Cooperation and Development (OECD)/Nuclear Energy Agency's (NEA's) Committee on the Safety of Nuclear Installations (CSNI). Motivation for the project was derived from recognition by the CSNI-PWG/3 that inconsistencies were being revealed in predictive capabilities of a variety of fracture assessment methods, especially in ductile fracture applications. As a consequence, the CSNI/FAG was formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear components. Members are from laboratories and research organizations in Western Europe, Japan, and the United States of America (USA). On behalf of the CSNI/FAG, the US Nuclear Regulatory Commission's (NRC's) Heavy-Section Steel Technology (HSST) Program at the Oak Ridge National Laboratory (ORNL) and the Gesellschaft fuer Anlagen--und Reaktorsicherheit (GRS), Koeln, Federal Republic of Germany (FRG) had responsibility for organization arrangements related to Project FALSIRE. The group is chaired by H. Schulz from GRS, Koeln, FRG

  7. CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (Project FALSIRE)

    Energy Technology Data Exchange (ETDEWEB)

    Bass, B.R.; Pugh, C.E.; Keeney-Walker, J. [Oak Ridge National Lab., TN (United States); Schulz, H.; Sievers, J. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Gemany)

    1993-06-01

    This report summarizes the recently completed Phase I of the Project for Fracture Analysis of Large-Scale International Reference Experiments (Project FALSIRE). Project FALSIRE was created by the Fracture Assessment Group (FAG) of Principal Working Group No. 3 (PWG/3) of the Organization for Economic Cooperation and Development (OECD)/Nuclear Energy Agency`s (NEA`s) Committee on the Safety of Nuclear Installations (CSNI). Motivation for the project was derived from recognition by the CSNI-PWG/3 that inconsistencies were being revealed in predictive capabilities of a variety of fracture assessment methods, especially in ductile fracture applications. As a consequence, the CSNI/FAG was formed to evaluate fracture prediction capabilities currently used in safety assessments of nuclear components. Members are from laboratories and research organizations in Western Europe, Japan, and the United States of America (USA). On behalf of the CSNI/FAG, the US Nuclear Regulatory Commission`s (NRC`s) Heavy-Section Steel Technology (HSST) Program at the Oak Ridge National Laboratory (ORNL) and the Gesellschaft fuer Anlagen--und Reaktorsicherheit (GRS), Koeln, Federal Republic of Germany (FRG) had responsibility for organization arrangements related to Project FALSIRE. The group is chaired by H. Schulz from GRS, Koeln, FRG.

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

    International Nuclear Information System (INIS)

    1988-07-01

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

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

    International Nuclear Information System (INIS)

    1988-04-01

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

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

    International Nuclear Information System (INIS)

    1982-05-01

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

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

    International Nuclear Information System (INIS)

    1984-04-01

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

  12. Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing

    International Nuclear Information System (INIS)

    1993-10-01

    temperatures. The meeting in Oak Ridge was designed to allow leading specialists to share and review recent large - scale fracture experiments and to discuss them relative to verification of fracture mechanics methods. The objective was to assess the ability of analytical methods that may currently be used to model the fracture behavior of nuclear reactor components and structures. The meeting was organized into six technical sessions: Session I: CSNI Project FALSIRE - Current Results; Session II: Large-Scale Experiments and Applications; Session III: Assessments of Fracture Mechanics Analysis Methods; Session IV: Large-Scale Plate Experiments and Analyses; Session V: Fracture Modeling and Transferability; Session VI: Large-Scale Piping Experiments and Analyses. This report records all the papers presented at this meeting along with two others whose authors could not be present. While the report does not include session dividers, the table of contents shows the grouping of papers by session. The final chapter of this report provides summaries that rapporteurs prepared on the day the papers were presented. The papers are printed in the order of their presentation in each session and describe recent large-scale fracture (brittle and/or ductile) experiments, analyses of these experiments, and comparisons between predictions and experimental results. The goal of the meeting was to allow international experts to examine the fracture behavior of various materials and structures under conditions relevant to nuclear reactor components and operating environments. The emphasis was on the ability of various fracture models and analysis methods to predict the wide range of experimental data now available. The international nature of the meeting is illustrated by the fact that papers were presented by researchers from CSFR, Finland, France, Germany, Japan, Russia, U.S.A., and the U.K. There were experts present from several other countries who participated in discussing the results

  13. Summary Record of the 15th Meeting of the Working Group on Risk Assessment (WGRISK)

    International Nuclear Information System (INIS)

    2015-01-01

    The main mission of the working group on risk assessment (WGRISK) is to advance the understanding and utilisation of probabilistic safety assessment (PSA) in ensuring the continued safety of nuclear installations in member countries. While PSA methodology has matured greatly over the years, further work is required. WGRISK has been active in several of these areas, including: human reliability; software reliability; low power and shutdown risk. In order to maintain a current perspective, the working group collaborates and assists other working groups within the CSNI, such as operating experience and organisational factors as well as keeping close co-ordination with other international organisations. Over the past twenty years, the NEA PWG5 and now WGRISK have looked at the technology and methods used for identifying contributors to risk and assessing their importance. Work during much of this period was concentrated on Level-1 PSA methodology. In recent years the focus has shifted into more specific PSA methodologies and risk-informed applications. This document summarizes the content of the 15. Meeting of WGRISK: - presentation of the new WGRISK Bureau, - Approval of the 14. WGRISK Meeting Summary Record [NEA/SEN/SIN/WGRISK (2013)1], - Use and Development of PSA in NEA Member Countries and by other International Organisations, - Report by the WGRISK Secretariat on the current WGRISK programme of work, actions taken by CSNI and CNRA and other recent developments in OECD/NEA, - Development of BPGs on failure mode taxonomy for reliability assessment of digital I and C systems for PSA [Task 2010-3], - Update Use of OECD Data Project Products in PSA [Task 2011-1], - Status report on the common WGHOF/WGRISK HRA Task, - Outcome on the International Workshop on PSA of Natural External Hazards Including Earthquakes, April 2014 [Task 2012-1], - Status report on the International Workshop on Fire PRA [Task 2012-2], - PSA insights relating to the loss of electrical sources

  14. Regulatory licensing status summary report. Nuclear power plants data for decisions (blue book), July 11-August 16, 1982

    International Nuclear Information System (INIS)

    1982-08-01

    This management report, Regulatory Licensing status summary report, is designed to provide the necessary information for controlling the progress of review processes for central station nuclear reactor applications. Section I of this edition consists of the three summary of accomplishments, the new application forecast for OL's and CP's, and an abbreviation key. Section II represents the main body of the report and consists of the facility information. All OL's are listed first, followed by CP's, standard design reviews, other reviews, and finally, a non-power reactor summary. Each project consists of general facility data, current status for all phases of the review, and targeted and actual completion dates for all key milestones in the review

  15. Regulatory licensing status summary report. Nuclear power plants data for decisions (blue book), April 20-May 15, 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This management report, regulatory licensing status summary report, is designed to provide the necessary information for controlling the progress of review processes for central station nuclear reactor applications. It utilizes data collected from the Office of Nuclear Reactor Regulation, Office of the Executive Legal Director, Office of Inspection and Enforcement, and the National Laboratories, and analyzed by the Office of Resource Management in the implementation of the regulatory information system. Section I of this edition consists of the three summary of accomplishments, the new application forecast for OL's and CP's, and an abbreviation key. Section II represents the main body of the report and consists of the facility information. All OL's are listed first, followed by CP's, standard design reviews, other reviews, and finally, a non-power reactor summary. Each project consists of general facility data, current status for all phases of the review, and targeted and actual completion dates for all key milestones in the review

  16. Regulatory licensing. Status summary report. Nuclear power plants data for decisions (Blue Book), August 17-September 15, 1982

    International Nuclear Information System (INIS)

    1982-09-01

    This management report, regulatory licensing status summary report, is designed to provide the necessary information for controlling the progress of review processes for central station nuclear reactor applications. Section I of this edition consists of the three summary of accomplishments, the new application forecast for OL's and CP's, and an abbreviation key. Section II represents the main body of the report and consists of the facility information. All OL's are listed first, followed by CP's, standard design reviews, other reviews, and finally, a non-power reactor summary. Each project consists of general facility data, current status for all phases of the review, and targeted and actual completion dates for all key milestones in the review

  17. Regulatory licensing status summary report. Nuclear power plants data for decisions (blue book), June 17-July 10, 1982

    International Nuclear Information System (INIS)

    1982-07-01

    This management report, Regulatory Licensing Status Summary Report, is designed to provide the necessary information for controlling the progress of review processes for central station nuclear reactor applications. It utilizes data collected from the Office of Nuclear Reactor Regulation, Office of the Executive Legal Director, Office of Inspection and Enforcement, and the National Laboratories, and analyzed by the Office of Resource Management in the implementation of the Regulatory Information System. Section I of this edition consists of the three summary of accomplishments, the new application forecast for OL's and CP's, and an abbreviation key. Section II represents the main body of the report and consists of the facility information. All OL's are listed first, followed by CP's, standard design reviews, other reviews, and finally, a non-power reactor summary. Each project consists of general facility data, current status for all phases of the review, and targeted and actual completion dates for all key milestones in the review

  18. Fuel safety criteria and review by OECD / CSNI task force

    International Nuclear Information System (INIS)

    Van Doesburg, W.

    1999-01-01

    Full text of publication follows: with the advent of advanced fuel and core designs, and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a general feeling that safety margins have been or are being reduced. Historically, fuel safety margins were defined by adding conservatism to the safety limits, which in turn were also fixed in a conservative manner, here, the expression 'conservatism' expresses the fact that bounding or limiting numbers were chosen for model parameters, plant and fuel design data, and fuel operating history values. Unfortunately, as these conservatisms were not quantified (or quantifiable), the amount of safety available or the reduction thereof is difficult to substantiate. For the regulator, it is important to know the margin available with the utilities' request for approval of new fuel or methods; likewise, for the utility and vendor it is important to know what margins exist and what they are based on, to identify in which direction they can make further progress and optimize fuel and fuel cycle cost. Naturally, each party involved will have to decide on how much margin should be in place, to establish operational criteria and ensure that these can actually be met during operation. To assess the margins issue, safety criteria themselves need to be reviewed first. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel available at that time - mostly at zero exposure. Of course, verification was performed as designs progressed in later years, primarily with the aim to be able to prove that safety criteria were adequate as long as the said conservatisms would be retained, and not with the aim to reestablish limits. The mandate to the OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) is to assess the adequacy of existing fuel safety criteria, in view of the 'new design' elements (new

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

    International Nuclear Information System (INIS)

    1986-05-01

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

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

    International Nuclear Information System (INIS)

    1988-12-01

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

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

    International Nuclear Information System (INIS)

    1988-09-01

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

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

    International Nuclear Information System (INIS)

    1988-10-01

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

  3. 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

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

    International Nuclear Information System (INIS)

    Schwartz, I.

    1988-07-01

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

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

    International Nuclear Information System (INIS)

    1982-04-01

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

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

    International Nuclear Information System (INIS)

    1989-06-01

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

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

    International Nuclear Information System (INIS)

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    1985-12-01

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

  9. OECD/CSNI specialist meeting on nuclear aerosols in reactor safety - Summary and Conclusions

    International Nuclear Information System (INIS)

    Allelein, Hans-Josef; Boulaud, Denis; Guentay, Salih; Dehbi, Abdelouahab; Hontanon, Esther; Jokiniemi, Jorma; Jones, Alan V.; Koroll, Grant W.; Tinkler, Charles G.; Schaperow, J.; Royen, Jacques

    1999-01-01

    The Third OECD Specialist Meeting on Nuclear Aerosols in Reactor Safety was organised in Cologne, Germany, from 15-18 June 1998, in collaboration with the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH. It was attended by sixty-five specialists representing thirteen OECD Member countries and the Commission of the European Communities. Thirty-nine papers were presented, in eight sessions. The meeting was concluded by a general discussion devoted to the following topics: - What has been solved up to the level of plant applications and accident management? - Where is more work needed for plant applications? Over the last eight years significant progress has been made in source term modelling and code development. Results have been consolidated in codes which are being used for plant calculations to address safety issues. For example, two countries used their source term codes last year to assess the impact of heating from deposited fission products on the potential for steam generator tube rupture. Also, another source term code was used to assess the need of sprays for fission product removal in the proposed design of a new type of reactor. Over the next few years, experiments and model development will continue, with more emphasis on application to risk-important severe accident scenarios

  10. OECD/CSNI specialist meeting on advanced instrumentation and measurements techniques: summary and conclusions

    International Nuclear Information System (INIS)

    1997-01-01

    This specialist meeting on Advanced Instrumentation and Measurements Techniques was held in Santa Barbara (USA) in 1997 and attracted some 70 participants in ten technical sessions and a session of the round table discussions, with a total of 41 papers. It was intended to bring together the international experts in multi-phase flow instrumentation, experiment and modeling to review the state-of-the-art of the two-phase flow instrumentation methods and to discuss the relation between modeling needs and instrumentation capabilities. The following topics were included: Modeling needs and future direction for improved constitutive relations, interfacial area transport equation, and multi-dimensional two-fluid model formulation; local instrumentation developments for void fraction, interfacial area, phase velocities, turbulence, entrainment, particle size, thermal non-equilibrium, shear stress, nucleation, condensation and boiling; global instrumentation developments for void fraction, mass flow, two-phase level, non-condensable concentration, flow regimes, low flow and break flow; relation between modeling needs and instrumentation capabilities, future directions for experiments focused on modeling needs and for instrumentation developments

  11. Systematic evaluation program status summary report: November 1-30, 1981

    International Nuclear Information System (INIS)

    1981-12-01

    The Systematic Evaluation Program is intended to examine many safety related aspects of eleven of the older light water reactors. This document provides the existing status of the review process including individual topic and overall completion status

  12. Proceedings of the CSNI specialists meeting on fuel-coolant interactions

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-03-01

    A specialists meeting on fuel-coolant interactions was held in Santa Barbara, CA from January 5-7, 1993. The meeting was sponsored by the United States Nuclear Regulatory Commission in collaboration with the Committee on the Safety of Nuclear Installation (CSNI) of the OECD Nuclear Energy Agency (NEA) and the University of California at Santa Barbara. The objectives of the meeting are to cross-fertilize on-going work, provide opportunities for mutual check points, seek to focus the technical issues on matters of practical significance and re-evaluate both the objectives as well as path of future research. Individual papers have been cataloged separately.

  13. Proceedings of the CSNI specialists meeting on fuel-coolant interactions

    International Nuclear Information System (INIS)

    1994-03-01

    A specialists meeting on fuel-coolant interactions was held in Santa Barbara, CA from January 5--7, 1993. The meeting was sponsored by the United States Nuclear Regulatory Commission in collaboration with the Committee on the Safety of Nuclear Installation (CSNI) of the OECD Nuclear Energy Agency (NEA) and the University of California at Santa Barbara. The objectives of the meeting are to cross-fertilize on-going work, provide opportunities for mutual check points, seek to focus the technical issues on matters of practical significance and re-evaluate both the objectives as well as path of future research. Individual papers have been cataloged separately

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

    International Nuclear Information System (INIS)

    1996-06-01

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

  15. Is subjective social status a summary of life-course socioeconomic position?

    Science.gov (United States)

    Ferreira, Wasney de Almeida; Camelo, Lidyane; Viana, Maria Carmen; Giatti, Luana; Barreto, Sandhi Maria

    2018-01-01

    Very little is known about the association between objective indicators of socioeconomic position in childhood and adolescence and low subjective social status in adult life, after adjusting for adult socioeconomic position. We used baseline data (2008-2010) from the Brazilian Longitudinal Study of Adult Health (ELSA-Brasil), a multicenter cohort study of 15,105 civil servants from six Brazilian states. Subjective social status was measured using the The MacArthur Scale of Subjective Social Status, which represents social hierarchy in the form of a 10-rung ladder with the top rung representing the highest subjective social status. Participants who chose the bottom four rungs in the ladder were assigned to the low subjective social status category. The following socioeconomic position indicators were investigated: childhood (maternal education), adolescence (occupational social class of the household head; participant's occupational social class of first job; nature of occupation of household head; participant's nature of occupation of first job), and adulthood (participant's occupational social class, nature of occupation and education). The associations between low subjective social status and socioeconomic position were determined using multiple logistic regression, after adjusting for sociodemographic factors and socioeconomic position indicators from other stages of life. After adjustments, low socioeconomic position in childhood, adolescence and adulthood remained significantly associated with low subjective social status in adulthood with dose-response gradients. The magnitude of these associations was stronger for intra-individual than for intergenerational socioeconomic positions. Results suggest that subjective social status in adulthood is the result of a complex developmental process of acquiring socioeconomic self-perception, which is intrinsic to subjective social status and includes current and past, individual and family household experiences.

  16. The National Criticality Experiments Research Center at the Device Assembly Facility, Nevada National Security Site: Status and Capabilities, Summary Report

    International Nuclear Information System (INIS)

    Bragg-Sitton, S.; Bess, J.; Werner, J.

    2011-01-01

    The National Criticality Experiments Research Center (NCERC) was officially opened on August 29, 2011. Located within the Device Assembly Facility (DAF) at the Nevada National Security Site (NNSS), the NCERC has become a consolidation facility within the United States for critical configuration testing, particularly those involving highly enriched uranium (HEU). The DAF is a Department of Energy (DOE) owned facility that is operated by the National Nuclear Security Agency/Nevada Site Office (NNSA/NSO). User laboratories include the Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL). Personnel bring their home lab qualifications and procedures with them to the DAF, such that non-site specific training need not be repeated to conduct work at DAF. The NNSS Management and Operating contractor is National Security Technologies, LLC (NSTec) and the NNSS Safeguards and Security contractor is Wackenhut Services. The complete report provides an overview and status of the available laboratories and test bays at NCERC, available test materials and test support configurations, and test requirements and limitations for performing sub-critical and critical tests. The current summary provides a brief summary of the facility status and the method by which experiments may be introduced to NCERC.

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

    International Nuclear Information System (INIS)

    1995-04-01

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

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

    International Nuclear Information System (INIS)

    Hartfield, R.A.

    1993-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hartfield, R.A.

    1994-03-01

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

  1. Standards development: status summary report. Quarterly report, April-June 1982

    International Nuclear Information System (INIS)

    1982-01-01

    This report gives in summary form, the current schedule plans for development of regulations, guides, reports, petitions and environmental statements. Approved schedules are identified by a T (Target) date below each milestone description on the computerized network. Schedule estimates that have not yet been approved by standards development management are also included and are identified by an E (estimated) date below the approved target date. E dates do not represent approved changes and are printed for information purposes only

  2. The CSNI International Standard Problem Programme: Overall Presentation on Objectives; Rationale and Lessons Learnt: a Joint Venture of the Thermalhydraulic International Community

    International Nuclear Information System (INIS)

    Reocreux, M.

    2008-01-01

    The CSNI International Standard Problems have been one of the key activities of the CSNI thermal hydraulics groups during the last 25 years. After recalling the way the international standard problems were initiated in the late 1970 years -they were called at that time CSNI LOCA Standard Problem- the process which has led to make from the ISPs a full CSNI activity, is described. Rules have been defined which formalized the way experimental results were provided and the way the comparison exercise were performed. The long series of ISPs from 1975 up to nowadays is described, explaining the different trends in the ISPs choices. The findings which have been obtained are reviewed on both technical and programmatic aspects.

  3. ISP - 26 OECD/NEA/CSNI International standard problem n. 26. Rosa-4 LSTF Cold-Leg Small-Break Loca experiment. Comparison report

    International Nuclear Information System (INIS)

    1992-02-01

    This report is the final comparison report for the CSNI ISP-26 which was performed for a 5 pc cold-leg small-break LOCA experiment conducted in the ROSA-IV Large scale test facility (LSTF), and simulation of the thermal-hydraulic response of a pressurized water reactor during a small break loss-of-coolant accident or an operational transient. The facility has an overall scaling factor of 1/48, with hot and cold legs sized to conserve the volume scaling. Both the initial steady-state conditions and the test procedures are designed to minimize the effects of scaling compromises. 10 seconds into the break, the turbine throttle valve was closed at a pressurizer pressure of 12.97 MPa. The turbine bypass was inactive, since loss-of-offsite power was assumed concurrently with the scram. The reactor coolant pumps stopped at 265 seconds. The core was uncovered between 120 seconds and 155 seconds into the break. The comparison report presents all the nineteen submitted calculations. A summary description of the participants as well as the computer codes and input decks used by them is provided

  4. Status Report on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions - Final Report

    International Nuclear Information System (INIS)

    Adorni, M.; Esmaili, H.; Grant, W.; Hollands, T.; Hozer, Z.; Jaeckel, B.; Munoz, M.; Nakajima, T.; Rocchi, F.; Strucic, M.; ); Tregoures, N.; Vokac, P.; Ahn, K.I.; Bourgue, L.; Dickson, R.; Douxchamps, P.A.; Herranz, L.E.; Jernkvist, L.O.; Amri, A.; Kissane, M.P.; )

    2015-01-01

    Following the 2011 accident at the Fukushima Daiichi Nuclear Power Station, the Nuclear Energy Agency Committee on the Safety of Nuclear Installations decided to launch several high-priority activities to address certain technical issues. Among other things, it was decided to prepare a status report on spent fuel pools (SFPs) under loss of cooling accident conditions. This activity was proposed jointly by the CSNI Working Group on Analysis and Management of Accidents (WGAMA) and the Working Group on Fuel Safety (WGFS). The main objectives, as defined by these working groups, were to: - Produce a brief summary of the status of SFP accident and mitigation strategies, to better contribute to the post-Fukushima accident decision making process; - Provide a brief assessment of current experimental and analytical knowledge about loss of cooling accidents in SFPs and their associated mitigation strategies; - Briefly describe the strengths and weaknesses of analytical methods used in codes to predict SFP accident evolution and assess the efficiency of different cooling mechanisms for mitigation of such accidents; - Identify and list additional research activities required to address gaps in the understanding of relevant phenomenological processes, to identify where analytical tool deficiencies exist, and to reduce the uncertainties in this understanding. The proposed activity was agreed and approved by CSNI in December 2012, and the first of four meetings of the appointed writing group was held in March 2013. The writing group consisted of members of the WGAMA and the WGFS, representing the European Commission and the following countries: Belgium, Canada, Czech Republic, France, Germany, Hungary, Italy, Japan, Korea, Spain, Sweden, Switzerland and the USA. This report mostly covers the information provided by these countries. The report is organised into 8 Chapters and 4 Appendices: Chapter 1: Introduction; Chapter 2: Spent fuel pools; Chapter 3: Possible accident

  5. Bioenergy. A sustainable and reliable energy source. A review of status and prospects. Executive Summary

    International Nuclear Information System (INIS)

    Bauen, A.; Vuille, F.; Berndes, G.; Junginger, M.; Londo, M.

    2009-08-01

    This publication is the Executive Summary of a report prepared for IEA Bioenergy. The full report 'Bioenergy - a Sustainable and Reliable Energy Source' will be available on the website of IEA Bioenergy in digital form and in hard copy in a few months time. The purpose of the project was to produce an authoritative review of the entire bioenergy sector aimed at policy and investment decision makers. The brief to the contractors was to provide a global perspective of the potential for bioenergy, the main opportunities for deployment in the short and medium term and the principal issues and challenges facing the development of the sector.

  6. Summary of the Current Status of Lessons Learned From Fukushima Accident

    International Nuclear Information System (INIS)

    Pasamehmetoglu, Kemal

    2013-01-01

    This presentation introduced the current status of the lessons learned from the Fukushima accident, and in particular, the recommendations released by a NRC Near-term Task Force to enhance reactor safety in the 21. century. The near-term recommendations are focused on emergency power and emergency cooling availability during station blackout accidents

  7. Debris impact on emergency coolant recirculation - summary and conclusions

    International Nuclear Information System (INIS)

    Jain, Bhagwat; Hsia, Anthony; Armand, Yves; Mattei, Jean-Marie; Hyvaerinen, Juhani; Maqua, Michael; Puetter, Bernhard; Sandervaag, Oddbjoern; Vandewalle, Andre; Tombuyses, Beatrice; Pyy, Pekka; Royen, Jacques

    2004-01-01

    to two orders of magnitude because of strainer clogging. Consequently, the CSNI decided to continue its previous efforts in the area. The overall purpose of the 2004 Workshop was to discuss the impact of new information made available since 1996 and to promote consensus among member countries on identification of remaining technical issues important to safety, and on possible paths for their resolution. The specific purposes of the Workshop were: a. To review the knowledge base and in particular information developed after 1999, and to consider the validity of the conclusions drawn. b. To exchange information on the current status of research related to debris generation, debris transportation, and sump strainer clogging and penetration phenomena, in particular for PWRs, and to assess uncertainties. c. To exchange and disseminate information on recent and current activities and practices in these areas. d. To identify and discuss differences between approaches relevant to reactor safety. e. To identify technical issues and programs of interest for international collaborative research and develop an Action Plan outlining activities that CSNI should undertake in the area of strainer or sump screen clogging during the next few years. Summary of the main findings: a. The safety significance of the sump strainer clogging depends on the plant design (e.g. sump strainer, ECCS) and backfitting measures performed. b. The following are examples of PWR design features that could influence the debris impact on the ECCS sump performance: - Type of insulation (material, combination of materials, protection). - Break size to be postulated. - Transport in containment with or without containment spray system (CSS). - Degree of turbulence and flow velocities in the sump influenced by CSS, water level, break flow location and sump geometry. - Redundancy of sumps and residual heat removal system (RHRS). - Strainer design (area, mesh size). - Positioning of recirculation pumps and vortex

  8. CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

    Energy Technology Data Exchange (ETDEWEB)

    1984-08-01

    On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break.

  9. CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings

    International Nuclear Information System (INIS)

    1984-08-01

    On September 1 and 2, 1983, the CSNI subcommittee on primary system integrity held a special meeting in Monterey, California, on the subject of leak-before-break in nuclear reactor piping systems. The purpose of the meeting was to provide an international forum for the exchange of ideas, positions, and research results; to identify areas requiring additional research and development; and to determine the general attitude toward acceptance of the leak-before-break concept. The importance of the leak-before-break issue was evidenced by excellent attendance at the meeting and through active participation by the meeting attendees. Approximately 125 people representing fifteen different nations attended the meeting. The meeting was divided into four technical sessions addressing the following areas: Application of Piping Fracture Mechanics to Leak-Before Break, Leak Rate and Leak Detection, Leak-Before-Break Studies, Methods and Results, Current and Proposed Positions on Leak-Before-Break

  10. Lessons learned from OECD/CSNI ISP on small break LOCA: final report

    International Nuclear Information System (INIS)

    1996-07-01

    This document presents an overview of the results obtained from five recent OECD/CSNI International Standard Problems (ISPs) dealing with phenomenologies typical of Small Break LOCA in PWR nuclear power plants of western design. The experiment in four Integral test Facilities, Lobi, Spes, Bethsy and Lstf and the recorded data from a steam generator tube rupture transient in the Belgian PWR of Doel, were taken as reference for the calculations. Relevant hardware characteristics of the facilities and of the plant are firstly given, including the correlation between key thermalhydraulic phenomena and the reference experimental scenarios. A statistical evaluation of the general data connected with each ISP is then presented. The lessons learned from the ISPs are then considered. Four areas have been identified: code deficiencies and capabilities, scaling of the data, progress in code capabilities and various additional aspects

  11. Analysis of CSNI benchmark test on containment using the code CONTRAN

    International Nuclear Information System (INIS)

    Haware, S.K.; Ghosh, A.K.; Raj, V.V.; Kakodkar, A.

    1994-01-01

    A programme of experimental as well as analytical studies on the behaviour of nuclear reactor containment is being actively pursued. A large number ol' experiments on pressure and temperature transients have been carried out on a one-tenth scale model vapour suppression pool containment experimental facility, simulating the 220 MWe Indian Pressurised Heavy Water Reactors. A programme of development of computer codes is underway to enable prediction of containment behaviour under accident conditions. This includes codes for pressure and temperature transients, hydrogen behaviour, aerosol behaviour etc. As a part of this ongoing work, the code CONTRAN (CONtainment TRansient ANalysis) has been developed for predicting the thermal hydraulic transients in a multicompartment containment. For the assessment of the hydrogen behaviour, the models for hydrogen transportation in a multicompartment configuration and hydrogen combustion have been incorporated in the code CONTRAN. The code also has models for the heat and mass transfer due to condensation and convection heat transfer. The structural heat transfer is modeled using the one-dimensional transient heat conduction equation. Extensive validation exercises have been carried out with the code CONTRAN. The code CONTRAN has been successfully used for the analysis of the benchmark test devised by Committee on the Safety of Nuclear Installations (CSNI) of the Organisation for Economic Cooperation and Development (OECD), to test the numerical accuracy and convergence errors in the computation of mass and energy conservation for the fluid and in the computation of heat conduction in structural walls. The salient features of the code CONTRAN, description of the CSNI benchmark test and a comparison of the CONTRAN predictions with the benchmark test results are presented and discussed in the paper. (author)

  12. Network, system, and status software enhancements for the autonomously managed electrical power system breadboard. Volume 1: Project summary

    Science.gov (United States)

    Mckee, James W.

    1990-01-01

    This volume (1 of 4) gives a summary of the original AMPS software system configuration, points out some of the problem areas in the original software design that this project is to address, and in the appendix collects all the bimonthly status reports. The purpose of AMPS is to provide a self reliant system to control the generation and distribution of power in the space station. The software in the AMPS breadboard can be divided into three levels: the operating environment software, the protocol software, and the station specific software. This project deals only with the operating environment software and the protocol software. The present station specific software will not change except as necessary to conform to new data formats.

  13. Civilian Power Program. Part 1, Summary, Current status of reactor concepts

    Energy Technology Data Exchange (ETDEWEB)

    Author, Not Given

    1959-09-01

    This study group covered the following: delineation of the specific objectives of the overall US AEC civilian power reactor program, technical objectives of each reactor concept, preparation of a chronological development program for each reactor concept, evaluation of the economic potential of each reactor type, a program to encourage the the development, and yardsticks for measuring the development. Results were used for policy review by AEC, program direction, authorization and appropriation requests, etc. This evaluation encompassed civilian power reactors rated at 25 MW(e) or larger and related experimental facilities and R&D. This Part I summarizes the significant results of the comprehensive effort to determine the current technical and economic status for each reactor concept; it is based on the 8 individual technical status reports (Part III).

  14. Tank farm surveillance and waste status summary report for May 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-08-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations

  15. Benchmarking dairy herd health status using routinely recorded herd summary data.

    Science.gov (United States)

    Parker Gaddis, K L; Cole, J B; Clay, J S; Maltecca, C

    2016-02-01

    Genetic improvement of dairy cattle health through the use of producer-recorded data has been determined to be feasible. Low estimated heritabilities indicate that genetic progress will be slow. Variation observed in lowly heritable traits can largely be attributed to nongenetic factors, such as the environment. More rapid improvement of dairy cattle health may be attainable if herd health programs incorporate environmental and managerial aspects. More than 1,100 herd characteristics are regularly recorded on farm test-days. We combined these data with producer-recorded health event data, and parametric and nonparametric models were used to benchmark herd and cow health status. Health events were grouped into 3 categories for analyses: mastitis, reproductive, and metabolic. Both herd incidence and individual incidence were used as dependent variables. Models implemented included stepwise logistic regression, support vector machines, and random forests. At both the herd and individual levels, random forest models attained the highest accuracy for predicting health status in all health event categories when evaluated with 10-fold cross-validation. Accuracy (SD) ranged from 0.61 (0.04) to 0.63 (0.04) when using random forest models at the herd level. Accuracy of prediction (SD) at the individual cow level ranged from 0.87 (0.06) to 0.93 (0.001) with random forest models. Highly significant variables and key words from logistic regression and random forest models were also investigated. All models identified several of the same key factors for each health event category, including movement out of the herd, size of the herd, and weather-related variables. We concluded that benchmarking health status using routinely collected herd data is feasible. Nonparametric models were better suited to handle this complex data with numerous variables. These data mining techniques were able to perform prediction of health status and could add evidence to personal experience in herd

  16. Employee or independent contractor? A summary of court, umpire and referee decisions relating to employee status

    International Nuclear Information System (INIS)

    Baird, S.; Morris, M.

    1999-01-01

    Nine case examples of disputes regarding the distinction between contractor personnel and employee status were presented. The cases involved people hired for services by Sunstar Uniforms Inc., S.A.M. Distributors, Malibu Homes Construction Ltd., Perfect Drywall Co. Ltd., Tim Horton's, Badger Mechanical Services Whitecourt Ltd., Hostage Musical Group, a chocolate bar seller in Regina, and Normatec Consultants Inc. This presentation described the disputes for each unique case and presented the outcome as decided by the courts

  17. Tank Farm surveillance and waste status summary report for April 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-07-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations

  18. Employee or independent contractor? A summary of court, umpire and referee decisions relating to employee status

    Energy Technology Data Exchange (ETDEWEB)

    Baird, S.; Morris, M. [Alberta Labour, Edmonton, AB (Canada)

    1999-07-01

    Nine case examples of disputes regarding the distinction between contractor personnel and employee status were presented. The cases involved people hired for services by Sunstar Uniforms Inc., S.A.M. Distributors, Malibu Homes Construction Ltd., Perfect Drywall Co. Ltd., Tim Horton's, Badger Mechanical Services Whitecourt Ltd., Hostage Musical Group, a chocolate bar seller in Regina, and Normatec Consultants Inc. This presentation described the disputes for each unique case and presented the outcome as decided by the courts.

  19. Employee or independent contractor? A summary of court, umpire and referee decisions relating to employee status

    Energy Technology Data Exchange (ETDEWEB)

    Baird, S.; Morris, M. [Alberta Labour, Edmonton, AB (Canada)

    1999-10-01

    Nine case examples of disputes regarding the distinction between contractor personnel and employee status were presented. The cases involved people hired for services by Sunstar Uniforms Inc., S.A.M. Distributors, Malibu Homes Construction Ltd., Perfect Drywall Co. Ltd., Tim Horton`s, Badger Mechanical Services Whitecourt Ltd., Hostage Musical Group, a chocolate bar seller in Regina, and Normatec Consultants Inc. This presentation described the disputes for each unique case and presented the outcome as decided by the courts.

  20. Recent and current activities of the OECD/NEA Working Group on Fuel Safety (NEA/CSNI). Recent and Current Activities of the Working Group on Fuel Safety (NEA/CSNI)

    International Nuclear Information System (INIS)

    Petit, Marc

    2013-01-01

    The Working Group on Fuel Safety (WGFS) is part of the Committee on the Safety of Nuclear Installations (CSNI) of the Nuclear Energy Agency and has the main mission of advancing the current understanding and addressing fuel safety issues. Recent and current activities of the working group have addressed mainly the loss of coolant accident (LOCA), the reactivity initiated accident (RIA), the fuel safety criteria and leaking fuel issues, as well as Fukushima-related fuel topics. In the area of LOCA, the group issued different documents, the most notable being a very comprehensive state of the art report [NEA/CSNI/R (2009)15]. Regarding RIA, some documents were finalised and issued in the recent years, as well as a state of the art report [NEA/CSNI/R (2010)1]. The question of leaking fuel and how it is handled in the reactors is an activity that is just starting. Of particular interest to people developing new fuel concepts is the Nuclear Fuel Safety Criteria Technical Review - Second Edition [NEA/CSNI/R (2012)3]. This document provides a broad overview of the numerous criteria used in the NEA member countries to demonstrate to safe use of fuel in light water reactors. The WGFS has started discussions about fuel related issues raised by the Fukushima accident, in particular, hydrogen production. New concepts have been proposed to solve these issues but it appears that these concepts will need to go through a long qualification process to assess their adequacy for the different situations considered in the evaluation of fuel safety, from normal operation to accident conditions

  1. Status of research reactor spent fuel world-wide: Database summary

    International Nuclear Information System (INIS)

    Ritchie, I.G.

    1996-01-01

    Results complied in the research reactor spent fuel database are used to assess the status of research reactor spent fuel world-wide. Fuel assemblies, their types, enrichment, origin of enrichment and geological distribution among the industrialized and developed countries of the world are discussed. Fuel management practices in wet and dry storage facilities and the concerns of reactor operators about long-term storage of their spent fuel are presented and some of the activities carried out by the International Atomic Energy Agency to address the issues associated with research reactor spent fuel are outlined. (author). 4 refs, 17 figs, 4 tabs

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

    International Nuclear Information System (INIS)

    1987-06-01

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

  3. Tank farm surveillance and waste status summary report for October 1992

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  4. Tank farm surveillance and waste status summary report for January 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-03-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  5. Tank farm surveillance and waste status summary report for November 1992

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-02-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  6. Tank Farm surveillance and waste status summary report for September 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1994-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

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

    International Nuclear Information System (INIS)

    1981-07-01

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

  8. Tank farm surveillance and waste status summary report for May 1994

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1994-08-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  9. Tank farm surveillance and waste status summary report for May 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1994-08-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  10. Tank farm surveillance and waste status summary report for October 1992

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1993-01-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter 1, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  11. Tank farm surveillance and waste status summary report for June 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-10-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

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

    International Nuclear Information System (INIS)

    1989-12-01

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

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

    International Nuclear Information System (INIS)

    1986-12-01

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

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

    International Nuclear Information System (INIS)

    1987-10-01

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

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

    International Nuclear Information System (INIS)

    1987-12-01

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

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

    International Nuclear Information System (INIS)

    Schwartz, I.

    1987-12-01

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

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

    International Nuclear Information System (INIS)

    1987-10-01

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

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

    International Nuclear Information System (INIS)

    1987-07-01

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

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

    International Nuclear Information System (INIS)

    1990-02-01

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

  20. Tank farm surveillance and waste status summary report for December 1992

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-02-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  1. Tank Farm surveillance and waste status summary report for March 1993

    International Nuclear Information System (INIS)

    Hanlon, B.M.

    1993-05-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are Contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding flank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks

  2. Tank farm surveillance and waste status summary report for December 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1994-05-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special 9 surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of U.S. Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, U.S. Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

  3. Tank farm surveillance and waste status summary report for December 1992

    Energy Technology Data Exchange (ETDEWEB)

    Hanlon, B.M.

    1993-02-01

    This report is the official inventory for radioactive waste stored in underground tanks in the 200 Areas at the Hanford Site. Data that depict the status of stored radioactive waste and tank vessel integrity are contained within the report. This report provides data on each of the existing 177 large underground waste storage tanks and 49 smaller catch tanks and special surveillance facilities, and supplemental information regarding tank surveillance anomalies and ongoing investigations. This report is intended to meet the requirement of US Department of Energy-Richland Operations Office Order 5820.2A, Chapter I, Section 3.e. (3) (DOE-RL, 1990, Radioactive Waste Management, US Department of Energy-Richland Operation Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm Tanks.

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

    International Nuclear Information System (INIS)

    1987-10-01

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

  5. Status summary of chemical processing development in plutonium-238 supply program

    Energy Technology Data Exchange (ETDEWEB)

    Collins, Emory D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Benker, Dennis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wham, Robert M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); DePaoli, David W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Delmau, Laetitia Helene [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sherman, Steven R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-10-01

    This document summarizes the status of development of chemical processing in the Plutonium-238 Supply Program (PSP) near the end of Demonstration 1. The objective of the PSP is “to develop, demonstrate, and document a production process that meets program objectives and to prepare for its operation” (Frazier et al. 2016). Success in the effort includes establishing capability using the current infrastructure to produce Np targets for irradiation in Department of Energy research reactors, chemically processing the irradiated targets to separate and purify the produced Pu and transferring the PuO2 product to Los Alamos National Laboratory (LANL) at an average rate of 1.5 kg/y.

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

    International Nuclear Information System (INIS)

    1987-10-01

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

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

    International Nuclear Information System (INIS)

    1988-05-01

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

  8. Waste package materials testing for a salt repository: 1983 status summary report

    International Nuclear Information System (INIS)

    Moak, D.P.

    1986-09-01

    The United States plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy is sponsoring research on the designing and testing of waste packages and waste package materials. This fiscal year 1983 status report summarizes recent results of waste package materials testing in a salt environment. The results from these tests will be used by waste package designers and performance assessment experts. Release characteristics data are available on two waste forms (spent fuel and waste-containing glass) that were exposed to leaching tests at various radiation levels, temperatures, pH, glass surface area to solution volume ratios, and brine solutions simulating expected salt repository conditions. Candidate materials tested for corrosion resistance and other properties include iron alloys; TI-CODE 12, the most promising titanium alloy for containment; and nickel alloys. In component interaction testing, synergistic effects have not ruled out any candidate material. 21 refs., 37 figs., 15 tabs

  9. Results from the Application of Uncertainty Methods in the CSNI Uncertainty Methods Study (UMS)

    International Nuclear Information System (INIS)

    Glaeser, H.

    2008-01-01

    Within licensing procedures there is the incentive to replace the conservative requirements for code application by a - best estimate - concept supplemented by an uncertainty analysis to account for predictive uncertainties of code results. Methods have been developed to quantify these uncertainties. The Uncertainty Methods Study (UMS) Group, following a mandate from CSNI, has compared five methods for calculating the uncertainty in the predictions of advanced -best estimate- thermal-hydraulic codes. Most of the methods identify and combine input uncertainties. The major differences between the predictions of the methods came from the choice of uncertain parameters and the quantification of the input uncertainties, i.e. the wideness of the uncertainty ranges. Therefore, suitable experimental and analytical information has to be selected to specify these uncertainty ranges or distributions. After the closure of the Uncertainty Method Study (UMS) and after the report was issued comparison calculations of experiment LSTF-SB-CL-18 were performed by University of Pisa using different versions of the RELAP 5 code. It turned out that the version used by two of the participants calculated a 170 K higher peak clad temperature compared with other versions using the same input deck. This may contribute to the differences of the upper limit of the uncertainty ranges.

  10. Proceedings of the 2nd CSNI Specialist Meeting on Simulators and Plant Analysers

    International Nuclear Information System (INIS)

    Tiihonen, O.

    1999-01-01

    The safe utilisation of nuclear power plants requires the availability of different computerised tools for analysing the plant behaviour and training the plant personnel. These can be grouped into three categories: accident analysis codes, plant analysers and training simulators. The safety analysis of nuclear power plants has traditionally been limited to the worst accident cases expected for the specific plant design. Many accident analysis codes have been developed for different plant types. The scope of the analyses has continuously expanded. The plant analysers are now emerging tools intended for extensive analysis of the plant behaviour using a best estimate model for the whole plant including the reactor and full thermodynamic process, both combined with automation and electrical systems. The comprehensive model is also supported by good visualisation tools. Training simulators with real time plant model are tools for training the plant operators to run the plant. Modern training simulators have also features supporting visualisation of the important phenomena occurring in the plant during transients. The 2nd CSNI Specialist Meeting on Simulators and Plant Analysers in Espoo attracted some 90 participants from 17 countries. A total of 49 invited papers were presented in the meeting in addition to 7 simulator system demonstrations. Ample time was reserved for the presentations and informal discussions during the four meeting days. (orig.)

  11. Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

    International Nuclear Information System (INIS)

    Ebert, D.

    1997-07-01

    This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts' meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes

  12. Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

    Energy Technology Data Exchange (ETDEWEB)

    Ebert, D.

    1997-07-01

    This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts` meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes.

  13. Proceedings of the NEA/CSNI-UNIPEDE Specialist Meeting on Operating Experience with Steam Generators

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-07-01

    The long history of operating experience with pressurized water reactors has indicated that the steam generators are of primary importance in nuclear power plant design and operation; this is furthermore confirmed by analyzing the data of the Incident Reporting System (IRS). It is for this reason that the OECD/NEA Committee on the Safety of Nuclear Installations organizes, in cooperation with UNIPEDE, a Specialist Meeting on 'Operating Experience with Steam Generators'. This Specialist Meeting, held in Brussels, Belgium, in September 1991, is hosted by the Belgian Government and AIB-Vincotte Nuclear. In addition to being a follow-up to the October 1984 meeting (organized by the CSNI and UNIPEDE in Stockholm, Sweden), this Meeting reviews the current state-of-the-art of steam generator technology thus providing a forum for the exchange of related experience in operation, inspection, maintenance, repair, modifications, replacement, and licensing requirements pertaining to steam generators. Forty-seven papers are presented in eight sessions entitled: Operating Experience (two sessions), Structural Integrity and Licensing Issues, Analysis and Prediction of Degradation Mechanisms, Inservice Inspection Methods, Preventive and Corrective Actions (two sessions) and Replacement of Steam Generators. There are furthermore two panel sessions entitled 'Observed Degradation Mechanisms and Licensing Positions', and 'Inspection, Repair and Replacement Strategies'. These proceedings consist of a compilation of the papers presented at the Meeting, which is attended by more than one hundred and fifty participants from fifteen countries and several international organisations.

  14. CSNI technical opinion papers no.5. Managing and regulating organisational change in nuclear installations

    International Nuclear Information System (INIS)

    2004-01-01

    Nuclear licensees are increasingly required to adapt to a more challenging commercial environment as electricity markets are liberalized. One of the costs that is often perceived as being amenable to control is staffing, and hence there is significant exploration of new strategies for managing this cost - for example, by reducing staffing levels, changing organisational structures, adopting new shift strategies, introducing new technology or increasing the proportion of work carried out by external contractors. However, if changes to staffing levels or organisational structures and systems are inadequately conceived or executed they have the potential to affect the way in which safety is managed. In this context, the NEA Committee on the Safety of Nuclear Installations (CSNI) and its Special Expert Group on Human and Organisational Factors (SEGHOF) organised an international workshop to discuss the management and regulation of organisational change in 2001. This technical opinion paper distills the findings of that workshop and sets out the factors that regulatory bodies might reasonably expect to be addressed within licensees arrangements to manage organisational change. The paper should be of particular interest to both regulators and managers of nuclear utilities. (author)

  15. Report on the CSNI workshop on nuclear power plant transition from operation into decommissioning: human factors and organisation considerations

    International Nuclear Information System (INIS)

    2000-01-01

    The Senior Expert Group of the Committee on the Safety of Nuclear Installations (CSNI) proposed to Principal Working Group 1 (PWG1) of CSNI that a workshop be held to identify and discuss issues related to the impact of human factors and organisational aspects on decommissioning. This workshop was held in May 1999 in conjunction with the Joint NEA/IAEA/EC workshop on The Regulatory Aspects of Decommissioning. The workshop goals, as stated in the NEA Research Strategies for Human Performance, were 'to convene an information exchange meeting with interested Member countries in order to discuss areas of concern in this respect and identify possible areas that merit further research and their priorities'. The workshop highlighted a comparative lack of developed work in this area concerning the way in which organisational weaknesses can manifest themselves and how best to prevent or mitigate their effects. Eight key issues were identified and discussed by the participants. For each of the eight issues discussed by working groups, the potential risks of failing to address the Issue were identified. These potential risks formed a focal point for generating discussion about current experience and for drawing out gaps in current knowledge and understanding. From this base, participants then focused on specific types of information and questions that need further research in order to improve understanding and successful implementation of the transition from operations to decommissioning. The eight issues and suggested high priority needs are: - Creating a system to share international experience: Establish improved methods for obtaining and sharing information and experience on a regular basis in order to identify organisational and human factors issues, good practices and lessons learned as regulators and utilities deal with decommissioning. - Organisational memory and competence: Identify effective approaches to retain expertise during the transition from operations to

  16. Compliance status summaries for federal and state statutory directives that apply to the Salt Repository Project at the Deaf Smith County Site, Texas

    International Nuclear Information System (INIS)

    1986-07-01

    This document contains statutory summaries, checklists of compliance requirements, status summaries, and lists of information needs for the environmental and health and safety statutory directives at Federal and State levels that apply to the Salt Repository Project at the Deaf Smith County Site, Texas. Statutes that apply in general to any repository project but not specifically to the Deaf Smith are not included. The information herein supplements the Salt Repository Project Statutory Compliance Plan and the Salt Repository Project Permitting Management Plan by providing lengthy details on statutory directives, compliance requirements, information needs, and the overall status of the environmental and health and safety compliance program for the Salt Repository Project at the Deaf Smith County Site, Texas

  17. Status of nuclear data needed for radiation therapy and existing data development activities in Member States. Summary report of a consultants' meeting

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1997-01-01

    The present report contains the summary of the IAEA Consultants' Meeting on the ''Status of nuclear data needed for radiation therapy and existing data development activities in Member States'' held at the IAEA Headquarters, Vienna, 9-11 December 1996. The present activities on nuclear data for radiotherapy are summarized in Member States, the present status of nuclear data for photon, neutron and proton therapy is reviewed and topics which are not presently covered by other institutions are identified. (author). 4 refs, 2 figs

  18. OECD/CSNI Workshop on Best Estimate Methods and Uncertainty Evaluations - Workshop Proceedings

    International Nuclear Information System (INIS)

    2013-01-01

    Best-Estimate Methods plus Uncertainty Evaluation are gaining increased interest in the licensing process. On the other hand, lessons learnt from the BEMUSE (NEA/CSNI/R(2011)3) and SM2A (NEA/CSNI/R(2011)3) benchmarks, progress of UAM benchmark, and answers to the WGAMA questionnaire on the Use of Best-Estimate Methodologies show that improvements of the present methods are necessary and new applications appear. The objective of this workshop is to provide a forum for a wide range of experts to exchange information in the area of best estimate analysis and uncertainty evaluation methods and address issues drawn-up from BEMUSE, UAM and SM2A activities. Both, improvement of existing methods and recent new developments are included. As a result of the workshop development, a set of recommendations, including lines for future activities were proposed. The organisation of the Workshop was divided into three parts: Opening session including key notes from OECD and IAEA representatives, Technical sessions, and a Wrap-up session. All sessions included a debate with participation from the audience constituted by 71 attendees. The workshop consisted of four technical sessions: a) Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches to deal with Best Estimate codes and uncertainties evaluations. A total of six papers were presented. One initial paper summarized the existing methods; the following open papers were focused on specific methods stressing their bases, peculiarities and advantages. As a result of the session a picture of the current State of the Art was obtained. b) International comparative activities: This session reviewed the set of international activities around the subject of BEPU methods benchmarking and development. From each of the activities a description of the objectives, development, main results, conclusions and recommendations (in case it is finalized) was presented. This

  19. The Findings from the OECD/NEA/CSNI UMS (Uncertainty Method Study)

    International Nuclear Information System (INIS)

    D'Auria, F.; Glaeser, H.

    2013-01-01

    Within licensing procedures there is the incentive to replace the conservative requirements for code application by a 'best estimate' concept supplemented by an uncertainty analysis to account for predictive uncertainties of code results. Methods have been developed to quantify these uncertainties. The Uncertainty Methods Study (UMS) Group, following a mandate from CSNI (Committee on the Safety of Nuclear Installations) of OECD/NEA (Organization for Economic Cooperation and Development / Nuclear Energy Agency), has compared five methods for calculating the uncertainty in the predictions of advanced 'best estimate' thermal-hydraulic codes. Most of the methods identify and combine input uncertainties. The major differences between the predictions of the methods came from the choice of uncertain parameters and the quantification of the input uncertainties, i.e. the wideness of the uncertainty ranges. Therefore, suitable experimental and analytical information has to be selected to specify these uncertainty ranges or distributions. After the closure of the Uncertainty Method Study (UMS) and after the report was issued comparison calculations of experiment LSTF-SB-CL-18 were performed by University of Pisa using different versions of the RELAP 5 code. It turned out that the version used by two of the participants calculated a 170 K higher peak clad temperature compared with other versions using the same input deck. This may contribute to the differences of the upper limit of the uncertainty ranges. A 'bifurcation' analysis was also performed by the same research group also providing another way of interpreting the high temperature peak calculated by two of the participants. (authors)

  20. Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety

    International Nuclear Information System (INIS)

    Ishigure, K.; Saeki, M.; Soda, K.; Sugimoto, J.

    1992-03-01

    The Third CSNI Workshop on Iodine Chemistry in Reactor Safety was held at Tokai Research Establishment of Japan Atomic Energy Research Institute at Tokai-mura, Ibaraki-ken, Japan, on September 11 to 13, 1991. About 60 experts attended the Workshop from 10 countries and 2 international organizations. In the Workshop, 29 papers were presented in five sessions on various aspects of iodine chemistry in reactor safety, such as radiolytic and surface reactions of iodine species, fundamental and integral tests, modeling and code developments. The information exchanged and the discussions followed resulted in extended and promoted understanding of iodine behavior in accidents of light water reactors and also gave a large expectation for the further progresses coming in the future. It should be emphasized that a most important and unique forum has been established through the Workshop for exchanging information and collaboratively solving the important problems in the field of the iodine chemistry in nuclear reactor safety. At the Workshop, an effort was made to integrate all information for better use by safety analysts. There is no doubt that a lot of information on iodine behaviour has been accumulated, but in many cases this information needs to be co-ordinated and well organised for safety analyses of nuclear reactors. It is essential that the results of laboratory studies and integral experiments together with modelling activities are well co-ordinated. Therefore, the goal was: - to review the knowledge and understanding of the chemistry of iodine of relevance to the prediction of its behaviour in nuclear reactors during a range of operational and accident conditions; - to define those areas of chemistry which are important but poorly understood and require further study. As shown by the conclusions of the Workshop, there is no doubt that this objective was widely attained

  1. Executive Summary

    International Nuclear Information System (INIS)

    2013-01-01

    This report documents the proceedings of the Workshop on 'Safety Assessment of Fuel Cycle Facilities - Regulatory Approaches and Industry Perspectives' held in Toronto, Canada, on 27-29 September 2011. The workshop was organised by the Committee for the Safety on Nuclear Installations (CSNI) of the OECD/Nuclear Energy Agency (NEA) and hosted by the Canadian Nuclear Safety Commission (CNSC). More than 60 specialists representing 11 countries and international organisations attended the workshop. A total of 31 papers were presented and discussed in open forum. In addition, an opportunity was taken to consider the impacts of the events at Fukushima on Fuel Cycle Facilities (FCFs) in general. Nuclear fuel is produced, processed, and stored mainly in industrial-scale facilities. Uranium ores are processed and refined to produce a pure uranium salt stream, Uranium is converted and enriched, nuclear fuel is fabricated (U fuel and U/Pu fuel for the close cycle option); and spent fuel is stored and in some countries also reprocessed (close cycle option). Facilities dedicated to the research and development of new fuel or new processes are also considered as Fuel Cycle Facilities. The safety assessment of nuclear facilities has often been led by the methodology and techniques initially developed for Nuclear Power Plants (NPPs). As FCFs cover a wide diversity of installations, the various approaches of national regulators, and their technical support organizations (TSO), for the Safety Assessment of Fuel Cycle Facilities are also diverse as are the approaches by their industries in providing safety justifications for their facilities. The objective of this workshop was to review the various approaches of national regulators, and their technical support organizations, in the Safety Assessment of Fuel Cycle Facilities and the experience of their industry in providing safety justification for their facilities. It addressed the present situation in various NEA member

  2. Executive summary

    International Nuclear Information System (INIS)

    2009-01-01

    Prior to the workshop two CSNI/WGHOF surveys were distributed - one addressing regulatory expectations and the other focussing on approaches the licensees use to justify organisational suitability. The regulatory survey requested a brief overview of the situation related to plant organisations in their country - both regulatory expectations and formal requirements. The licensee survey requested information on how they ensure effective organisational suitability, resources and competencies at their plants. The findings from these surveys were used in conjunction with other factors to identify the key issues for the workshop discussions sessions. Although there have been noticeable improvements in recent years in the documentation of the suitability of licensee organisations, almost all regulatory and licensee survey respondents stated that serious questions remain concerning the maturity of the processes to demonstrate the adequacy of the organisational resources and competencies. Other needed improvements identified by licensees include: - indicators for early detection of losses associated with organisational resources and knowledge; - measures for the preservation of specialised knowledge; - refinement of event (root cause) analyses processes to better take into account and identify organisational causes and contributing factors; - better means to evaluate the adequacy of resources. The survey revealed that methods that licensees have found useful to identify and demonstrate the adequacy of the organisational structure, resources and competencies include business oversight process, peer reviews and benchmarking, event and change analysis and establishment of a reference 'organisational baseline'. The workshop participants identified a number of important attributes that characterise a 'good' organisation. One attribute is that the organisation should be open to learning from their experiences and from the experiences of others. This would include taking advantage

  3. Thermal cycling in LWR components in OECD-NEA member countries - CSNI integrity and ageing working group

    International Nuclear Information System (INIS)

    Faidy, Claude; Chapuliot, Stephane; Mathet, Eric

    2005-01-01

    Thermal cycling is a widespread and recurring problem in nuclear power plants worldwide. Several incidents with leakage of primary water inside the containment challenged the integrity of NPPs although no release outside of containment occurred. Thermal cycling was not taken into account at the design stage. Regulatory bodies, utilities and researchers have to address it for their operating plants. It is a complex phenomenon that involves and links thermal hydraulic, fracture mechanic, materials and plant operation. Thermal cycling is connected either to operating transients (low cycle fatigue) or to complex phenomenon like stratification, vortex and mixing (low and high cycle fatigue). The former is covered by existing rules and codes. The latter is partially addressed by national rules and constitutes the subject of this report. In 2002, the Committee on the Safety of Nuclear Installations (CSNI) requested the working group on the integrity of reactor components and structures (IAGE WG) to prepare a program of work on thermal cycling to provide information to NEA member countries on operational experience, regulatory policies, countermeasures in place, current status of research and development, and to identify areas where research is needed both at national and international levels. The working group proposed a 3 fold program that covered: - Review of operating experience, regulatory framework, countermeasures and current research; - Benchmark to assess calculation capabilities in NEA member countries for crack initiation and propagation under a cyclic thermal loading, and ultimately to develop screening criteria to identify susceptible components; results of the benchmark were published in 2005; - Organisation of an international conference in cooperation with the EPRI and the USNRC on fatigue of reactor components. This conference reviews progress in the areas and provides a forum for discussion and exchange of information between high level experts. The

  4. Analysis of OECD/CSNI ISP-42 phase A PANDA experiment using coupled code R5G (RELAP5-GOTHIC)

    International Nuclear Information System (INIS)

    Bencik, V.; Debrecin, N.; Grgic, D.; Bajs, T.

    2010-01-01

    In the paper, the results of the analysis of OECD/CSNI ISP-42 Phase A experiment at PANDA facility using stand-alone codes RELAP5/mod3.3 and GOTHIC 7.2b as well as coupled code R5G (RELAP5/mod3.3-GOTHIC 7.2b) are presented. PANDA is a large-scale thermal-hydraulic test facility installed at PSI (Paul Scherrer Institute) in Switzerland. The OECD/CSNI ISP-42 test consists of six sequential phases (Phase A through F). The present work deals with the post-test calculation of the Phase A, including the break of the main steam line and the Passive Containment Cooling (PCC) System Start-Up. The objective of the test is to investigate the start-up phenomenology of passive cooling system when steam is injected into cold vessel filled with air. The calculation was performed using stand-alone RELAP5/mod3.3 and GOTHIC 7.2b models, and then the same calculation was performed using coupled code with RELAP5 being responsible for reactor part of the model and GOTHIC being responsible for containment part of the model. The prediction capability, running time and modeling aspects were discussed for all three cases. (authors)

  5. Implementation of severe accident management measures - Summary and conclusions

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of the meeting were: 1) to exchange information on activities in the area of SAM implementation and on the rationale for such actions, 2) to monitor progress made, 3) to identify cases of agreement or disagreement, 4) to discuss future orientations of work, 5) to make recommendations to the CSNI. Session summaries prepared by the Chairpersons and discussed by the whole writing group are given in Annex. During the first session, 'SAM Programmes Implementation', papers from one regulator and several utilities and national research institutes were presented to outline the status of implementation of SAM programmes in countries like Switzerland, Russia, Spain, Finland, Belgium and Korea. Also, the contribution of SAM to the safety of Japanese plants (in terms of core damage frequency) was quantified in a paper. One paper gave an overview on the situation regarding SAM implementation in Europe. The second session, 'SAM Approach', provided background and bases for Severe Accident Management in countries like Sweden, Japan, Germany and Switzerland, as well as for hardware features in advanced light water reactor designs, such as the European Pressurised Reactor (EPR), regarding Severe Accident Management. The third session, 'SAM Mitigation Measures', was about hardware measures, in particular those oriented towards hydrogen mitigation where fundamentally different approaches have been taken in Scandinavian countries, France, Germany and Korea. Three papers addressed specific contributions from research to provide a broader basis for the assumptions made in certain computer codes used for the assessment of plant risk arising from beyond-design accident sequences. The fourth session, 'Implementation of SAM Measures on VVER-1000 Reactors', was about the status of work on Severe Accident Management implementation in VVER reactors of existing design and in a new plant currently under construction. The overall picture is that Severe Accident Management has been

  6. Safety margin evaluation concepts for plant Up rates and life extension. Results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP)

    International Nuclear Information System (INIS)

    Belac, J

    2006-01-01

    This presentation summarizes results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP) aimed to develop generalized safety margin concept and means of its quantification for the process of evaluating plant safety in the frame of plant life extension and power up rating activities to be used by OECD member countries. (author)

  7. IRIS-2012 OECD/NEA/CSNI benchmark: Numerical simulations of structural impact

    International Nuclear Information System (INIS)

    Orbovic, Nebojsa; Tarallo, Francois; Rambach, Jean-Mathieu; Sagals, Genadijs; Blahoianu, Andrei

    2015-01-01

    A benchmark of numerical simulations related to the missile impact on reinforced concrete (RC) slabs has been launched in the frame of OECD/NEA/CSNI research program “Improving Robustness Assessment Methodologies for Structures Impacted by Missiles”, under the acronym IRIS. The goal of the research program is to simulate RC structural, flexural and punching, behavior under deformable and rigid missile impact. The first phase called IRIS-2010 was a blind prediction of the tests performed at VTT facility in Espoo, Finland. The two simulations were performed related to two series of tests: (1) two tests on the impact of a deformable missile exhibiting damage mainly by flexural (so-called “flexural tests”) or global response and (2) three tests on the impact of a rigid missile exhibiting damage mainly by punching response (so-called “punching tests”) or local response. The simulation results showed significant scatter (coefficient of variation up to 132%) for both flexural and punching cases. The IRIS-2012 is the second, post-test, phase of the benchmark with the goal to improve simulations and reduce the scatter of the results. Based on the IRIS-2010 recommendations and to better calibrate concrete constitutive models, a series of tri-axial tests as well as Brazilian tests were performed as a part of the IRIS-2012 benchmark. 25 teams from 11 countries took part in this exercise. Majority of participants were part of the IRIS-2010 benchmark. Participants showed significant improvement in reducing epistemic uncertainties in impact simulations. Several teams presented both finite element (FE) and simplified analysis as per recommendations of the IRIS-2010. The improvements were at the level of simulation results but also at the level of understanding of impact phenomena and its modeling. Due to the complexity of the physical phenomena and its simulation (high geometric and material non-linear behavior) and inherent epistemic and aleatory uncertainties, the

  8. IRIS-2012 OECD/NEA/CSNI benchmark: Numerical simulations of structural impact

    Energy Technology Data Exchange (ETDEWEB)

    Orbovic, Nebojsa, E-mail: nebojsa.orbovic@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, ON (Canada); Tarallo, Francois [IRSN, Fontenay aux Roses (France); Rambach, Jean-Mathieu [Géodynamique et Structures, Bagneux (France); Sagals, Genadijs; Blahoianu, Andrei [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)

    2015-12-15

    A benchmark of numerical simulations related to the missile impact on reinforced concrete (RC) slabs has been launched in the frame of OECD/NEA/CSNI research program “Improving Robustness Assessment Methodologies for Structures Impacted by Missiles”, under the acronym IRIS. The goal of the research program is to simulate RC structural, flexural and punching, behavior under deformable and rigid missile impact. The first phase called IRIS-2010 was a blind prediction of the tests performed at VTT facility in Espoo, Finland. The two simulations were performed related to two series of tests: (1) two tests on the impact of a deformable missile exhibiting damage mainly by flexural (so-called “flexural tests”) or global response and (2) three tests on the impact of a rigid missile exhibiting damage mainly by punching response (so-called “punching tests”) or local response. The simulation results showed significant scatter (coefficient of variation up to 132%) for both flexural and punching cases. The IRIS-2012 is the second, post-test, phase of the benchmark with the goal to improve simulations and reduce the scatter of the results. Based on the IRIS-2010 recommendations and to better calibrate concrete constitutive models, a series of tri-axial tests as well as Brazilian tests were performed as a part of the IRIS-2012 benchmark. 25 teams from 11 countries took part in this exercise. Majority of participants were part of the IRIS-2010 benchmark. Participants showed significant improvement in reducing epistemic uncertainties in impact simulations. Several teams presented both finite element (FE) and simplified analysis as per recommendations of the IRIS-2010. The improvements were at the level of simulation results but also at the level of understanding of impact phenomena and its modeling. Due to the complexity of the physical phenomena and its simulation (high geometric and material non-linear behavior) and inherent epistemic and aleatory uncertainties, the

  9. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity

  10. Differences in Approach between Nuclear and Conventional Seismic Standards with regard to Hazard Definition - CSNI Integrity And Ageing Working Group

    International Nuclear Information System (INIS)

    Djaoudi, Ali; Labbe, Pierre; Murphy, Andrew; Kitada, Yoshio

    2008-01-01

    The Committee on the safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities related to maintaining and advancing the scientific and technological knowledge base of the safety of nuclear installations. The Integrity and Ageing of Components and Structures Working Group of the CSNI is responsible for work related to the development and use of methods, data and information to assess the behaviour of materials and structures. It has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The CSNI, at its meeting in June 2003, agreed to initiate an activity aimed to identify any difference between nuclear and non-nuclear conventional standards and their potential significance with regard to seismic hazards and design methods. There was a perception, mainly in some of the European countries that nuclear seismic hazard and design standards may be lagging behind developments in similar standards for conventional facilities. Adequate answer to such perception, need the examination of the following aspects and their significance on the seismic assessment of structures and components: - The safety philosophy behind the seismic nuclear and conventional standards. - The differences in approach regarding the seismic hazard definition. - The difference in approach regarding the design and the methods of analysis. These topics are examined in this report. Appendices A to H of this report contain a brief description of the conventional and the nuclear approaches in the NEA member countries: Belgium, Canada, Czech Republic, Germany, Japan, South Korea, Spain,and USA. The following general conclusions can be drawn: - The approach adopted by the nuclear seismic standards is more conservative and more reliable (in particular for meeting the continued operation criteria) than the recommended by the currently applicable force based conventional seismic codes

  11. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor defueling and disassembly. Summary status report. Volume 3

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to the preparations for defueling the Three Mile Island Unit 2 (TMI-2) reactor and disassembly activities being performed concurrently with decontamination of the facility. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data sysem which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during the period of April 23, 1979 to April 16, 1985, in the completion of activities related to preparation for reactor defueling. Support activities conducted outside of radiation areas are not included within the scope of this report. Computerized reports included in this document are: A chronological summary listing work performed for the period; and summary reports for each major task undertaken in connection with the specific scope of this report. Presented in chronological order for the referenced time period. Manually-assembled table summaries are included for: Labor and exposures by department; and labor and exposures by major activity

  12. ISP 22 OECD/NEA/CSNI International standard problem n. 22. Evaluation of post-test analyses

    International Nuclear Information System (INIS)

    1992-07-01

    The present report deals with the open re-evaluation of the originally double-blind CSNI International Standard Problem 22 based on the test SP-FW-02 performed in the SPES facility. The SPES apparatus is an experimental simulator of the Westinghouse PWR-PUN plant. The test SP-FW-02 (ISP22) simulates a complete loss of feedwater with delayed injection of auxiliary feedwater. The main parts of the report are: outline of the test facility and of the SP-FW-02 experiment; overview of pre-test activities; overview of input models used by post-test participants; evaluation of participant predictions; evaluation of qualitative and quantitative code accuracy of pre-test and post-test calculations

  13. Fuel safety criteria technical review - Results of OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria

    International Nuclear Information System (INIS)

    Hollasky, N.; Valtonen, K.; Hache, G.; Gross, H.; Bakker, K.; Recio, M.; Bart, G.; Zimmermann, M.; Van Doesburg, W.; Killeen, J.; Meyer, R.O.; Speis, T.

    2000-01-01

    With the advent of advanced fuel and core designs, the adoption of more aggressive operational modes and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a concern if safety margins have remained adequate. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel that was available at that time, mostly with unirradiated specimens. Verification was of course performed as designs progressed in later years, however mostly with the aim to be able to prove that these designs adequately complied with existing criteria, and not to establish new limits. The OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) was therefore given the mandate to technically review the existing fuel safety criteria, focusing on the 'new design' elements (new fuel and core design, cladding materials, manufacturing processes, high burnup, MOX, etc.) introduced by the industry. It should also identify if additional efforts may be required (experimental, analytical) to ensure that the basis for fuel safety criteria is adequate to address the relevant safety issues. In this report, fuel-related criteria are discussed without attempting to categorize them according to event type or risk significance. For each of these 20 criteria, we present a brief description of the criterion as it is used in several applications along with the rationale for having such a criterion. New design elements, such as different cladding materials, higher burnup, and the use of MOX fuels, can affect fuel-related margins and, in some cases, the criteria themselves. Some of the more important effects are mentioned in order to indicate whether the criteria need to be re-evaluated. The discussion may not cover all possible effects, but should be sufficient to identify those criteria that need to be addressed. A summary of these discussions is given in Section 7. As part

  14. OECD/NEA WGRisk CAPS on PSA for Advanced Reactors: a summary of questionnaires and answers report

    International Nuclear Information System (INIS)

    Ahn, K.I.; Han, S.J.; Han, S.H.; Yang, J.E.

    2012-01-01

    Main objectives of the WGRisk CAPS on the probabilistic safety analysis for advanced reactors which was approved by the OECD/NEA CSNI in June 2008, are to 1) characterize the ability of current PSA (Probability Safety Assessment) technology to address key questions regarding the development and licensing of advanced reactor designs; 2) characterize the potential value of advanced PSA methods and tools; and 3) develop recommendations to CSNI for any needed developments. For this purpose, the two following sub-tasks have been set up: -) A survey of participating countries regarding the state of PSA technologies for advanced reactors and -) Organization of an international workshop for detailed follow-up discussions related to the topic. In order to meet the objectives of the CAPS (CSNI Activity Proposal Sheet), the questionnaires to elicit the respondents' viewpoints had been distributed to the WGRisk member countries during the period of 2009 to 2010, and answers from the 12 countries (13 organizations) have been collected until February 2010. This paper summarizes the current status of the answers to the questionnaires and the international status and insights into PSA technologies for advanced reactors. (authors)

  15. Current Status and Open Issues of the 235U Evaluation. Summary Report of an IAEA Consultants’ Meeting

    International Nuclear Information System (INIS)

    Noguere, Gilles; Trkov, Andrej

    2016-08-01

    The objective of this consultancy meeting was to discuss the status of the 235 U neutron cross sections from the thermal to MeV energy ranges, to identify the main difficulties and to propose recommendations for improving the current experimental and evaluation works

  16. Research Project Control System (RPCS); research results utilization data as of 06/30/81. Status summary report

    International Nuclear Information System (INIS)

    1981-09-01

    The report on 'Research Results Utilization' provides status and control information concerning the utilization of research results in the regulatory policies and practices of the NRC. Research Information Letters (RILs) are prepared by RES to transmit research results to NRC user offices upon completion of a substantial, coherent and reasonably complete body of experimental and/or analytical research work. Section 3.0 of this report lists the RILs issued to date, together with an identification of the research program manager and the research program element which generated the RIL. The potential applicability of each RIL to the regulatory process is also identified, and comments from the cognizant RES and user office staff are summarized which relate to the expected impact of the reported RILs on the regulatory process

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

    International Nuclear Information System (INIS)

    2009-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-07-01

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

  19. ISP-31 OECD/NEA/CSNI International Standard Problem n.31. Cora-13 experiment on severe fuel damage. Comparison report

    International Nuclear Information System (INIS)

    Firnhaber, M.; Trambauer, K.; Hagen, S.; Hofmann, P.; Schanz, G.; Sepold, L.

    1993-07-01

    The severe fuel damage experiment CORA-13 has been offered as CSNI-International Standard Problem (ISP) No. 31. The out-of-pile experiment CORA-13 was executed in November 1990 at Kernforschungszentrum Karlsruhe. The major objectives of this experiment were to investigate the behavior of PWR fuel elements during early core degradation and fast cooldown due to refill. Measured quantities are boundary conditions, bundle temperatures, hydrogen generation and the final bundle configuration. The ISP was conducted as a blind exercise. Boundary conditions which could not be measured, but which are necessary for simplified test simulation (axial power profile, shroud insulation temperature, bundle refill flow) were estimated using ATHLET-CD. Results to the ISP were submitted by 9 participants using different versions of SCDAP/RELAP5, and codes such as FRAS-SFD, ICARE2, KESS-III, MELCOR. The thermal behavior up to significant oxidation has been predicted quite well by most of the codes. In general, the capability of the codes in calculating the main degradation phenomena has been clearly illustrated and weaknesses concerning the modelling of some degradation processes have been identified. Among the degradation phenomena involved in the test, the more severe limitations concern the UO 2 -ZrO 2 dissolution by molten Zr, the solubility limits in the resulting U-Zr-O mixture and the cladding failure by the molten mixture

  20. An analysis of the CSNI/GREST core concrete interaction chemical thermodynamic benchmark exercise using the MPEC2 computer code

    International Nuclear Information System (INIS)

    Muramatsu, Ken; Kondo, Yasuhiko; Uchida, Masaaki; Soda, Kunihisa

    1989-01-01

    Fission product (EP) release during a core concrete interaction (CCI) is an important factor of the uncertainty associated with a source term estimation for an LWR severe accident. An analysis was made on the CCI Chemical Thermodynamic Benchmark Exercise organized by OECD/NEA/CSNI Group of Experts on Source Terms (GREST) for investigating the uncertainty in thermodynamic modeling for CCI. The benchmark exercise was to calculate the equilibrium FP vapor pressure for given system of temperature, pressure, and debris composition. The benchmark consisted of two parts, A and B. Part A was a simplified problem intended to test the numerical techniques. In part B, the participants were requested to use their own best estimate thermodynamic data base to examine the variability of the results due to the difference in thermodynamic data base. JAERI participated in this benchmark exercise with use of the MPEC2 code. Chemical thermodynamic data base needed for analysis of Part B was taken from the VENESA code. This report describes the computer code used, inputs to the code, and results from the calculation by JAERI. The present calculation indicates that the FP vapor pressure depends strongly on temperature and Oxygen potential in core debris and the pattern of dependency may be different for different FP elements. (author)

  1. Proceedings of the CSNI workshop on International Standard Problem 48 - Analysis of 1:4-scale prestressed concrete containment vessel model under severe accident conditions

    International Nuclear Information System (INIS)

    2005-01-01

    At the CSNI meeting in June 2002, the proposal for an International Standard Problem on containment integrity (ISP 48) based on the NRC/NUPEC/Sandia test was approved. Objectives were to extend the understanding of capacities of actual containment structures based on results of the recent PCCV Model test and other previous research. The ISP was sponsored by the USNRC, and results had been made available thanks to NUPEC and to the USNRC. Sandia National Laboratory was contracted to manage the technical aspects of the ISP. At the end of the ISP48, a workshop was organized in Lyon, France on April 6-7, 2005 hosted by Electricite de France. Its overall objective was to present results obtained by participants in the ISP 48 and to assess the current practices and the state of the art with respect to the calculation of concrete structures under severe accident conditions. Experience from other areas in civil engineering related to the modelling of complex structures was greatly beneficial to all. Information obtained as a result of this assessment were utilized to develop a consensus on these calculations and identify issues or 'gaps' in the present knowledge for the primary purpose of formulating and prioritizing research needs on this topic. The ISP48 exercise was published in the report referenced NEA/CSNI/R(2005)5 in 3 volumes. Volume 1 contains the synthesis of the exercise; Volumes 2 and 3 contain individual contributions of participating organizations. The CSNI Working Group on the Integrity and Ageing and in particular its sub-group on the behaviour of concrete structures has produced extensive material over the last few years. The complete list of references is given in this document. These proceedings gather the papers and presentations given by the participants at the Lyon workshop

  2. Mergeable summaries

    DEFF Research Database (Denmark)

    Agarwal, Pankaj K.; Graham, Graham; Huang, Zengfeng

    2013-01-01

    We study the mergeability of data summaries. Informally speaking, mergeability requires that, given two summaries on two datasets, there is a way to merge the two summaries into a single summary on the two datasets combined together, while preserving the error and size guarantees. This property m...

  3. CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (FALSIRE II)

    Energy Technology Data Exchange (ETDEWEB)

    Bass, B.R.; Pugh, C.E.; Keeney, J. [Oak Ridge National Lab., TN (United States); Schulz, H.; Sievers, J. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Gemany)

    1996-11-01

    A summary of Phase II of the Project for FALSIRE is presented. FALSIRE was created by the Fracture Assessment Group (FAG) of the OECD/NEA`s Committee on the Safety of Nuclear Installations (CNSI) Principal Working Group No. 3. FALSIRE I in 1988 assessed fracture methods through interpretive analyses of 6 large-scale fracture experiments in reactor pressure vessel (RPV) steels under pressurized- thermal-shock (PTS) loading. In FALSIRE II, experiments examined cleavage fracture in RPV steels for a wide range of materials, crack geometries, and constraint and loading conditions. The cracks were relatively shallow, in the transition temperature region. Included were cracks showing either unstable extension or two stages of extensions under transient thermal and mechanical loads. Crack initiation was also investigated in connection with clad surfaces and with biaxial load. Within FALSIRE II, comparative assessments were performed for 7 reference fracture experiments based on 45 analyses received from 22 organizations representing 12 countries. Temperature distributions in thermal shock loaded samples were approximated with high accuracy and small scatter bands. Structural response was predicted reasonably well; discrepancies could usually be traced to the assumed material models and approximated material properties. Almost all participants elected to use the finite element method.

  4. Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Diercks, D.R. [Argonne National Lab., IL (United States)

    1997-02-01

    The objective of the workshop was to provide a working forum for the exchange of information by contributing experts on current issues related to PWR steam generator tube integrity. One hundred persons from 15 countries attended the workshop, including 36 from regulatory and nuclear policy agencies, 28 from research and development laboratories, 18 from nuclear vendors and consulting firms, and 18 from electrical utilities. The workshop opened with a plenary session; the first part of the session covered international steam generator regulatory practices and issues, featuring speakers from regulatory bodies in Belgium, France, Japan, Spain, and the US. In Part 2 of the plenary session, comprehensive technical overviews on steam generator tubing degradation, inspection, and integrity were presented by authorities in these fields from the US, France, and Belgium. Parallel working sessions on the second and third days of the workshop then developed findings and recommendations in the areas of (1) tubing degradation, (2) tubing inspection, (3) tubing integrity, (4) preventative and corrective measures, and (5) operational aspects and risk analysis. On the final day of the workshop, the working-session facilitators presented summaries of their sessions to the workshop attendees. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  5. Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants

    International Nuclear Information System (INIS)

    Diercks, D.R.

    1997-02-01

    The objective of the workshop was to provide a working forum for the exchange of information by contributing experts on current issues related to PWR steam generator tube integrity. One hundred persons from 15 countries attended the workshop, including 36 from regulatory and nuclear policy agencies, 28 from research and development laboratories, 18 from nuclear vendors and consulting firms, and 18 from electrical utilities. The workshop opened with a plenary session; the first part of the session covered international steam generator regulatory practices and issues, featuring speakers from regulatory bodies in Belgium, France, Japan, Spain, and the US. In Part 2 of the plenary session, comprehensive technical overviews on steam generator tubing degradation, inspection, and integrity were presented by authorities in these fields from the US, France, and Belgium. Parallel working sessions on the second and third days of the workshop then developed findings and recommendations in the areas of (1) tubing degradation, (2) tubing inspection, (3) tubing integrity, (4) preventative and corrective measures, and (5) operational aspects and risk analysis. On the final day of the workshop, the working-session facilitators presented summaries of their sessions to the workshop attendees. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  6. CSNI Project for Fracture Analyses of Large-Scale International Reference Experiments (FALSIRE II)

    International Nuclear Information System (INIS)

    Bass, B.R.; Pugh, C.E.; Keeney, J.; Schulz, H.; Sievers, J.

    1996-11-01

    A summary of Phase II of the Project for FALSIRE is presented. FALSIRE was created by the Fracture Assessment Group (FAG) of the OECD/NEA's Committee on the Safety of Nuclear Installations (CNSI) Principal Working Group No. 3. FALSIRE I in 1988 assessed fracture methods through interpretive analyses of 6 large-scale fracture experiments in reactor pressure vessel (RPV) steels under pressurized- thermal-shock (PTS) loading. In FALSIRE II, experiments examined cleavage fracture in RPV steels for a wide range of materials, crack geometries, and constraint and loading conditions. The cracks were relatively shallow, in the transition temperature region. Included were cracks showing either unstable extension or two stages of extensions under transient thermal and mechanical loads. Crack initiation was also investigated in connection with clad surfaces and with biaxial load. Within FALSIRE II, comparative assessments were performed for 7 reference fracture experiments based on 45 analyses received from 22 organizations representing 12 countries. Temperature distributions in thermal shock loaded samples were approximated with high accuracy and small scatter bands. Structural response was predicted reasonably well; discrepancies could usually be traced to the assumed material models and approximated material properties. Almost all participants elected to use the finite element method

  7. The contribution of the CSNI Principal Working Group on Confinement of Accidental Radioactive Releases to the technical consensus and spreading of knowledge on severe accidents

    International Nuclear Information System (INIS)

    De Boeck, B.; Royen, J.

    1999-01-01

    The Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations (CSNI) is an international committee made up of scientists and engineers. It was set up 1973 to develop and co-ordinate the activities of the NEA concerning the technical aspects of the design, construction and operation of nuclear installations insofar as they affect the safety of such installations. The Committee's purpose is to foster international cooperation in nuclear safety amongst the Member countries. Five Principal Working Groups (PWG) operate under the leadership of CSNI. PWG4 is named 'Confinement of Accidental Radioactive Releases' and its main activities are State of the Art Reports, International Standard Problem exercises, Specialist Meetings and Technical Opinion Papers. Together with other groups of experts involved in severe accident work, PWG4 has strongly contributed to the understanding of phenomena and the development of the knowledge base in that area, to the resolution of technical issues, and to the dissemination of the results. Taking examples from the products of the work of PWG4, the paper shows how this working group fosters international co-operation in the area of severe accidents and their management, and contributes to the development of a technical consensus. (author)

  8. Biofuels: Project summaries

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The US DOE, through the Biofuels Systems Division (BSD) is addressing the issues surrounding US vulnerability to petroleum supply. The BSD goal is to develop technologies that are competitive with fossil fuels, in both cost and environmental performance, by the end of the decade. This document contains summaries of ongoing research sponsored by the DOE BSD. A summary sheet is presented for each project funded or in existence during FY 1993. Each summary sheet contains and account of project funding, objectives, accomplishments and current status, and significant publications.

  9. Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety

    International Nuclear Information System (INIS)

    Guentay, S.

    1996-12-01

    The 4. OECD workshop on the chemistry of iodine in reactor safety was held in Wuerenlingen, Switzerland from June 10th to 12th, 1996. It was organised in collaboration with the Laboratory for Safety and Accident Research of the Paul Scherrer Institute. About seventy experts from fourteen OECD member countries attended the meeting, as well as experts from Latvia and the Commission of the European Communities. Thirty-four papers were presented in five sessions on various aspects of national and international programmes, integral and intermediate-scale experiments, experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies and safety applications. Throughout the meeting, emphasis was placed on detailed and open discussions. The purpose of the workshop was to exchange information on the iodine chemistry and other important fission products relevant to reactor safety, to discuss the status of the open issues identified during the previous workshop held in 1991, to define reactor safety issues and to discuss developments and future plans. (author) figs., tabs., refs

  10. Proceedings of the 4. CSNI workshop on the chemistry of iodine in reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Guentay, S [ed.; Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-12-01

    The 4. OECD workshop on the chemistry of iodine in reactor safety was held in Wuerenlingen, Switzerland from June 10th to 12th, 1996. It was organised in collaboration with the Laboratory for Safety and Accident Research of the Paul Scherrer Institute. About seventy experts from fourteen OECD member countries attended the meeting, as well as experts from Latvia and the Commission of the European Communities. Thirty-four papers were presented in five sessions on various aspects of national and international programmes, integral and intermediate-scale experiments, experimental homogeneous phase chemistry, surface processes, thermodynamic and kinetic studies and safety applications. Throughout the meeting, emphasis was placed on detailed and open discussions. The purpose of the workshop was to exchange information on the iodine chemistry and other important fission products relevant to reactor safety, to discuss the status of the open issues identified during the previous workshop held in 1991, to define reactor safety issues and to discuss developments and future plans. (author) figs., tabs., refs.

  11. Summaries and future projections

    International Nuclear Information System (INIS)

    Egelstaff, P.A.

    1989-01-01

    In this paper the author gives a brief summary of this meeting. He discusses the status at the current neutron sources and future sources. The current problems with targets, moderators, performance of storage rings and shields are briefly mentioned. Finally, he speculates on the prospects of neutron sources for the future and gives his version of the ultimate source

  12. Proceedings of the Joint IAEA/CSNI Specialists` Meeting on Fracture Mechanics Verification by Large-Scale Testing held at Pollard Auditorium, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Pugh, C.E.; Bass, B.R.; Keeney, J.A. [comps.] [Oak Ridge National Lab., TN (United States)

    1993-10-01

    This report contains 40 papers that were presented at the Joint IAEA/CSNI Specialists` Meeting Fracture Mechanics Verification by Large-Scale Testing held at the Pollard Auditorium, Oak Ridge, Tennessee, during the week of October 26--29, 1992. The papers are printed in the order of their presentation in each session and describe recent large-scale fracture (brittle and/or ductile) experiments, analyses of these experiments, and comparisons between predictions and experimental results. The goal of the meeting was to allow international experts to examine the fracture behavior of various materials and structures under conditions relevant to nuclear reactor components and operating environments. The emphasis was on the ability of various fracture models and analysis methods to predict the wide range of experimental data now available. The individual papers have been cataloged separately.

  13. CSNI group of experts on statistics and decision theories applicable to rare events. Final report may 1978 summary for presentation to the Garching meeting

    International Nuclear Information System (INIS)

    1978-01-01

    The essential features of statistical techniques which are most useful for rare events may be grouped around four poles corresponding to four kinds of problems: decomposition of events and combination of probabilities; extrapolation (extreme values); Bayesian methods (and their relation with biased methods); dependencies (common modes). The main shadows, for the statistician point of view, are related to the confidence which can be attached to the data. Concerning rare events, much remains to be done in order to clarify the role and limits of efficiency of statistical methods. Recommendations are given: methods assembled by the group should be applied to different types of rare events encountered in nuclear safety; the necessary taking into account of the balance between the socio-economic advantages and potential drawbacks of nuclear technology

  14. Algae as a Feedstock for Biofuels. An Assessment of the Current Status and Potential for Algal Biofuels Production. Joint Summary report of IEA-AMF Annex XXXIV-2 and IEA Bioenergy Task 39

    Energy Technology Data Exchange (ETDEWEB)

    O' Conner, D. [S and T2 Consultants, Inc. (Canada)

    2011-09-15

    In 2010, the IEA Advanced Motor Fuels Implementing Agreement and the IEA Bioenergy Task 39 both commissioned reports on the status and potential opportunities for Algal Biofuels. While there were substantial similarities in the findings of the two reports, each report provides unique perspectives on different aspects of the technology and the opportunities. This summary draws on both of those reports. The Task 39 report (Bioenergy Algal Biofuels.pdf) was authored by Al Darzins and Philip Pienkos (NREL, US) and Les Edye (BioIndustry Partners, Australia). The IEA AMF report was prepared by Karen Sikes and Ralph McGill (Sentech, Inc. US) and Martijn Van Walwijk (Independent Researcher).

  15. CSNI ISP 34 (Falcon)

    International Nuclear Information System (INIS)

    Bennett, P.J.; Bowsher, B.R.; Williams, D.A.

    1992-04-01

    The objective of International Standard Problem (ISP) number 34 is to test computer codes designed to follow the transport and deposition, in both the primary circuit and containment building, of fission products and bulk-reactor materials aerosols released from degrading fuel in a severe reactor accident. A meeting was held to discuss the objectives and timescales of the ISP, to define the modelling procedures, and to agree the specifications of the tests. (UK)

  16. Research Summaries

    Science.gov (United States)

    Brock, Stephen E., Ed.

    2011-01-01

    This article presents summaries of three articles relevant to school crisis response: (1) "Factors Contributing to Posttraumatic Growth," summarized by Steve DeBlois; (2) "Psychological Debriefing in Cross-Cultural Contexts" (Stacey Rice); and (3) "Brain Abnormalities in PTSD" (Sunny Windingstad). The first summary reports the findings of a…

  17. Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor coolant system and systems decontamination. Summary status report. Volume 1

    International Nuclear Information System (INIS)

    Doerge, D.H.; Miller, R.L.; Scotti, K.S.

    1986-05-01

    This document summarizes information relating to the decontamination and restoration of the Three Mile Island Unit 2 reactor coolant system and other plant systems. Data have been collected from activity reports, reactor containment entry records, and other sources and entered in a computerized data system which permits extraction/manipulation of specific data which can be used in planning for recovery from a loss of coolant event similar to that experienced by the Three Mile Island Unit 2 on March 28, 1979. This report contains a summary of radiation exposures, manpower, and time spent in radiation areas during the referenced period. Support activities conducted outside of radiation areas are not included. Computer reports included are: A chronological listing of all activities related to decomtamination and restoration of the reactor coolant system and other plant systems for the period of April 5, 1979, through December 19, 1984; a summary of labor and exposures by department for the same time period; and summary reports for each major task undertaken in connection with this specific work scope during the referenced time period

  18. Executive summary

    International Nuclear Information System (INIS)

    2010-01-01

    The special session on Fuel cycle strategies and transition scenarios comprised three invited papers and five oral presentations: INL (USA) was invited to present US activities on fuel cycle transition scenarios; JAEA (Japan) presented the current status of the Japanese nuclear fuel cycle; CEA and EDF (France) gave a presentation on the French fuel cycle strategy and transition scenarios; CEA and INL presented the latest outcomes from the NEA activity on fuel cycle transition scenarios and the European approach; JAEA reported on the results of global scenarios for fast reactor deployment; AECL (Canada) discussed actinide transmutation in Candu reactors, which may efficiently transmute TRU; Materials assessments, which could be used in advanced nuclear fuel cycles from a safeguard perspective, were presented by LANL (USA); The technical session about Impact on P and T on waste management and geological disposal comprised one invited paper and two oral presentations: JAEA presented on the concept of waste management and geological disposal incorporating P and T technology; CIEMAT (Spain) gave a summary of the RED-IMPACT study, which is the study of the impact of P and T on the HLW management programme of the EC; Chalmers University(Sweden) presented an estimation of maximum permissible step losses in P and T processing; The technical session about Progress in transmutation fuels and targets comprised one invited paper and seven oral presentations: The invited talk of the session was given by ITU (EC), on advanced fuel fabrication processes for transmutation; INL presented the development status of transuranic-bearing metal fuels in the USA; CEA summarised European projects on design, development and qualification of advanced fuels for an industrial ADS prototype; The Japanese study of the microstructural evolution and Am migration behaviour in Am-containing MOX fuels at the initial stage of irradiation was presented by JAEA discussed Japanese status on the

  19. Meteorological Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Multi-year summaries of one or more meteorological elements at a station or in a state. Primarily includes Form 1078, a United States Weather Bureau form designed...

  20. Survey Summary

    Data.gov (United States)

    U.S. Department of Health & Human Services — Nursing home summary information for the Health and Fire Safety Inspections currently listed on Nursing Home Compare, including dates of the three most recent...

  1. Proceedings of the CSNI/IAEA workshop on maintaining oversight of licensee safety culture - methods and approaches. Held from 21 to 23 May 2007 in Chester, UK

    International Nuclear Information System (INIS)

    2008-01-01

    Weaknesses in safety culture have contributed to a number of high profile events in the nuclear and other high hazard sectors. The nuclear industry also faces challenges such as deregulation, out-sourcing, phase-out, upgrading and new builds which, if not properly planned and implemented, have the potential to make a negative impact on safety culture. These factors have fostered an increasing awareness of the need for licensees to develop a strong safety culture to support successful and sustainable nuclear safety performance. Regulatory bodies are taking a growing interest in this issue, and several are actively working to develop and implement approaches to maintaining oversight of licensee safety culture. However, these approaches are not yet well-established, and it was considered prudent to share experiences and developing methodologies in order to disseminate good practices and avoid potential pitfalls. An NEA/CSNI/IAEA workshop was therefore held in Chester, UK, in May 2007 in order to explore and discuss the approaches that different regulatory bodies are taking to maintain oversight of licensee safety culture. It was organised by the UK Nuclear Installations Inspectorate on behalf of the CSNI's Working Group on Human and Organisational Factors. This report sets out the findings of the Chester workshop. The workshop was attended by 50 representatives of nuclear regulatory bodies in 20 countries plus IAEA, WANO, EU and NEA. It included both specialists in safety culture and site/resident inspectors, whose attendance was facilitated by the CNRA's Working Group on Inspection Practices. The workshop comprised structured discussion sessions, in which a set of issues were explored by small discussion groups and then discussed in plenary, complemented by short presentations on national regulatory positions. The workshop revealed a broad consensus that nuclear regulators should have processes in place to maintain oversight of licensee safety culture. The approaches

  2. 78 FR 17746 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-03-22

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... information in the summary is intended to affect the legal status of the petition or its final disposition...

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    Science.gov (United States)

    2013-08-28

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    Science.gov (United States)

    2010-04-15

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    2013-08-01

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    Science.gov (United States)

    2010-09-29

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    Science.gov (United States)

    2012-01-13

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    Science.gov (United States)

    2013-12-09

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  9. 78 FR 13746 - Petition for Exemption; Summary of Petition Received

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    2013-02-28

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    Science.gov (United States)

    2011-07-07

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    2013-08-01

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    2013-01-07

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    Science.gov (United States)

    2011-03-17

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    2013-06-17

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    Science.gov (United States)

    2013-11-07

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    Science.gov (United States)

    2013-07-02

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  17. Application of the Relap5-3D to phase 1 and 3 of the OECD-CSNI/NSC PWR MSLB benchmark related to TMI-1

    International Nuclear Information System (INIS)

    D'Auria, F.; Galassi, G.; Spadoni, A.; Hassan, Y.

    2001-01-01

    The Relap5-3D, the latest in the series of the Relap5 code, distinguishes from the previous versions by the fully integrated, multi-dimensional thermalhydraulic and kinetic modeling capability. It has been applied to Phase I and III of OECD-CSNI/ NSC PWR MSLB Benchmark adopting the same thermalhydraulic input deck already used with Relap5/Parcs and Relap5/Quabbox coupled codes during the previous MSLB analysis. The OECD jointly with the US NRC proposed the PWR MSLB Benchmark in order to gather a common understanding about the coupling between thermal hydraulics and neutronics, and evaluating the behavior of this transient with different coupled codes, giving emphasis to the 3-D modeling. This paper deals with the application of Relap5-3D code to phase I and III of the PWR MSLB Benchmark. The Relap5-3D is a thermal hydraulics-neutronics internally coupled code, the thermal hydraulics module is the INEEL version of Relap and the neutronics module is derived from NESTLE multi-dimension kinetics code. (author)

  18. Application of NEA/CSNI standard problem 3 (blowdown and flow reversal in the IETA-1 rig) to the validation of the RELAP-UK Mk IV code

    International Nuclear Information System (INIS)

    Bryce, W.M.

    1977-10-01

    NEA/CSNI Standard Problem 3 consists of the modelling of an experiment on the IETI-1 rig, in which there is initially flow upwards through a feeder, heated section and riser. The inlet and outlet are then closed and a breach opened at the bottom so that the flow reverses and the rig depressurises. Calculations of this problem by many countries using several computer codes have been reported and show a wide spread of results. The purpose of the study reported here was the following. First, to show the sensitivity of the calculation of Standard Problem 3. Second, to perform an ab initio best estimate calculation using the RELAP-UK Mark IV code with the standard recommended options, and third, to use the results of the sensitivity study to show where tuning of the RELAP-UK Mark IV recommended model options was required. This study has shown that the calculation of Standard Problem 3 is sensitive to model assumptions and that the use of the loss-of-coolant accident code RELAP-UK Mk IV with the standard recommended model options predicts the experimental results very well over most of the transient. (U.K.)

  19. Research Summaries

    Science.gov (United States)

    Brock, Stephen E., Ed.

    2010-01-01

    This column features summaries of research articles from 3 recent crisis management publications. The first, "School Shootings and Counselor Leadership: Four Lessons from the Field" summarized by Kristi Fenning, was conducted as the result of the increased demand for trained crisis personnel on school campuses. Survey participants were…

  20. Conference summaries

    International Nuclear Information System (INIS)

    1986-01-01

    This volume contains conference summaries of the international conference on radioactive waste management of the Canadian Nuclear Society. Topics of discussion include: storage and disposal; hydrogeology and geochemistry; transportation; buffers and backfill; public attitudes; tailings; site investigations and geomechanics; concrete; economics; licensing; matrix materials and container design; durability of fuel; biosphere modelling; radioactive waste processing; and, future options

  1. Executive summary

    NARCIS (Netherlands)

    van Nimwegen, N.; van Nimwegen, N.; van der Erf, R.

    2009-01-01

    The Demography Monitor 2008 gives a concise overview of current demographic trends and related developments in education, the labour market and retirement for the European Union and some other countries. This executive summary highlights the major findings of the Demography Monitor 2008 and further

  2. Workshop on iodine aspects of severe accident management. Summary and conclusions

    International Nuclear Information System (INIS)

    2000-03-01

    Following a recommendation of the OECD Workshop on the Chemistry of Iodine in Reactor Safety held in Wuerenlingen (Switzerland) in June 1996 [Summary and Conclusions of the Workshop, Report NEA/CSNI/R(96)7], the CSNI decided to sponsor a Workshop on Iodine Aspects of Severe Accident Management, and their planned or effective implementation. The starting point for this conclusion was the realization that the consolidation of the accumulated iodine chemistry knowledge into accident management guidelines and procedures remained, to a large extent, to be done. The purpose of the meeting was therefore to help build a bridge between iodine research and the application of its results in nuclear power plants, with particular emphasis on severe accident management. Specifically, the Workshop was expected to answer the following questions: - what is the role of iodine in severe accident management? - what are the needs of the utilities? - how can research fulfill these needs? The Workshop was organized in Vantaa (Helsinki), Finland, from 18 to 20 May 1999, in collaboration with Fortum Engineering Ltd. It was attended by forty-six specialists representing fifteen Member countries and the European Commission. Twenty-eight papers were presented. These included four utility papers, representing the views of Electricite de France (EDF), Teollisuuden Voima Oy and Fortum Engineering Ltd (Finland), the Nuclear Energy Institute (USA), and Japanese utilities. The papers were presented in five sessions: - iodine speciation; - organic compound control; - iodine control; - modeling; - iodine management; A sixth session was devoted to a general discussion on iodine management under severe accident conditions. This report summarizes the content of the papers and the conclusions of the workshop

  3. Conference Summary

    International Nuclear Information System (INIS)

    Tinkham, M.

    1991-01-01

    This summary will begin with short remarks, trying to recall some of the spirit of the presentations of each of the speakers during the first day, with no attempt at detail or completeness, given the need for a 20:1 compression relative to the original talk. The author hopes these idiosyncratic recollections do not infuriate the speakers too much. Since the speakers on the second day presented such interlocking topics, he simply tries to present some sort of consensus report, to which he adds some comments of his own. The two talks preceding this Summary on the final day dealt with the prospects for applications; since he had no chance to attempt to prepare a proper report on these, he says only a few words about those presentations

  4. Conference summaries

    International Nuclear Information System (INIS)

    1987-01-01

    This volume contains summaries of 28 papers presented at the 27. conference of the Canadian Nuclear Association. These papers discuss the general situation of the Canadian nuclear industry and the CANDU reactor; dialogue with the public; the International Atomic Energy Agency; and economic goals and operating lessons. It also contains summaries of 70 papers presented at the 8. conference of the Canadian Nuclear Society, which discuss plant life extension; safety and the environment; reactor physics; thermalhydraulics; risk assessment; the CANDU spacer location and repositioning project; CANDU operations; safety research after Chernobyl; fuel channels; and nuclear technology developments. The individual papers are also available in INIS-mf--13673 (CNA), and INIS-mf--12909 (CNS). (L.L.)

  5. Good practices for user effect reduction - Status Report

    International Nuclear Information System (INIS)

    Ashley, R.; El-Shanawany, M.; Eltawila, F.; D'Auria, F.

    1999-01-01

    User effect has been identified in previous CSNI activities since 1991. The present report has as objectives to outline the consideration given to the user effect problem by various concerned organisations, and to present a consensus about recommended practices for user effect reduction. A survey of relevant literature is summarised, together with the answers collected through the Task Group on Thermal Hydraulics Applications members about characteristics of overall safety analysis process including validation, safety culture, staffing levels, staff competencies and responsibilities, on the job training, required documentation, and quality assurance. An outline is given of the adequacy demonstration process to be undertaken by a code user, when the code is being used in new situations for which assessment has not been performed by the code developers or by other user groups. A list of fifteen recommendations is set up, dealing with organisation and responsibilities, build up of competence, checks and assessments, and uncertainties. In summary: this report provides a review and discussion of earlier work relevant to the user effect on the results of system codes transient analyses; responses to a questionnaire proposed by the OECD/CSNI Task Group on Thermal-Hydraulic Applications are considered, together with results of activities started in 1991 in the same CSNI context. Some recommendations aim at reducing the user effect. These recommendations are generally based on good common practices adopted by organisations involved in safety analyses. Some of the reasons for the user effect are mentioned in the report. Code deficiencies may be to blame in a number of cases; however, here the attention is focussed on the application of the code and not on improving of the code models. A critical aspect is the internal organisation of institutions performing system code applications; the engagement of permanent and hired staff has a role in the quality and reliability of

  6. Advanced thermal-hydraulic and neutronic codes: current and future applications. Summary and conclusions

    International Nuclear Information System (INIS)

    2001-05-01

    An OECD Workshop on Advanced Thermal-Hydraulic and Neutronic Codes Applications was held from 10 to 13 April 2000, in Barcelona, Spain, sponsored by the Committee on the Safety of Nuclear Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). It was organised in collaboration with the Spanish Nuclear Safety Council (CSN) and hosted by CSN and the Polytechnic University of Catalonia (UPC) in collaboration with the Spanish Electricity Association (UNESA). The objectives of the Workshop were to review the developments since the previous CSNI Workshop held in Annapolis [NEA/CSNI/ R(97)4; NUREG/CP-0159], to analyse the present status of maturity and remnant needs of thermal-hydraulic (TH) and neutronic system codes and methods, and finally to evaluate the role of these tools in the evolving regulatory environment. The Technical Sessions and Discussion Sessions covered the following topics: - Regulatory requirements for Best-Estimate (BE) code assessment; - Application of TH and neutronic codes for current safety issues; - Uncertainty analysis; - Needs for integral plant transient and accident analysis; - Simulators and fast running codes; - Advances in next generation TH and neutronic codes; - Future trends in physical modeling; - Long term plans for development of advanced codes. The focus of the Workshop was on system codes. An incursion was made, however, in the new field of applying Computational Fluid Dynamic (CFD) codes to nuclear safety analysis. As a general conclusion, the Barcelona Workshop can be considered representative of the progress towards the targets marked at Annapolis almost four years ago. The Annapolis Workshop had identified areas where further development and specific improvements were needed, among them: multi-field models, transport of interfacial area, 2D and 3D thermal-hydraulics, 3-D neutronics consistent with level of details of thermal-hydraulics. Recommendations issued at Annapolis included: developing small pilot/test codes for

  7. Summary talk

    International Nuclear Information System (INIS)

    Harari, H.

    1978-10-01

    A general overview is given in this high energy physics conference summary. Quantum chromodynamics as a theory of strong interactions and studied by experimental tests, SU(2) x U(1) theory of weak and electromagnetic interactions and its experimental tests, weak interactions above 100 GeV, simple unification of weak and electromagnetic interactions, and the grand and the ultimate unifications with extended supergravity are discussed. 28 references

  8. Summary talk

    International Nuclear Information System (INIS)

    Johnson, R.C.

    1981-01-01

    In this summary talk some implications of points raised during the Daresbury Study Weekend on heavy-ion reactions are examined and discussed in particular those concerning polarized heavy ions, the connection between analyzing powers and dynamics, transfer reactions, total reaction cross section measurements with polarized beams, and the implications of break-up reaction results for theories of nuclear reactions involving loosely bound projectiles. (U.K.)

  9. Conference summaries

    International Nuclear Information System (INIS)

    1991-01-01

    This volume contains conference summaries for the 31. annual conference of the Canadian Nuclear Association and the 12. annual conference of the Canadian Nuclear Society. Topics of discussion include: reactor physics; thermalhydraulics; industrial irradiation; computer applications; fuel channel analysis; small reactors; severe accidents; fuel behaviour under accident conditions; reactor components, safety related computer software; nuclear fuel management; fuel behaviour and performance; reactor safety; reactor engineering; nuclear waste management; and, uranium mining and processing

  10. Motivation, description, and summary status of geomechanical and geochemical modeling studies in Task D of the International DECOVALEX-THMC Project

    International Nuclear Information System (INIS)

    Birkholzer, J.T.; Barr, D.; Rutqvist, J.; Sonnenthal, E.

    2005-01-01

    The DECOVALEX project is an international cooperative project initiated by SKI, the Swedish Nuclear Power Inspectorate, with participation of about 10 international organizations. The general goal of this project is to encourage multidisciplinary interactive and cooperative research on modeling coupled thermo-hydro-mechanical-chemical (THMC) processes in geologic formations in support of the performance assessment for underground storage of radioactive waste. One of the research tasks, initiated in 2004 by the U.S. Department of Energy (DOE), addresses the long-term impact of geomechanical and geochemical processes on the flow conditions near waste emplacement tunnels. Within this task, four international research teams conduct predictive analysis of the coupled processes in two generic repositories, using multiple approaches and different computer codes. Below, we give an overview of the research task and report its current status

  11. Status of implementation and organization of cancer screening in The European Union Member States-Summary results from the second European screening report.

    Science.gov (United States)

    Basu, Partha; Ponti, Antonio; Anttila, Ahti; Ronco, Guglielmo; Senore, Carlo; Vale, Diama Bhadra; Segnan, Nereo; Tomatis, Mariano; Soerjomataram, Isabelle; Primic Žakelj, Maja; Dillner, Joakim; Elfström, Klara Miriam; Lönnberg, Stefan; Sankaranarayanan, Rengaswamy

    2018-01-01

    The second report on the implementation status of cancer screening in European Union (EU) was published in 2017. The report described the implementation status, protocols and organization (updated till 2016) and invitation coverage (for index year 2013) of breast, cervical and colorectal cancer screening in the EU. Experts in screening programme monitoring (N = 80) from the EU Member States having access to requisite information in their respective countries provided data on breast, cervical and colorectal cancer screening through online questionnaires. Data was collected for screening performed in the framework of publicly mandated programmes only. Filled in questionnaires were received from 26 Member States for all three sites and from one Member State for breast cancer only. Substantial improvement in screening implementation using population-based approach was documented. Among the age-eligible women, 94.7% were residents of Member States implementing or planning population-based breast cancer screening in 2016, compared to 91.6% in 2007. The corresponding figures for cervical cancer screening were 72.3 and 51.3% in 2016 and 2007, respectively. Most significant improvement was documented for colorectal cancer screening with roll-out ongoing or completed in 17 Member States in 2016, compared to only five in 2007. So the access to population-based screening increased to 72.4% of the age-eligible populations in 2016 as opposed to only 42.6% in 2007. The invitation coverage was highly variable, ranging from 0.2-111% for breast cancer, 7.6-105% for cervical cancer and 1.8-127% for colorectal cancer in the target populations. In spite of the considerable progress, much work remains to be done to achieve optimal effectiveness. Continued monitoring, regular feedbacks and periodic reporting are needed to ensure the desired impacts of the programmes. © 2017 UICC.

  12. FALSIRE Phase II. CSNI project for Fracture Analyses of Large-Scale International Reference Experiments (Phase II). Comparison report

    International Nuclear Information System (INIS)

    Sievers, J.; Schulz, H.; Bass, R.; Pugh, C.; Keeney, J.

    1996-11-01

    A summary of Phase II of the Project for Fracture Analysis of Large-Scale International Reference Experiments (FALSIRE) is presented. A FALSIRE II Workshop focused on analyses of reference fracture experiments. More than 30 participants representing 22 organizations from 12 countries took part in the workshop. Final results for 45 analyses of the reference experiments were received from the participating analysts. For each experiment, analysis results provided estimates of variables that include temperature, crack-mouth-opening displacement, stress, strain, and applied K and J values. The data were sent electronically to the Organizing Committee, who assembled the results into a comparative data base using a special-purpose computer program. A comparative assessment and discussion of the analysis results are presented in the report. Generally, structural responses of the test specimens were predicted with tolerable scatter bands. (orig./DG)

  13. Current State of Dental Education: Executive Summary.

    Science.gov (United States)

    Formicola, Allan J

    2017-08-01

    This executive summary for Section 1 of the "Advancing Dental Education in the 21 st Century" project provides a composite picture of information from 12 background articles on the current state of dental education in the United States. The summary includes the following topics: the current status of the dental curriculum, the implications of student debt and dental school finances, the expansion of enrollment, student diversity, pre- and postdoctoral education, safety net status of dental school clinics, and trends in faculty.

  14. Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

    On 18 May 2001, the Finnish Parliament ratified the Decision in Principle on the final disposal facility for spent nuclear fuel at Olkiluoto, within the municipality of Eurajoki. The Municipality Council and the government has made positive decisions earlier, at the end of 2000, and in compliance with the Nuclear Energy Act, Parliament's ratification was then required. The decision is valid for the spent fuel generated by the existing Finnish nuclear power plants and means that the construction of the final disposal facility is considered to be in line with the overall good of society. Earlier steps included, amongst others, the approval of the technical project by the Safety Authority. Future steps include construction of an underground rock characterisation facility, ONKALO (2003-2004), and application for separate construction and operating licences for the final disposal facility (from about 2010). How did this political and societal decision come about? The FSC Workshop provided the opportunity to present the history leading up to the Decision in Principle (DiP), and to examine future perspectives with an emphasis on stakeholder involvement. This Executive Summary gives an overview of the presentations and discussions that took place at the workshop. It presents, for the most part, a factual account of the individual presentations and of the discussions that took place. It relies importantly on the notes that were taken at the meeting. Most materials are elaborated upon in a fuller way in the texts that the various speakers and session moderators contributed for these proceedings. The structure of the Executive Summary follows the structure of the workshop itself. Complementary to this Summary and also provided with this document, is a NEA Secretariat's perspective aiming to place the results of all discussions, feedback and site visit into an international perspective. (authors)

  15. Executive summary

    International Nuclear Information System (INIS)

    1981-02-01

    This paper is an 'executive summary' of work undertaken to review proposals for transport, handling and emplacement of high level radioactive wastes in an underground repository, appropriate to the U.K. context, with particular reference to: waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transportation within the repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; and costs. The paper contains a section on general conclusions and recommendations. (U.K.)

  16. Summary guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Halsnaes, K.; Painuly, J.P.; Turkson, J.; Meyer, H.J.; Markandya, A.

    1999-09-01

    This document is a summary version of the methodological guidelines for climate change mitigation assessment developed as part of the Global Environment Facility (GEF) project Economics of Greenhouse Gas Limitations; Methodological Guidelines. The objectives of this project have been to develop a methodology, an implementing framework and a reporting system which countries can use in the construction of national climate change mitigation policies and in meeting their future reporting obligations under the FCCC. The methodological framework developed in the Methodological Guidelines covers key economic concepts, scenario building, modelling tools and common assumptions. It was used by several country studies included in the project. (au) 13 refs.

  17. Conference summaries

    International Nuclear Information System (INIS)

    1988-01-01

    This volume contains conference summaries of the 28. annual conference of the Canadian Nuclear Association, and the 9. annual conference of the Canadian Nuclear Society. Topics of discussion include: power reactors; fuel cycles; nuclear power and public understanding; future trends; applications of nuclear technology; CANDU reactors; operational enhancements; design of small reactors; accident behaviour in fuel channels; fuel storage and waste management; reactor commissioning/decommissioning; nuclear safety experiments and modelling; the next generation reactors; advances in nuclear engineering education in Canada; safety of small reactors; current position and improvements of fuel channels; current issues in nuclear safety; and radiation applications - medical and industrial

  18. Status of national programmes on fast breeder reactors. Twenty-fifth annual meeting of the International Working Group on Fast Reactors. Summary report. Working material

    International Nuclear Information System (INIS)

    1992-01-01

    'burning' of the associated extremely long-life transuranic waste, particularly actinides, thus reducing the required isolation time for high level waste from tens of thousands of years to hundreds of years for fission products only. This additional important mission for the LMFBR is gaining worldwide interest. In the framework of disarmament of nuclear weapons and the utilization of the nuclear material for peaceful purposes a role for fast reactors can be also considered. Over the past 25 years, the IAEA has actively encouraged and advocated international cooperation in Fast Breeder Reactor Technology. At the present time the Working Group on Fast Reactors is the oldest and one of the most active groups in the Division of Nuclear Power. The present document contains information on the status of fast breeder reactor development and on worldwide activities in this advanced nuclear power technology during 1991, as reported at the 25th jubilee Annual Meeting of the IWGFR in Vienna, 27-30 April 1992. The publication is intended to provide information regarding the current status of LMFBR development in IAEA Member States and CEC

  19. Status of national programmes on fast breeder reactors. Twenty-fifth annual meeting of the International Working Group on Fast Reactors. Summary report. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    'burning' of the associated extremely long-life transuranic waste, particularly actinides, thus reducing the required isolation time for high level waste from tens of thousands of years to hundreds of years for fission products only. This additional important mission for the LMFBR is gaining worldwide interest. In the framework of disarmament of nuclear weapons and the utilization of the nuclear material for peaceful purposes a role for fast reactors can be also considered. Over the past 25 years, the IAEA has actively encouraged and advocated international cooperation in Fast Breeder Reactor Technology. At the present time the Working Group on Fast Reactors is the oldest and one of the most active groups in the Division of Nuclear Power. The present document contains information on the status of fast breeder reactor development and on worldwide activities in this advanced nuclear power technology during 1991, as reported at the 25th jubilee Annual Meeting of the IWGFR in Vienna, 27-30 April 1992. The publication is intended to provide information regarding the current status of LMFBR development in IAEA Member States and CEC.

  20. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1993 through December 1995

    Science.gov (United States)

    Torikai, J.D.

    1996-01-01

    This report contains hydrologic and climatic data that describe the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1993 through December 1995, although the report focuses on hydrologic events from October through December 1995 (fourth quarter of 1995). Cumulative rainfall for October through December 1995 was about 41 inches, which is 32 percent more than the mean cumulative rainfall of about 31 inches for October through December. The period October through December is within the annual wet season. Mean cumulative rainfall is calculated for the fixed base period 1951-90. Ground-water withdrawal during October through December 1995 averaged 931,000 gallons per day. Withdrawal for the same 3 months in 1994 averaged 902,900 gallons per day. Patterns of withdrawal during the fourth quarter of 1995 did not change significantly since 1993 at all five ground-water production areas. At the end of December 1995, the chloride concentration of the composite water supply was 60 milligrams per liter, well below the 250 milligrams per liter secondary drinking-water standard established by the U.S. Environmental Protection Agency. Chloride concentrations of the composite water supply from October through December 1995 ranged between 28 and 67 milligrams per liter. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations continued to decrease during the fourth quarter of 1995, with water from the deepest monitoring wells decreasing in chloride concentration by as much as 2,000 milligrams per liter. This trend follows increases in chloride concentration during the first half of 1995. A fuel leak at Air Operations caused the shutdown of ten wells in May 1991. Four of the wells resumed pumping for water-supply purposes in April 1992. The remaining six wells are being used to hydraulically divert fuel migration away from water-supply wells by recirculating about 150,000 gallons of water

  1. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1992 through September 1994

    Science.gov (United States)

    Torikai, J.D.

    1995-01-01

    This report contains hydrologic and climatic data that describe the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data are presented from January 1992 through September 1994. This report concentrates on data from July through September 1994, and references historic data from 1992 through June 1994. Total rainfall for the first nine months of 1994 was about 77 inches which is 72 percent of the mean annual rainfall of 106 inches. In comparison, total rainfall for the first nine months of 1992 and 1993 was 67 inches and 69 inches, respectively. Annual rainfall totals in 1992 and 1993 were 93 inches and 95 inches, respectively. Ground-water withdrawal during July through September 1994 has averaged 919,400 gallons per day, while annual withdrawals in 1992 and 1993 averaged 935,900 gallons per day and 953,800 gallons per day, respectively. At the end of September 1994, the chloride concentration of the composite water supply was 56 milligrams per liter, well below the 250 milligrams per liter secondary drinking-water standard established by the U.S. Environmental Protection Agency. Chloride concentrations of the composite water supply from July through September 1994 ranged between 51 and 78 milligrams per liter. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations increased in July and August, but have leveled off or decreased in September. There has been a general trend of increasing chloride concentrations in the deeper monitoring wells since the 1992 dry season, which began in March 1992. A fuel leak at Air Operations caused the shutdown of ten wells in May 1991. Four of the wells resumed pumping for water-supply purposes in April 1992. The remaining six wells are being used to hydraulically contain and divert fuel migration by recirculating 150,000 gallons of water each day.

  2. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1993 through March 1995

    Science.gov (United States)

    Torikai, J.D.

    1995-01-01

    This report contains hydrologic and climatic data that describe the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1993 through March 1995, although the report focuses on hydrologic events from January through March 1995. Cumulative rainfall for January through March 1995 was about 42 inches which is higher than the mean cumulative rainfall of about 33 inches for the same 3 months in a year. January and February are part of the annual wet season and March is the start of the annual dry season. Rainfall for each month was above average from the respective mean monthly rainfall. Ground- water withdrawal during January through March 1995 averaged 894,600 gallons per day. Withdrawal for the same 3 months in 1994 averaged 999,600 gallons per day. At the end of March 1995, the chloride concentration of the composite water supply was 26 milligrams per liter, well below the 250 milligrams per liter secondary drinking-water standard established by the U.S. Environmental Protection Agency. Chloride concentrations of the composite water supply from January through March 1995 ranged between 19 and 49 milligrams per liter. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations decreased since November 1994. The deepest monitoring wells show declines in chloride concentration by as much as 4,000 milligrams per liter. A fuel leak at Air Operations caused the shutdown of ten wells in May 1991. Four of the wells resumed pumping for water- supply purposes in April 1992. The remaining six wells are being used to hydraulically contain and divert fuel migration by recirculating about 150,000 gallons of water each day.

  3. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1993 through September 1995

    Science.gov (United States)

    Torikai, J.D.

    1996-01-01

    This report contains hydrologic and climatic data that describe the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1993 through September 1995, although the report focuses on hydrologic events from July through September 1995. Cumulative rainfall for July through September 1995 was about 15 inches which is 32 percent less than the mean cumulative rainfall of about 22 inches for July through September. July and August are within the annual dry season, while September is the start of the annual wet season. Mean cumulative rainfall is calculated for the fixed base period 1951-90. Ground-water withdrawal during July through September 1995 averaged 888,500 gallons per day. Withdrawal for the same 3 months in 1994 averaged 919,400 gallons per day. Patterns of withdrawal during the third quarter of 1995 did not change significantly since 1993 at all five ground-water production areas. At the end of September 1995, the chloride concentration of the composite water supply was 51 milligrams per liter, well below the 250 milligrams per liter secondary drinking-water standard established by the U.S. Environmental Protection Agency. Chloride concentrations of the composite water supply from July through September 1995 ranged between 42 and 68 milligrams per liter. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations continued to increase since April 1995, with water from the deepest monitoring wells increasing in chloride concentration by as much as 2,000 milligrams per liter. A fuel leak at Air Operations caused the shutdown of ten wells in May 1991. Four of the wells resumed pumping for water-supply purposes in April 1992. The remaining six wells are being used to hydraulically divert fuel migration away from water-supply wells by recirculating about 150,000 gallons of water each day.

  4. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1994 through September 1996

    Science.gov (United States)

    Torikai, J.D.

    1996-01-01

    This report describes the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1994 through September 1996, with a focus on data from July through September 1996 (third quarter of 1996). A complete database of ground-water withdrawals and chloride-concentration records since 1985 is maintained by the U.S. Geological Survey. Total rainfall for the period July through September 1996 was 8.94 inches, which is 60 percent less than the mean rainfall of 22.23 inches for the period July through September. July and August are part of the annual dry season, while September is the start of the annual wet season. Ground-water withdrawal during July through September 1996 averaged 1,038,300 gallons per day. Withdrawal for the same 3 months in 1995 averaged 888,500 gallons per day. Ground-water withdrawals have steadily increased since about April 1995. At the end of September 1996, the chloride concentration of water from the elevated tanks at Cantonment and Air Operations were 68 and 150 milligrams per liter, respectively. The chloride concentration from all five production areas increased throughout the third quarter of 1996, and started the upward trend in about April 1995. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations also increased throughout the third quarter of 1996, with the largest increases from water in the deepest monitoring wells. Chloride concentrations have not been at this level since the dry season of 1994. A fuel-pipeline leak at Air Operations in May 1991 decreased total islandwide withdrawals by 15 percent. This lost pumping capacity is being offset by increased pumpage at Cantonment. Six wells do not contribute to the water supply because they are being used to hydraulically divert fuel migration away from water-supply wells by a program of ground-water withdrawal and injection.

  5. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1993 through June 1995

    Science.gov (United States)

    Torikai, J.D.

    1995-01-01

    This report contains hydrologic and climatic data that describe the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1993 through June 1995, although the report focuses on hydrologic events from April through June 1995. Cumulative rainfall for April through June 1995 was about 14 inches which is 70 percent of the mean cumulative rainfall of about 20 inches for the same 3 months in a year. April through June is within the annual dry season. Rainfall for each month was below average from the respective mean monthly rainfall. All mean rainfall values are calculated for the fixed base period 1951-90. Ground-water withdrawal during April through June 1995 averaged 833,700 gallons per day. Withdrawal for the same 3 months in 1994 averaged 950,000 gallons per day. At the end of June 1995, the chloride concentration of the composite water supply was 57 milligrams per liter, well below the 250 milligrams per liter secondary drinking-water standard established by the U.S. Environmental Protection Agency. Chloride concentrations of the composite water supply from April through June 1995 ranged between 26 and 62 milligrams per liter. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations increased since April 1995, with water from the deepest monitoring wells increasing in chloride concentra- tion by about 1000 milligrams per liter. A fuel leak at Air Operations caused the shutdown of ten wells in May 1991. Four of the wells resumed pumping for water-supply purposes in April 1992. The remaining six wells are being used to hydraulically contain and divert fuel migration away from water-supply wells by recirculating about 150,000 gallons of water each day.

  6. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1994 through March 1996

    Science.gov (United States)

    Torikai, J.D.

    1996-01-01

    This report describes the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1994 through March 1996, with a focus on data from January through March 1996 (first quarter of 1996). A complete database of ground-water withdrawals and chloride-concentration records since 1985 is maintained by the U.S. Geological Survey. Cumulative rainfall for January through March 1996 was about 30 inches, which is 9 percent less than the mean cumulative rainfall of about 33 inches for January through March. The period January through February is the end of the annual wet season, while March marks the start of the annual dry season. Ground-water withdrawal during January through March 1996 averaged 970,300 gallons per day. Withdrawal for the same 3 months in 1995 averaged 894,600 gallons per day. With- drawal patterns during the first quarter of 1996 did not change significantly since 1991, with the Cantonment and Air Operations areas supplying about 99 percent of total islandwide pumpage. At the end of March 1996, the chloride concentration of water from the elevated tanks at Cantonment and Air Operations were 47 and 80 milligrams per liter, respectively. The chloride data from all five production areas showed no significant upward or downward trends throughout the first quarter of 1996. Potable levels of chloride concentrations have been maintained by adjusting individual pumping rates, and also because of the absence of long-term droughts. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations also showed no significant trends throughout the first quarter of 1996. Chloride concentrations have been about the same since the last quarter of 1995. A fuel-pipeline leak at Air Operations in May 1991 decreased total islandwide withdrawals by 15 percent. This lost pumping capacity is being offset by increased pumpage at Cantonment. Six wells do not contribute to the water supply because they

  7. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1992 through December 1994

    Science.gov (United States)

    Torikai, J.D.

    1995-01-01

    This report contains hydrologic and climatic data that describe the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1992 through December 1994. This report concentrates on data from October through December 1994, and references previous data from 1992 through 1994. Cumulative rainfall for October through December 1994 was 55 inches which is higher than the mean cumulative rainfall of about 31 inches for the same 3 months. Total rainfall for 1994 was 131 inches which is 24 percent higher than the mean annual rainfall of 106 inches. In com- parison, total rainfall in 1992 and 1993 were 93 inches and 95 inches, respectively. Ground-water withdrawal during October through December 1994 averaged 903,000 gallons per day, while the annual withdrawal in 1994 was 942,700 gallons per day. Annual withdrawals in 1992 and 1993 averaged 935,900 gallons per day and 953,800 gallons per day, respectively. At the end of December 1994, the chloride concentration of the composite water supply was 28 milligrams per liter, well below the 250 milligrams per liter secondary drinking-water standard established by the U.S. Environmental Protection Agency. Chloride concentrations of the composite water supply from October through December 1994 ranged between 28 and 86 milligrams per liter. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations decreased in November and December, and seems to have leveled off by the end of the year. Although chloride concen- trations have decreased during the fourth quarter of 1994, there has been a general trend of increasing chloride concentrations in the deeper monitoring wells since the 1992 dry season, which began in March 1992. A fuel leak at Air Operations caused the shutdown of ten wells in May 1991. Four of the wells resumed pumping for water-supply purposes in April 1992. The remaining six wells are being used to hydraulically contain and divert fuel

  8. Status of ground-water resources at U.S. Navy Support Facility, Diego Garcia; summary of hydrologic and climatic data, January 1994 through June 1996

    Science.gov (United States)

    Torikai, J.D.

    1996-01-01

    This report describes the status of ground-water resources at U.S. Navy Support Facility, Diego Garcia. Data presented are from January 1994 through June 1996, with a focus on data from April through June 1996 (second quarter of 1996). A complete database of ground-water withdrawals and chloride-concentration records since 1985 is maintained by the U.S. Geological Survey. Cumulative rainfall for April through June 1996 was 22.64 inches, which is 12 percent more than the mean cumulative rainfall of 20.21 inches for April through June. The period April through June is part of the annual dry season. Ground-water withdrawal during April through June 1996 averaged 1,048,000 gallons per day. Withdrawal for the same 3 months in 1995 averaged 833,700 gallons per day. Withdrawal patterns during the second quarter of 1996 did not change significantly since 1991, with the Cantonment and Air Operations areas supplying about 99 percent of total islandwide pumpage. At the end of June 1996, the chloride concentration of water from the elevated tanks at Cantonment and Air Operations were 52 and 80 milligrams per liter, respectively. The chloride data from all five production areas showed no significant upward or downward trends throughout the second quarter of 1996. Potable levels of chloride concentrations have been maintained by adjusting individual pumping rates, and also because of the absence of long-term droughts. Chloride concentration of ground water in monitoring wells at Cantonment and Air Operations also showed no significant trends throughout the second quarter of 1996. Chloride concentrations have been about the same since the last quarter of 1995. A fuel-pipeline leak at Air Operations in May 1991 decreased total islandwide withdrawals by 15 percent. This lost pumping capacity is being offset by increased pumpage at Cantonment. Six wells do not contribute to the water supply because they are being used to hydraulically divert fuel migration away from water

  9. 75 FR 20881 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-04-21

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  10. 76 FR 33807 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-06-09

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  11. 76 FR 39976 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-07-07

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATE: Comments on this petition must...

  12. 75 FR 60859 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-10-01

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  13. 77 FR 35103 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-06-12

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  14. 77 FR 36333 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-06-18

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  15. 78 FR 57676 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-09-19

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  16. 76 FR 65772 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-10-24

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  17. 78 FR 53186 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-08-28

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATE: Comments on this petition must...

  18. 76 FR 16653 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-03-24

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  19. 78 FR 56768 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-09-13

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  20. 75 FR 26839 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-05-12

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  1. 78 FR 13745 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-02-28

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  2. 77 FR 58210 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-09-19

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  3. 75 FR 65396 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-10-22

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  4. 77 FR 71865 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-12-04

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  5. 78 FR 73919 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-12-09

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  6. 78 FR 34139 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-06-06

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  7. 77 FR 50760 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-08-22

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  8. 76 FR 2746 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-01-14

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  9. 75 FR 21388 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-04-23

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petitions or their final disposition. DATES: Comments on these petitions must...

  10. 76 FR 51119 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-08-17

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  11. 76 FR 9852 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-02-22

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  12. 75 FR 80107 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-12-21

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  13. 78 FR 979 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-01-07

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  14. 75 FR 21389 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-04-23

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petitions or their final disposition. DATES: Comments on these petitions must...

  15. 77 FR 71864 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-12-04

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATE: Comments on this petition must...

  16. 78 FR 66098 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-11-04

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  17. 75 FR 21387 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-04-23

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  18. 76 FR 24560 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-05-02

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  19. 75 FR 10016 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-03-04

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATE: Comments on this petition must...

  20. 78 FR 53818 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-08-30

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  1. 77 FR 5087 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-02-01

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  2. 75 FR 51525 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-08-20

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petitions or their final disposition. DATES: Comments on these petitions must...

  3. 78 FR 35353 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-06-12

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  4. 77 FR 44309 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-07-27

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  5. 77 FR 31064 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2012-05-24

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  6. 75 FR 26843 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2010-05-12

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of any petition or its final disposition. DATES: Comments on petitions received must...

  7. 78 FR 24290 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-04-24

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  8. 78 FR 66099 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-11-04

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  9. 78 FR 39825 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-07-02

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  10. 76 FR 20806 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2011-04-13

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  11. 78 FR 21701 - Petition for Exemption; Summary of Petition Received

    Science.gov (United States)

    2013-04-11

    ...] Petition for Exemption; Summary of Petition Received AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of petition for exemption received. SUMMARY: This notice contains a summary of a petition... the legal status of the petition or its final disposition. DATES: Comments on this petition must...

  12. Conference summaries

    Energy Technology Data Exchange (ETDEWEB)

    Reynolds, Tim [Inta Communication Limited for European Service Network/ DG Research, Trillium House, 32 New Street, St. Neots, Cambridge PE19 1AJ (United Kingdom)

    2004-07-01

    The summaries were derived from presentations, interviews and discussions at the conference. The summaries are given at two levels, overall for the conference and for specific sessions as follows: 1) Overall Conference: 'A Sound Scientific Basis for Serious Decisions; 2) Sessions on EC Policy and Socio-Political Issues: 'Promoting Safety and Protecting Society'; 3) Session on P and T: 'Partitioning and Transmutation: A Technical Fix or Technical Training?'; 4) Sessions on Geological Disposal and Research Networking: 'No Technical Barriers to Geological Disposal'. First an overall summary of Euradwaste '04 is presented. Significant progress was made on the technical and scientific basis for geological disposal of radioactive waste during the European Commission's Fifth EURATOM Framework Programme for Research (FP5). Deep geological disposal is technically feasible now and can demonstrate the guarantees of long-term isolation and protection of the public. In parallel, socio-political studies have produced methodologies for constructive dialogue with potential host communities that reflect the honesty and openness expected by a democratic society. A harmonized legislative framework for nuclear safety and waste disposal across the enlarged European Union is currently being discussed. Disposal in deep (> 300 metre) geological repositories, the favoured strategy in Europe for long-lived high-level radioactive waste, is now possible. The Sessions on EC Policy and Socio-Political Issues are summarized as follows. The opening day of Euradwaste '04 focused on European Commission policy, including the proposed Directives on disposal of radioactive waste and nuclear safety and socio-political aspects including governance and decision making, public perception/acceptance of waste disposal and its sustainability. A decision on the proposed package will now be made after Union enlargement. Public agreement on the siting of

  13. Proceedings of a C.S.N.I. specialist meeting on instrumented pre-cracked Charpy testing

    Energy Technology Data Exchange (ETDEWEB)

    Wullaert, R A [Fracture Control Corp., 340 South Kellogg Avenue, Suite G, Goleta, California 93017 (United States)

    1981-11-15

    This report presents the status of the testing and data analysis procedures for the instrumented pre-cracked Charpy test with emphasis on the application of the test technique to the nuclear industry. The report (Proceedings) consist of invited technical papers by specialists in the field and a synopsis of the comments, conclusions, and recommendations reached in a workshop session. The CSNl-sponsored and EPRI-hosted meeting confirmed both the popularity of the test technique in the nuclear industry and the problems associated with the test technique due to the lack of a national or international consensus standard. Major emphasis in the meeting was devoted to evaluating the existing industry testing procedure (EPRI procedure) and proposed national standards (ASTM, ASK). The EPRI procedures were considered adequate by specialists concerned with engineering applications, but too restrictive by specialists concerned with research applications. As a result of the conference, a compilation of state-of-the-art papers is now available to code and standard committees. Specific comments concerning test and data analysis procedures, applications in the nuclear industry, and future research areas are also contained in the proceedings

  14. Executive Summary

    International Nuclear Information System (INIS)

    2014-01-01

    Each session of the workshop consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided. Session 1: National approaches for long term interim storage facilities. Seven papers were presented during this session by representatives of research institutes in USA (EPRI) and in Norway (IFE), governmental authorities for the nuclear industry in Finland (STUK) and Slovak Republic (UJD), technical support organizations in Germany (GRS) and France (IRSN) and the public company in charge of waste management in Spain (ENRESA). The papers discussed the national policy, the regulatory framework and the current situation for storage of SF and HLW in various European countries (Germany, Spain, Finland, Norway and Slovak Republic). The main activities the EPRI is undertaking to establish the technical bases for extended (long-term) storage and the IRSN's definition of the safety principles and objectives for new storage facilities regarding long-term storage are also discussed. Session 2: Safety requirements, regulatory framework and implementation issues. Eleven papers were presented during this session by representatives from international groups (the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA)), representatives of regulatory bodies from the United States (Nuclear Regulatory Commission) and Germany (Bundesamt fuer Strahlenschutz (BfS)), German Federal Institute for Materials Research and Testing (BAM), operators from the United Kingdom (Sellafield Limited, UK) and France (EDF), vendors (AREVA), and representatives of TSOs in Germany (TUV and Oko-Institut). Session 3: Technical issues and operational experience, needs for R and D. This session was chaired by Karl Wasinger (AREVA, Germany) and Fumihisa Nagase (JAEA, Japan). Ten papers were presented during this session by representatives of research institutes of Japan (CRIEPI

  15. Symposium summary

    International Nuclear Information System (INIS)

    Wall, G.

    1990-01-01

    A summary is provided of the issues discussed at the climate change implications for water and ecological resources conference, and recommendations that came out of the conference. The objectives of the meeting were to present and discuss results of recent climate change experiments undertaken in Canada; evaluate a variety of climate models and impact analyses and to develop methods and strategies for future study; and to establish working linkages between modellers and analysts in the fields of climate, hydrology, and ecosystem research, as well as between social scientists and policy makers interested in the implications of climate change. Recommendations were made in the five areas of research, monitoring, risk assessment, policy and information dissemination. Additional research should be undertaken to foster improved understanding of relationships between climate, climate change, and ecological and human processes. A suitable monitoring program, including a national wetlands monitoring program, should be established. Risk assessments should be undertaken to evaluate vulnerabilities of ecosystem components, to assess options, and to provide the information required to develop and implement appropriate policy objectives. The impacts of a range of public policy responses and feedbacks should be assessed. The dissemination of well-targeted and accurate information is vital if basic societal attitudes regarding the value of water and ecosystems are to be changed

  16. Session summaries

    International Nuclear Information System (INIS)

    Sudo, Y.

    2002-01-01

    In the summary session, possible international activities in the field of basic studies on high-temperature engineering were discussed within the framework of the OECD/NEA Nuclear Science Committee (NSC). It was recommended to include topics relevant to fission-product behaviour and safety issues of HTGR in next meeting, in addition to the topics discussed in this meeting. The chairperson of the last session summarised the recommendations to be presented to the NSC into the following five topics as possible international activities: - Basic studies on behaviour of irradiated graphite/carbon and ceramic materials including their composites under both operation and storage conditions. - Development of in-core material characterisation and instrumentation methods. - Improvement in material properties through high-temperature irradiation. - Basic studies on HTGR fuel fabrication and performance including fission-product release. - Basic studies on safety issues of HTGR. It was also recommended that a further information exchange meeting focused on the organisation of the interactive collaboration activity with regard to the above topics be planned in 2003, tentatively in Oarai, Japan. (author)

  17. Management summary

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    A most pressing problem in many environmental assessments is determining the extent of contamination to the biosphere resulting from a given activity. This could result from the planned or accidental release of a contaminant to the environment and its subsequent transport through air, water, or the food chain. In either case, three critical questions need to be raised in the environmental assessment of the problem: Where are the contaminants; When will they arrive at a specific location; How much of the contaminant will be at the point of uptake. The location of the contaminant is important, since a contaminant isolated from man both now and in the future may represent little hazard, even in rather large quantities. Under other conditions, small amounts of contaminants arriving at critical locations over a short period may involve severe hazard. The problem of location is simplified by concentrating on those places where the contaminants will interface with the biosphere. Applications in evaluating the consequences of ground water contamination are discussed. Environmental consequences or impacts are most effectively and efficiently communicated by: Blending extensive technical results and reducing them to simple summary relationships, i.e., the arrival distributions; focusing on the arrival distributions as the central theme of communication efforts; and determining quantitative consequences or impacts to the biosphere through use of the arrival distributions. Appropriately applied, these principles can reduce a voluminous impact statement on subsurface pollution to a few pages that are directly useful to decision-makers and the public

  18. Theory summary

    International Nuclear Information System (INIS)

    Tang, W.M.

    2001-01-01

    This is a summary of the advances in magnetic fusion energy theory research presented at the 17th International Atomic Energy Agency Fusion Energy Conference from 19 24 October, 1998 in Yokohama, Japan. Theory and simulation results from this conference provided encouraging evidence of significant progress in understanding the physics of thermonuclear plasmas. Indeed, the grand challenge for this field is to acquire the basic understanding that can readily enable the innovations which would make fusion energy practical. In this sense, research in fusion energy is increasingly able to be categorized as fitting well the 'Pasteur's Quadrant' paradigm, where the research strongly couples basic science ('Bohr's Quadrant') to technological impact ('Edison's Quadrant'). As supported by some of the work presented at this conference, this trend will be further enhanced by advanced simulations. Eventually, realistic three-dimensional modeling capabilities, when properly combined with rapid and complete data interpretation of results from both experiments and simulations, can contribute to a greatly enhanced cycle of understanding and innovation. Plasma science theory and simulation have provided reliable foundations for this improved modeling capability, and the exciting advances in high-performance computational resources have further accelerated progress. There were 68 papers presented at this conference in the area of magnetic fusion energy theory

  19. Par Pond vegetation status Summer 1995 -- Summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1996-01-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the newly emergent, shoreline aquatic plant communities of Par Pond began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level. These surveys continued in July, September, and late October, 1995. Communities similar to the pre-drawdown, Par Pond aquatic plant communities are becoming re-established. Emergent beds of maidencane, lotus, waterlily, and watershield are extensive and well developed. Cattail occurrence continued to increase during the summer, but large beds common to Par Pond prior to the drawdown have not formed. Estimates from SPOT HRV, remote sensing satellite data indicated that as much as 120 hectares of emergent wetlands vegetation may have been present along the Par Pond shoreline by early October, 1995. To track the continued development of macrophytes in Par Pond, future surveys throughout 1996 and 1997, along with the continued evaluation of satellite data to map the areal extent of the macrophyte beds of Par Pond, are planned

  20. Summary talk - status of accelerator neutrino physics

    International Nuclear Information System (INIS)

    Lee, B.W.

    1977-01-01

    I shall address theoretical questions that are immediately relevant to today's accelerator neutrino physics. The frame of reference I shall dwell in is quantum chromodynamics, in which quarks are assumed to carry both flavors and colors, and confining forces among quarks are transmitted by color gluons. The physical hadrons are color-neutral. Quarks presumably cannot be isolated at least at the present accelerator energies. For most phenomenological considerations, whether confinement is permanent or temporary does not really matter, but I insist that quarks behave as if they were free at short distances, and a color symmetry is exact. Inasmuch as quark cannot exist in an isolated state, what one means by a quark mass is a matter of definition. One definition might be superior to others in a given context. (orig.) [de

  1. Neutrino physics: Summary talk

    International Nuclear Information System (INIS)

    Marciano, W.J.

    1989-04-01

    This paper is organized as follows: First, I describe the state of neutrino phenomenology. Emphasis is placed on sin 2 θ W , its present status and future prospects. In addition, some signatures of ''new physics'' are described. Then, kaon physics at Fermilab is briefly discussed. I concentrate on the interesting rare decay K L → π 0 e + e - which may be a clean probe direct CP violation. Neutrino mass, mixing, and electromagnetic moments are surveyed. There, I describe the present state and future direction of accelerator based experiments. Finally, I conclude with an outlook on the future. Throughout this summary, I have drawn from and incorporated ideas discussed by other speakers at this workshop. However, I have tried to combine their ideas with my own perspective on neutrino physics and where it is headed. 49 refs., 3 figs., 4 tabs

  2. Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

    systems. The scope of the workshop comprised reactor physics, fuel performance and fuel material technology, thermal-hydraulics, core behaviour and fuel cycle of advanced reactors with different types of fuels or fuel lattices. Reactor types considered were water-cooled, high-temperature gas-cooled and fast spectrum reactors as well as hybrid reactors with fast and thermal neutron spectra. The emphasis was on innovative concepts and issues related to the reactor and fuel. The workshop concluded with a wide-ranging panel discussion which considered some difficult questions from which it is hoped that some recommendations for future priorities can be derived. A record of the discussion is included at the end of this summary. (author)

  3. Double blind post-test prediction for LOBI-MOD2 small break experiment A2-81 using RELAP5/MOD1/19 computer code as contribution to international CSNI-standardproblem no. 18

    International Nuclear Information System (INIS)

    Jacobs, G.; Mansoor, S.H.

    1986-06-01

    The first small break experiment A2-81 performed in the LOBI-MOD2 test facility was the base of the 18th international CSNI standard problem (ISP 18). Taking part in this exercise, a blind post-test prediction was performed using the light water reactor transient analysis code RELAP5/MOD1. This paper describes the input model preparation and summarizes the findings of the pre-calculation comparing the calculational results with the experimental data. The results show that there was a good agreement between prediction and experiment in the initial stage (up to 250 sec) of the transient and an adequate prediction of the global behaviour (thermal response of the core), which is important for safety related considerations. However, the prediction confirmed some deficiencies of the models in the code concerning vertical and horizontal stratification resulting in a high break mass flow and an erroneous distribution of mass over the primary loops. (orig.) [de

  4. Review of international developments and cooperation on Risk-Informed In-Service-Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification in OECD-NEA member countries- Responses to the questionnaire - CSNI/integrity and ageing working group

    International Nuclear Information System (INIS)

    2005-01-01

    In December 2000, the Committee on Nuclear Regulatory Activities (CNRA) and the Committee on the Safety of Nuclear Installations (CSNI) agreed to prepare a state-of-the art report addressing the present situation and regulatory aspects in NEA member countries on: - Risk based / risk informed in-service inspections (ISI) developments, - Qualification of NDT system to be used for the inspections. The CSNI gave mandate to the CSNI working group on the Integrity of Components and Structures (IAGE) to prepare the report. In order to get a good basis for compiling the report with an overview on the present situation in OECD countries and regulatory aspects on the further developments of RI-ISI and NDT qualification approaches a questionnaire was prepared. This questionnaire was organised in two parts. The first part addressed used risk based / risk informed ISI approaches and regulatory aspects on the further developments. The second part addressed used NDT qualification approaches and other measures for getting reliable inspection results as well as regulatory aspects on the further developments of qualification approaches. Some parts of the questionnaire addressed topics, which have been dealt with in other European or national programs. Available relevant information from these programs has been also collected. The questionnaire was circulated in 2003 among NEA member countries organisations. Appendix 1 contains the questionnaire. Appendix 2 contains the compilation of responses to the questionnaire. A workshop was organized to complement the questionnaire (NEA/CSNI/R(2004)9 Proceedings of the CSNI Workshop on 'International developments and cooperation on Risk-Informed In-Service- Inspection (RI-ISI) and Non-destructive Testing (NDT) Qualification' held in Stockholm, Sweden on 13-14 April 2004 and hosted by SKI). In addition to regulators, licensees, manufacturers and researchers, this workshop gathered international organisations (i.e. EC, IAEA) and the main

  5. Summary Record

    International Nuclear Information System (INIS)

    2008-01-01

    (II-3) - Uncertainty analysis of the steady state benchmark. It should be recognized that the purpose of this benchmark is not only to compare currently available macroscopic approaches but above-all to encourage the development of novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The technical topics to be addressed at the workshop include: - Review of the benchmark activities after the 4. Workshop; - Presentation and discussion of summary of comparisons of final submitted results for Exercise 1 of Phase I (I-1); for Exercise 0 of Phase II (II-0); and for Exercise 1 of Phase II (II-1); - Presentation and discussion of comparison of final submitted results for Exercise 2 of Phase I (I-2); - Presentation and discussion of comparison of final submitted results for Exercise 3 of Phase I (I-3); - Presentation and discussion of comparison of final submitted results for Exercise 2 of Phase II (II-2); - Presentation and discussion of preliminary uncertainty results for Exercise 4 of Phase I (I-4); - Presentation and discussion of preliminary uncertainty results for Exercise 3 of Phase II (II-3); - Preparing a special issue in a journal with participants' BFBT papers; - Defining a work plan and schedule outlining actions to advance the two phases of the benchmark activities

  6. Summary of Technical Sessions - Summary and Recommendations

    International Nuclear Information System (INIS)

    2013-01-01

    margins or the use of PSA. This session comprised 7 papers. The recommendations of the workshop can be summarized by emphasizing that a great advance has been achieved since the beginning of BEPU activities, pointing to the consolidation of practices and nevertheless identifying still pending concerns. While the added value to safety with origin in the use of BEPU methods is recognized, the full potential of BEPU approach to a comprehensive safety assessment is still pending with regard to development. The CSNI and other international organizations like IAEA should play a leading role in this advancement

  7. Gradual linguistic summaries

    NARCIS (Netherlands)

    Wilbik, A.M.; Kaymak, U.; Laurent, A.; Strauss, O.; Bouchon-Meunier, xx

    2014-01-01

    In this paper we propose a new type of protoform-based linguistic summary – the gradual summary. This new type of summaries aims in capturing the change over some time span. Such summaries can be useful in many domains, for instance in economics, e.g., "prices of X are getting smaller" in eldercare,

  8. Human Performance under Extreme Conditions with Respect to a Resilient Organisation. Proceedings of a CSNI International Workshop, 24-26 February 2015, Brugg, Switzerland

    International Nuclear Information System (INIS)

    2015-01-01

    After the Fukushima Daiichi accident a number of initiatives have been undertaken internationally to learn from the accident and to implement lessons learned to improve nuclear safety. The accident has shown in particular the challenges in supporting reliable human performance under extreme conditions. Acknowledging that further work is needed to be better prepared for the HOF (Human and Organisational Factors) challenges of the extreme conditions that may be present in severe accidents, the NEA's Working Group on Human and Organisational Factors (WGHOF), one of the working groups for the Committee on the Safety of Nuclear Installations (CSNI) initiated a new task with the objectives to: - share experiences and knowledge of human and organisational performance under extreme conditions, - identify specific currently applied HOF principles in nuclear and other high risk industries and compare them with the available knowledge, - provide a basis for improvements and necessary research taking into account HOF issues in the design and use of measures, and - make recommendations with the aim to achieve the best level of human and organisational performance as possible under extreme conditions. In order to move those issues forward WGHOF hosted together with the Swiss Federal Nuclear Safety Inspectorate ENSI a workshop entitled 'Human Performance under Extreme Conditions with respect to a Resilient Organization'. The workshop was conducted with participation of a number of invited key speakers from academic research and a range of industries, including nuclear. Thirty-four experts from 12 countries, the IAEA and OECD/Halden participated. Experts came from nuclear authorities, research centres, technical support organisations, training simulator centres, utilities and from non-nuclear field (aircraft accident investigation, fire fighting, military, design of resilient organisations). From the discussions at the workshop, it is clear that the accident at Fukushima has

  9. Neurophysiology Summary

    Science.gov (United States)

    Paloski, William H.

    2001-01-01

    flight. Building on these basic research studies are more applied studies focused on the development of countermeasures to the untoward neurophysiological responses to space flight. At the 2001 workshop, applied research studies were presented addressing issues related to the use of rotational artificial gravity (centripetal acceleration) as a multisystem (bone, muscle, cardiovascular, and, perhaps, neurovestibular) countermeasure. Also presented was a clinical study reporting on a new rating system for clinical evaluation of postflight functional neurological status.

  10. Nonconvulsive status epilepticus after electroconvulsive therapy

    DEFF Research Database (Denmark)

    Povlsen, Uffe Juul; Wildschiødtz, Gordon; Høgenhaven, Hans

    2003-01-01

    SUMMARY: We describe three cases of nonconvulsive status epilepticus induced by electroconvulsive therapy (ECT). Nonconvulsive status epilepticus is an important differential diagnosis in patients who develop prolonged confusion after ECT. The present cases exemplify the difficulty in defining...

  11. Summary record

    International Nuclear Information System (INIS)

    2009-01-01

    ; Exercise 3 (II-3) - Uncertainty analysis of the steady critical power benchmark. It should be recognized that the purpose of this benchmark is not only to compare currently available macroscopic approaches but above-all to encourage the development of novel next-generation approaches that focus on more microscopic processes. Thus, the benchmark problem includes both macroscopic and microscopic measurement data. In this context, the sub-channel grade void fraction data are regarded as the macroscopic data and the digitized computer graphic images are the microscopic data. The technical topics addressed at the workshop included: - Review of the benchmark activities after the 5. Workshop - Discussion of the report on Phase I - Participants' presentations on their models and results for Exercises I-1, I-2 and I-3 - Discussion of the report on Phase II - Participants' presentations on their models and results for Exercises II-0, II-1 and II-2 - Presentation and discussion of the results submitted for the uncertainty analysis exercises - Participants' presentations on their models and results for Exercises I-4 and II-3 - Introduction and presentation of the new OECD benchmark based on NUPEC PWR Sub-channel and Bundle Tests (PSBT) (as follow-up benchmark activities of the OECD/NRC BFBT benchmark): database, specification and schedule. - Status of the NED special issue with participants' BFBT papers - Defining a work plan and schedule outlining actions to progress the two phases of the benchmark activities

  12. Pediatric Status Epilepticus Management

    Science.gov (United States)

    Abend, Nicholas S; Loddenkemper, Tobias

    2014-01-01

    Purpose of Review This review discusses management of status epilepticus in children including both anticonvulsant medications and overall management approaches. Recent Findings Rapid management of status epilepticus is associated with a greater likelihood of seizure termination and better outcomes, yet data indicate there are often management delays. This review discusses an overall management approach aiming to simultaneously identify and manage underlying precipitant etiologies, administer anticonvulsants in rapid succession until seizures have terminated, and identify and manage systemic complications. An example management pathway is provided. Summary Status epilepticus is a common neurologic emergency in children and requires rapid intervention. Having a predetermined status epilepticus management pathway can expedite management. PMID:25304961

  13. Summary report for the second TUV-workshop proceedings on living PSA application

    International Nuclear Information System (INIS)

    1991-01-01

    This workshop on living PSA Application was organized to support the OECD/NEA CSNI-Principal Working Group No.5 on Risk Assessment for an international exchange of experience on living PSA application. The first session was devoted to Living PSA Applications and the second session to Tools for Living PSA. Living PSA Applications: Reasons for performing PSA (regulatory requirement, targets; corporate requirement, targets; safety related activity prioritization; other); Logistic of Living PSA Management (Corporate management involvement, Decision making levels and guidance, Plant level involvement, Required personnel commitment, Frequency and extent of re-quantification of PSA, Types of safety/risk parameters to be monitored, Quality assurance on maintaining Living PSA); Examples of Application (Experiences of application, State of Living PSA/e.g. all accident sequences involved, Details of component level involvement). Tools for Living PSA: Data Collection Systems and Codes (Source and type of data collected, Probabilistic parameter quantification, Interface to basic event data, Data code systems). An executive summary of the workshop is given

  14. Evidence of aging effects on certain safety-related components: summary and analysis

    International Nuclear Information System (INIS)

    1995-09-01

    In response to interest shown by the Nuclear Energy Agency (NEA), Principal Working Group I (PWG- 1) of the Committee on the Safety of Nuclear Installations (CSNI) conducted a generic study on the effects of aging of active components in nuclear power plants. Representatives from France, Sweden, Finland, Japan, the United States, and the United Kingdom participated in the study by submitting reports documenting aging studies performed in their countries. This report consists of summaries of those reports, along with a comparison of the various statistical analysis methods used in the studies. The studies indicate that with some exceptions, active components generally do not present a significant aging problem in nuclear power plants. Design criteria and effective preventative maintenance programs, including timely replacement of components, are effective in mitigating potential aging problems. However, aging studies (such as qualitative and statistical analyses of failure modes and maintenance data) are an important part of efforts to identify and solve potential aging problems. Solving these problems typically includes such strategies as replacing suspect components with improved components, and implementing improved maintenance programs

  15. Summary report on the use of plant safety performance indicators

    International Nuclear Information System (INIS)

    2001-09-01

    In 1998, the OECD/NEA committee on Nuclear Regulatory Activities (CNRA) initiated an activity with the objective of advancing the discussion on how to enhance and measure regulatory effectiveness in relation to nuclear installations. One of the outcome of this activity was to establish a Task group to develop internal (direct) performance indicators which would be used to monitor regulatory efficiency. In parallel, a joint CNRA/CSNI group was launched in December 2000 to exchange information and develop external (indirect) indicators to measure regulatory effectiveness, i.e. impact on licensee's safety performance. These external indicators are, in other words, the traditional plant performance indicators (PI's) and these are the ones that this report deals with. This report presents the work performed by the joint CNRA/CSNI task group mentioned above. It provides a summary of the sets of PI's being used by different regulatory bodies and WANO, it describes the national practices on the use of PI's and proposes a set of PI's that could be used nationally describing regulatory effectiveness and also as a basis for an international system. The task force consisted of regulators, organisations which have a performance indicators system in operation or under testing. The task force met in Paris on February 19-20, 2001. Each participant provided a brief description of the PI System at his organisation and its usage. The group identified a list of PI's that are recommended to be used nationally by regulators. This paper has been elaborated based on the information exchanged and discussions held in the February meeting. The participating countries (Spain, Finland, US, Sweden) and WANO were asked to provide an overview of systems in use. The presently used Performance Indicators were reviewed in a three steps process. 1. First indicators used in at least two agencies were identified. 2. The second step was to identify the most used indicators. 3. The third step was to

  16. Severe accident management (SAM), operator training and instrumentation capabilities - Summary and conclusions

    International Nuclear Information System (INIS)

    2002-01-01

    The Workshop on Operator Training for Severe Accident Management (SAM) and Instrumentation Capabilities During Severe Accidents was organised in collaboration with Electricite de France (Service Etudes et Projets Thermiques et Nucleaires). There were 34 participants, representing thirteen OECD Member countries, the Russian Federation and the OECD/NEA. Almost half the participants represented utilities. The second largest group was regulatory authorities and their technical support organisations. Basically, the Workshop was a follow-up to the 1997 Second Specialist Meeting on Operator Aids for Severe Accident Management (SAMOA-2) [Reports NEA/CSNI/R(97)10 and 27] and to the 1992 Specialist Meeting on Instrumentation to Manage Severe Accidents [Reports NEA/CSNI/R(92)11 and (93)3]. It was aimed at sharing and comparing progress made and experience gained from these two meetings, emphasizing practical lessons learnt during training or incidents as well as feedback from instrumentation capability assessment. The objectives of the Workshop were therefore: - to exchange information on recent and current activities in the area of operator training for SAM, and lessons learnt during the management of real incidents ('operator' is defined hear as all personnel involved in SAM); - to compare capabilities and use of instrumentation available during severe accidents; - to monitor progress made; - to identify and discuss differences between approaches relevant to reactor safety; - and to make recommendations to the Working Group on the Analysis and Management of Accidents and the CSNI (GAMA). The Workshop was organised into five sessions: - 1: Introduction; - 2: Tools and Methods; - 3: Training Programmes and Experience; - 4: SAM Organisation Efficiency; - 5: Instrumentation Capabilities. It was concluded by a Panel and General Discussion. This report presents the summary and conclusions: the meeting confirmed that only limited information is needed for making required decisions

  17. Proceedings of the CSNI WGOE/SEGHOF workshop on modifications at nuclear power plants - Operating experience, safety significance and the role of human factors and organisation

    International Nuclear Information System (INIS)

    2004-01-01

    Operating experience repeatedly shows that changes and modifications at nuclear power plants (NPPs) may lead to safety significant events. At the same time, modifications are necessary to ensure a safe and economic functioning of the NPPs. To ensure the continuing safety of NPPs it is important that processes for change and modification are given proper attention both by the NPPs and the regulators. The operability, maintainability and testability of every modification should be thoroughly assessed from different points of view to ensure that no safety problems are introduced. The OECD/NEA Committee on Safety of Nuclear Installations (CSNI) addressed the issue of modifications at a 'Workshop on Modifications at Nuclear Power Plants - Operating Experience, Safety Significance and Role of Human Factors' held at the OECD headquarters in Paris on October 6 to 8, 2003. This workshop was undertaken as a joint effort of the Working Group on Operating Experience (WGOE) and the Special Experts Group on Human and Organisational Factors (SEGHOF). During the workshop, WGOE focused on the theme of 'Minor Modifications and their Safety Significance', while SEGHOF focused on the topic 'Human and Organisational Factors in NPP Modifications'. The workshop was attended by 55 experts from the industry, regulators and technical support organizations in 15 countries. The workshop programme consisted of plenary and parallel sessions for presentations and discussions. One important part of the workshop was to discuss findings of the WGOE and SEGHOF surveys of utility and regulatory experience from modifications at the NPPs. Modifications at the NPPs are controlled by written procedures. The process varies depending on the type of the modification. Large modifications generally lead to fewer problems, because the projects are given both a great deal of attention and resources. In contrast, minor modifications seem to represent a generic challenge because they are less likely to be

  18. BEAUTY'99 Conference Summary

    International Nuclear Information System (INIS)

    Eerola, Paula

    2000-01-01

    Investigations of B hadrons are expected to break new ground in measuring CP-violation effects. This series of BEAUTY conferences, originating from the 1993 conference in Liblice, has contributed significantly in developing ideas of CP-violation measurements using B hadrons and formulating and comparing critically the B-physics experiments. In the '99 conference in Bled we saw the ripening of the field and the first fruit emerging - Tevatron have produced beautiful B-physics results and more are expected to come with the next run, while the B-physics experiments at DESY, SLAC and KEK are starting their operation. The longer-term projects at LHC and Tevatron have taken their shape and detailed prototyping work is going on. Meanwhile, on the phenomenological side, there has been impressive theoretical progress in understanding deeper the 'standard' measurements and proposing new signatures. In this summary, I will highlight the status of the field as presented in the conference, concentrating on signatures, experiments and R and D programmes

  19. Mineral commodity summaries 2013

    Science.gov (United States)

    ,

    2013-01-01

    Each chapter of the 2013 edition of the U.S. Geological Survey (USGS) Mineral Commodity Summaries (MCS) includes information on events, trends, and issues for each mineral commodity as well as discussions and tabular presentations on domestic industry structure, Government programs, tariffs, 5-year salient statistics, and world production and resources. The MCS is the earliest comprehensive source of 2012 mineral production data for the world. More than 90 individual minerals and materials are covered by two-page synopses. For mineral commodities for which there is a Government stockpile, detailed information concerning the stockpile status is included in the two-page synopsis. Abbreviations and units of measure, and definitions of selected terms used in the report, are in Appendix A and Appendix B, respectively. “Appendix C—Reserves and Resources” includes “Part A—Resource/Reserve Classification for Minerals” and “Part B—Sources of Reserves Data.” A directory of USGS minerals information country specialists and their responsibilities is Appendix D. The USGS continually strives to improve the value of its publications to users. Constructive comments and suggestions by readers of the MCS 2013 are welcomed.

  20. Mineral commodity summaries 2014

    Science.gov (United States)

    ,

    2014-01-01

    Each chapter of the 2014 edition of the U.S. Geological Survey (USGS) Mineral Commodity Summaries (MCS) includes information on events, trends, and issues for each mineral commodity as well as discussions and tabular presentations on domestic industry structure, Government programs, tariffs, 5-year salient statistics, and world production and resources. The MCS is the earliest comprehensive source of 2013 mineral production data for the world. More than 90 individual minerals and materials are covered by two-page synopses. For mineral commodities for which there is a Government stockpile, detailed information concerning the stockpile status is included in the two-page synopsis. Abbreviations and units of measure, and definitions of selected terms used in the report, are in Appendix A and Appendix B, respectively. “Appendix C—Reserves and Resources” includes “Part A—Resource/Reserve Classification for Minerals” and “Part B—Sources of Reserves Data.” A directory of USGS minerals information country specialists and their responsibilities is Appendix D. The USGS continually strives to improve the value of its publications to users. Constructive comments and suggestions by readers of the MCS 2014 are welcomed.

  1. Summary of exotic collider concepts group

    International Nuclear Information System (INIS)

    Pellegrini, C.

    1995-01-01

    We present a summary of the discussions in the Exotic Collider Concepts Group. Most of the discussions were centered around the status and open problems for muon-muon and gamma-gamma colliders. In addition the group discussed some general problems and new results of accelerator physics. copyright 1995 American Institute of Physics

  2. Summary of nuclear fuel reprocessing activities around the world

    International Nuclear Information System (INIS)

    Mellinger, P.J.; Harmon, K.M.; Lakey, L.T.

    1984-11-01

    This review of international practices for nuclear fuel reprocessing was prepared to provide a nontechnical summary of the current status of nuclear fuel reprocessing activities around the world. The sources of information are widely varied

  3. Status of solar neutrino experiments

    International Nuclear Information System (INIS)

    Beier, E.W.; Davis, R. Jr.; Kim, S.B.; Jelley, N.

    1990-01-01

    A summary of the status of four solar neutrino experiments is presented. The Homestake 37 Cl data are presented and the possible time dependence of the data is addressed. Data from 1040 days of operation of the Kamiokande II detector are presented next. The status of the 71 Ga experiment in the Baksan Neutrino Observatory, which has operated for a short time, is discussed. The summary concludes with a discussion of the status of the Sudbury Neutrino Observatory, which has been under construction since the beginning of 1990. 7 refs., 6 figs

  4. Comparison report of the OECD/CSNI international standard problem 21 (Piper-one experiment PO-SB-7). Volume 1 comparison report. Volume 2 evaluation of code accuracy in the prediction of ISP 21

    International Nuclear Information System (INIS)

    1989-11-01

    The present report deals with the comparison of 6 blind predictions, submitted by 5 participants, and the experimental results measured during the test PO-SB-7 performed in PIPER-ONE facility. The PIPER-ONE apparatus is an experimental simulator of a General Electric BWR. The test PO-SB-7 simulates a SB-LOCA originated by a break in one recirculation line of the reference BWR-6 plant, without intervention of high pressure ECCS. The overall activity constitutes the CSNI ISP-21. The main parts of the report are: a) outline of the test facility and of the PO-SB-7 experiment; b) overview of input models used by participants; c) evaluation of participant predictions on the basis of one-by-one comparison with selected experimental trends; d) evaluation of present code capabilities and accuracy, on the basis of the overall comparison between measured data and participants double blind predictions. Finally, a judgement is given in relation to the overall value of the activity

  5. Mineral Commodity Summaries 2009

    Science.gov (United States)

    ,

    2009-01-01

    Each chapter of the 2009 edition of the U.S. Geological Survey (USGS) Mineral Commodity Summaries (MCS) includes information on events, trends, and issues for each mineral commodity as well as discussions and tabular presentations on domestic industry structure, Government programs, tariffs, 5-year salient statistics, and world production and resources. The MCS is the earliest comprehensive source of 2008 mineral production data for the world. More than 90 individual minerals and materials are covered by two-page synopses. For mineral commodities for which there is a Government stockpile, detailed information concerning the stockpile status is included in the two-page synopsis. Because specific information concerning committed inventory was no longer available from the Defense Logistics Agency, National Defense Stockpile Center, that information, which was included in earlier Mineral Commodity Summaries publications, has been deleted from Mineral Commodity Summaries 2009. National reserves and reserve base information for most mineral commodities found in this report, including those for the United States, are derived from a variety of sources. The ideal source of such information would be comprehensive evaluations that apply the same criteria to deposits in different geographic areas and report the results by country. In the absence of such evaluations, national reserves and reserve base estimates compiled by countries for selected mineral commodities are a primary source of national reserves and reserve base information. Lacking national assessment information by governments, sources such as academic articles, company reports, common business practice, presentations by company representatives, and trade journal articles, or a combination of these, serve as the basis for national reserves and reserve base information reported in the mineral commodity sections of this publication. A national estimate may be assembled from the following: historically reported

  6. FEMA Disaster Declarations Summary

    Data.gov (United States)

    Department of Homeland Security — The FEMA Disaster Declarations Summary is a summarized dataset describing all federally declared disasters, starting with the first disaster declaration in 1953,...

  7. Summary information report

    International Nuclear Information System (INIS)

    1982-07-01

    The Summary Information Report (SIR) provides summary data concerning NRC and its licensees for general use by the Chairman, other Commissioners and Commission staff offices, the Executive Director for Operations, and the Office Directors. SIR is published quarterly by the Management Information Branch (49-27834) of the Office of Resource Management

  8. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1982-06-01

    The unresolved safety issues summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to Congress pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the Office of Resource Management. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  9. Summary big data

    CERN Document Server

    2014-01-01

    This work offers a summary of Cukier the book: "Big Data: A Revolution That Will Transform How we Live, Work, and Think" by Viktor Mayer-Schonberg and Kenneth. Summary of the ideas in Viktor Mayer-Schonberg's and Kenneth Cukier's book: " Big Data " explains that big data is where we use huge quantities of data to make better predictions based on the fact we identify patters in the data rather than trying to understand the underlying causes in more detail. This summary highlights that big data will be a source of new economic value and innovation in the future. Moreover, it shows that it will

  10. Computer software summaries. Numbers 1 through 423

    International Nuclear Information System (INIS)

    1979-09-01

    The National Energy Software Center (NESC) serves as the software exchange and information center for the US Department of Energy and the Nuclear Regulatory Commission. A major activity of the Center is the preparation and publication of two reports issued periodically - the Center's compilation of program abstracts, ANL-7411, and this software summaries report, ANL-8040. The abstracts describe the softward packages available in the software exchange library maintained and distributed by the Center. The summaries describe agency-sponsored software that is at the specification stage, under development, being checked out, in use, or available at agency offices, laboratories, and contractor installations. Summaries describe software that is not included in the NESC library due to its preliminary status or because it is believed to be of limited interest. The purpose of the summaries report is to keep agency and contractor personnel informed as to the existence, status, and availability of computer programs within the agency, and thereby minimize duplication costs and maximize the value of agency software development efforts

  11. A summary of INSITE activities in tracking SKB's spent fuel repository site investigations from 2002-2009 and of advice provided to the regulatory authorities on the status of site understanding at the end of the surface-based investigations

    International Nuclear Information System (INIS)

    Chapman, Neil; Bath, Adrian; Geier, Joel; Ove Stephansson; Tiren, Sven; Tsang, Chin-Fu

    2010-11-01

    SSM and its predecessor SKI employed a team of earth scientists who followed and reviewed SKB's investigations of the potential spent nuclear fuel repository sites at Forsmark and Laxemar. This group was named INSITE (INdependent Site Investigation Tracking and Evaluation) and began its work in 2002 and completed its task with the review of the final versions SKB's site descriptive models, SDM-Site, in 2009. This report is a summary of INSITE's work over the eight-and-a-half year period of the site investigations and the lead-in and the wind-down to the work. It is intended to provide an outline and a record of how INSITE has worked and how its advice was generated and provided to SKI and, latterly, to SSM. Together with all the other documentation generated by INSITE, this report is intended to support the regulatory review of SKB's licence application for a spent nuclear fuel repository

  12. Worldwide Airfield Summary

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Worldwide Airfield Summary contains a selection of climatological data produced by the U.S. Air Force, Air Weather Service. The reports were compiled from dozens...

  13. Annual Meteorological Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Single-year summaries of observations at Weather Bureau and cooperative stations across the United States. Predominantly the single page Form 1066, which includes...

  14. Summary of Research 1997

    OpenAIRE

    Maier, William B.; Cleary, David D.

    1997-01-01

    This report contains summaries of research projects in the Department of Physics. A list of recent publications in also included which consists of conference presentations and publications, books, contributions to books, published jounal papers, technical reports, and thesis abstracts.

  15. Global Climate Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The Global Hourly Summaries are simple indicators of observational normals which include climatic data summarizations and frequency distributions. These typically...

  16. Cancer Information Summaries

    Science.gov (United States)

    Peer-reviewed, evidence-based summaries on topics including adult and pediatric cancer treatment, supportive and palliative care, screening, prevention, genetics, and complementary and alternative medicine. References to published literature are included.

  17. Summaries of poster contributions

    International Nuclear Information System (INIS)

    1981-01-01

    The 10. meeting covered subjects on the application of electron microscopy in numerous fields such as biology and medicine, solid state physics, semiconductor research and production, crystallography, materials science, and chemistry of polymers. 174 summaries of poster contributions are included

  18. Oceanographic Monthly Summary

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Oceanographic Monthly Summary contains sea surface temperature (SST) analyses on both regional and ocean basin scales for the Atlantic, Pacific, and Indian Oceans....

  19. MSIS State Summary Datamarts

    Data.gov (United States)

    U.S. Department of Health & Human Services — This page provides background needed to take advantage of the capabilities of the MSIS State Summary Datamart. This mart allows the user to develop high-level...

  20. Summary of blog

    CERN Document Server

    Reader, Capitol

    2013-01-01

    This ebook consists of a summary of the ideas, viewpoints and facts presented by Hugh Hewitt in his book "Blog: Understanding the Information Reformation that's Changing Your World". This summary offers a concise overview of the entire book in less than 30 minutes reading time. However this work does not replace in any case Hugh Hewitt's book.Hewitt argues that blogs have an important potential and he believes that it would be a dreadful mistake to avoid their power.

  1. Site environmental report summary

    International Nuclear Information System (INIS)

    1992-01-01

    In this summary of the Fernald 1992 Site Environmental Report the authors will describe the impact of the Fernald site on man and the environment and provide results from the ongoing Environmental Monitoring Program. Also included is a summary of the data obtained from sampling conducted to determine if the site complies with DOE, US Environmental Protection Agency (USEPA), and Ohio EPA (OEPA) requirements. These requirements are set to protect both man and the environment

  2. Challenges and Enhancements to Defence-in-Depth (DiD) in Light of the Fukushima Daiichi NPP Accident. Proceedings of a Joint CNRA/CSNI Workshop, Paris, France, 5 June 2013

    International Nuclear Information System (INIS)

    Niel, Jean-Christophe; Autorite de surete nucleaire - ASN; ); Echavarri, Luis; ); Schneider, Thierry; ); Borchardt, Bill; Wanner, Hans; Park, Youn Won; Glenn, Tracy; Regaldo, Jacques; Fuketa, Toyoshi; Repussard, Jacques; Bolshov, Leonid; Chevet, Pierre Frank

    2014-01-01

    An international Workshop on Challenges and Enhancements to Defence in Depth (DiD) in Light of the Fukushima Daiichi Accident was jointly organised by the NEA Committee on Nuclear Regulatory Activities (CNRA) and the NEA Committee on the Safety on Nuclear Installations (CSNI), with input from the NEA Committee on Radiation Protection and Public Health (CRPPH), on 5 June 2013 in Paris. About 100 participants from NEA member countries, India, the International Atomic Energy Agency (IAEA), the World Association of Nuclear Operators (WANO) and Eurelectric held in-depth discussions on the defence-in-depth concept and its implementation in the post-Fukushima context. They also considered additional steps to be taken at the national and international levels to address the challenges identified and to make further enhancements to nuclear safety, along with future NEA activities in support of these processes. The concept of DiD - of multiple levels of protection - has been developed and refined by the nuclear safety community over many years. The concept is based on the experience and practice of high hazard industry in general as well as developments within the nuclear industry. The accident at the Fukushima Daiichi Nuclear Power Station in Japan on the 11 March 2011 demonstrated the importance of the concept of DiD, how these multiple levels of protection can operate and how some can be challenged. Just as with the nuclear accidents at Three Mile Island and Chernobyl and accidents from other industries (e.g. chemical, aerospace, oil and gas), the NEA felt it important that lessons learned are used to further develop the concept and implementation of Defence-in-Depth to help ensure and enhance the safe operation of nuclear power plants around the world. The NEA has therefore looked at the concept and implementation of Defence-in-Depth and possible challenges and enhancements. It was noted that a great deal of interest has been shown in this area, particularly in the

  3. ATLAS @ LHC: status and recent results

    CERN Document Server

    McPherson, Robert; The ATLAS collaboration

    2017-01-01

    The status and data taking summary of the ATLAS experiment at the CERN Large Hadron Collider is reviewed. Recent physics analysis results are presented, and the detector upgrade program is briefly summarized.

  4. EOS Aqua: Mission Status at Earth Science Constellation

    Science.gov (United States)

    Guit, Bill

    2016-01-01

    This is an EOS Aqua Mission Status presentation to be given at the MOWG meeting in Albuquerque NM. The topics to discus are: mission summary, spacecraft subsystems summary, recent and planned activities, inclination adjust maneuvers, propellant usage and lifetime estimate, and mission summary.

  5. Workshop on large molten pool heat transfer summary and conclusions

    International Nuclear Information System (INIS)

    1994-01-01

    The CSNI Workshop on Large Molten Heat Transfer held at Grenoble (France) in March 1994 was organised by CSNI's Principal Working Group on the Confinement of Accidental Radioactive Releases (PWG4) with the cooperation of the Principal Working Group on Coolant System Behaviour (FWG2) and in collaboration with the Grenoble Nuclear Research Centre of the French Commissariat a l'Energie Atomique (CEA). Conclusions and recommendations are given for each of the five sessions of the workshops: Feasibility of in-vessel core debris cooling through external cooling of the vessel; Experiments on molten pool heat transfer; Calculational efforts on molten pool convection; Heat transfer to the surrounding water - experimental techniques; Future experiments and ex-vessel studies (open forum discussion)

  6. A summary of fish and wildlife information needs to surface mine coal in the United States. Part 2. The status of state surface mining regulations as of January 1980 and the fish and wildlife information needs. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This is part 2 of a three part series to assist government agencies and private citizens in determining fish and wildlife information needs for new coal mining operations pursuant to the Surface Mining Control and Reclamation Act of 1977. This portion documents the status of individual state surface mining regulations as of January 1980 in those states having significant strippable reserves and/or active strip mining operations. It also provides documentation of fish and wildlife information needs identified in the state regulations of compliance to PL 95-87.

  7. Current Status and Recommendations for the Future of Research, Teaching, and Testing in the Biological Sciences of Radiation Oncology: Report of the American Society for Radiation Oncology Cancer Biology/Radiation Biology Task Force, Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Wallner, Paul E., E-mail: pwallner@theabr.org [21st Century Oncology, LLC, and the American Board of Radiology, Bethesda, Maryland (United States); Anscher, Mitchell S. [Department of Radiation Oncology, Virginia Commonwealth University, Richmond, Virginia (United States); Barker, Christopher A. [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Bassetti, Michael [Department of Human Oncology, University of Wisconsin Carbone Cancer Center, Madison, Wisconsin (United States); Bristow, Robert G. [Departments of Radiation Oncology and Medical Biophysics, Princess Margaret Cancer Center/University of Toronto, Toronto, Ontario (Canada); Cha, Yong I. [Department of Radiation Oncology, Norton Cancer Center, Louisville, Kentucky (United States); Dicker, Adam P. [Department of Radiation Oncology, Thomas Jefferson University, Philadelphia, Pennsylvania (United States); Formenti, Silvia C. [Department of Radiation Oncology, New York University, New York, New York (United States); Graves, Edward E. [Departments of Radiation Oncology and Radiology, Stanford University, Stanford, California (United States); Hahn, Stephen M. [Department of Radiation Oncology, University of Pennsylvania (United States); Hei, Tom K. [Center for Radiation Research, Columbia University, New York, New York (United States); Kimmelman, Alec C. [Department of Radiation Oncology, Dana-Farber Cancer Institute, Boston, Massachusetts (United States); Kirsch, David G. [Department of Radiation Oncology, Duke University, Durham, North Carolina (United States); Kozak, Kevin R. [Department of Human Oncology, University of Wisconsin (United States); Lawrence, Theodore S. [Department of Radiation Oncology, University of Michigan (United States); Marples, Brian [Department of Radiation Oncology, Oakland University, Oakland, California (United States); and others

    2014-01-01

    In early 2011, a dialogue was initiated within the Board of Directors (BOD) of the American Society for Radiation Oncology (ASTRO) regarding the future of the basic sciences of the specialty, primarily focused on the current state and potential future direction of basic research within radiation oncology. After consideration of the complexity of the issues involved and the precise nature of the undertaking, in August 2011, the BOD empanelled a Cancer Biology/Radiation Biology Task Force (TF). The TF was charged with developing an accurate snapshot of the current state of basic (preclinical) research in radiation oncology from the perspective of relevance to the modern clinical practice of radiation oncology as well as the education of our trainees and attending physicians in the biological sciences. The TF was further charged with making suggestions as to critical areas of biological basic research investigation that might be most likely to maintain and build further the scientific foundation and vitality of radiation oncology as an independent and vibrant medical specialty. It was not within the scope of service of the TF to consider the quality of ongoing research efforts within the broader radiation oncology space, to presume to consider their future potential, or to discourage in any way the investigators committed to areas of interest other than those targeted. The TF charge specifically precluded consideration of research issues related to technology, physics, or clinical investigations. This document represents an Executive Summary of the Task Force report.

  8. Summary of ENDF/B pre-processing codes

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1981-12-01

    This document contains the summary documentation for the ENDF/B pre-processing codes: LINEAR, RECENT, SIGMA1, GROUPIE, EVALPLOT, MERGER, DICTION, CONVERT. This summary documentation is merely a copy of the comment cards that appear at the beginning of each programme; these comment cards always reflect the latest status of input options, etc. For the latest published documentation on the methods used in these codes see UCRL-50400, Vol.17 parts A-E, Lawrence Livermore Laboratory (1979)

  9. Indexing for summary queries

    DEFF Research Database (Denmark)

    Yi, Ke; Wang, Lu; Wei, Zhewei

    2014-01-01

    ), of a particular attribute of these records. Aggregation queries are especially useful in business intelligence and data analysis applications where users are interested not in the actual records, but some statistics of them. They can also be executed much more efficiently than reporting queries, by embedding...... returned by reporting queries. In this article, we design indexing techniques that allow for extracting a statistical summary of all the records in the query. The summaries we support include frequent items, quantiles, and various sketches, all of which are of central importance in massive data analysis....... Our indexes require linear space and extract a summary with the optimal or near-optimal query cost. We illustrate the efficiency and usefulness of our designs through extensive experiments and a system demonstration....

  10. Specialist meeting on selected containment severe accident management strategies. Summary and conclusions

    International Nuclear Information System (INIS)

    1994-01-01

    The CSNI Specialist Meeting on Selected Containment Severe Accident Management Strategies held in Stockholm, Sweden in June 1994 was organised by the Task Group on Containment Aspects of Severe Accident Management (CAM) of CSNI's Principal Working Group on the Confinement of Accidental Radioactive Releases (PWG4) in collaboration with the Swedish Nuclear Power Inspectorate (SKI). Conclusions and recommendations are given for each of the sessions of the workshops: Containment accident management strategies (general aspects); hydrogen management techniques and other containment accident management techniques; surveillance and protection of containment function

  11. 2007 status of climate change: Mitigation of Climate Change. Contribution of Working Group III to the Fourth Assessment Report of the Intergovernmental Panel on Climate Change. Summary for Policy-makers

    International Nuclear Information System (INIS)

    Barker, T.; Bashmakov, I.; Bernstein, L.; Bogner, J.; Bosch, P.; Dave, R.; Davidson, O.; Fisher, B.; Grubb, M.; Gupta, S.; Halsnaes, K.; Heij, B.; Kahn Ribeiro, S.; Kobayashi, S.; Levine, M.; Martino, D.; Masera Cerutti, O.; Metz, B.; Meyer, L.; Nabuurs, G.J.; Najam, A.; Nakicenovic, N.; Holger Rogner, H.; Roy, J.; Sathaye, J.; Schock, R.; Shukla, P.; Sims, R.; Smith, P.; Swart, R.; Tirpak, D.; Urge-Vorsatz, D.; Dadi, Z.

    2007-01-01

    The Working Group III contribution to the IPCC Fourth Assessment Report (AR4) focuses on new literature on the scientific, technological, environmental, economic and social aspects of mitigation of climate change, published since the IPCC Third Assessment Report (TAR) and the Special Reports on CO 2 Capture and Storage (SRCCS) and on Safeguarding the Ozone Layer and the Global Climate System (SROC).The main aim of this summary report is to assess options for mitigating climate change. Several aspects link climate change with development issues. This report explores these links in detail, and illustrates where climate change and sustainable development are mutually reinforcing. Economic development needs, resource endowments and mitigative and adaptive capacities differ across regions. There is no one-size-fits-all approach to the climate change problem, and solutions need to be regionally differentiated to reflect different socio-economic conditions and, to a lesser extent, geographical differences. Although this report has a global focus, an attempt is made to differentiate the assessment of scientific and technical findings for the various regions. Given that mitigation options vary significantly between economic sectors, it was decided to use the economic sectors to organize the material on short- to medium-term mitigation options. Contrary to what was done in the Third Assessment Report, all relevant aspects of sectoral mitigation options, such as technology, cost, policies etc., are discussed together, to provide the user with a comprehensive discussion of the sectoral mitigation options. The report is organised into six sections after the introduction: - Greenhouse gas (GHG) emission trends; - Mitigation in the short and medium term, across different economic sectors (until 2030); - Mitigation in the long-term (beyond 2030); - Policies, measures and instruments to mitigate climate change; - Sustainable development and climate change mitigation; - Gaps in

  12. MIV Project: Executive Summary

    DEFF Research Database (Denmark)

    Ravazzotti, Mariolina T.; Jørgensen, John Leif; Neefs, Marc

    1997-01-01

    Under the ESA contract #11453/95/NL/JG(SC), aiming at assessing the feasibility of Rendez-vous and docking of unmanned spacecrafts, a reference mission scenario was defined. This report gives an executive summary of the achievements and results from the project.......Under the ESA contract #11453/95/NL/JG(SC), aiming at assessing the feasibility of Rendez-vous and docking of unmanned spacecrafts, a reference mission scenario was defined. This report gives an executive summary of the achievements and results from the project....

  13. Experimental Status of B Physics

    International Nuclear Information System (INIS)

    Stone, Sheldon

    2006-01-01

    A short summary is given of the current status of B physics. Reasons for physics beyond the Standard Model are discussed. Constraints on New Physics are given using measurements of B mixing, BS mixing, and CP violation, along with |Vub|. Future goals, and upcoming new experiments are also mentioned

  14. Crisis Management: Research Summaries

    Science.gov (United States)

    Brock, Stephen E., Ed.; Dorman, Sally; Anderson, Luke; McNair, Daniel

    2013-01-01

    This article presents summaries of three studies relevant to school crisis response. The first report, "A Framework for International Crisis Intervention" (Sally Dorman), is a review of how existing crisis intervention models (including the NASP PREPaRE model) have been adapted for international use. The second article, "Responding…

  15. Summary of Trends

    Indian Academy of Sciences (India)

    First page Back Continue Last page Overview Graphics. Summary of Trends. Optical Ethernet: Direct Ethernet connectivity to businesses through optical fiber. Automation of network infrastructure: Cross-connects for interconnections; Intelligence through software for OA&M. New “data-centric” protection mechanisms ...

  16. Summary of discussion

    International Nuclear Information System (INIS)

    2006-01-01

    This document provides summaries of the discussions occurred during the second international workshop on the indemnification of nuclear damage. It concerns the second accident scenario: a fire on board of a ship transporting enriched uranium hexafluoride along the Danube River. (A.L.B.)

  17. Geothermal energy. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    Brief descriptions of geothermal projects funded through the Department of Energy during FY 1978 are presented. Each summary gives the project title, contractor name, contract number, funding level, dates, location, and name of the principal investigator, together with project highlights, which provide informaion such as objectives, strategies, and a brief project description. (MHR)

  18. Symposium summary and prognosis

    International Nuclear Information System (INIS)

    Bjorken, J.D.

    1975-11-01

    The summary of the symposium on high energy physics experiments includes phenomena at low energies, the foundations of physics (considered to be mainly gravitation and quantum electrodynamics), standards of reference used for interpretation of experimental data, the new physics, particle proliferation, theoretical development, and a prognosis for the future

  19. Summary of Session III

    International Nuclear Information System (INIS)

    Furman, M.A.

    2002-01-01

    This is a summary of the talks presented in Session III ''Simulations of Electron-Cloud Build Up'' of the Mini-Workshop on Electron-Cloud Simulations for Proton and Positron Beams ECLOUD-02, held at CERN, 15-18 April 2002

  20. Executive Summaries: CIL '90.

    Science.gov (United States)

    Elsweiler, John A., Jr.; And Others

    1990-01-01

    Presents summaries of 12 papers presented at the 1990 Computers in Libraries Conference. Topics discussed include online searching; microcomputer-based serials management; microcomputer-based workstations; online public access catalogs (OPACs); multitype library networking; CD-ROM searches; locally mounted online databases; collection evaluation;…

  1. Healthcare. Executive Summary

    Science.gov (United States)

    Carnevale, Anthony P.; Smith, Nicole; Gulish, Artem; Beach, Bennett H.

    2012-01-01

    This executive summary highlights several findings about healthcare. These are: (1) Healthcare is 18 percent of the U.S. economy, twice as high as in other countries; (2) There are two labor markets in healthcare: high-skill, high-wage professional and technical jobs and low-skill, low-wage support jobs; (3) Demand for postsecondary education in…

  2. Summary Stage 2018 - SEER

    Science.gov (United States)

    Access this manual of codes and coding instructions for the summary stage field for cases diagnosed January 1, 2018 and forward. 2018 version applies to every site and/or histology combination, including lymphomas and leukemias. Historically, also called General Staging, California Staging, and SEER Staging.

  3. Preliminary Integrated Safety Analysis Status Report

    International Nuclear Information System (INIS)

    Gwyn, D.

    2001-01-01

    This report provides the status of the potential Monitored Geologic Repository (MGR) Integrated Safety Analysis (EA) by identifying the initial work scope scheduled for completion during the ISA development period, the schedules associated with the tasks identified, safety analysis issues encountered, and a summary of accomplishments during the reporting period. This status covers the period from October 1, 2000 through March 30, 2001

  4. Report of the task group on the seismic behaviour of structures: status report

    International Nuclear Information System (INIS)

    1997-04-01

    In 1995, the CSNI Committee on the Safety of Nuclear Installations) approved a new mandate for PWG-3 and the new title 'Integrity of Components and Structures'. The PWG-3 is assisted by three task groups, one of which is addressing the problem of seismic behavior of structures. Ten topics were identified: engineering characterization of seismic input, site response, soil structure interaction, identification of functions and classification of systems, structures and components, structural response and capacity evaluation (including effects of aging and degradation), component and equipment response and capacity evaluation (including effects of aging and degradation), response and capacity evaluation of distribution systems (piping, cable trays, conduit, HVAC), load combination and acceptance criteria, uncertainties (PSA and margins), plant seismic instrumentation and trip. This report summarizes the seismic issues and activities in various member countries (Canada, Czech Republic, France, Hungary, Italy, Japan, Spain, Switzerland, United Kingdom, United States) and international organizations (IAEA), provides a summary of the important issues that are of collective interest to the group members, and recommends a future programme of work to address these issues

  5. Mirror Confinement Systems: project summaries

    International Nuclear Information System (INIS)

    1980-07-01

    This report contains descriptions of the projects supported by the Mirror Confinement Systems (MCS) Division of the Office of Fusion Energy. The individual project summaries were prepared by the principal investigators, in collaboration with MCS staff office, and include objectives and milestones for each project. In addition to project summaries, statements of Division objectives and budget summaries are also provided

  6. Summary on experiments

    International Nuclear Information System (INIS)

    Livingston, A.E.

    1981-01-01

    Experimental studies of the atomic structures of both simple and complex atoms and ions provide crucial tests of atomic structure theory and of calculational techniques for a wide range of atomic systems. This summary is restricted to a brief discussion of some recent and current experiments in few-electron and many-electron atoms and ions which represent exciting challenges to sophisticated atomic structure calculations, discussed elsewhere. In particular the emphasis is on high-Z systems

  7. Blois V: Experimental summary

    International Nuclear Information System (INIS)

    Albrow, M.G.

    1993-09-01

    The author gives a summary talk of the best experimental data given at the Vth Blois Workshop on Elastic and Diffractive Scattering. He addresses the following eight areas in his talk: total and elastic cross sections; single diffractive excitation; electron-proton scattering; di-jets and rapidity gaps; areas of future study; spins and asymmetries; high-transverse momentum and masses at the Tevatron; and disoriented chiral condensates and cosmic radiation

  8. Summary and outlook

    Energy Technology Data Exchange (ETDEWEB)

    Jong, M. de, E-mail: mjg@nikhef.nl [Nikhef - National Institute for Subatomic Physics, Science Park 105, 1098 XG Amsterdam (Netherlands); LION - Leiden Institute of Physics, Leiden University, PO Box 9504, 2300 RA Leiden (Netherlands)

    2013-10-11

    In 2003, a series of Very Large Volume Neutrino Telescope Workshops (VLVnT) was initiated in Amsterdam, the Netherlands. The 5th workshop in this series took place in Erlangen, Germany, between 12–14 October 2011 and focused on the aspects of high-energy neutrino astronomy. In this summary report, an overview of the activities world-wide is presented as well as the perspectives of the field.

  9. Blois 5: Experimental summary

    Science.gov (United States)

    Albrow, M. G.

    1993-09-01

    The author gives a summary talk of the best experimental data given at the 5th Blois Workshop on Elastic and Diffractive Scattering. He addresses the following eight areas in his talk: total and elastic cross sections; single diffractive excitation; electron-proton scattering; di-jets and rapidity gaps; areas of future study; spins and asymmetries; high-transverse momentum and masses at the Tevatron; and disoriented chiral condensates and cosmic radiation.

  10. Mineral commodity summaries 2015

    Science.gov (United States)

    ,

    2015-01-01

    Each chapter of the 2015 edition of the U.S. Geological Survey (USGS) Mineral Commodity Summaries (MCS) includes information on events, trends, and issues for each mineral commodity as well as discussions and tabular presentations on domestic industry structure, Government programs, tariffs, 5-year salient statistics, and world production and resources. The MCS is the earliest comprehensive source of 2014 mineral production data for the world. More than 90 individual minerals and materials are covered by two-page synopses.

  11. Blois V: Experimental summary

    Energy Technology Data Exchange (ETDEWEB)

    Albrow, M.G.

    1993-09-01

    The author gives a summary talk of the best experimental data given at the Vth Blois Workshop on Elastic and Diffractive Scattering. He addresses the following eight areas in his talk: total and elastic cross sections; single diffractive excitation; electron-proton scattering; di-jets and rapidity gaps; areas of future study; spins and asymmetries; high-transverse momentum and masses at the Tevatron; and disoriented chiral condensates and cosmic radiation.

  12. ULSGEN (Uplink Summary Generator)

    Science.gov (United States)

    Wang, Y.-F.; Schrock, M.; Reeve, T.; Nguyen, K.; Smith, B.

    2014-01-01

    Uplink is an important part of spacecraft operations. Ensuring the accuracy of uplink content is essential to mission success. Before commands are radiated to the spacecraft, the command and sequence must be reviewed and verified by various teams. In most cases, this process requires collecting the command data, reviewing the data during a command conference meeting, and providing physical signatures by designated members of various teams to signify approval of the data. If commands or sequences are disapproved for some reason, the whole process must be restarted. Recording data and decision history is important for traceability reasons. Given that many steps and people are involved in this process, an easily accessible software tool for managing the process is vital to reducing human error which could result in uplinking incorrect data to the spacecraft. An uplink summary generator called ULSGEN was developed to assist this uplink content approval process. ULSGEN generates a web-based summary of uplink file content and provides an online review process. Spacecraft operations personnel view this summary as a final check before actual radiation of the uplink data. .

  13. Summary of fuel safety research meeting 2004

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

    2004-10-01

    Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

  14. Summary of current issues regarding space flight habitability.

    Science.gov (United States)

    Novak, J B

    2000-09-01

    One of the implicit, yet often under-emphasized qualities of human tended spaceflight is the habitability of the spacecraft and mission. This document summarizes some of the points that characterize the current status of this topic. In addition, the summary concludes with goals for future development for this issue.

  15. Short rotation woody crops program: 1982 program summary

    Energy Technology Data Exchange (ETDEWEB)

    Ranney, J.W.; Cushman, J.H.; Trimble, J.L.

    1982-09-01

    The general objective and overall approach of the program are discussed, and the status, specific goals, and recent results of the three major research areas are presented. The report concludes with brief summaries of the individual research projects in the program.

  16. Quarterly environmental radiological survey summary: 100, 200, 300 and 600 Areas. Fourth quarter 1994

    International Nuclear Information System (INIS)

    McKinney, S.M.

    1995-01-01

    This report provides a summary of the radiological surveys performed on waste disposal sites located at the Hanford Site. The Fourth Quarter 1994 survey results and the status of actions required from current and past reports are summarized

  17. Biomass energy systems program summary. Information current as of September 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    This program summary describes each of the DOE's Biomass Energy System's projects funded or in existence during fiscal year 1979 and reflects their status as of September 30, 1979. The summary provides an overview of the ongoing research, development, and demonstration efforts of the preceding fiscal year as well. (DMC)

  18. Summary of ENDF/B Pre-Processing Codes June 1983

    International Nuclear Information System (INIS)

    Cullen, D.E.

    1983-06-01

    This is the summary documentation for the 1983 version of the ENDF/B Pre-Processing Codes LINEAR, RECENT, SIGMA1, GROUPIE, EVALPLOT, MERGER, DICTION, COMPLOT, CONVERT. This summary documentation is merely a copy of the comment cards that appear at the beginning of each programme; these comment cards always reflect the latest status of input options, etc

  19. LEAP 1992: Conference summary

    International Nuclear Information System (INIS)

    Dover, C.B.

    1992-12-01

    We present a summary of the many new results in antiproton (bar p) physics presented at the LEAP '92 conference, in the areas of meson spectroscopy, bar NN scattering, annihilation and spin observables, strangeness and charm production, bar N annihilation in nuclei, atomic physics with very low energy bar p's, the exploration of fundamental symmetries and interactions with bar p (CP, T, CPT, gravitation), and the prospects for new bar p facilities at ultralow energies or energies above the LEAR regime (≥ 2 GeV/c)

  20. FY 1996 activity summary

    International Nuclear Information System (INIS)

    1997-01-01

    The US Department of Energy Office of Nuclear and Facility Safety provides nuclear safety policy, independent technical evaluation, and technical support. A summary of these activities is provided in this report. These include: (1) changing the mission of the former production facilities to storage and waste management; (2) stabilizing nuclear materials not recycled due to production cessation or interruptions; (3) reformulating the authorization basis for existing facilities to convert to a standards based approach for operations consistent with modern expectations; and (4) implementing a modern regulatory framework for nuclear facilities. Enforcement of the Price-Anderson Amendments Act is also reported

  1. Program summary report

    International Nuclear Information System (INIS)

    1978-01-01

    The report provides summary information on all phases of nuclear regulation, and is intended as an information and decision-making tool for mid and upper level management of the Nuclear Regulatory Commission. The report is divided functionally into ten sections: (1) nuclear power plants in the United States; (2) operating nuclear power plants; (3) reactors under construction; (4) operating license applications under NRC review; (5) construction permit applications and special projects under NRC review; (6) ACRS and ASLBP; (7) nuclear materials; (8) standards and regulations; (9) research projects; and (10) foreign reactors

  2. 39 CFR 3060.22 - Financial status report.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Financial status report. 3060.22 Section 3060.22... THEORETICAL COMPETITIVE PRODUCTS ENTERPRISE § 3060.22 Financial status report. The Postal Service shall file a Financial Status Report in the form and content of Table 2, below. Table 2—Annual Summary of Competitive...

  3. Summary of main points

    International Nuclear Information System (INIS)

    2006-01-01

    In conjunction with its 6. annual meeting, the WPDD in close co-operation with the FSC held a Topical session on 'Stakeholder Involvement in Decommissioning' on November 14, 2005. The session was attended by 36 participants totally representing 14 NEA member countries and 2 international organisations. Two keynote addresses were given at the Topical Session. The first one treated of what is needed for robust decisions and how to bring all stakeholders into the debate. In the second keynote address a summary was made on what have been said on stakeholder involvement in decommissioning during earlier meetings of the WPDD. The main part of the session was then devoted to views from different stakeholders regarding their role and their involvement. This part contained viewpoints from local communities (Kaevlinge in Sweden and Port Hope in Canada), authorities (Scottish Executive and CSNC) and operators (EDF from France and EWN from Germany). Case studies from the decommissioning of Dounrey in the UK and from Trojan and Main Yankee in the USA were presented in the end part of the Topical session followed by a summary and lessons learnt report by the Rapporteur. A detailed programme of the Topical session can be seen in Appendix 1

  4. Regulatory aspects of management of change - Summary and conclusions

    International Nuclear Information System (INIS)

    2002-01-01

    Nuclear licensees are increasingly required to adapt to a more challenging commercial environment as moves to de-regulate electricity markets gather pace. One of the costs that is often perceived as being amenable to control is staffing, and hence there is significant exploration of new strategies for managing staffing levels. This report presents the outputs from a Workshop convened by the Special Experts' Group in Human and Organisational Factors (SEGHOF) of the Committee for the Safety of Nuclear Installations (CSNI) and organised by the UK Nuclear Installations Inspectorate (NII). The purpose of the workshop was to facilitate the exchange of views on, and approaches towards, the regulation of organisational change. The major risks associated with organisational change were discussed, and a range of regulatory challenges was identified for detailed discussion. There was agreement that the licensee must retain the responsibility to manage its own business but that organisational issues should be subject to regulatory scrutiny if they have the potential to impact on safety. The regulator should be able to demonstrate an approach to oversight of organisational change which is valid, transparent and consistent, and should inform the licensee of its expectations in terms of information supplied, communication and timing. The workshop confirmed that there is significant agreement between regulators concerning the need for licensees to put in place arrangements to manage organisational change. There was also broad consensus on what should constitute the elements of a licensee's management of change process. Differing views were evident about the balance between regulatory scrutiny of the process, as opposed to the outcomes of change, which largely represents differing regulatory regimes and philosophies. However, it was acknowledged that the regulator must be capable of taking an early view of the adequacy of proposed changes, rather than monitoring outcomes alone

  5. SUMMARY OF ARTICLES

    Institute of Scientific and Technical Information of China (English)

    2012-01-01

    The Group of Middle-Aged Historians and Chinese Marxist Historiography In the seventeen years after the founding of People's Republic of China, those historians born around 1910 who possessed strong academic basis of textual research on historical materials, held certain academic status, and were being in their exuberant academic life went through a transformation.

  6. Hazmat Yearly Incident Summary Reports

    Data.gov (United States)

    Department of Transportation — Series of Incident data and summary statistics reports produced which provide statistical information on incidents by type, year, geographical location, and others....

  7. Panel: Current Status of Knowledge and Recommendations for Further Related Activities

    International Nuclear Information System (INIS)

    Caldarola, L.; Costa, J.; Fauske, Hans K.; Jakeman, D.; Mizuta, H.; Wright, R.W.; Stadie, K.B.

    1976-01-01

    This Panel consists of two parts, in the first part the participants attempt to summarise their views on the current status and knowledge of SFI and its importance for the LMFBR safety case and in the second part they try to agree on recommendations for future actions. The first question tackled was: what progress has been made since the Ispra meeting which was a little over two years ago - in answering the question: 'what role does SFI play in LMFBR safety'? The second question approached was: 'Is it possible to identify SFI areas which are not yet covered by the present research and development programme? Finally 4 recommendations were proposed: 1. to have another meeting of the same nature as this one and the previous ones in two years' time; 2. to create a group dealing with the fundamental science with a view to further the safety of the LMFBR. This group would meet more regularly and would not require, and that is the important thing, approval from-CSNI every time it meets; 3. to discontinue the group on calculational models; 4. to publish at least one to two newsletters between this SFI meeting and the next SFI meeting in two years

  8. ICHEP 2014 Summary: Theory Status after the First LHC Run

    Science.gov (United States)

    Pich, Antonio

    2016-04-01

    A brief overview of the main highlights discussed at ICHEP 2014 is presented. The experimental data confirm that the scalar boson discovered at the LHC couples to other particles as predicted in the Standard Model. This constitutes a great success of the present theoretical paradigm, which has been confirmed as the correct description at the electroweak scale. At the same time, the negative searches for signals of new phenomena tightly constrain many new-physics scenarios, challenging previous theoretical wisdom and opening new perspectives in fundamental physics. Fresh ideas are needed to face the many pending questions unanswered within the Standard Model framework.

  9. Summary of the status of lasers for inertial confinement fusion

    International Nuclear Information System (INIS)

    Holzrichter, J.F.

    1979-01-01

    Laser systems designed for plasma research are operating in many laboratories throughout the world. The laser performance itself has become reasonably consistant from laboratory to laboratory and the focusing properties of the laser beams are understood. The plasma physics data, obtained with these systems, also appears to be reasonably self-consistant and is of great interest for inertial fusion applications. These lasers are commonly providing output powers of 0.5 > 2 TW, and power densities on target of 10 13 -10- 16 W/cm 2 , pulse durations on the order of 100 psec to 3 nsec, wavelengths between 0.5 μ and 10 μ, and focal spot sizes of 100 μ or larger where focal spot edge effects are becoming less dominant. In addition, spurious target responses due to such behavior as pre-pulses, self-focusing, or imprecise focal spot measurement are being observed less often. The technical problems of large multi-beam systems, performing at the 10 TW level, have been overcome and these systems (e.g. the Shiva and Helios lasers) are providing high density compression data with ablative targets. The next step in laser design, the 100 to 300 kJ systems, are under construction and 1 MJ lasers are being contemplated

  10. The Earthquake Source Inversion Validation (SIV) - Project: Summary, Status, Outlook

    Science.gov (United States)

    Mai, P. M.

    2017-12-01

    Finite-fault earthquake source inversions infer the (time-dependent) displacement on the rupture surface from geophysical data. The resulting earthquake source models document the complexity of the rupture process. However, this kinematic source inversion is ill-posed and returns non-unique solutions, as seen for instance in multiple source models for the same earthquake, obtained by different research teams, that often exhibit remarkable dissimilarities. To address the uncertainties in earthquake-source inversions and to understand strengths and weaknesses of various methods, the Source Inversion Validation (SIV) project developed a set of forward-modeling exercises and inversion benchmarks. Several research teams then use these validation exercises to test their codes and methods, but also to develop and benchmark new approaches. In this presentation I will summarize the SIV strategy, the existing benchmark exercises and corresponding results. Using various waveform-misfit criteria and newly developed statistical comparison tools to quantify source-model (dis)similarities, the SIV platforms is able to rank solutions and identify particularly promising source inversion approaches. Existing SIV exercises (with related data and descriptions) and all computational tools remain available via the open online collaboration platform; additional exercises and benchmark tests will be uploaded once they are fully developed. I encourage source modelers to use the SIV benchmarks for developing and testing new methods. The SIV efforts have already led to several promising new techniques for tackling the earthquake-source imaging problem. I expect that future SIV benchmarks will provide further innovations and insights into earthquake source kinematics that will ultimately help to better understand the dynamics of the rupture process.

  11. National Status and Trends: Bioeffects Program - Massachusetts Bay Summary Database

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This study was based on the sediment quality triad (SQT) approach. The purpose was to define the extent and magnitude of contamination and biological effects...

  12. Par Pond vegetation status Summer 1995 -- June survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-06-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the shoreline aquatic plant communities in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level, indicated that much of the original plant communities and the intermediate shoreline communities present on the exposed sediments have been lost. The extensive old-field and emergent marsh communities that were present on the exposed shoreline during the drawdown have been flooded and much of the pre-drawdown Par Pond aquatic plant communities have not had sufficient time for re-establishment. The shoreline does, however, have extensive beds of maidencane which extend from the shoreline margin to areas as deep as 2 and perhaps 3 meters. Scattered individual plants of lotus and watershield are common and may indicate likely directions of future wetland development in Par Pond. In addition, within isolated coves, which apparently received ground water seepage and/or stream surface flows during the period of the Par Pond draw down, extensive beds of waterlilies and spike rush are common. Invasion of willow and red maple occurred along the lake shoreline as well. Although not absent from this survey, evidence of the extensive redevelopment of the large cattail and eel grass beds was not observed in this first survey of Par Pond. Future surveys during the growing seasons of 1995, 1996, and 1997 along with the evaluation of satellite date to map the areal extent of the macrophyte beds of Par Pond are planned

  13. Summary of the status of the NFS reprocessing plant

    International Nuclear Information System (INIS)

    Clark, J.R.

    The modification program at the West Valley, New York, reprocessing plant is described. The program involves expansion, improving the plant's on-stream factor and reducing the occupational exposures, installing natural phenomena protection, and improving effluent control and waste management. Licencing requirements and their effects on scheduling are discussed. (E.C.B.)

  14. Analysis of the Status and Impacts of NCTR Projects : [summary

    Science.gov (United States)

    2012-01-01

    The National Center for Transit Research (NCTR) was established in 1999 at the University of South Florida. NCTR examines public transit issues with an emphasis on innovation applied to public policy and a multidisciplinary, multimodal focus. NCTR ha...

  15. Par Pond vegetation status Summer 1995 -- September survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-09-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the emergent shoreline aquatic plant communities began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level and continued with this mid-September survey. Communities similar to the pre-drawdown Par Pond aquatic plant communities are becoming re-established; especially, beds of maidencane, lotus, waterlily, and watershield are now extensive and well established. Cattail occurrence continues to increase, but large beds common to Par Pond prior to the drawdown have not formed. Future surveys during the late growing seasons of 1995, and throughout 1996 and 1997, along with the evaluation of satellite data to map the areal extent of the macrophyte beds of Par Pond, are planned

  16. Par Pond vegetation status Summer 1995 -- October survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-11-01

    The water level of Par Pond was lowered approximately 20 feet in mid-1991 in order to protect downstream residents from possible dam failure suggested by subsidence on the downstream slope of the dam and to repair the dam. This lowering exposed both emergent and nonemergent macrophyte beds to drying conditions resulting in extensive losses. A survey of the emergent shoreline aquatic plant communities began in June 1995, three months after the refilling of Par Pond to approximately 200 feet above mean sea level and continued with this late October survey. Communities similar to the pre-drawdown Par Pond aquatic plant communities are becoming re-established; especially, beds of maiden cane, lotus, waterlily, and watershield are now extensive and well established. Cattail occurrence continues to increase, but large beds common to Par Pond prior to the drawdown have not formed. Future surveys throughout 1996 and 1997, along with the continued evaluation of satellite data to map the areal extent of the macrophyte beds of Par Pond, are planned

  17. Regulatory licensing, status summary report; Systematic evaluation program

    International Nuclear Information System (INIS)

    1978-01-01

    This document is part of a management information system presenting a logical flow of events that represent the evaluation of 11 of the older operating nuclear reactors. Information collected will be used to determine the degree to which the 11 plants meet current licensing requirements and to develop an overall balanced position concerning any needed backfitting of the facilities and the documentation of the results of such evaluations

  18. Summary of Workshop on InP: Status and Prospects

    Science.gov (United States)

    Walters, R. J.; Weinberg, I.

    1994-01-01

    The primary objective of most of the programs in InP solar cells is the development of the most radiation hard solar cell technology. In the workshop, it was generally agreed that the goal is a cell which displays high radiation tolerance in a radiation environment equivalent to a 1 MeV electron fluence of about 10(exp 16)/sq cm. Furthermore, it is desired that the radiation response of the cell be essentially flat out to this fluence - i.e. that the power output of the cell not decrease from its beginning of life (BOL) value in this radiation environment. It was also agreed in the workshop that the manufacturability of InP solar cells needs to be improved. In particular, since InP wafers are relatively dense and brittle, alternative substrates need to be developed. Research on hetero-epitaxial InP cells grown on Si, Ge, and GaAs substrates is currently underway. The ultimate goal is to develop hetero-epitaxial InP solar cells using a cheap, strong, and lightweight substrate.

  19. Summary and status of the Horizons ephemeris system

    Science.gov (United States)

    Giorgini, J.

    2011-10-01

    Since 1996, the Horizons system has provided searchable access to JPL ephemerides for all known solar system bodies, several dozen spacecraft, planetary system barycenters, and some libration points. Responding to 18 400 000 requests from 300 000 unique addresses, the system has recently averaged 420 000 ephemeris requests per month. Horizons is accessed and automated using three interfaces: interactive telnet, web-browser form, and e-mail command-file. Asteroid and comet ephemerides are numerically integrated from JPL's database of initial conditions. This small-body database is updated hourly by a separate process as new measurements and discoveries are reported by the Minor Planet Center and automatically incorporated into new JPL orbit solutions. Ephemerides for other objects are derived by interpolating previously developed solutions whose trajectories have been represented in a file. For asteroids and comets, such files may be dynamically created and transferred to users, effectively recording integrator output. These small-body SPK files may then be interpolated by user software to reproduce the trajectory without duplicating the numerically integrated n-body dynamical model or PPN equations of motion. Other Horizons output is numerical and in the form of plain-text observer, vector, osculating element, or close-approach tables, typically expected be read by other software as input. About one hundred quantities can be requested in various time-scales and coordinate systems. For JPL small-body solutions, this includes statistical uncertainties derived from measurement covariance and state transition matrices. With the exception of some natural satellites, Horizons is consistent with DE405/DE406, the IAU 1976 constants, ITRF93, and IAU2009 rotational models.

  20. Par Pond vegetation status summer 1995 - July survey descriptive summary

    International Nuclear Information System (INIS)

    Mackey, H.E. Jr.; Riley, R.S.

    1995-07-01

    A survey of the emergent shoreline aquatic plant, communities began in June 1995, three months after the refilling of Par Pond to approximately 200 feet (61 meters) above mean sea level, and continued with this July survey. Aquatic plant communities, similar to the pre-drawdown Par Pond communities, are becoming reestablished. Beds of maidencane (Panicum hemitomon), lotus (Nelumbo lutea), water lily (Nymphaea odorata), and watershield (Brasenia schreberi) are now extensive and well established. In addition, within isolated coves, extensive beds of water lilies and spike-rush (Eleocharis sp.) are common. Cattail occurrence has increased since refill, but large beds common to Par Pond prior to the drawdown have not formed. Invasion of willow (Salix sp.) and red maple (Acer rubrum) occurred along the lake shoreline during drawdown. The red maples along the present shoreline are beginning to show evidence of stress and mortality from flooding over the past four months. Some of the willows appear to be stressed as well. The loblolly pines (Pinus taeda), which were flooded in all but the shallow shoreline areas, are now dead. Future surveys are planned for the growing seasons of 1995, 1996, and 1997, along with the evaluation of satellite data for mapping the areal extent of the macrophyte beds of Par Pond

  1. Summary of group discussions

    International Nuclear Information System (INIS)

    2009-01-01

    A key aspect of the workshop was the interaction and exchange of ideas and information among the 40 participants. To facilitate this activity the workshop participants were divided into five discussions groups. These groups reviewed selected subjects and reported back to the main body with summaries of their considerations. Over the 3 days the 5 discussion groups were requested to focus on the following subjects: the characteristics and capabilities of 'good' organisations; how to ensure sufficient resources; how to ensure competence within the organisation; how to demonstrate organisational suitability; the regulatory oversight processes - including their strengths and weaknesses. A list of the related questions that were provided to the discussion groups can be found in Appendix 3. Also included in Appendix 3 are copies of the slides the groups prepared that summarised their considerations

  2. Vacuum considerations: summary

    International Nuclear Information System (INIS)

    Blechschmidt, D.; Halama, H.J.

    1978-01-01

    A summary is given of the efforts of a vacuum systems study group of the workshop on a Heavy Ion Demonstration Experiment (HIDE) for heavy ion fusion. An inadequate knowledge of cross-sections prevents a more concrete vacuum system design. Experiments leading to trustworthy numbers for charge exchange, stripping and capture cross-sections are badly needed and should start as soon as possible. In linacs, beam loss will be almost directly proportional to the pressure inside the tanks. The tanks should, therefore, be built in such a way that they can be baked-out in situ to improve their vacuum, especially if the cross-sections turn out to be higher than anticipated. Using standard UHV techniques and existing pumps, an even lower pressure can be achieved. The vacuum system design for circular machines will be very difficult, and in some cases, beyond the present state-of-the-art

  3. Summary and conclusions

    International Nuclear Information System (INIS)

    2000-01-01

    The international workshop on 'Nuclear Power Plant Life Management in a Changing Business World' was held in Washington, DC, on 26-27 June 2000. This workshop was attended by more than 50 experts from 12 countries and three international organisations. The workshop included a series of presentations to a plenary session of all participants. A spectrum of experiences in plant life extension activities as well as experiences in operating a nuclear power plant (NPP) in a 'free-market' electricity environment were presented: The workshop also included three working groups in which major issues facing PLIM activities for NPPs were identified and discussed. The three working groups covered technology, regulation and business. The following sections of this report consist of summaries of the discussions that took place in each of the three working groups. (author)

  4. Summary: Hadron dynamics sessions

    International Nuclear Information System (INIS)

    Carroll, A.S.; Londergan, J.T.

    1993-01-01

    Four sessions on Hadron Dynamics were organized at this Workshop. The first topic, QCD Exclusive Reactions and Color Transparency, featured talks by Ralston, Heppelman and Strikman; the second, QCD and Inclusive Reactions had talks by Garvey, Speth and Kisslinger. The third dynamics session, Medium Modification of Elementary Interactions had contributions from Kopeliovich, Alves and Gyulassy; the fourth session Pre-QCD Dynamics and Scattering, had talks by Harris, Myhrer and Brown. An additional joint Spectroscopy/Dynamics session featured talks by Zumbro, Johnson and McClelland. These contributions are reviewed briefly in this summary. Two additional joint sessions between Dynamics and η physics are reviewed by the organizers of the Eta sessions. In such a brief review there is no way the authors can adequately summarize the details of the physics presented here. As a result, they concentrate only on brief impressionistic sketches of the physics topics discussed and their interrelations. They include no bibliography in this summary, but simply refer to the talks given in more detail in the Workshop proceedings. They focus on topics which were common to several presentations in these sessions. First, nuclear and particle descriptions of phenomena are now clearly converging, in both a qualitative and quantitative sense; they show several examples of this convergence. Second, an important issue in hadron dynamics is the extent to which elementary interactions are modified in nuclei at high energies and/or densities, and they illustrate some of these medium effects. Finally, they focus on those dynamical issues where hadron facilities can make an important, or even a unique, contribution to the knowledge of particle and nuclear physics

  5. Photovoltaic systems. Program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    Each of the Department of Energy's Photovoltaic Systems Program projects funded and/or in existence during fiscal year 1978 (October 1, 1977 through September 30, 1978) are described. The project sheets list the contractor, principal investigator, and contract number and funding and summarize the programs and status. The program is divided into various elements: program assessment and integration, research and advanced development, technology development, system definition and development, system application experiments, and standards and performance criteria. (WHK)

  6. Degraded Core Quench: Summary of Progress 1996-1999 - Executive Summary

    International Nuclear Information System (INIS)

    Haste, T.J.; Trambauer, K.

    2000-01-01

    A status report on experiments and modelling relating to quench of degraded cores was issued by CSNI in August 1996, following the publication of the In-Vessel Core Degradation Code Validation Matrix. In response to a request by PWG2 through the TG-DCC, a review of progress since then to June 1999 has been performed. The scope is broadly the same as before, restricted to mainly rod-like geometries and not considering pure debris bed configurations. The scope has been increased slightly to include a VVER bundle quench experiment, CODEX-3, which falls within the parameter range of the Western bundle experiments performed to date. The same format has been adopted as before, with the experimental results for bundle and separate-effects tests being summarised in separate tables, updated from the earlier report. This review shows further evolutionary progress made in understanding the phenomena of fuel rod quench under severe accident conditions. The successful performance of commissioning and four main tests in the new bundle QUENCH facility at FZ Karlsruhe has provided valuable new data, supplemented by the VVER test CODEX-3 at AEKI Budapest. Temperature excursions and excess hydrogen production were only observed for quench from high temperature (2300 K) with a non pre-oxidised bundle (2 relevant tests); for quench from lower temperatures (1750-1870 K) and with pre-oxidation (50- 500 μm oxide) smooth cooling with no significant excess hydrogen production was observed (3 relevant tests). When cooling a non pre-oxidised bundle from 1870 K rapidly by steam, no significant excursion was observed (1 test). These new lower temperature bundle tests have usefully extended the parameter range down from that previously covered (quench temperature 2150 K and above, no pre-oxidation, temperature excursions/excess hydrogen production always observed), and have shown that there are conditions for quench from high temperature where excess temperatures and hydrogen production do not

  7. 7 CFR 295.4 - Program evaluation status reports.

    Science.gov (United States)

    2010-01-01

    ... evaluation status reports. FNS also publishes summaries of objectives and findings of completed studies and... completed studies may be obtained by writing the Director, Office of Analysis and Evaluation, Food and...

  8. Generating Concise Natural Language Summaries.

    Science.gov (United States)

    McKeown, Kathleen; And Others

    1995-01-01

    Presents an approach to summarization that combines information from multiple facts into a single sentence using linguistic constructions. Describes two applications: one produces summaries of basketball games, and the other contains summaries of telephone network planning activity. Both summarize input data as opposed to full text. Discusses…

  9. Statistical summary 1990-91

    International Nuclear Information System (INIS)

    1991-01-01

    The information contained in this statistical summary leaflet summarizes in bar charts or pie charts Nuclear Electric's performance in 1990-91 in the areas of finance, plant and plant operations, safety, commercial operations and manpower. It is intended that the information will provide a basis for comparison in future years. The leaflet also includes a summary of Nuclear Electric's environmental policy statement. (UK)

  10. Fuel Assembly Damping Summary

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kanghee; Kang, Heungseok; Oh, Dongseok; Yoon, Kyungho; Kim, Hyungkyu; Kim, Jaeyong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    This paper summary the fuel assembly damping data in air/in still water/under flow, released from foreign fuel vendors, compared our data with the published data. Some technical issues in fuel assembly damping measurement testing are also briefly discussed. Understanding of each fuel assembly damping mechanisms according to the surrounding medium and flow velocity can support the fuel design improvement in fuel assembly dynamics and structural integrity aspect. Because the upgraded requirements of the newly-developed advanced reactor system will demands to minimize fuel design margin in integrity evaluation, reduction in conservatism of fuel assembly damping can contribute to alleviate the fuel design margin for sure. Damping is an energy dissipation mechanism in a vibrating mechanical structure and prevents a resonant structure from having infinite vibration amplitudes. The sources of fuel assembly damping are various from support friction to flow contribution, and it can be increased by the viscosity or drag of surrounding fluid medium or the average velocity of water flowing. Fuel licensing requires fuel design evaluation in transient or accidental condition. Dynamic response analysis of fuel assembly is to show fuel integrity and requires information on assembly-wise damping in dry condition and under wet or water flowing condition. However, damping measurement test for the full-scale fuel assembly prototype is not easy to carry out because of the scale (fuel prototype, test facility), unsteadiness of test data (scattering, random sampling and processing), instrumentation under water flowing (water-proof response measurement), and noise. LWR fuel technology division in KAERI is preparing the infra structure for damping measurement test of full-scale fuel assembly, to support fuel industries and related research activities. Here is a preliminary summary of fuel assembly damping, published in the literature. Some technical issues in fuel assembly damping

  11. Status epilepticus

    NARCIS (Netherlands)

    Hensiek, AE; Absalom, Anthony

    2006-01-01

    Status epilepticus is defined as epileptic activity that continues for more than 30 minutes as a single seizure or as recurrent seizures without inter-ictal return of consciousness. The seizure activity is usually classified as partial or generalized. Although status epilepticus is an uncommon

  12. Priority knowledge needs. Summary

    International Nuclear Information System (INIS)

    2012-01-01

    This report gives an overview of the knowledge needs identified during the work on the scientific basis for the management plan. The overview includes knowledge needs identified in: the impact assessments for various sectors; the reports on the vulnerability of particularly valuable areas; proposed indicators for a monitoring system; cumulative environmental effects; conflicting interests and the need for coordination; and the report on analysis of population and, economic activity and ecosystem services. In addition, the working group has identified several additional knowledge needs. The present report summarises the 2010 status report and describes new developments since its publication.(Author)

  13. Summary of transient analysis

    International Nuclear Information System (INIS)

    Saha, P.

    1984-01-01

    This chapter reviews the papers on the pressurized water reactor (PWR) and boiling water reactor (BWR) transient analyses given at the American Nuclear Society Topical Meeting on Anticipated and Abnormal Plant Transients in Light Water Reactors. Most of the papers were based on the systems calculations performed using the TRAC-PWR, RELAP5 and RETRAN codes. The status of the nuclear industry in the code applications area is discussed. It is concluded that even though comprehensive computer codes are available for plant transient analysis, there is still a need to exercise engineering judgment, simpler tools and even hand calculations to supplement these codes

  14. Priority knowledge needs. Summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-01

    This report gives an overview of the knowledge needs identified during the work on the scientific basis for the management plan. The overview includes knowledge needs identified in: the impact assessments for various sectors; the reports on the vulnerability of particularly valuable areas; proposed indicators for a monitoring system; cumulative environmental effects; conflicting interests and the need for coordination; and the report on analysis of population and, economic activity and ecosystem services. In addition, the working group has identified several additional knowledge needs. The present report summarises the 2010 status report and describes new developments since its publication.(Author)

  15. Astronautics summary and prospects

    CERN Document Server

    Kiselev, Anatoly Ivanovich; Menshikov, Valery Alexandrovich

    2003-01-01

    The monograph by A.I.Kiselev, A.A. Medvedev and Y.A.Menshikov, Astronautics: Summary and Prospects, aroused enthusiasm both among experts and the public at large. This is due to the felicitous choice of presentation that combines a simple description of complex space matters with scientificsubstantiation of the sub­ jectmatter described. The wealth of color photos makes the book still more attractive, and it was nominated for an award at the 14th International Moscow Book Fair, being singled out as the "best publication of the book fair". The book's popularity led to a second edition, substantially revised and enlarged. Since the first edition did not sufficiently cover the issues of space impact on ecology and the prospective development of space systems, the authors revised the entire volume, including in it the chapter "Space activity and ecology" and the section "Multi-function space systems". Using the federal monitoring system, now in the phase of system engi­ neering, as an example, the authors consi...

  16. Summary of the Workshop

    International Nuclear Information System (INIS)

    Myers, S; Zimmermann, F

    2012-01-01

    The summary session of the LHC Performance Workshop in Chamonix, 6-10 February 2012, synthesized one week of presentations and intense discussions on the near-, medium- and long-term strategy for the LHC and LHC upgrades. In particular, Chamonix’12 discussed the lessons from 2011, the strategy, beam energy and beam parameters for 2012, the planning for the Long Shutdown no. 1 (LS1), the measures and schemes for improving or maintaining the machine availability at higher beam energy, the injector performance and injector upgrade schedule, the HL-LHC project as well as possible additional or future LHC upgrades like LHeC and HELHC. Key workshop themes included the risk associated with 4 TeV beam energy in 2012, the beam energy after LS1, the turnaround time, the physics goal and optimized running schedule for 2012, the achievements and plans for Pb-Pb and p-Pb collisions, beam-beam effects, electron-cloud phenomena and UFOs. We report the proposals for decisions which have emerged at the Chamonix’12 workshop. (author)

  17. Summary of the Workshop

    Energy Technology Data Exchange (ETDEWEB)

    Myers, S; Zimmermann, F [European Organization for Nuclear Research, Geneva (Switzerland)

    2012-07-01

    The summary session of the LHC Performance Workshop in Chamonix, 6-10 February 2012, synthesized one week of presentations and intense discussions on the near-, medium- and long-term strategy for the LHC and LHC upgrades. In particular, Chamonix’12 discussed the lessons from 2011, the strategy, beam energy and beam parameters for 2012, the planning for the Long Shutdown no. 1 (LS1), the measures and schemes for improving or maintaining the machine availability at higher beam energy, the injector performance and injector upgrade schedule, the HL-LHC project as well as possible additional or future LHC upgrades like LHeC and HELHC. Key workshop themes included the risk associated with 4 TeV beam energy in 2012, the beam energy after LS1, the turnaround time, the physics goal and optimized running schedule for 2012, the achievements and plans for Pb-Pb and p-Pb collisions, beam-beam effects, electron-cloud phenomena and UFOs. We report the proposals for decisions which have emerged at the Chamonix’12 workshop. (author)

  18. Status Report on Hydrogen Management and Related Computer Codes

    International Nuclear Information System (INIS)

    Liang, Z.; Chan, C.K.; Sonnenkalb, M.; Bentaib, A.; Malet, J.; Sangiorgi, M.; Gryffroy, D.; Gyepi-Garbrah, S.; Duspiva, J.; Sevon, T.; Kelm, S.; Reinecke, E.A.; Xu, Z.J.; Cervone, A.; Utsuno, H.; Hotta, A.; Hong, S.W.; Kim, J.T.; Visser, D.C.; Stempniewicz, M.M.; Kuriene, L.; Prusinski, P.; Martin-Valdepenas, J.M.; Frid, W.; Isaksson, P.; Dreier, J.; Paladino, D.; Algama, D.; Notafrancesco, A.; Amri, A.; Kissane, M.; )

    2014-01-01

    In follow-up to the Fukushima Daiichi NPP accident, the Committee on the Safety of Nuclear Installations (CSNI) decided to launch several high priority activities. At the 14. plenary meeting of the Working Group on Analysis and Management of Accidents (WGAMA), a proposal for a status paper on hydrogen generation, transport and mitigation under severe accident conditions was approved. The proposed activity is in line with the WGAMA mandate and it was considered to be needed to revisit the hydrogen issue. The report is broken down into five Chapters and two appendixes. Chapter 1 provides background information for this activity and expected topics defined by the WGAMA members. A general understanding of hydrogen behavior and control in severe accidents is discussed. A brief literature review is included in this chapter to summarize the progress obtained from the early US NRC sponsored research on hydrogen and recent international OECD or EC sponsored projects on hydrogen related topics (generation, distribution, combustion and mitigation). Chapter 2 provides a general overview of the various reactor designs of Western PWRs, BWRs, Eastern European VVERs and PHWRs (CANDUs). The purpose is to understand the containment design features in relation to hydrogen management measures. Chapter 3 provides a detailed description of national requirements on hydrogen management and hydrogen mitigation measures inside the containment and other places (e.g., annulus space, secondary buildings, spent fuel pool, etc.). Discussions are followed on hydrogen analysis approaches, application of safety systems (e.g., spray, containment ventilation, local air cooler, suppression pool, and latch systems), hydrogen measurement strategies as well as lessons learnt from the Fukushima Daiichi nuclear power accident. Chapter 4 provides an overview of various codes that are being used for hydrogen risk assessment, and the codes capabilities and validation status in terms of hydrogen related

  19. Stock Status

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — These data inform the public of the most recent stock status for all stocks (FSSI and non-FSSI) in the fishery management unit contained in a fishery managment plan....

  20. Messengers of the universe: Session IV Summary

    International Nuclear Information System (INIS)

    Bernardini, Elisa; Serpico, Pasquale Dario

    2013-01-01

    Being stable, light and neutral weakly interacting particles, neutrinos are ideal messengers of the deep universe and a channel of choice in particular to explore the very high energy Galactic and Extragalactic sky, playing a synergic role most notably with gamma-ray observations. Neutrino astronomy—long after the SN1987A detection in the MeV range—is mature enough for decisive tests of astrophysical paradigms. Its current status constitutes one of the two big pillars of the “Messengers of the universe” session of the Neutrino Oscillation Workshop 2012. Neutrinos may also play a role in some cosmological contexts, such as the early universe and the dark matter problem. We review both aspects in this session summary report

  1. Areva and sustainable development 2003 summary report

    International Nuclear Information System (INIS)

    2004-01-01

    This document is a summary of the 2003 report on the sustainable development of the world nuclear industry leader, Areva. The 2002 report helped establish the status of Areva entities sustainable development performance and identity areas for improvement. The 2003 report presents the continuous improvement process, including accomplishments and projects initiated as well as difficulties encountered and ground yet to be covered. Two new tools support this process. The Areva Way self assessment model allows each unit to assess its own performance against the sustainable development commitments and the Areva values charter lays down ethical principles of action and rules of conduct. Over the coming months, the Group will devote considerable effort to extending the sustainable development initiative to the activities resulting from the acquisition of Alstom Transmission and Distribution operations in early 2004. (A.L.B.)

  2. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  3. Unresolved safety issues summary: aqua book

    International Nuclear Information System (INIS)

    1983-06-01

    The unresolved safety issues summary is designed to provide the management of the nuclear regulatory commission with a quarterly overview of the progress and plans for completion of generic tasks addressing unresolved safety issues reported to congress pursuant to section 210 of the Energy Reorganization Act of 1974 as amended. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

  4. Summary of the Day (CDMP)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This Summary of the Day data file contains daily selected elements of observations recorded by certified observers. The stations were located in the U.S. and were...

  5. Long term performance session summary

    Energy Technology Data Exchange (ETDEWEB)

    Hanauer, S.

    1996-05-01

    This paper presents brief summaries of reports given on plutonium disposal. Topics include: performance of waste forms; glass leaching; ceramic leaching; safeguards and security issues; safeguards of vitrification; and proliferation risks of geologic disposal.

  6. Summary of Meson'98 Workshop

    International Nuclear Information System (INIS)

    Henley, E.M.

    1998-01-01

    One never quite knows what to say in a summary. If you were at the sessions, you heard the same talks I did. Perhaps the purpose is to summarize the parallel sessions, but like you, I can only attend one of these sessions. In addition, the time is short, so that this cannot be a real summary. What I will present are impressions of the past two days, and these will certainly be colored by my own views. Thus at the outset, let me apologize for any and all omissions and distortions. I will cover primarily the plenary session talks, but will organize this summary along the following lines: 1. vector (V) mesons; 2. pseudoscalar mesons, and 3. other subjects, notably with electrons. This afternoon's talks are so close in time to this summary that I shall omit them. (author)

  7. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1981-08-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  8. Summary 2010 Greenhouse Gas Data

    Data.gov (United States)

    U.S. Environmental Protection Agency — This file contains a summary of the publicly available data from the GHG Reporting Program for 2010. This data includes non-confidential data reported by facilities...

  9. Accelerator technology working group summary

    International Nuclear Information System (INIS)

    Jameson, R.A.

    1985-01-01

    A summary is presented of workshop deliberations on basic scaling, the economic viability of laser drive power for HEP accelerators, the availability of electron beam injectors for near-term experiments, and a few very general remarks on technology issues

  10. Summary and conclusions [Chapter 11

    Science.gov (United States)

    Daniel G. Neary; John N. Rinne; Alvin L.. Medina

    2012-01-01

    Summaries and conclusions of each chapter are compiled here to provide a “Quick Reference” guide of major results and recommendations for the UVR. More detail can be obtained from individual chapters.

  11. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1984-03-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the U.S. Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  12. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1983-02-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, vandalism, arson, firearms, radiological sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  13. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1982-07-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, vandalism, arson, firearms, sabotage and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  14. Overview and summary

    International Nuclear Information System (INIS)

    1999-01-01

    The ITER Physics Basis presents and evaluates the physics rules and methodologies for plasma performance projections, which provide the basis for the design of a tokamak burning plasma device whose goal is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. This Chapter summarizes the physics basis for burning plasma projections, which is developed in detail by the ITER Physics Expert Groups in subsequent chapters. To set context, the design guidelines and requirements established in the report of ITER Special Working Group 1 are presented, as are the specifics of the tokamak design developed in the Final Design Report of the ITER Engineering Design Activities, which exemplifies burning tokamak plasma experiments. The behaviour of a tokamak plasma is determined by the interaction of many diverse physics processes, all of which bear on projections for both a burning plasma experiment and an eventual tokamak reactor. Key processes summarized here are energy and particle confinement and the H-mode power threshold; MHD stability, including pressure and density limits, neoclassical islands, error fields, disruptions, sawteeth, and ELMs; power and particle exhaust, involving divertor power dispersal, helium exhaust, fuelling and density control, H-mode edge transition region, erosion of plasma facing components, tritium retention; energetic particle physics; auxiliary power physics; and the physics of plasma diagnostics. Summaries of projection methodologies, together with estimates of their attendant uncertainties, are presented in each of these areas. Since each physics element has its own scaling properties, an integrated experimental demonstration of the balance between the combined processes which obtains in a reactor plasma is inaccessible to contemporary experimental facilities: it requires a reactor scale device. It is argued, moreover, that a burning plasma experiment can be sufficiently flexible to permit

  15. Current status of the world's research reactors

    International Nuclear Information System (INIS)

    Dodd, B.

    1999-01-01

    Data from the IAEA's Research Reactor Database (RRDB) provides information with respect to the status of the world's research reactors. Some summary data are given. Recent initiatives by the IAEA regarding communications and information flow with respect to research reactors are discussed. Future plans and perspectives are also introduced. (author)

  16. Status Report on the MCNP 2020 Initiative

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-10-02

    The discussion below provides a status report on the MCNP 2020 initiative. It includes discussion of the history of MCNP 2020, accomplishments during 2013-17, priorities for near-term development, other related efforts, a brief summary, and a list of references for the plans and work accomplished.

  17. PIUS reactor progress summary

    International Nuclear Information System (INIS)

    Hannerz, K.; Nilsson, L.

    1989-01-01

    Operating excellence is becoming the key concept for assuring the safety of the present generation of light water reactors (LWRs). Human excellence is a scarce commodity, however, and in uncertain supply and of questionable durability. The basis for ABB Atom's long-term development program is a firm conviction that a truly large-scale future expansion of nuclear power must be based on a technology in which safe operation makes much reduced demands on this scarce commodity. The present goal in the United States is to obtain U.S. Nuclear Regulatory Commission design certification by the mid-1990s with lead plant construction closely following. The difference in principle between PIUS and other (existing or proposed) LWR concepts is explained. In other LWR concepts, protection of core integrity, and thereby avoidance of accidents with significant environmental impact, depends on the necessarily uncertain status of safety equipment and on the actions of plant operators. In contrast, in PIUS, core integrity in transients is ensured by the reactor system configuration itself and the resulting self-protective thermohydraulic feedback mechanism. Extended core cooling by submergence in water is assured without any external intervention in spite of any credible structural failures. the safety of an operating core becomes practically invulnerable to human mistake or mischief

  18. 7 CFR 3402.12 - Project summary.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Project summary. 3402.12 Section 3402.12 Agriculture... FELLOWSHIP GRANTS PROGRAM Preparation of an Application § 3402.12 Project summary. Using the Project Summary.... The summary should not include any reference to the specific number of fellowships requested. The...

  19. 49 CFR 194.113 - Information summary.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Information summary. 194.113 Section 194.113... Response Plans § 194.113 Information summary. (a) The information summary for the core plan, required by... state(s). (b) The information summary for the response zone appendix, required in § 194.107, must...

  20. Summary of OLF's Business trends report 2006

    International Nuclear Information System (INIS)

    2006-01-01

    A summary of OLF's business trends report 2006. The first in a series of annual business trends reports which The Norwegian Oil Industry Association (OLF) has decided to publish. The report highlights features in the development of the global economy and the energy markets, and presents an analysis of the level of activity on the Norwegian Shelf through to 2010. It also gives a status report and outlines the challenges that lie within three important areas for the oil industry: the relationship with the external environment, health, safety and working environment, and personnel and competence requirements within the industry. The main message contained in the report is summarised as follows: 'While prospects for the immediate future look good, we foresee a lack of new, important and technically challenging projects in the longer term. Discoveries made on the Norwegian Shelf during recent years have been small. Exploration activity must be intensified and its results must be improved. The most important and effective stimulus in this connection is new prospective exploration acreage. The Comprehensive Management Plan for Lofoten and the Barents Sea will be revised in 2010. By that time the knowledge gaps in the plan have to be filled so that the decision-making basis is as good as possible. Even though the level of activity looks as if it will continue to be high in the medium term, we have no time to lose.' Environmental status and challenges are briefly reviewed, as well as the industry's future recruitment challenges (author) (ml)

  1. Summary talk at the international symposium on strangeness in hadronic matter

    International Nuclear Information System (INIS)

    Garvey, G.T.

    1987-01-01

    A selected summary of the workshop is presented. Emphasis is placed on the future role of studying kaon rare decay and an apparent solution of the ΔI = 1/2 enhancement in strangeness-changing weak decays. Also discussed is a proposed kaon condensate of hadronic matter as well as recent and proposed experiments on S = -1, -2 dibaryons. The summary concludes with a brief discussion of the status of hypernucleus research. 12 refs., 4 figs., 1 tab

  2. Executive Summary - Overview

    International Nuclear Information System (INIS)

    2005-01-01

    Professor Andrzej Budzanowski was Director of IFJ in the years 1990-2004. On September 1st 2004, on IFJ joining the Polish Academy of Sciences, Professor Marek Jezabek has been nominated by the President of PAN as the Director of IFJ, for a 4-year term. Our Institute, with a personnel of 450 (182 research staff) and over 50 Ph.D. students, is presently one of the largest institutes of the Polish Academy of Sciences and one of the largest research institutes in Poland. The scientific staff consists on 120 post-doctoral researchers, 26 Associated Professors and 36 State-Nominated Professors. The total budget of the Institute for the year 2004 was about 56 million Euro. The IFJ is financed mainly from the state budget of the Ministry of Scientific Research and Information Technology. In 2004 this financing was about 4 million Euro, constituting 72% of the Institute's total budget. The remaining part of our 2004 budget came from individual research projects, also sponsored by the Ministry of Scientific Research (688 kEuro), from international projects (368 kEuro) and from the Institute's entrepreneurship activities (498 kEuro). Between 2003 and 2004 we doubled our income from international projects. For further budget information. The Scientific Council of the Institute, which consists of 40 elected members of the Institute's staff and 4 external members (elected representatives from other Polish institutes and universities), is authorized to confer Ph.D. degrees in Physics and related disciplines, and to initiate and conduct habilitation and professorship procedures. In 2003-2004 17 Ph.D. theses and 11 habilitations have been completed. Following their review procedures, 3 Associate Professors at the IFJ became state-nominated Professors, receiving their nominations from Poland's President, Mr. A. Kwasniewski. The Institute is structured into 17 scientific departments which cover the range of our scientific interests. A summary of our main scientific achievements in

  3. Compliance status

    International Nuclear Information System (INIS)

    Black, D.G.

    1995-01-01

    This section of the 1994 Hanford Site Environmental Report summarizes the activities conducted to ensure that the Hanford Site is in compliance with federal environmental protection statutes and related Washington State and local environmental protection regulations and the status of Hanford's compliance with these requirements. Environmental permits required under the environmental protection regulations are discussed under the applicable statute

  4. Compliance status

    Energy Technology Data Exchange (ETDEWEB)

    Black, D.G.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the activities conducted to ensure that the Hanford Site is in compliance with federal environmental protection statutes and related Washington State and local environmental protection regulations and the status of Hanford`s compliance with these requirements. Environmental permits required under the environmental protection regulations are discussed under the applicable statute.

  5. STATUS REPORT

    Indian Academy of Sciences (India)

    First page Back Continue Last page Graphics. STATUS REPORT. Raman scattering observed – 90, 135, 180 degrees and back scattering. Traditionally specific angle dependence to learn about polarization response. Learn molecular information from the surface or materials just below the surface (upto 12 mm depth) ...

  6. Safeguards summary event list (SSEL)

    International Nuclear Information System (INIS)

    1989-07-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Because of public interest, also included are events reported involving byproduct material which is exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, alcohol and drugs, and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  7. Meson 2000 Conference Summary lite

    International Nuclear Information System (INIS)

    Barnes, T.

    2000-01-01

    This short contribution is a late MESON2000 conference summary. As appropriate for the 600th anniversary of the Jagiellonian University, it begins with a brief summary of the last 600 years of European history and its place in hadron physics. Next a ''physicist chirality'' order parameter PC is introduced. When applied to MESON2000 plenary speakers this order parameter illustrates the separation of hadron physicists into disjoint communities. The individual plenary talks in MESON2000 are next sorted according to the subconference associated with each of the 36 plenary speakers. Finally, I conclude with a previously unreported Feynman story regarding the use of models in hadron physics. (author)

  8. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1983-01-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  9. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    Fadden, M.; Yardumian, J.

    1993-07-01

    The Safeguards Summary Event List provides brief summaries of hundreds of safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission. Events are described under the categories: Bomb-related, Intrusion, Missing/Allegedly Stolen, Transportation-related, Tampering/Vandalism, Arson, Firearms-related, Radiological Sabotage, Non-radiological Sabotage, and Miscellaneous. Because of the public interest, the Miscellaneous category also includes events reported involving source material, byproduct material, and natural uranium, which are exempt from safeguards requirements. Information in the event descriptions was obtained from official NRC sources

  10. Experimental Plasma Research project summaries

    International Nuclear Information System (INIS)

    1980-09-01

    This report contains descriptions of the activities supported by the Experimental Plasma Research Branch of APP. The individual project summaries were prepared by the principal investigators and include objectives and milestones for each project. The projects are arranged in six research categories: Plasma Properties; Plasma Heating; Plasma Diagnostics; Atomic, Molecular and Nuclear Physics; Advanced Superconducting Materials; and the Fusion Plasma Research Facility (FPRF). Each category is introduced with a statement of objectives and recent progress and followed by descriptions of individual projects. An overall budget summary is provided at the beginning of the report

  11. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-05-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  12. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1983-03-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  13. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  14. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-11-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  15. Experimental plasma research project summaries

    International Nuclear Information System (INIS)

    1978-08-01

    This report contans descriptions of the activities supported by the Experimental Plasma Research Branch of APP. The individual project summaries were prepared by the principal investigators and include objectives and milestones for each project. The projects are arranged in six research categories: Plasma Properties; Plasma Heating; Plasma Measurements and Instrumentation; Atomic, Molecular and Nuclear Physics; Advanced Superconducting Materials; and the Fusion Plasma Research Facility (FPRF). Each category is introduced with a statement of objectives and recent progress and followed by descriptions of individual projects. An overall budget summary is provided at the beginning of the report

  16. Experimental Plasma Research project summaries

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-09-01

    This report contains descriptions of the activities supported by the Experimental Plasma Research Branch of APP. The individual project summaries were prepared by the principal investigators and include objectives and milestones for each project. The projects are arranged in six research categories: Plasma Properties; Plasma Heating; Plasma Diagnostics; Atomic, Molecular and Nuclear Physics; Advanced Superconducting Materials; and the Fusion Plasma Research Facility (FPRF). Each category is introduced with a statement of objectives and recent progress and followed by descriptions of individual projects. An overall budget summary is provided at the beginning of the report.

  17. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-10-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  18. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-08-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  19. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-09-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  20. Summary of Epidemiology Studies or Activities Involving Workers at the Savannah River Site or the Surrounding Public: An Update

    Energy Technology Data Exchange (ETDEWEB)

    Brown, K.T.

    2002-10-18

    There have been numerous health studies or related activities over time that have involved workers at the Savannah River Site (SRS) or the surrounding public. While most of these epidemiology studies or activities have been performed by external agencies, it has proved useful to provide interested parties an overall summary of such activities. The first such summary was provided in an October 1998 report. The 1998 summary was updated in a February 2000 report. This report provides an update on the status or findings of epidemiology studies or activities involving SRS workers or the surrounding public, as an update to the previous summaries.

  1. LHC Status and Upgrade Challenges

    Science.gov (United States)

    Smith, Jeffrey

    2009-11-01

    The Large Hadron Collider has had a trying start-up and a challenging operational future lays ahead. Critical to the machine's performance is controlling a beam of particles whose stored energy is equivalent to 80 kg of TNT. Unavoidable beam losses result in energy deposition throughout the machine and without adequate protection this power would result in quenching of the superconducting magnets. A brief overview of the machine layout and principles of operation will be reviewed including a summary of the September 2008 accident. The current status of the LHC, startup schedule and upgrade options to achieve the target luminosity will be presented.

  2. Lattice QCD: Status and Prospect

    International Nuclear Information System (INIS)

    Ukawa, Akira

    2006-01-01

    A brief review is given of the current status and near-future prospect of lattice QCD studies of the Standard Model. After summarizing a bit of history, we describe current attempts toward inclusion of dynamical up, down and strange quarks. Recent results on the light hadron mass spectrum as well as those on the heavy quark quantities are described. Recent work on lattice pentaquark search is summarized. We touch upon the PACS-CS Project for building our next machine for lattice QCD, and conclude with a summary of computer situation and the physics possibilities over the next several years

  3. Status Epilepticus

    Science.gov (United States)

    Seinfeld, Syndi; Goodkin, Howard P.; Shinnar, Shlomo

    2016-01-01

    Although the majority of seizures are brief and cause no long-term consequences, a subset is sufficiently prolonged that long-term consequences can result. These very prolonged seizures are termed “status epilepticus” (SE) and are considered a neurological emergency. The clinical presentation of SE can be diverse. SE can occur at any age but most commonly occurs in the very young and the very old. There are numerous studies on SE in animals in which the pathophysiology, medication responses, and pathology can be rigorously studied in a controlled fashion. Human data are consistent with the animal data. In particular, febrile status epilepticus (FSE), a form of SE common in young children, is associated with injury to the hippocampus and subsequent temporal lobe epilepsy (TLE) in both animals and humans. PMID:26931807

  4. Biomass energy systems program summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-07-01

    Research programs in biomass which were funded by the US DOE during fiscal year 1978 are listed in this program summary. The conversion technologies and their applications have been grouped into program elements according to the time frame in which they are expected to enter the commercial market. (DMC)

  5. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    1982-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis

  6. Summary Staging Manual 2000 - SEER

    Science.gov (United States)

    Access this manual of codes and coding instructions for the summary stage field for cases diagnosed 2001-2017. 2000 version applies to every anatomic site. It uses all information in the medical record. Also called General Staging, California Staging, and SEER Staging.

  7. Improving low power and shutdown PSA methods and data to permit better risk comparison and trade-off decision-making. Volume 1: summary of COOPRA and WGRISK surveys; Volume 2: responses to the WGRISK survey; Volume 3: responses to the COOPRA survey

    International Nuclear Information System (INIS)

    2005-01-01

    The COOPRA LPSD working group is charged with the responsibility to assess their Member country's plant operations at Low Power and Shutdown (LPSD) conditions. The sharing of information is expected to provide each of the Member country the means from which to render informed regulatory decisions for the benefit of public health and safety. Each organization had developed a questionnaire to gather information from Member countries on LPSD PSAs experiences. The responses cover a broad spectrum of LPSD PSA topics, and identifies work for improving risk-informed trade-off decisions, using PSA techniques, between LPSD and full power operational states. Each organization recognized potential benefit for improving the state-of-the-art by combining the wealth of experiences from the questionnaire responses into a common report. This report provides a summary of the current LPSD PSAs in Member countries, covering the elements which make up the PSAs. This report identifies the uses of the LPSD PSAs, summarizes current approaches, aspects, and good practices, identifies and defines differences between methods and data in full power and LPSD PSAs, and identifies guidance, methods, data, and basic research needs to address the differences. The responses to the questionnaires are provided in the Appendixes. The information contained in this report was gathered from two surveys, one by COOPRA and the other by WGRisk, which were performed over several years. Volume 2 of this report contains the responses from the CSNI / WGRisk Survey; Volume 3 contains the responses from the COOPRA Survey

  8. Top physics at high-energy lepton colliders. Summary

    International Nuclear Information System (INIS)

    Vos, M.

    2016-04-01

    A summary is presented of the workshop ''top physics at linear colliders'' that was held at IFIC Valencia from the 30"t"h of June to the 3"r"d July 2015. We present an up-to-date status report of studies into the potential for top quark physics of lepton colliders with an energy reach that exceeds the top quark pair production threshold, with a focus on the linear collider projects ILC and CLIC. This summary shows that such projects can offer very competitive determinations of top quark properties (mass, width) and its interactions with other Standard Model particles, in particular electroweak gauge bosons and the Higgs boson. In both areas the prospects exceed the LHC potential significantly - often by an order of magnitude.

  9. CMS Status

    International Nuclear Information System (INIS)

    Dobrzynski, L.

    2007-01-01

    The status of the construction and installation of CMS detector is reviewed. The 4T magnet is cold since end of February 2006. Its commissioning up to the nominal field started in July 2006 allowing a Cosmic Challenge in which elements of the final detector are involved. All big mechanical pieces equipped with muons chambers have been assembled in the surface hall SX5. Since mid July the detector is closed with commissioned HCAL, two ECAL supermodules and representative elements of the silicon tracker. The trigger system as well as the DAQ are tested. After the achievement of the physics TDR, CMS is now ready for the promising signal hunting. (author)

  10. U.S. Annual Climatological Summaries

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Annual Climatological Summary contains historical monthly and annual summaries for over 8000 U.S. locations. Observing stations are located in the United States of...

  11. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-07-01

    The Summary Report - Part II of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - includes reports on development of fast reactors in France from 1977 to 1978; review of the activities related to fast reactors in Germany; status of fast breeder reactors development in Belgium and Netherlands; status of activities related to fast reactors in USSR, Japan USA, UK and Italy.

  12. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part II

    International Nuclear Information System (INIS)

    1978-07-01

    The Summary Report - Part II of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - includes reports on development of fast reactors in France from 1977 to 1978; review of the activities related to fast reactors in Germany; status of fast breeder reactors development in Belgium and Netherlands; status of activities related to fast reactors in USSR, Japan USA, UK and Italy

  13. Safeguards Summary Event List (SSEL)

    International Nuclear Information System (INIS)

    1991-07-01

    The Safeguards Summary Event List (SSEL) provides brief summaries of several hundred safeguards-related events involving nuclear material or facilities regulated by the US Nuclear Regulatory Commission (NRC). Because of public interest, the Miscellaneous category includes a few events which involve either source material, byproduct material, or natural uranium which are exempt from safeguards requirements. Events are described under the categories of bomb-related, intrusion, missing and/or allegedly stolen, transportation, tampering/vandalism, arson, firearms, radiological sabotage, nonradiological sabotage, pre-1990 alcohol and drugs (involving reactor operators, security force members, or management persons), and miscellaneous. The information contained in the event descriptions is derived primarily from official NRC reporting channels

  14. ENDF/B summary documentation

    International Nuclear Information System (INIS)

    Kinsey, R.

    1979-07-01

    This publication provides a localized source of descriptions for the evaluations contained in the ENDF/B Library. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The summary documentations were written by the CSEWB (Cross Section Evaluation Working Group) evaluators and compiled by NNDC (National Nuclear Data Center). This edition includes documentation for materials found on ENDF/B Version V tapes 501 to 516 (General Purpose File) excluding tape 504. ENDF/B-V also includes tapes containing partial evaluations for the Special Purpose Actinide (521, 522), Dosimetry (531), Activation (532), Gas Production (533), and Fission Product (541-546) files. The materials found on these tapes are documented elsewhere. Some of the evaluation descriptions in this report contain cross sections or energy level information

  15. Visualizing Summary Statistics and Uncertainty

    KAUST Repository

    Potter, K.

    2010-08-12

    The graphical depiction of uncertainty information is emerging as a problem of great importance. Scientific data sets are not considered complete without indications of error, accuracy, or levels of confidence. The visual portrayal of this information is a challenging task. This work takes inspiration from graphical data analysis to create visual representations that show not only the data value, but also important characteristics of the data including uncertainty. The canonical box plot is reexamined and a new hybrid summary plot is presented that incorporates a collection of descriptive statistics to highlight salient features of the data. Additionally, we present an extension of the summary plot to two dimensional distributions. Finally, a use-case of these new plots is presented, demonstrating their ability to present high-level overviews as well as detailed insight into the salient features of the underlying data distribution. © 2010 The Eurographics Association and Blackwell Publishing Ltd.

  16. Visualizing Summary Statistics and Uncertainty

    KAUST Repository

    Potter, K.; Kniss, J.; Riesenfeld, R.; Johnson, C.R.

    2010-01-01

    The graphical depiction of uncertainty information is emerging as a problem of great importance. Scientific data sets are not considered complete without indications of error, accuracy, or levels of confidence. The visual portrayal of this information is a challenging task. This work takes inspiration from graphical data analysis to create visual representations that show not only the data value, but also important characteristics of the data including uncertainty. The canonical box plot is reexamined and a new hybrid summary plot is presented that incorporates a collection of descriptive statistics to highlight salient features of the data. Additionally, we present an extension of the summary plot to two dimensional distributions. Finally, a use-case of these new plots is presented, demonstrating their ability to present high-level overviews as well as detailed insight into the salient features of the underlying data distribution. © 2010 The Eurographics Association and Blackwell Publishing Ltd.

  17. ENDF/B summary documentation

    Energy Technology Data Exchange (ETDEWEB)

    Kinsey, R. (comp.)

    1979-07-01

    This publication provides a localized source of descriptions for the evaluations contained in the ENDF/B Library. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The summary documentations were written by the CSEWB (Cross Section Evaluation Working Group) evaluators and compiled by NNDC (National Nuclear Data Center). This edition includes documentation for materials found on ENDF/B Version V tapes 501 to 516 (General Purpose File) excluding tape 504. ENDF/B-V also includes tapes containing partial evaluations for the Special Purpose Actinide (521, 522), Dosimetry (531), Activation (532), Gas Production (533), and Fission Product (541-546) files. The materials found on these tapes are documented elsewhere. Some of the evaluation descriptions in this report contain cross sections or energy level information. (RWR)

  18. 19 CFR 210.18 - Summary determinations.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 3 2010-04-01 2010-04-01 false Summary determinations. 210.18 Section 210.18 Customs Duties UNITED STATES INTERNATIONAL TRADE COMMISSION INVESTIGATIONS OF UNFAIR PRACTICES IN IMPORT TRADE ADJUDICATION AND ENFORCEMENT Motions § 210.18 Summary determinations. (a) Motions for summary...

  19. Sexual Harassment and Organizational Outcomes Executive Summary

    Science.gov (United States)

    2011-10-01

    quid pro quo type of Sexual harassment and Organizational, 4 sexual harassment (e.g., sexual coercion). This should drive organizational efforts to... Sexual Harassment and Organizational Outcomes Executive Summary Charlie L. Law DEFENSE EQUAL...Executive Summary] No. 99-11 Sexual harassment and Organizational, 2 Executive Summary Issue

  20. 29 CFR 1905.41 - Summary decision.

    Science.gov (United States)

    2010-07-01

    ... OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 Summary Decisions § 1905.41 Summary decision. (a) No genuine issue... 29 Labor 5 2010-07-01 2010-07-01 false Summary decision. 1905.41 Section 1905.41 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR RULES OF...

  1. 40 CFR 1502.12 - Summary.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 32 2010-07-01 2010-07-01 false Summary. 1502.12 Section 1502.12 Protection of Environment COUNCIL ON ENVIRONMENTAL QUALITY ENVIRONMENTAL IMPACT STATEMENT § 1502.12 Summary. Each environmental impact statement shall contain a summary which adequately and accurately summarizes...

  2. 40 CFR 68.155 - Executive summary.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Executive summary. 68.155 Section 68...) CHEMICAL ACCIDENT PREVENTION PROVISIONS Risk Management Plan § 68.155 Executive summary. The owner or operator shall provide in the RMP an executive summary that includes a brief description of the following...

  3. 77 FR 12865 - Enforcement Actions Summary

    Science.gov (United States)

    2012-03-02

    ...] Enforcement Actions Summary AGENCY: Transportation Security Administration, DHS. ACTION: Notice of availability. SUMMARY: The Transportation Security Administration (TSA) is providing notice that it has issued an annual summary of all enforcement actions taken by TSA under the authority granted in the...

  4. 49 CFR 1150.44 - Caption summary.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 8 2010-10-01 2010-10-01 false Caption summary. 1150.44 Section 1150.44... Exempt Transactions Under 49 U.S.C. 10902 for Class III Rail Carriers § 1150.44 Caption summary. The caption summary must be in the following form. The information symbolized by numbers is identified in the...

  5. 29 CFR 1904.32 - Annual summary.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 5 2010-07-01 2010-07-01 false Annual summary. 1904.32 Section 1904.32 Labor Regulations... Requirements § 1904.32 Annual summary. (a) Basic requirement. At the end of each calendar year, you must: (1... deficiencies identified; (2) Create an annual summary of injuries and illnesses recorded on the OSHA 300 Log...

  6. 78 FR 11216 - Enforcement Actions Summary

    Science.gov (United States)

    2013-02-15

    ...] Enforcement Actions Summary AGENCY: Transportation Security Administration, DHS. ACTION: Notice of availability. SUMMARY: The Transportation Security Administration (TSA) is providing notice that it has issued an annual summary of all enforcement actions taken by TSA under the authority granted in the...

  7. 76 FR 9357 - Enforcement Actions Summary

    Science.gov (United States)

    2011-02-17

    ...] Enforcement Actions Summary AGENCY: Transportation Security Administration, DHS. ACTION: Notice of Availability. SUMMARY: The Transportation Security Administration (TSA) is providing notice that it has issued an annual summary of all enforcement actions taken by TSA under the authority granted in the...

  8. Regional Management Plan: Summary report

    International Nuclear Information System (INIS)

    Drobny, N.L.

    1986-01-01

    This summary report describes the results of a 16-month project to develop a Regional Management Plan for low-level radioactive waste management in a seven-state area. The seven states are Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio, and Wisconsin. These states have formed the Midwest Interstate Low-Level Radioactive Waste Commission in accord with Congressional requirements established in 1980. 14 refs., 13 figs., 9 tabs

  9. ENDF/B summary documentation

    International Nuclear Information System (INIS)

    Garber, D.

    1975-10-01

    Descriptions of the evaluations contained in the ENDF/B library are given. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer-readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The documentations were written by the CSEWG evaluators and compiled by NNCSC. Selected materials which comprise this volume include from 1 H to 244 Cm

  10. Separations innovative concepts: Project summary

    Energy Technology Data Exchange (ETDEWEB)

    Lee, V.E. (ed.)

    1988-05-01

    This project summary includes the results of 10 innovations that were funded under the US Department's Innovative Concept Programs. The concepts address innovations that can substantially reduce the energy used in industrial separations. Each paper describes the proposed concept, and discusses the concept's potential energy savings, market applications, technical feasibility, prior work and state of the art, and future development needs.

  11. Status of national gas cooled reactor programmes

    International Nuclear Information System (INIS)

    1991-08-01

    This report has been compiled as a central source of summary-level information on the present status of High Temperature Gas-Cooled Reactor (HTGR) programmes in the world and on future plans for the continued development and deployment of HTGRs. Most of the information concerns the programmes in the United States, Germany, Japan and the Soviet Union, countries that have had large programmes related to HTGR technology for several years. Summary-level information is also provided in the report on HTGR-related activities in several other countries who either have an increasing interest in the technology and/or who are performing some development efforts related to HTGR technology. The report contains a summary-level update on the MAGNOX and AGR programmes. This is the twelfth issue of the document, the first of which was issued in March, 1979. The report has been prepared in the IAEA Nuclear Power Technology Development Section. Figs and tabs

  12. Compact Visualisation of Video Summaries

    Directory of Open Access Journals (Sweden)

    Janko Ćalić

    2007-01-01

    Full Text Available This paper presents a system for compact and intuitive video summarisation aimed at both high-end professional production environments and small-screen portable devices. To represent large amounts of information in the form of a video key-frame summary, this paper studies the narrative grammar of comics, and using its universal and intuitive rules, lays out visual summaries in an efficient and user-centered way. In addition, the system exploits visual attention modelling and rapid serial visual presentation to generate highly compact summaries on mobile devices. A robust real-time algorithm for key-frame extraction is presented. The system ranks importance of key-frame sizes in the final layout by balancing the dominant visual representability and discovery of unanticipated content utilising a specific cost function and an unsupervised robust spectral clustering technique. A final layout is created using an optimisation algorithm based on dynamic programming. Algorithm efficiency and robustness are demonstrated by comparing the results with a manually labelled ground truth and with optimal panelling solutions.

  13. Summary

    International Nuclear Information System (INIS)

    1982-01-01

    The International Tokamak Reactor (INTOR) Workshop is an unique collaborative effort among Euratom, Japan, the USA and the USSR, under the auspices of the IAEA, to assess, define, design, construct and operate the next major experiment in the World Tokamak Program beyond the TFTR, JET, JT-60, T-15 generation. During the Zero-Phase (1979), a technical data base assessment was performed, leading to a positive assessment of feasibility. During Phase-1 (1/80-6/81), a conceptual design was developed to define the concept. The programmatic objectives are that INTOR should: (1) be the maximum reasonable step beyond the TFTR, JET, JT-60, T-15 generation of tokamaks, (2) demonstrate the plasma performance required for tokamak DEMOs, (3) test the development and integration into a reactor system of those technologies required for a DEMO, (4) serve as a test facility for blanket, tritium production, materials, and plasma engineering technology, (5) test fusion reactor component reliability, (6) test the maintainability of a fusion reactor, and (7) test the factors affecting the reliability, safety and environmental acceptability of a fusion reactor. A conceptual design has been developed to define a device which is consistent with these objectives. The design concept could, with a reasonable degree of confidence, be developed into a workable engineering design of a tokamak that met the performance objectives of INTOR. There is some margin in the design to allow for uncertainty. While design solutions have been found for all of the critical issues, the overall design may not yet be optimal

  14. Summary

    International Nuclear Information System (INIS)

    Bickerton, George

    1997-01-01

    The Chernobyl accident has pushed many countries in analyzing critically their radiological emergency plans in order to identify the fields requiring amelioration or reinforcement. A common topic was the necessity of informing and drilling efficiently the civil population as well as different intervening agents against effects of nuclear accidents. It was stressed that the health and safety of populations, potentially most exposed, constitute a top priority, followed by the protection of food storage. The majority of the countries, were the management of public affairs is effected at two or more echelons, is confronted with the difficulty of developing plans clearly defining the missions and responsibilities of different administration levels as well as the interactions between them in case of emergency. Emphasized are also the requirements of information tools able of computing the contamination of foods or forages taking into account of factors like annual season, the phase of crop growth and the meteorological conditions. Obviously, such programs permit forecasting, surveying and evaluating the contamination and consequently, establishing the proper level of intervention. Also, the question of intervention thresholds was approached as well as the necessity of harmonizing intervention on international scale. A number of topics were mentioned to be under current study among which the relations between soil contamination and radionuclide concentration in milk and forage as well as the methods of managing the highly cesium-contaminated milk. Finally, it was argued for the necessity of ensuring the population confidence in the measures of intervention as well as in the indications of competent officials in charge with emergency actions

  15. Summary

    International Nuclear Information System (INIS)

    2002-01-01

    This report summarizes the progress made that resulted in the improvement of the organizational and analytical performance on Nuclear Analytical Laboratories at the Ankara Nuclear Research and Training Centre in accordance with ISO 17025 requirements. This report lists the main accomplishments and presents future plans of the Laboratory

  16. Summary

    Indian Academy of Sciences (India)

    In explaining this, we determine spin (frequency) of black holes which is a parameter of our model. For the best observational fit, we obtain the spin parameter of black holes ranges: 0.6 ≤ a ≤ 0.8: None of them corresponds to an extremally (a~1) rotating black hole. This is a test of Einstein's theory of General Relativity.

  17. Summary

    International Nuclear Information System (INIS)

    Roehlig, Klaus-Juergen

    2014-01-01

    Document available in abstract form only. Full text follows: During the five sessions of the workshop, much insight has been gained in a variety of issues and challenges that national programmes will encounter as they approach the construction phase of deep geologic repositories as well as their plans to address and resolve these issues. Due to the wide range of participating programmes and due to the different phases of repository development represented, the information presented at the workshop ranged from general and generic questions to specific technical, managerial, administrative, legal, regulatory and procedural issues. Although many issues still awaiting their resolutions, it can be observed that there were joint views amongst the participants with respect to the nature and specificities of these issues. These include: - the need for flexibility (within a so-called safety envelope) when projects evolve over time, - the need to address targets could be very difficult in nature and in some cases may compete with each other when developing and optimising repository systems, - the central role of management with regard to developing adequate professional attitudes and an appropriate safety culture, taking into account the various professional disciplines involved, - the need for integrating different legal and regulatory fields, often addressed by different authorities, and the question of a 'leading regulator'; - the technical challenge of conceptualising parallel processes such as excavation in parts of a repository and emplacement in others and the need to fulfil related safety requirements (mining and occupational, radiation protection etc.), - monitoring may have different roles in different phases of repository development, or - the outstanding role of the safety case prepared in advance to operation (waste emplacement) compared to the cases prepared at other stages of repository development, and the need to act accordingly in the regulatory and licensing process. This set of issues is by no means complete. For the Regulators' Forum and the IGSC it is now necessary to identify those issues and approaches to their resolutions which are of joint interest in order to address them in their programmes of work. The IGSC will, in accordance with its mandate, focus on topics related to safety case development and to the links to establish between different components of repository development. Subjects which have to be discussed and perhaps addressed in the Programme of Work include: - Operational safety: In the past, IGSC focussed on the relationship of operational and postclosure safety. A move towards questions specific for operational safety and in particular the potential for developing a list of events, incident causes etc. to be accounted for when assessing operational safety ('operational safety FEP list') will be considered. - Further attention will be devoted to establishing the linkage between the construction of engineered components and safety assessment, i.e. to the issue of feasibility to construct components according to the design specifications made by, or used in, safety assessments. - The IGSC will contribute to the EU MoDerN project in order to address issues related to monitoring and its linkage to safety demonstration. - IGSC also will further address organisational issues. (author)

  18. SUMMARY

    African Journals Online (AJOL)

    Health services, whether preventive, curative or rehabilitative, ... price (premium) that they will be prepared to pay for health ... nurses, 4% each accountants, administrators, research ..... Ghana. Exchange Health Economics and ... approaches.

  19. 31 CFR 26.3 - Availability of Environmental Impact Assessment Summaries (EIA Summaries) and Environmental...

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Availability of Environmental Impact Assessment Summaries (EIA Summaries) and Environmental Impact Assessments (EIAs). 26.3 Section 26.3 Money and... DEVELOPMENT BANDS (MDBs) § 26.3 Availability of Environmental Impact Assessment Summaries (EIA Summaries) and...

  20. Computer software summaries. Numbers 325 through 423

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-01

    The National Energy Software Center (NESC) serves as the software exchange and information center for the U.S. Department of Energy and the Nuclear Regulatory Commission. These summaries describe agency-sponsored software which is at the specification stage, under development, being checked out, in use, or available at agency offices, laboratories, and contractor installations. They describe software which is not included in the NESC library due to its preliminary status or because it is believed to be of limited interest. Codes dealing with the following subjects are included: cross section and resonance integral calculations; spectrum calculations, generation of group constants, lattice and cell problems; static design studies; depletion, fuel management, cost analysis, and power plant economics; space-independent kinetics; space--time kinetics, coupled neutronics--hydrodynamics--thermodynamics; and excursion simulations; radiological safety, hazard and accident analysis; heat transfer and fluid flow; deformation and stress distribution computations, structural analysis, and engineering design studies; gamma heating and shield design; reactor systems analysis; data preparation; data management; subsidiary calculations; experimental data processing; general mathematical and computing system routines; materials; environmental and earth sciences; space sciences; electronics and engineering equipment; chemistry; particle accelerators and high-voltage machines; physics; magnetic fusion research; biology and medicine; and data. (RWR)