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Sample records for waste executive summary

  1. 2014 Zero Waste Strategic Plan Executive Summary.

    Energy Technology Data Exchange (ETDEWEB)

    Wrons, Ralph J.

    2016-05-01

    Sandia National Laboratories/New Mexico is located in Albuquerque, New Mexico, primarily on Department of Energy (DOE) permitted land on approximately 2,800 acres of Kirtland Air Force Base. There are approximately 5.5 million square feet of buildings, with a workforce of approximately 9200 personnel. Sandia National Laboratories Materials Sustainability and Pollution Prevention (MSP2) program adopted in 2008 an internal team goal for New Mexico site operations for Zero Waste to Landfill by 2025. Sandia solicited a consultant to assist in the development of a Zero Waste Strategic Plan. The Zero Waste Consultant Team selected is a partnership of SBM Management Services and Gary Liss & Associates. The scope of this Plan is non-hazardous solid waste and covers the life cycle of material purchases to the use and final disposal of the items at the end of their life cycle.

  2. 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.)

  3. Transuranic waste form characterization and data base. Executive summary

    International Nuclear Information System (INIS)

    1980-01-01

    The Transuranic Waste Form Characterization and Data Base (Volume 1) provides a wide range of information from which a comprehensive data base can be established and from which standards and criteria can be developed for the present NRC waste management program. Supplementary information on each of the areas discussed in Volume 1 is presented in Appendices A through K (Volumes 2 and 3). The structure of the study (Volume 1) is outlined and appendices of Volumes 2 and 3 correlate with each main section of the report. The Executive Summary reviews the sources, quantities, characteristics and treatment of transuranic wastes in the United States. Due to the variety of potential treatment processes for transuranic wastes, the end products for long-term storage may have corresponding variations in quantities and characteristics

  4. 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

  5. Environmental Impact Statement: Waste Isolation Pilot Plant (WIPP): Executive summary

    International Nuclear Information System (INIS)

    1980-10-01

    The purpose of this document is to provide a summary of the environmental impact statement for the Waste Isolation Pilot Plant (WIPP) project. The Draft Environmental Impact Statement for the WIPP was published by the US Department of Energy (DOE) in April 1979. This document was reviewed and commented on by members of the general public, private organizations, and governmental agencies. The Final Environmental Impact Statement was subsequently published in October, 1980. This summary is designed to assist decision-maker and interested individuals in reviewing the material presented in the environmental impact statement for the WIPP project. To make this material widely available, this summary is published in both Spanish and English. Additional, more detailed information concerning the environmental and safety consequences of the WIPP project is available in the Final Environmental Impact Statement. Written comments and public hearing comments on the Draft Environmental Impact Statement are available for review. 27 refs., 4 figs., 7 tabs

  6. 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)

  7. 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

  8. 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

  9. Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

    A new generation of reactor designs is being developed that is intended to meet the requirements of the 21. century. In the short term, the most important requirement is to overcome the relative non-competitiveness of current reactor designs in the de-regulated market. For this purpose, evolutionary light water reactor (LWR) designs have been maturing and are being actively promoted. These are specifically designed to be less expensive to build and operate than the previous generation of LWRs, genuinely competitive with alternative forms of generation and at the same time establish higher levels of safety. A new generation of modular, small-to-medium (100-300 MWe/module), integral design water-cooled reactors are under development. These are designed to be competitive with nuclear and non-nuclear power plants, to have significantly enhanced safety, to be proliferation-resistant and to reduce the amount of radioactive waste produced. A different approach to improve competitiveness is the re-emergence of high-temperature reactors (HTRs) using gas turbine technology to obtain higher thermal efficiencies, low construction and operating costs, inherent safety characteristics and low proliferation risk. In the longer term, assuming that the current stagnation in the market is successfully overcome, other requirements related to long-term sustainability will emerge. Important amongst these will be the need to minimise the environmental burden passed on to future generations (or at least to ensure that the cost to future generations is in balance with the benefits to the current generation), the need to establish sustainability of fuel and the need to minimise stocks of separated plutonium at the minimum possible working level and to minimise accessibility to plutonium. In this context, topics of interest to the workshop were: reactors consuming excess plutonium, advanced LWRs, HTRs, fast spectrum reactors, subcritical systems, minor-actinide systems and radical innovative

  10. Executive Summary

    International Nuclear Information System (INIS)

    2012-01-01

    The OECD Nuclear Energy Agency (NEA) Integration Group for the Safety Case (IGSC) organised a workshop to assess current understanding on the use of cementitious materials in radioactive waste disposal. The workshop was hosted by the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (Ondraf/Niras), in Brussels, Belgium on 17-19 November 2009. The workshop brought together a wide range of people involved in supporting safety case development and having an interest in cementitious materials: namely, cement and concrete experts, repository designers, scientists, safety assessors, disposal programme managers and regulators. The workshop was designed primarily to consider issues relevant to the post-closure safety of radioactive waste disposal, but also addressed some related operational issues, such as cementitious barrier emplacement. Where relevant, information on cementitious materials from analogous natural and anthropogenic systems was also considered. The workshop agenda is included as Appendix A. The workshop focused on: - The uses of different cementitious materials in various repository designs. - The evolution of cementitious materials over long time scales (1000s to 100000s of years). - The interaction of cementitious materials with surrounding components of the repository (e.g. waste, container, buffer, backfill, host rock). - The workshop comprised: - Plenary sessions in which the state-of-the-art on repository design and understanding the phenomenology of cementitious materials and their interactions were presented and discussed. - Dedicated working group sessions, which were used to discuss key safety assessment and safety case questions in more detail. For example: How strong is the scientific basis for incorporating the various aspects of the behaviour and interactions of cementitious materials in safety assessments and safety cases? How can the behaviour and interactions of cementitious materials best be incorporated within the

  11. Executive Summary

    International Nuclear Information System (INIS)

    Plompen, A.; Woznicka, U.; Dupont, E.

    2011-01-01

    In the session on data needs and impact, the use of sensitivity studies is highlighted to determine lists of nuclides requiring reduced uncertainty according to the type of activities: reactor design or waste management. In the session on nuclear data validation nuclear databases like ENDF/B-VII, JENDL-3.3 and JEFF-3.1.1 were confronted to some experimental results. During the workshop new experimental setups and measurement methodologies were presented particularly for (n, xng), (n,t) reactions and deuteron-induced activation reactions and fission yields

  12. Executive Summary

    International Nuclear Information System (INIS)

    2015-01-01

    The 13. Information Exchange Meeting was held in Seoul (Republic of Korea) on 23-26 September 2014, hosted by Seoul National University. The workshop comprised a plenary session on national and international programmes followed by technical sessions and a poster session covering various aspects of P and T. The information exchange meetings on P and T form a part of the NEA programme of work in the field of advanced nuclear fuel cycles. These proceedings include papers presented at the 13. Information Exchange Meeting. The meeting covered strategic and scientific developments in the field of P and T such as: fuel cycle strategies and transition scenarios, the role of P and T in the potential evolution of nuclear energy as part of the future energy mix; radioactive waste management strategies; transmutation fuels and targets; advances in pyro and aqueous separation processes; P and T specific technology requirements (materials, spallation targets, coolants, etc.); transmutation systems: design, performance and safety; impact of P and T on the fuel cycle; fabrication, handling and transportation of transmutation fuels. A total of 103 presentations (39 oral and 64 posters) were discussed among the 110 participants from 19 countries and 2 international organisations. The meeting consisted of one plenary session where national and international programmes were presented followed by 5 technical sessions: - Fuel Cycle Strategies and Transition Scenarios; - Transmutation Systems and Infrastructures; - Waste Management for P and T Scenarios; - Advanced Nuclear Fuel Recycling (Aqueous and Pyro-processing); - Transmutation Fuels and Targets

  13. Executive Summary

    International Nuclear Information System (INIS)

    Vari, Anna; Sakuma, Hideki

    2008-01-01

    Within the radioactive waste management community it is now broadly agreed that any decision making will, and should, take place in stages. This allows for better use of current knowledge, for further knowledge to be generated, and for increased opportunity for collective learning and self-training of the various actors. In this process each actor must feel the ability to influence the decision making process, including generating complementary investigations on topics of significance in the field of safety and regarding the long-term impacts. In the technical field of the long-term safety case for disposal it is specifically acknowledged that a safety case (SC) is built in stages, and that it should recognise, at each stage, the open issues and the relevant role of research, development and demonstration (RD and D). It is also acknowledged, in connection with the SC, that stakeholders have a role to play as partners or reviewers and, ultimately, can help to shape the concept of safety. Because today the issue is no longer how to implement an economically-optimal project of waste storage or disposal on a site imposed by the authorities, new challenges are posed to the technical community and to the roles and approaches they take. Important questions are: 1. How to improve on the interaction between science and society, and ensure opportunities for societal direction of RD and D? 2. How to clearly and effectively communicate scientific findings and uncertainties and/or address contradictory views of process participants? Alternatively, how to communicate confidence in the results so far and in the process of acquiring those results? 3. How to encourage 'stretching' of specialists for disclosure of interests, greater transparency, broader dialogue, and to ensure rigour of research programmes? On June 6, 2007 a Topical Session to discuss the above questions was held at OECD NEA. Presentations were invited from delegates of five RWM organisations, including SKI and

  14. Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1978-11-01

    A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

  15. Executive Summary

    International Nuclear Information System (INIS)

    2013-01-01

    countries (MC) and concerned both initial safety assessment of new facilities and reassessment of existing ones (periodic safety review). It also considered trends of future improvement of safety assessment techniques. The workshop was organised in an opening session, four technical sessions, one special session and a conclusion session. The technical sessions were focussed on: - General approach including human aspects (9 papers); - Front end facilities (5 papers); - Chemical hazards - release limits (6 papers); and - Back end facilities (6 papers). In addition, a special session (4 presentations) was held to discuss the lessons learnt for FCFs from the Fukushima accident in Japan. The workshop ended with an organized site visit to Cameco Corporation's Port Hope Conversion Facility in Port Hope, Ontario on the last day of the workshop. This paper presents the Summary of the technical and special sessions, the General Conclusions and Recommendation of the workshop and some future directions

  16. Executive summary

    International Nuclear Information System (INIS)

    2009-01-01

    assessment process, licensee actions, regulatory actions. Summaries from the three days of workshop discussions as well as information from the licensee and regulatory responses to two pre-workshop surveys are presented. Also included are highlights from the numerous invited presentations. The conclusions and findings from the extensive group and plenary discussions are summarised too. Supporting material, discussion group presentation slides, slides from the invited presenters, and information/responses to the licensee and regulatory surveys are included in the attached Appendices

  17. Waste Isolation Pilot Plant (WIPP) conceptual design report. Part I: executive summary. Part II: facilities and system

    International Nuclear Information System (INIS)

    1977-06-01

    The pilot plant is developed for ERDA low-level contact-handled transuranic waste, ERDA remote-handled intermediate-level transuranic waste, and for high-level waste experiments. All wastes placed in the WIPP arrive at the site processed and packaged; no waste processing is done at the WIPP. All wastes placed into the WIPP are retrievable. The proposed site for WIPP lies 26 miles east of Carlsbad, New Mexico. This document includes the executive summary and a detailed description of the facilities and systems

  18. 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....

  19. 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…

  20. Proceedings of the ninth annual DOE low-level waste management forum: executive summary, technical and special session summaries, attendees

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This first volume of proceedings contains summaries of each of six technical sessions as well as three special sessions held during the conference. The six technical sessions were: Disposal technology and facility development (15 papers); Institutional and regulatory issues (10); Performance assessment (14); Waste characterization and verification (7); Site closure and stabilization (6); and Waste treatment (8). The three special sessions were: 1) Review of criteria for guidance on alternative disposal technology; 2) Hazardous waste regulatory update; and 3) Challenges to meeting the 1993 deadline. All papers have been indexed for inclusion on the Energy Data Base

  1. A Research Needs Assessment for waste plastics recycling: Volume 1, Executive summary. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    This first volume provides a summary of the entire project. The study utilized the talents of a large number of participants, including a significant number of peer reviewers from industrial companies, government agencies, and research institutes. in addition, an extensive analysis of relevant literature was carried out. In considering the attractiveness of recycling technologies that are alternatives to waste-to-energy combustion units, a systems approach was utilized. Collection of waste streams containing plastics, sortation, and reclamation of plastics and plastic mixtures, reprocessing or chemical conversion of the reclaimed polymers, and the applicability of the products to specific market segments have been analyzed in the study.

  2. DECOVALEX III PROJECT. Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Jing, L.; Stephansson, O. [Royal Inst. of Technology, Stockholm (Sweden). Engineering Geology; Tsang, C.F. [Lawrence Berkely National Laboratory, Berkeley, CA (United States). Earth Science Div.; Mayor, J.C. [ENRESA, Madrid (Spain); Kautzky, F. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)] (eds.)

    2005-02-15

    DECOVALEX is an international consortium of governmental agencies associated with the disposal of high-level nuclear waste in a number of countries. The consortium's mission is the DEvelopment of COupled models and their VALidation against EXperiments. Hence the acronym/name DECOVALEX. Currently, agencies from Canada, Finland, France, Germany, Japan, Spain, Switzerland, Sweden, United Kingdom, and the United States are in DECOVALEX. Emplacement of nuclear waste in a repository in geologic media causes a number of physical processes to be intensified in the surrounding rock mass due to the decay heat from the waste. The four main processes of concern are thermal, hydrological, mechanical and chemical. Interactions or coupling between these heat-driven processes must be taken into account in modeling the performance of the repository for such modeling to be meaningful and reliable. DECOVALEX III is organized around four tasks. The FEBEX (Full-scale Engineered Barriers EXperiment) in situ experiment being conducted at the Grimsel site in Switzerland is to be simulated and analyzed in Task 1. Task 2, centered around the Drift Scale Test (DST) at Yucca Mountain in Nevada, USA, has several sub-tasks (Task 2A, Task 2B, Task 2C and Task 2D) to investigate a number of the coupled processes in the DST. Task 3 studies three benchmark problems: a) the effects of thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2); and c) the effect of glaciation on rock mass behavior (BMT3). Task 4 is on the direct application of THM coupled process modeling in the performance assessment of nuclear waste repositories in geologic media. This executive summary presents the motivation, structure, objectives, approaches, and the highlights of the main achievements and outstanding issues of the tasks studied in the DECOVALEX III project

  3. DECOVALEX III PROJECT. Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories. Executive Summary

    International Nuclear Information System (INIS)

    Jing, L.; Stephansson, O.; Kautzky, F.

    2005-02-01

    DECOVALEX is an international consortium of governmental agencies associated with the disposal of high-level nuclear waste in a number of countries. The consortium's mission is the DEvelopment of COupled models and their VALidation against EXperiments. Hence the acronym/name DECOVALEX. Currently, agencies from Canada, Finland, France, Germany, Japan, Spain, Switzerland, Sweden, United Kingdom, and the United States are in DECOVALEX. Emplacement of nuclear waste in a repository in geologic media causes a number of physical processes to be intensified in the surrounding rock mass due to the decay heat from the waste. The four main processes of concern are thermal, hydrological, mechanical and chemical. Interactions or coupling between these heat-driven processes must be taken into account in modeling the performance of the repository for such modeling to be meaningful and reliable. DECOVALEX III is organized around four tasks. The FEBEX (Full-scale Engineered Barriers EXperiment) in situ experiment being conducted at the Grimsel site in Switzerland is to be simulated and analyzed in Task 1. Task 2, centered around the Drift Scale Test (DST) at Yucca Mountain in Nevada, USA, has several sub-tasks (Task 2A, Task 2B, Task 2C and Task 2D) to investigate a number of the coupled processes in the DST. Task 3 studies three benchmark problems: a) the effects of thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2); and c) the effect of glaciation on rock mass behavior (BMT3). Task 4 is on the direct application of THM coupled process modeling in the performance assessment of nuclear waste repositories in geologic media. This executive summary presents the motivation, structure, objectives, approaches, and the highlights of the main achievements and outstanding issues of the tasks studied in the DECOVALEX III project. The

  4. Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) program plan: Executive summary

    International Nuclear Information System (INIS)

    McGinnis, C.P.; Eisenhower, B.M.; Reeves, M.E.; DePaoli, S.M.; Stinton, L.H.; Harrington, E.H.

    1989-02-01

    The Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) Program Plan provides a strategy for management of hazardous and mixed wastes generated by the five Department of Energy (DOE) installations managed by Martin Marietta Energy Systems, Inc. (Energy Systems). This integrated corporate plan is based on the individual installation plans, which identify waste streams, facility capabilities, problem wastes, future needs, and funding needs. Using this information, the corporate plan identifies common concerns and technology/facility needs over the next 10 years. The overall objective of this corporate plan is to ensure that treatment, storage, and disposal (TSD) needs for all hazardous and mixed wastes generated by Energy Systems installations have been identified and planned for. Specific objectives of the program plan are to (1) identify all hazardous and mixed waste streams; (2) identify hazardous and mixed waste TSD requirements; (3) identify any unresolved technical issues preventing implementation of the strategy; (4) develop schedules for studies, demonstrations, and facilities to resolve the issues; and (5) define the interfaces with the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. 10 refs., 7 figs

  5. Municipal solid waste options : integrating organics management and residual disposal treatment : executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Cant, M. (comp.) [Totten Sims Hubicki Associates Ltd., Calgary, AB (Canada); Van der Werf, P. [2cg Inc., Edmonton, AB (Canada); Kelleher, M. [Kelleher Environmental, Toronto, ON (Canada); Merriman, D. [MacViro Consultants, Markham, ON (Canada); Fitcher, K. [Gartner Lee Ltd., Toronto, ON (Canada); MacDonald, N. [CH2M Hill Engineering Ltd., Calgary, AB (Canada)

    2006-04-15

    The Municipal Solid Waste (MSW) Options Report explored different MSW management options for 3 community sizes: 20,000, 80,000 and 200,0000 people. It was released at a time when many communities were developing waste management plans to cost-effectively reduce environmental impacts and conserve landfill capacity. The purpose of this report was to provide a greater understanding on the environmental, social, economic, energy recovery/utilization and greenhouse gas (GHG) considerations of MSW management. The report also demonstrated the interrelationships between the management of organics and residuals. It was based on information from existing waste diversion and organics management options and emerging residual treatment technology options. The following organics management and residual treatment disposal options were evaluated: composting; anaerobic digestion; sanitary landfills; bioreactor landfills; and thermal treatment. Composting was examined with reference to both source separated organics (SSO) and mixed waste composting. SSO refers to the separation of materials suitable for composting solid waste from households, while mixed waste composting refers to the manual or mechanical removal of recyclable material from the waste, including compost. The composting process was reviewed along with available technologies such as non-reactor windrow; aerated static pile; reactor enclosed channel; and, container tunnel. An evaluation of SSO and mixed waste composting was then presented in terms of environmental, social, financial and GHG impacts. refs., tabs., figs.

  6. Radioactive waste disposal programme and siting regions for geological deep repositories. Executive summary. November 2008

    International Nuclear Information System (INIS)

    2008-11-01

    There are radioactive wastes in Switzerland. Since many decades they are produced by the operation of the five nuclear power plants, by medicine, industry and research. Important steps towards the disposal of these wastes are already realized; the corresponding activities are practised. This particularly concerns handling and packaging of the radioactive wastes, their characterization and inventory, as well as the interim storage and the inferred transportations. Preparatory works in the field of scientific research on deep geological repositories have allowed to acquire high level of technical and scientific expertise in that domain. The feasibility of building long-term safe geological repositories in Switzerland was demonstrated for all types of radioactive wastes; the demonstration was accepted by the Federal Council. There is enough knowledge to propose geological siting regions for further works. The financial funds already accumulated guaranty the financing of the dismantling of the power plants as well as building deep geological repositories for the radioactive wastes. The regulations already exist and the organisational arrangements necessary for the fruitful continuation of the works already done have been taken. The programme of the disposal of radioactive wastes also describes the next stages towards the timely realization of the deep repositories as well as the level of the financial needs. The programme is updated every five years, checked by the regulatory bodies and accepted by the Federal Council who reports to the parliament. The process of choosing a site, which will be completed in the next years, is detailed in the conceptual part of the programme for deep geological repositories. The NAGRA proposals are based exclusively on technical and scientific considerations; the global evaluation taking into account also political considerations has to be performed by the authorities and the Federal Council. The programme states that at the beginning of

  7. Feasibility of Space Disposal of Radioactive Nuclear Waste. 1: Executive Summary

    Science.gov (United States)

    1973-01-01

    This NASA study, performed at the request of the AEC, concludes that transporting radioactive waste (primarily long-lived isotopes) into space is feasible. Tentative solutions are presented for technical problems involving safe packaging. Launch systems (existing and planned), trajectories, potential hazards, and various destinations were evaluated. Solar system escape is possible and would have the advantage of ultimate removal of the radioactive waste from man's environment. Transportation costs would be low (comparable to less than a 5 percent increase in the cost of electricity) even though more than 100 space shuttle launches per year would be required by the year 2000.

  8. High level radioactive waste repositories. Task 3. Review of underground handling and emplacement. 1. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    A review is presented of proposals for transport, handling and emplacement of high-level radioactive waste 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; transport by road/rail to repository site; handling techniques within repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; conventional and radiological safety; costs; and major areas of uncertainty requiring research or development.

  9. Waste Isolation Pilot Plant no-migration variance petition. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-31

    Section 3004 of RCRA allows EPA to grant a variance from the land disposal restrictions when a demonstration can be made that, to a reasonable degree of certainty, there will be no migration of hazardous constituents from the disposal unit for as long as the waste remains hazardous. Specific requirements for making this demonstration are found in 40 CFR 268.6, and EPA has published a draft guidance document to assist petitioners in preparing a variance request. Throughout the course of preparing this petition, technical staff from DOE, EPA, and their contractors have met frequently to discuss and attempt to resolve issues specific to radioactive mixed waste and the WIPP facility. The DOE believes it meets or exceeds all requirements set forth for making a successful ``no-migration`` demonstration. The petition presents information under five general headings: (1) waste information; (2) site characterization; (3) facility information; (4) assessment of environmental impacts, including the results of waste mobility modeling; and (5) analysis of uncertainties. Additional background and supporting documentation is contained in the 15 appendices to the petition, as well as in an extensive addendum published in October 1989.

  10. Analysis of nuclear waste disposal in space, phase 3. Volume 1: Executive summary of technical report

    Science.gov (United States)

    Rice, E. E.; Miller, N. E.; Yates, K. R.; Martin, W. E.; Friedlander, A. L.

    1980-01-01

    The objectives, approach, assumptions, and limitations of a study of nuclear waste disposal in space are discussed with emphasis on the following: (1) payload characterization; (2) safety assessment; (3) health effects assessment; (4) long-term risk assessment; and (5) program planning support to NASA and DOE. Conclusions are presented for each task.

  11. Geohydrological studies for nuclear waste isolation at the Hanford Reservation. Volume I. Executive summary

    International Nuclear Information System (INIS)

    Apps, J.; Doe, T.; Doty, B.

    1979-08-01

    A study of the hydrology of the Pasco Basin near Richland, Washington, was initiated during FY 1978 as part of a long-term study on the feasibility of nuclear waste disposal in the Columbia River Basalt underlying the Hanford Reservation. This report summarizes the hydrology field program, Pasco Basin modeling, and groundwater chemistry program. Hanford well logs are also reviewed

  12. 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;…

  13. Eleventh annual U.S. DOE low-level radioactive waste management conference: Executive summary, opening plenary, technical session summaries, and attendees

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-01-01

    The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

  14. Savannah River Plant Low-Level Waste Heat Utilization Project preliminary analysis. Volume I. Executive summary

    International Nuclear Information System (INIS)

    1978-11-01

    A preliminary feasibility study of capturing energy ejected in hot water at the Savannah River Plant (SRP) is presented. The cooling water, drawn from the river or a pond at the rate of 500,000 gallons per minute, is typically heated 80 0 F to about 150 0 F and is then allowed to cool in the atmosphere. The energy added to the water is equivalent to 20 million barrels of oil a year. This study reports that the reject heat can be used directly in an organic Rankine cycle system to evaporate fluids which drive electric generators. The output of one reactor can produce 45,000 kilowatts of electricity. Since the fuel is waste heat, an estimated 45% savings over conventional electric costs is possible over a thirty year period

  15. Preliminary risk assessment for nuclear waste disposal in space. Volume I. Executive summary of technical report

    International Nuclear Information System (INIS)

    Rice, E.E.; Denning, R.S.; Friedlander, A.L.

    1982-01-01

    Three major conclusions come from this preliminary risk assessment of nuclear waste disposal in space. Preliminary estimates of space disposal risk are low, even with the estimated uncertainty bounds. If calculated mined geologic repository (MGR) release risks remain low, and the EPA requirements continue to be met, then no additional space disposal study effort is warranted. If risks perceived by the public are significant in the acceptance of mined geologic repositories, then consideration of space disposal as an MGR complement is warranted. As a result of this study, the following recommendations are made to NASA and the US DOE: During the continued evaluation of the mined geologic repository risk over the years ahead by DOE, if any significant increase in the calculated health risk is predicted for the MGR, then space disposal should be reevaluated at that time. The risks perceived by the public for the MGR should be evaluated on a broad basis by an independent organization to evaluate acceptance. If, in the future, MGR risks are found to be significant due to some presently unknown technical or social factor, and space disposal is selected as an alternative that may be useful in mitigating the risks, then the following space disposal study activities are recommended: improvement in chemical processing technology for wastes; payload accident response analysis; risk uncertainty analysis for both MGR and space disposal; health risk modeling that includes pathway and dose estimates; space disposal cost modeling; assessment of space disposal perceived (by public) risk benefit; and space systems analysis supporting risk and cost modeling

  16. Review of potential host rocks for radioactive waste disposal in the southeastern United States. Executive summary

    International Nuclear Information System (INIS)

    Bledsoe, H.W. Jr.; Marine, I.W.

    1980-10-01

    The geology of the southeastern United States was studied to recommend areas that should be considered for field exploration in order to select a site for a radioactive waste repository. The region studied included the Piedmont Province, the Triassic Basins, and the Atlantic Coastal Plain in Maryland, Virginia, North Carolina, South Carolina, and Georgia. This study was entirely a review of literature and existing knowledge from a geotechnical point of view and was performed by subcontractors whose individual reports are listed in the bibliography. No field work was involved. The entire study was geotechnical in nature, and no consideration was given to socioeconomic or demographic factors. These factors need to be addressed in a separate study. For all areas, field study is needed before any area is further considered. A total of 29 areas are recommended for further consideration in the Piedmont Province subregion: one area in Maryland, 8 areas in Virginia, 4 areas in North Carolina, 6 areas in South Carolina, and 10 areas in Georgia. Of the 14 exposed and 5 buried or hypothesized basins identified in the Triassic basin subregion, 6 are recommended for further study: one basin in Virginia, 3 basins in North Carolina, and 2 basins in South Carolina. Four potential candidate areas are identified within the Atlantic Coastal Plain subregion: one in Maryland, one in North Carolina, and 2 in Georgia

  17. A European roadmap for developing accelerator driven systems (ADS) for nuclear waste incineration. Executive summary

    International Nuclear Information System (INIS)

    The European Technical Working Group on ADS

    2001-01-01

    In 1998 the Research Ministers of France, Italy and Spain, set up a Ministers' Advisors Group on the use of accelerator driven systems (ADS) for nuclear waste transmutation. This led to the establishing of a technical working group under the chairmanship of Prof. Carlo Rubbia to identify the critical technical issues and to prepare a 'Roadmap' for a demonstration programme to be performed within 12 years. In the following Roadmap, the technical working group (consisting of representatives from Austria, Belgium, Finland, France, Germany, Italy, Portugal, Spain, Sweden and the JRC) has identified the steps necessary to start the construction of an experimental accelerator driven system towards the end of the decade. This is considered as an essential prerequisite to assess the safe and efficient behaviour of such systems for a large-scale deployment for transmutation purposes in the first half of this century. The development and deployment of accelerator driven systems requires three steps: a comprehensive mid- and long-term R and D program, to develop the single elements and components of the system. This includes development of new fuels and fuel cycle systems; planning, design, construction and operation of an Experimental Accelerator Driven System for the demonstration of the concept; planning, design, construction and operation of a large size prototype accelerator driven systems with subsequent large-scale deployment. Following a first phase of R and D focused on the understanding of the basic principles of ADS (already partly underway), the programmes should be streamlined and focused on a practical demonstration of the key issues. These demonstrations should cover high intensity proton accelerators (beam currents in the range 1-20 mA), spallation targets of high power (of power in excess of 1 megawatt), and their effective coupling with a sub-critical core. Cost estimates are taken into account as well as the ADS activities in Japan and USA

  18. WEO-2011 Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    There are few signs that the urgently needed change in direction in global energy trends is underway. Although the recovery in the world economy since 2009 has been uneven, and future economic prospects remain uncertain, global primary energy demand rebounded by a remarkable 5% in 2010, pushing CO2 emissions to a new high. Subsidies that encourage wasteful consumption of fossil fuels jumped to over $400 billion. The number of people without access to electricity remained unacceptably high at 1.3 billion, around 20% of the world's population. Despite the priority in many countries to increase energy efficiency, global energy intensity worsened for the second straight year. Against this unpromising background, events such as those at the Fukushima Daiichi nuclear power plant and the turmoil in parts of the Middle East and North Africa (MENA) have cast doubts on the reliability of energy supply, while concerns about sovereign financial integrity have shifted the focus of government attention away from energy policy and limited their means of policy intervention, boding ill for agreed global climate change objectives.

  19. DECOVALEX - Mathematical models of coupled T-H-M processes for nuclear waste repositories. Executive summary for Phases I,II and III

    International Nuclear Information System (INIS)

    Jing, L.; Stephansson, O.; Tsang, C.F.; Kautsky, F.

    1996-06-01

    This executive summary presents the motivation, structure, objectives, methodologies and results of the first stage of the international DECOVALEX project - DECOVALEX I (1992-1995). The acronym stands for Development of Coupled Models and their Validation against Experiment in Nuclear Waste Isolation, and the project is an international effort to develop mathematical models, numerical methods and computer codes for coupled thermo-hydro-mechanical processes in fractured rocks and buffer materials for geological isolation of spent nuclear fuel and other radioactive wastes, and validate them against laboratory and field experiments. 24 refs

  20. 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

  1. 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

  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. Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary

    International Nuclear Information System (INIS)

    1996-03-01

    A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

  4. Executive summary of the Cryofracture demonstration program

    International Nuclear Information System (INIS)

    Loomis, G.; Osborne, D.; Ancho, M.

    1991-09-01

    This report provides an executive summary of the Cryofracture demonstration program performed at Nuclear Remedial Technologies Corporation under contract to EG ampersand G Idaho, Inc., for the Department of Energy (DOE). Cryofracture is a size-reducing process whereby objects are frozen whereby objects are frozen to liquid nitrogen temperatures and crushed in a large hydraulic press. Material at the cryogenic temperatures have low ductility and are easily size reduced by fracturing. The main application being investigated for the DOE is for retrieved buried and stored transuranic (TRU) waste. Six 55-gallon drums and six 2 ft x 2 ft x 8 ft boxes containing simulated waste with tracers were subjected to the Cryofracture process. Data was obtained on (a) cool-down time, (b) yield strength of the containers, (c) size distribution of the waste before and after the Cryofracture process, (d) volume reduction of the waste, and (e) sampling of air and surface dusts for spread of tracers to evaluate potential contamination spread. The Cryofracture process was compared to conventional shredders and detailed cost estimates were established for construction of a Cryofracture facility at the Idaho National Engineering Laboratory. Although cost estimates for conventional shredding are higher for Cryofracture, the potential for fire and explosion during conventional shredding would incur additional costs to preclude these events. These additional costs are unknown and would require considerable research and development. 4 refs., 6 figs., 7 tabs

  5. FIXING HEALTH SYSTEMS / Executive Summary (2008 update ...

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

    2010-12-14

    Dec 14, 2010 ... FIXING HEALTH SYSTEMS / Executive Summary (2008 update) ... In several cases, specific approaches recommended by the TEHIP team have been acted upon regionally and internationally, including the ... Related articles ...

  6. Charles River Residual Designation: Executive Summary

    Science.gov (United States)

    Read an executive summary of the Record of Decision's preliminary decision by the Regional Administrator of EPA Region 1 that storm water permits are needed to address serious water quality problems in the Charles River.

  7. Analysis of space systems for the space disposal of nuclear waste follow-on study. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1982-01-01

    The following major conclusions resulted from this study: Parameters for the reference cermet waste form are available only by analogy. Detail design of the waste payload would require determination of actual waste form properties. Billet configuration constraints for the cermet waste form limit waste payload packing efficiency to slightly under 75% net volume, resulting in a 20% increase in the number of flights and subsequent increases in both cost and risk. Alternative systems for waste mixes requiring low launch rates (technetium-99, iodine-129) can make effective use of the existing 65K space transportation system in either single- or dual-launch scenarios. A trade study involving a comprehensive comparison of life cycle costs would be required to select the optimum orbit transfer system for low-launch-rate systems. This was not a part of the present effort due to selection of the cermet waste form as the reference for the study. The reference space system offers the best combination of cost, risk, and alignment with ongoing NASA technology development for disposal of the reference cermet waste form within specified system safety guidelines

  8. Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1983-08-01

    Nuclear byproducts are a major national resource that has yet to be incorporated into the economy. The current Defense Byproducts Program is designed to match specific military and commercial needs with the availability of valuable products which are currently treated as waste at considerable expense in waste management costs. This program plan focuses on a few specific areas with the greatest potential for near-term development and application. It also recognizes the need for a continuing effort to develop new applications for byproducts and to continue to assess the impacts on waste management. The entire program has been, and will continue to be structured so as to ensure the safety of the public and maintain the purity of the environment. Social and institutional concerns have been recognized and will be handled appropriately. A significant effort will be undertaken to inform the public of the benefits of byproduct use and of the care being taken to ensure safe, efficient operation

  9. Department of Energy plan for recovery and utilization of nuclear byproducts from defense wastes. Volume 1. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-08-01

    Nuclear byproducts are a major national resource that has yet to be incorporated into the economy. The current Defense Byproducts Program is designed to match specific military and commercial needs with the availability of valuable products which are currently treated as waste at considerable expense in waste management costs. This program plan focuses on a few specific areas with the greatest potential for near-term development and application. It also recognizes the need for a continuing effort to develop new applications for byproducts and to continue to assess the impacts on waste management. The entire program has been, and will continue to be structured so as to ensure the safety of the public and maintain the purity of the environment. Social and institutional concerns have been recognized and will be handled appropriately. A significant effort will be undertaken to inform the public of the benefits of byproduct use and of the care being taken to ensure safe, efficient operation.

  10. Analysis of the total system life cycle cost for the Civilian Radioactive Waste Management Program: executive summary

    International Nuclear Information System (INIS)

    1985-04-01

    The total-system life-cycle cost (TSLCC) analysis for the Department of Energy's Civilian Radioactive Waste Management Progrram is an ongoing activity that helps determine whether the revenue-producing mechanism established by the Nuclear Waste Policy Act of 1982 is sufficient to cover the cost of the program. This report is an input into the third evaluation of the adequacy of the fee. The total-system cost for the reference waste-management program in this analysis is estimated to be 24 to 30 billion (1984) dollars. For the sensitivity cases studied in this report, the costs could be as high as 35 billion dollars and as low as 21 billion dollars. Because factors like repository location, the quantity of waste generated, transportation-cask technology, and repository startup dates exert substantial impacts on total-system costs, there are several tradeoffs between these factors, and these tradeoffs can greatly influence the total cost of the program. The total-system cost for the reference program described in this report is higher by 3 to 5 billion dollars, or 15 to 20%, than the cost for the reference program of the TSLCC analysis of April 1984. More than two-thirds of this increase is in the cost of repository construction and operation. These repository costs have increased because of changing design concepts, different assumptions about the effort required to perform the necessary activities, and a change in the source data on which the earlier analysis was based. Development and evaluation costs have similarly increased because of a net addition to the work content. Transportation costs have increased because of different assumptions about repository locations and several characteristics of the transportation system. It is expected that the estimates of total-system costs will continue to change in response to both an evolving program strategy and better definition of the work required to achieve the program objectives

  11. 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.

  12. Risk-based systems analysis of emerging high-level waste tank remediation technologies. Volume 1: Executive summary

    International Nuclear Information System (INIS)

    Peters, B.B.; Cameron, R.J.; McCormack, W.D.

    1994-08-01

    This report describes a System Analysis Model developed under the US Department of Energy (DOE) Office of Technology Development (OTD) Underground Storage Tank-Integrated Demonstration (UST-ID) program to aid technology development funding decisions for radioactive tank waste remediation. Current technology development selection methods evaluate new technologies in isolation from other components of an overall tank waste remediation system. These methods do not show the relative effect of new technologies on tank remediation systems as a whole. Consequently, DOE may spend its resources on technologies that promise to improve a single function but have a small or possibly negative, impact on the overall system, or DOE may overlook a technology that does not address a high priority problem in the system but that does, if implemented, offer sufficient overall improvements. Systems engineering and detailed analyses often conducted under the National Environmental Policy Act (NEPA 1969) use a ''whole system'' approach but are costly, too time-consuming, and often not sufficiently focused to support the needs of the technology program decision-makers. An alternative approach is required to evaluate these systems impacts but still meet the budget and schedule needs of the technology program

  13. Engineering studies: high-level radioactive waste repositories task 3 - review of underground handling and emplacement. 1. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1981-02-01

    The report reviews proposals for transport, handling and emplacement of high-level radioactive waste in an underground repository with particular reference to: waste block size and configuration; self-shielded or partially-shielded block; stages of disposal; transport by road/rail to repository site; handling techniques within repository; emplacement in vertical holes or horizontal tunnels; repository access by adit, incline or shaft; conventional and radiological safety; costs; and major areas of uncertainty requiring research or development. In carrying out this programme due attention was given to work already carried out both in the U.K. and overseas and where appropriate comparisons with this work have been made to substantiate and explain the observations made in this report. The examination and use of this previous work however has been confined to those proposals which were considered capable of meeting the basic design criterion for a U.K. based repository, that the maximum temperature achieved by the host rock should not exceed 100/sup 0/C.

  14. Guidelines for selecting codes for ground-water transport modeling of low-level waste burial sites. Executive summary

    International Nuclear Information System (INIS)

    Simmons, C.S.; Cole, C.R.

    1985-05-01

    This document was written to provide guidance to managers and site operators on how ground-water transport codes should be selected for assessing burial site performance. There is a need for a formal approach to selecting appropriate codes from the multitude of potentially useful ground-water transport codes that are currently available. Code selection is a problem that requires more than merely considering mathematical equation-solving methods. These guidelines are very general and flexible and are also meant for developing systems simulation models to be used to assess the environmental safety of low-level waste burial facilities. Code selection is only a single aspect of the overall objective of developing a systems simulation model for a burial site. The guidance given here is mainly directed toward applications-oriented users, but managers and site operators need to be familiar with this information to direct the development of scientifically credible and defensible transport assessment models. Some specific advice for managers and site operators on how to direct a modeling exercise is based on the following five steps: identify specific questions and study objectives; establish costs and schedules for achieving answers; enlist the aid of professional model applications group; decide on approach with applications group and guide code selection; and facilitate the availability of site-specific data. These five steps for managers/site operators are discussed in detail following an explanation of the nine systems model development steps, which are presented first to clarify what code selection entails

  15. Model Adoption Exchange Payment System: Executive Summary.

    Science.gov (United States)

    Ambrosino, Robert J.

    This executive summary provides a brief description of the Model Adoption Exchange Payment System (MAEPS), a unique payment system aimed at improving the delivery of adoption exchange services throughout the United States. Following a brief introductory overview, MAEPS is described in terms of (1) its six components (registration, listing,…

  16. Hawaii energy strategy: Executive summary, October 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This is an executive summary to a report on the Hawaii Energy Strategy Program. The topics of the report include the a description of the program including an overview, objectives, policy statement and purpose and objectives; energy strategy policy development; energy strategy projects; current energy situation; modeling Hawaii`s energy future; energy forecasts; reducing energy demand; scenario assessment, and recommendations.

  17. FAIR - Baseline technical report. Executive summary

    International Nuclear Information System (INIS)

    Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

    2006-09-01

    This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

  18. TFOS DEWS II Report Executive Summary.

    Science.gov (United States)

    Craig, Jennifer P; Nelson, J Daniel; Azar, Dimitri T; Belmonte, Carlos; Bron, Anthony J; Chauhan, Sunil K; de Paiva, Cintia S; Gomes, José A P; Hammitt, Katherine M; Jones, Lyndon; Nichols, Jason J; Nichols, Kelly K; Novack, Gary D; Stapleton, Fiona J; Willcox, Mark D P; Wolffsohn, James S; Sullivan, David A

    2017-10-01

    This article presents an Executive Summary of the conclusions and recommendations of the 10-chapter TFOS DEWS II report. The entire TFOS DEWS II report was published in the July 2017 issue of The Ocular Surface. A downloadable version of the document and additional material, including videos of diagnostic and management techniques, are available on the TFOS website: www.TearFilm.org. Copyright © 2017 Elsevier Inc. All rights reserved.

  19. Proceedings of the eighth annual DOE low-level waste management forum: Executive summary, opening plenary session, closing plenary session, attendees

    International Nuclear Information System (INIS)

    1987-02-01

    The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base

  20. Proceedings of the eighth annual DOE low-level waste management forum: Executive summary, opening plenary session, closing plenary session, attendees

    Energy Technology Data Exchange (ETDEWEB)

    1987-02-01

    The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base.

  1. North Central Regional Geologic Characterization Report. Executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final North Central Regional Geologic Characterization Report (RGCR) is issued primarily for public information purposes and provides a general overview of the report. The complete RGCR presents available regional geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Minnesota, Wisconsin, and the Upper Peninsula of Michigan. For each of the states within the North Central Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening

  2. Northeastern Regional Geologic Characterization Report: executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final Northeastern Regional Geologic Characterization Report (RGCR) is issued primarily for public information purposes and provides a general overview of the report. The complete RGCR presents available regional geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Connecticut, Maine, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont. For each of the states within the Northeastern Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening. 5 refs., 3 figs

  3. Southeastern Regional Geologic Characterization Report. Executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final Southeastern Regional Geologic Characterization Report (RGCR) is issued primarily for public information purposes, and provides a general overview of the report. The complete RGCR presents available regional geologic information pertinent to siting a repository for high-level nuclear waste in crystalline rock in central Maryland; noncoastal Virginia, North Carolina, and South Carolina; and northern Georgia. For each of the states within the Southeastern Region, information is provided on the geologic disqualifying factor and the geologic regional screening variables to be used in region-to-area screening

  4. Northeastern Regional Environmental Characterization Report. Executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final Northeastern Regional Environmental Characterization Report (RECR) is issued primarily for public information purposes and provides a general overview of the report. The complete RECR presents available regional environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Connecticut, Maine, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont. For each of the states within the Northeastern Region, information is provided on the environmental disqualifying factors and the environmental regional screening variables to be used in region-to-area screening

  5. North Central regional environmental characterization report: executive summary - final

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final North Central Regional Environmental Characterization Report (RECR) is issued primarily for public information purposes and provides a general overview of the report. The complete RECR presents available regional environmental information pertinent to siting a repository for high-level nuclear waste in crystalline rock in Minnesota, Wisconsin, and the Upper Peninsula of Michigan. For each of the States within the North Central Region, information is provided on the environmental disqualifying factors and the environmental regional screening variables to be used in region-to-area screening

  6. Southeastern Regional Environmental Characterization Report: executive summary. Final report

    International Nuclear Information System (INIS)

    1985-08-01

    This Executive Summary of the final ''Southeastern Regional Environmental Characterization Report'' (RECR) is issued primarily for public information purposes and provides a general overview of the report. The complete RECR presents available regional environmental information pertinent to siting a repository or high-level nuclear waste in crystalline rock in central Maryland; noncoastal Virginia, North Carolina, and South Carolina; and northern Georgia. For each of the states within the Southeastern Region, information is provided on the environmental disqualifying factors and the environmental regional screening variables to be used in region-to-area screening

  7. HEAO Block 2 study executive summary

    International Nuclear Information System (INIS)

    1976-03-01

    An executive summary is presented of a preliminary study done on several potential High Energy Astronomy Observatory (HEAO) missions which are follow-on missions to the currently defined HEAO program. The purpose was to examine several typical missions and determine the relative complexities associated with them. The four payloads investigated were a 1.2 m Diameter x-ray Telescope observatory, a Large Area Moderate Angular Resolution (LAMAR) observatory, a cosmic ray observatory, and (4) a gamma ray observatory. Each of the four observatories was considered a national facility. Low cost approaches were stressed throughout, with considerable use of HEAO Block I experience and designs effected to provide a high degree of confidence that such approaches were achievable. The use of the Multi-Mission Spacecraft (MMS) and the HEAO Block I spacecraft was considered as a result of this low cost emphasis. Also, NASA standard components were considered, where applicable

  8. The Allied Dental Professions: Executive Summary.

    Science.gov (United States)

    Fried, Jacquelyn L

    2017-09-01

    This executive summary for Section 5 of the "Advancing Dental Education in the 21 st Century" project addresses the current and future educational systems for dental assisting, dental hygiene, dental therapy, and dental laboratory technology. Nineteen experts prepared six background articles on the educational changes necessary for future roles and practices. The key issues addressed relate to delivery system changes, educational curricula, scopes of practice, regulatory measures, and the public's oral health. The major finding is that substantial reforms will be needed to adequately prepare allied oral health professionals for the changes anticipated in 2040. A reconsideration of current accreditation guidelines, more flexibility with scopes of practice, and an adherence to rigorous academic programs are essential elements for the future of these professions.

  9. Executive Summary, Hydraulic Fracturing Study - Draft Assessment 2015

    Science.gov (United States)

    In this Executive Summary of the HF Draft report, EPA highlights the reviews of scientific literature to assess the potential for hydraulic fracturing for oil and gas to change the quality or quantity of drinking water resources.

  10. Executive Headteachers: What's in a Name? Executive Summary

    Science.gov (United States)

    Theobald, Katy; Lord, Pippa

    2016-01-01

    Executive headteachers (EHTs) are becoming increasingly prevalent as the self-improving school system matures; there are over 620 EHTs in the school workforce today; and the number recorded in the School Workforce Census (SWC) has increased by 240 per cent between 2010 and 2014. The role is still evolving locally and nationally and, as EHTs take…

  11. Executive summary, Hanford Site Pollution Prevention Plan

    International Nuclear Information System (INIS)

    1992-08-01

    A pollution prevention plan is an organized, comprehensive, and continual effort to systematically reduce waste generation. The Hanford Site Pollution Prevention Plan is designed to eliminate or minimize pollutant releases to all environmental media from all aspects of Site operations. These efforts offer increased protection of public health and the environment. This plan reflects the goals and policies for pollution prevention at the Hanford Site and represents an ongoing effort to make pollution prevention part of the Site operating philosophy. The plan encompasses hazardous waste only and excludes radioactive waste and radioactive mixed waste

  12. Belgian Workshop (November 2003) - Executive Summary and International Perspective

    International Nuclear Information System (INIS)

    2004-01-01

    delegates to learn about the history, the natural environment and the socio-economic circumstances of potential host communities, as well as the day-by-day experiences of local people, involved in the local partnerships Visits also provided for interactions and exchange between local stakeholders and the FSC community. During Day 3 the central theme of the workshop was addressed. Invited plenary speakers including local stakeholders and social scientists gave presentations on how to integrate multiple interests, values and knowledge into joint risk management. Presentations provided a background to subsequent round table discussions, which allowed local stakeholders and international delegates to interact and exchange in detail. On Day 4 morning a panel discussion took place which focused on the design of a repository and investigated how it could reflect a plurality of interests, values, and knowledge. The rest of Day 4 was devoted to the feedback by two thematic rapporteurs. They evaluated the meeting from two distinct perspectives: that of urban and regional development, and of participatory decision making. 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

  13. Radioactive waste disposal programme and siting regions for geological deep repositories. Executive summary. November 2008; Entsorgungsprogramm und Standortgebiete fuer geologische Tiefenlager. Zusammenfassung. November 2008

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-11-15

    There are radioactive wastes in Switzerland. Since many decades they are produced by the operation of the five nuclear power plants, by medicine, industry and research. Important steps towards the disposal of these wastes are already realized; the corresponding activities are practised. This particularly concerns handling and packaging of the radioactive wastes, their characterization and inventory, as well as the interim storage and the inferred transportations. Preparatory works in the field of scientific research on deep geological repositories have allowed to acquire high level of technical and scientific expertise in that domain. The feasibility of building long-term safe geological repositories in Switzerland was demonstrated for all types of radioactive wastes; the demonstration was accepted by the Federal Council. There is enough knowledge to propose geological siting regions for further works. The financial funds already accumulated guaranty the financing of the dismantling of the power plants as well as building deep geological repositories for the radioactive wastes. The regulations already exist and the organisational arrangements necessary for the fruitful continuation of the works already done have been taken. The programme of the disposal of radioactive wastes also describes the next stages towards the timely realization of the deep repositories as well as the level of the financial needs. The programme is updated every five years, checked by the regulatory bodies and accepted by the Federal Council who reports to the parliament. The process of choosing a site, which will be completed in the next years, is detailed in the conceptual part of the programme for deep geological repositories. The NAGRA proposals are based exclusively on technical and scientific considerations; the global evaluation taking into account also political considerations has to be performed by the authorities and the Federal Council. The programme states that at the beginning of

  14. High-Impact Succession Management. Executive Summary

    Science.gov (United States)

    Lamoureux, Kim; Campbell, Michael; Smith, Roland

    2009-01-01

    Most companies have an opportunity to improve their succession management programs. The number one challenge for succession management (as identified by both HR leaders and executives) is developing a succession planning strategy. This comprehensive industry study sets out to determine how succession management (when done well) helps improve…

  15. Nuclear Energy Innovation Workshops. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Allen, Todd [Idaho National Lab. (INL), Idaho Falls, ID (United States); Jackson, John [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hildebrandt, Phil [Idaho National Lab. (INL), Idaho Falls, ID (United States); Baker, Suzy [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-06-01

    The nuclear energy innovation workshops were organized and conducted by INL on March 2-4, 2015 at the five NUC universities and Boise State University. The output from these workshops is summarized with particular attention to final summaries that were provided by technical leads at each of the workshops. The current revision includes 3-4 punctuation corrections and a correction of the month of release from May to June.

  16. Summon Post Implementation Interviews Study - Executive Summary

    KAUST Repository

    Ramli, Rindra M.

    2017-01-01

    This executive report summarizes the interview findings on the use of Summon by our community. Summon is the library's new webscale discovery layer that was launched in May 2016. The findings highlighted that Google Scholar remains the popular resource to search for articles. In addition to that, library website (Koral / Summon) is commonly used to search for known items such as book / electronic book titles. The report also includes the author's short and long term recommendations to address the shortcomings of the present situation.

  17. Summon Post Implementation Interviews Study - Executive Summary

    KAUST Repository

    Ramli, Rindra M.

    2017-04-12

    This executive report summarizes the interview findings on the use of Summon by our community. Summon is the library\\'s new webscale discovery layer that was launched in May 2016. The findings highlighted that Google Scholar remains the popular resource to search for articles. In addition to that, library website (Koral / Summon) is commonly used to search for known items such as book / electronic book titles. The report also includes the author\\'s short and long term recommendations to address the shortcomings of the present situation.

  18. Waste characterization practices: summary paper

    International Nuclear Information System (INIS)

    Logan, J.A.

    1987-01-01

    Recent reviews of the records on disposal waste at several DOE sites have indicated that records still contain little information practical to waste management. Much of the disposed waste is identified by vague terms, i.e., general plant waste. Attached to this paper is a new waste characterization code devised by the Idaho National Engineering Laboratory to aid in waste volume reduction and stabilization. It is recommended that every facility involved in waste generation and disposal needs to be detailing its wastes to support upgrading of waste management practices. 1 table

  19. The College Payoff: Education, Occupations, Lifetime Earnings. Executive Summary

    Science.gov (United States)

    Carnevale, Anthony P.; Rose, Stephen J.; Cheah, Ban

    2011-01-01

    Education and earnings interact in complex and often unexpected ways--but there are rules to the game. "The College Payoff," a new paper from the Georgetown University Center on Education and the Workforce, uses in-depth data analysis to identify, illuminate and elucidate those rules. This executive summary provides a glimpse of the education and…

  20. Malawi : Country Procurement Assessment Report, Volume 3. Executive Summary

    OpenAIRE

    World Bank

    2004-01-01

    The Malawi Country Procurement Assessment Report is a joint undertaking between the Malawi Government and the World Bank to analyze the country procurement system and recommend appropriate actions to improve the efficiency, economy and transparency of the system. This report is divided into (a) an Executive Summary, (b) Main Report on Findings and Recommendations, and (c) Annexes. Since th...

  1. FWP executive summaries: Basic energy sciences materials sciences programs

    Energy Technology Data Exchange (ETDEWEB)

    Samara, G.A.

    1996-02-01

    This report provides an Executive Summary of the various elements of the Materials Sciences Program which is funded by the Division of Materials Sciences, Office of Basic Energy Sciences, U.S. Department of Energy at Sandia National Laboratories, New Mexico.

  2. Executive Summary: Forests of the Northern United States

    Science.gov (United States)

    Stephen R. Shifley; Francisco X. Aguilar; Nianfu Song; Susan I. Stewart; David J. Nowak; Dale D. Gormanson; W. Keith Moser; Sherri Wormstead; Eric J. Greenfield

    2012-01-01

    This executive summary provides an overview of the 200-page report, Forests of the Northern United States, which covers in detail current forest conditions, recent trends, issues, threats and opportunities in the forests in the 20 Northern States. It provides a context for subsequent Northern Forest Futures Project analyses that will forecast alternative future...

  3. 2014 AFCI Glovebox Event Executive Summary

    International Nuclear Information System (INIS)

    Campbell, Joseph Lenard

    2016-01-01

    One of the primary INL missions is to support development of advanced fuels with the goal of creating reactor fuels that produce less waste and are easier to store. The Advanced Fuel Cycle Initiative (AFCI) Glovebox in the Fuel Manufacturing Facility (FMF) is used for several fuel fabrication steps that involve transuranic elements, including americium. The AFCI glove box contains equipment used for fuel fabrication, including an arc melter - a small, laboratory-scale version of an electric arc furnace used to make new metal alloys for research - and an americium distillation apparatus. This overview summarizes key findings related to the investigation into the releases of airborne radioactivity that occurred in the AFCI glovebox room in late August and early September 2014. The full report (AFCI Glovebox Radiological Release - Evaluation, Corrective Actions and Testing, INL/INL-15-36996) provides details of the identified issues, corrective actions taken as well as lessons learned

  4. INEL waste reduction: summary paper

    International Nuclear Information System (INIS)

    Rhoades, W.A.

    1987-01-01

    The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE) facility located in southeastern Idaho. Located at the INEL are a Waste Experimental Reduction Facility (WERF) which processes low level radioactive waste (LLW) materials and a Radioactive Waste Management Complex (RWMC) which provides for disposal of radioactive waste materials. There are currently 9 active facilities (waste generators) at the INEL which produce an average total volume of about 5000 cubic meters of solid LLW annually. This boxed or bulk waste is ultimately disposed of at the RWMC Subsurface Disposal Area (SDA). The SDA is currently the only active LLW disposal site at the INEL, and the prospects for opening another shallow land burial disposal facility are uncertain. Therefore, it has become imperative that EG and G Idaho Waste Management Department make every reasonable effort to extend the disposal life of the SDA. Among Waste Management Department's principal efforts to extend the SDA disposal life are operation of the Waste Experimental Reduction Facility (WERF) and administration of the INEL Waste Reduction Program. The INEL Waste Reduction Program is charged with providing assistance to all INEL facilities in reducing LLW generation rates to the lowest practical levels while at the same time encouraging optimum utilization of the volume reduction capabilities of WERF. Both waste volume and waste generation reductions are discussed

  5. International Consensus Statement on Allergy and Rhinology: Rhinosinusitis Executive Summary.

    Science.gov (United States)

    Orlandi, Richard R; Kingdom, Todd T; Hwang, Peter H

    2016-02-01

    The body of knowledge regarding rhinosinusitis (RS) continues to expand, with rapid growth in number of publications yet substantial variability in the quality of those presentations. In an effort to both consolidate and critically appraise this information, rhinologic experts from around the world have produced the International Consensus Statement on Allergy and Rhinology: Rhinosinusitis (ICAR:RS). This executive summary consolidates the findings of the ICAR:RS document. ICAR:RS presents over 140 topics in the forms of evidence-based reviews with recommendations (EBRRs) and evidence-based reviews (EBR). The structured recommendations of the EBRR sections are summarized in this executive summary. This summary compiles the EBRRs regarding medical and surgical management of acute RS (ARS) and chronic RS with and without nasal polyps (CRSwNP and CRSsNP). This ICAR:RS Executive Summary provides a compilation of the evidence-based recommendations for medical and surgical treatment of the most common forms of RS. © 2016 ARS-AAOA, LLC.

  6. Summary of Waste Calcination at INTEC

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, Barry Henry; Newby, Bill Joe

    2000-10-01

    Fluidized-bed calcination at the Idaho Nuclear Technologies and Engineering Center (INTEC, formally called the Idaho Chemical Processing Plant) has been used to solidify acidic metal nitrate fuel reprocessing and incidental wastes wastes since 1961. A summary of waste calcination in full-scale and pilot plant calciners has been compiled for future reference. It contains feed compositions and operating conditions for all the processing campaigns for the original Waste Calcining Facility (WCF), the New Waste Calcining Facility (NWCF) started up in 1982, and numerous small scale pilot plant tests for various feed types. This summary provides a historical record of calcination at INTEC, and will be useful for evaluating calcinability of future wastes.

  7. Annual Waste Minimization Summary Report

    International Nuclear Information System (INIS)

    Haworth, D.M.

    2011-01-01

    This report summarizes the waste minimization efforts undertaken by National Security TechnoIogies, LLC, for the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2010. The NNSA/NSO Pollution Prevention Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment.

  8. Technology Summary Advancing Tank Waste Retrieval And Processing

    International Nuclear Information System (INIS)

    Sams, T.L.; Mendoza, R.E.

    2010-01-01

    This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them. This technology overview provides a high-level summary of technologies being investigated, developed, and deployed by WRPS to advance Hanford Site tank waste retrieval and processing. Transformational technologies are needed to complete Hanford tank waste retrieval and treatment by 12/31/2047. Hanford's underground waste storage tanks hold approximately 57 million gallons of radiochemical waste from nuclear defense production - more tank waste than any other site in the United States. In addition, the waste is uniquely complicated because it contains constituents from at least six major radiochemical processes and several lesser processes. It is intermixed and complexed more than any other waste collection known to exist in the world. The multi-faceted nature of Hanford's tank waste means that legally binding agreements in the Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement) and between the Department of Energy (DOE) and its contractors may not be met using current vitrification schedules, plans, and methods. WRPS and the DOE are developing, testing, and deploying technologies to meet the necessary commitments and complete the DOE's River Protection Project (RPP) mission within environmentally acceptable requirements. Technology solutions are outlined, along with processes and priorities for selecting and developing them. DOE's Office of Environmental Management (EM) identifies the environmental management technology needs and the activities necessary to address them. The U.S. Congress then funds these activities through EM or the DOE field offices. Finally, an array of entities that include DOE site prime contractors and

  9. ILC Reference Design Report Volume 1 - Executive Summary

    CERN Document Server

    Brau, James; Walker, Nicholas; Aarons, Gerald; Abe, Toshinori; Abernathy, Jason; Ablikim, Medina; Abramowicz, Halina; Adey, David; Adloff, Catherine; Adolphsen, Chris; Afanaciev, Konstantin; Agapov, Ilya; Ahn, Jung-Keun; Aihara, Hiroaki; Akemoto, Mitsuo; del Carmen Alabau, Maria; Albert, Justin; Albrecht, Hartwig; Albrecht, Michael; Alesini, David; Alexander, Gideon; Alexander, Jim; Allison, Wade; Amann, John; Amirikas, Ramila; An, Qi; Anami, Shozo; Ananthanarayan, B.; Anderson, Terry; Andricek, Ladislav; Anduze, Marc; Anerella, Michael; Anfimov, Nikolai; Angal-Kalinin, Deepa; Antipov, Sergei; Antoine, Claire; Aoki, Mayumi; Aoza, Atsushi; Aplin, Steve; Appleby, Rob; Arai, Yasuo; Araki, Sakae; Arkan, Tug; Arnold, Ned; Arnold, Ray; Arnowitt, Richard; Artru, Xavier; Arya, Kunal; Aryshev, Alexander; Asakawa, Eri; Asiri, Fred; Asner, David; Atac, Muzaffer; Atoian, Grigor; Attié, David; Augustin, Jean-Eudes; Augustine, David B.; Ayres, Bradley; Aziz, Tariq; Baars, Derek; Badaud, Frederique; Baddams, Nigel; Bagger, Jonathan; Bai, Sha; Bailey, David; Bailey, Ian R.; Baker, David; Balalykin, Nikolai I.; Balbuena, Juan Pablo; Baldy, Jean-Luc; Ball, Markus; Ball, Maurice; Ballestrero, Alessandro; Ballin, Jamie; Baltay, Charles; Bambade, Philip; Ban, Syuichi; Band, Henry; Bane, Karl; Banerjee, Bakul; Barbanotti, Serena; Barbareschi, Daniele; Barbaro-Galtieri, Angela; Barber, Desmond P.; Barbi, Mauricio; Bardin, Dmitri Y.; Barish, Barry; Barklow, Timothy L.; Barlow, Roger; Barnes, Virgil E.; Barone, Maura; Bartels, Christoph; Bartsch, Valeria; Basu, Rahul; Battaglia, Marco; Batygin, Yuri; Baudot, Jerome; Baur, Ulrich; Elwyn Baynham, D.; Beard, Carl; Bebek, Chris; Bechtle, Philip; Becker, Ulrich J.; Bedeschi, Franco; Bedjidian, Marc; Behera, Prafulla; Behnke, Ties; Bellantoni, Leo; Bellerive, Alain; Bellomo, Paul; Bentson, Lynn D.; Benyamna, Mustapha; Bergauer, Thomas; Berger, Edmond; Bergholz, Matthias; Beri, Suman; Berndt, Martin; Bernreuther, Werner; Bertolini, Alessandro; Besancon, Marc; Besson, Auguste; Beteille, Andre; Bettoni, Simona; Beyer, Michael; Bhandari, R.K.; Bharadwaj, Vinod; Bhatnagar, Vipin; Bhattacharya, Satyaki; Bhattacharyya, Gautam; Bhattacherjee, Biplob; Bhuyan, Ruchika; Bi, Xiao-Jun; Biagini, Marica; Bialowons, Wilhelm; Biebel, Otmar; Bieler, Thomas; Bierwagen, John; Birch, Alison; Bisset, Mike; Biswal, S.S.; Blackmore, Victoria; Blair, Grahame; Blanchard, Guillaume; Blazey, Gerald; Blue, Andrew; Blümlein, Johannes; Boffo, Christian; Bohn, Courtlandt; Boiko, V.I.; Boisvert, Veronique; Bondarchuk, Eduard N.; Boni, Roberto; Bonvicini, Giovanni; Boogert, Stewart; Boonekamp, Maarten; Boorman, Gary; Borras, Kerstin; Bortoletto, Daniela; Bosco, Alessio; Bosio, Carlo; Bosland, Pierre; Bosotti, Angelo; Boudry, Vincent; Boumediene, Djamel-Eddine; Bouquet, Bernard; Bourov, Serguei; Bowden, Gordon; Bower, Gary; Boyarski, Adam; Bozovic-Jelisavcic, Ivanka; Bozzi, Concezio; Brachmann, Axel; Bradshaw, Tom W.; Brandt, Andrew; Brasser, Hans Peter; Brau, Benjamin; Breidenbach, Martin; Bricker, Steve; Brient, Jean-Claude; Brock, Ian; Brodsky, Stanley; Brooksby, Craig; Broome, Timothy A.; Brown, David; Brown, David; Brownell, James H.; Bruchon, Mélanie; Brueck, Heiner; Brummitt, Amanda J.; Brun, Nicole; Buchholz, Peter; Budagov, Yulian A.; Bulgheroni, Antonio; Bulyak, Eugene; Bungau, Adriana; Bürger, Jochen; Burke, Dan; Burkhart, Craig; Burrows, Philip; Burt, Graeme; Burton, David; Büsser, Karsten; Butler, John; Butterworth, Jonathan; Buzulutskov, Alexei; Cabruja, Enric; Caccia, Massimo; Cai, Yunhai; Calcaterra, Alessandro; Caliier, Stephane; Camporesi, Tiziano; Cao, Jun-Jie; Cao, J.S.; Capatina, Ofelia; Cappellini, Chiara; Carcagno, Ruben; Carena, Marcela; Carloganu, Cristina; Carosi, Roberto; Stephen Carr, F.; Carrion, Francisco; Carter, Harry F.; Carter, John; Carwardine, John; Cassel, Richard; Cassell, Ronald; Cavallari, Giorgio; Cavallo, Emanuela; Cembranos, Jose A.R.; Chakraborty, Dhiman; Chandez, Frederic; Charles, Matthew; Chase, Brian; Chattopadhyay, Subhasis; Chauveau, Jacques; Chefdeville, Maximilien; Chehab, Robert; Chel, Stéphane; Chelkov, Georgy; Chen, Chiping; Chen, He Sheng; Chen, Huai Bi; Chen, Jia Er; Chen, Sen Yu; Chen, Shaomin; Chen, Shenjian; Chen, Xun; Chen, Yuan Bo; Cheng, Jian; Chevallier, M.; Chi, Yun Long; Chickering, William; Cho, Gi-Chol; Cho, Moo-Hyun; Choi, Jin-Hyuk; Choi, Jong Bum; Choi, Seong Youl; Choi, Young-Il; Choudhary, Brajesh; Choudhury, Debajyoti; Rai Choudhury, S.; Christian, David; Christian, Glenn; Christophe, Grojean; Chung, Jin-Hyuk; Church, Mike; Ciborowski, Jacek; Cihangir, Selcuk; Ciovati, Gianluigi; Clarke, Christine; Clarke, Don G.; Clarke, James A.; Clements, Elizabeth; Coca, Cornelia; Coe, Paul; Cogan, John; Colas, Paul; Collard, Caroline; Colledani, Claude; Combaret, Christophe; Comerma, Albert; Compton, Chris; Constance, Ben; Conway, John; Cook, Ed; Cooke, Peter; Cooper, William; Corcoran, Sean; Cornat, Rémi; Corner, Laura; Cortina Gil, Eduardo; Clay Corvin, W.; Cotta Ramusino, Angelo; Cowan, Ray; Crawford, Curtis; Cremaldi, Lucien M; Crittenden, James A.; Cussans, David; Cvach, Jaroslav; da Silva, Wilfrid; Dabiri Khah, Hamid; Dabrowski, Anne; Dabrowski, Wladyslaw; Dadoun, Olivier; Dai, Jian Ping; Dainton, John; Daly, Colin; Damerell, Chris; Danilov, Mikhail; Daniluk, Witold; Daram, Sarojini; Datta, Anindya; Dauncey, Paul; David, Jacques; Davier, Michel; Davies, Ken P.; Dawson, Sally; De Boer, Wim; De Curtis, Stefania; De Groot, Nicolo; de la Taille, Christophe; de Lira, Antonio; De Roeck, Albert; de Sangro, Riccardo; De Santis,Stefano; Deacon, Laurence; Deandrea, Aldo; Dehmelt, Klaus; Delagnes, Eric; Delahaye, Jean-Pierre; Delebecque, Pierre; Delerue, Nicholas; Delferriere, Olivier; Demarteau, Marcel; Deng, Zhi; Denisov, Yu.N.; Densham, Christopher J.; Desch, Klaus; Deshpande, Nilendra; Devanz, Guillaume; Devetak, Erik; Dexter, Amos; Di benedetto, Vito; Diéguez, Angel; Diener, Ralf; Dinh, Nguyen Dinh; Dixit, Madhu; Dixit, Sudhir; Djouadi, Abdelhak; Dolezal, Zdenek; Dollan, Ralph; Dong, Dong; Dong, Hai Yi; Dorfan, Jonathan; Dorokhov, Andrei; Doucas, George; Downing, Robert; Doyle, Eric; Doziere, Guy; Drago, Alessandro; Dragt, Alex; Drake, Gary; Drásal, Zbynek; Dreiner, Herbert; Drell, Persis; Driouichi, Chafik; Drozhdin, Alexandr; Drugakov, Vladimir; Du, Shuxian; Dugan, Gerald; Duginov, Viktor; Dulinski, Wojciech; Dulucq, Frederic; Dutta, Sukanta; Dwivedi, Jishnu; Dychkant, Alexandre; Dzahini, Daniel; Eckerlin, Guenter; Edwards, Helen; Ehrenfeld, Wolfgang; Ehrlichman, Michael; Ehrlichmann, Heiko; Eigen, Gerald; Elagin, Andrey; Elementi, Luciano; Eliasson, Peder; Ellis, John; Ellwood, George; Elsen, Eckhard; Emery, Louis; Enami, Kazuhiro; Endo, Kuninori; Enomoto, Atsushi; Eozénou, Fabien; Erbacher, Robin; Erickson, Roger; Oleg Eyser, K.; Fadeyev, Vitaliy; Fang, Shou Xian; Fant, Karen; Fasso, Alberto; Faucci Giannelli, Michele; Fehlberg, John; Feld, Lutz; Feng, Jonathan L.; Ferguson, John; Fernandez-Garcia, Marcos; Luis Fernandez-Hernando, J.; Fiala, Pavel; Fieguth, Ted; Finch, Alexander; Finocchiaro, Giuseppe; Fischer, Peter; Fisher, Peter; Eugene Fisk, H.; Fitton, Mike D.; Fleck, Ivor; Fleischer, Manfred; Fleury, Julien; Flood, Kevin; Foley, Mike; Ford, Richard; Fortin, Dominique; Foster, Brian; Fourches, Nicolas; Francis, Kurt; Frey, Ariane; Frey, Raymond; Friedsam, Horst; Frisch, Josef; Frishman, Anatoli; Fuerst, Joel; Fujii, Keisuke; Fujimoto, Junpei; Fukuda, Masafumi; Fukuda, Shigeki; Funahashi, Yoshisato; Funk, Warren; Furletova, Julia; Furukawa, Kazuro; Furuta, Fumio; Fusayasu, Takahiro; Fuster, Juan; Gadow, Karsten; Gaede, Frank; Gaglione, Renaud; Gai, Wei; Gajewski, Jan; Galik, Richard; Galkin, Alexei; Galkin, Valery; Gallin-Martel, Laurent; Gannaway, Fred; Gao, Jian She; Gao, Jie; Gao, Yuanning; Garbincius, Peter; Garcia-Tabares, Luis; Garren, Lynn; Garrido, Luís; Garutti, Erika; Garvey, Terry; Garwin, Edward; Gascón, David; Gastal, Martin; Gatto, Corrado; Gatto, Raoul; Gay, Pascal; Ge, Lixin; Ge, Ming Qi; Ge, Rui; Geiser, Achim; Gellrich, Andreas; Genat, Jean-Francois; Geng, Zhe Qiao; Gentile, Simonetta; Gerbick, Scot; Gerig, Rod; Ghosh, Dilip Kumar; Ghosh, Kirtiman; Gibbons, Lawrence; Giganon, Arnaud; Gillespie, Allan; Gillman, Tony; Ginzburg, Ilya; Giomataris, Ioannis; Giunta, Michele; Gladkikh, Peter; Gluza, Janusz; Godbole, Rohini; Godfrey, Stephen; Goldhaber, Gerson; Goldstein, Joel; Gollin, George D.; Gonzalez-Sanchez, Francisco Javier; Goodrick, Maurice; Gornushkin, Yuri; Gostkin, Mikhail; Gottschalk, Erik; Goudket, Philippe; Gough Eschrich, Ivo; Gournaris, Filimon; Graciani, Ricardo; Graf, Norman; Grah, Christian; Grancagnolo, Francesco; Grandjean, Damien; Grannis, Paul; Grassellino, Anna; Graugés, Eugeni; Gray, Stephen; Green, Michael; Greenhalgh, Justin; Greenshaw, Timothy; Grefe, Christian; Gregor, Ingrid-Maria; Grenier, Gerald; Grimes, Mark; Grimm, Terry; Gris, Philippe; Grivaz, Jean-Francois; Groll, Marius; Gronberg, Jeffrey; Grondin, Denis; Groom, Donald; Gross, Eilam; Grunewald, Martin; Grupen, Claus; Grzelak, Grzegorz; Gu, Jun; Gu, Yun-Ting; Guchait, Monoranjan; Guiducci, Susanna; Guler, Ali Murat; Guler, Hayg; Gulmez, Erhan; Gunion, John; Guo, Zhi Yu; Gurtu, Atul; Ha, Huy Bang; Haas, Tobias; Haase, Andy; Haba, Naoyuki; Haber, Howard; Haensel, Stephan; Hagge, Lars; Hagura, Hiroyuki; Hajdu, Csaba; Haller, Gunther; Haller, Johannes; Hallermann, Lea; Halyo, Valerie; Hamaguchi, Koichi; Hammond, Larry; Han, Liang; Han, Tao; Hand, Louis; Handu, Virender K.; Hano, Hitoshi; Hansen, Christian; Hansen, Jørn Dines; Hansen, Jorgen Beck; Hara, Kazufumi; Harder, Kristian; Hartin, Anthony; Hartung, Walter; Hast, Carsten; Hauptman, John; Hauschild, Michael; Hauviller, Claude; Havranek, Miroslav; Hawkes, Chris; Hawkings, Richard; Hayano, Hitoshi; Hazumi, Masashi; He, An; He, Hong Jian; Hearty, Christopher; Heath, Helen; Hebbeker, Thomas; Hedberg, Vincent; Hedin, David; Heifets, Samuel; Heinemeyer, Sven; Heini, Sebastien; Helebrant, Christian; Helms, Richard; Heltsley, Brian; Henrot-Versille, Sophie; Henschel, Hans; Hensel, Carsten; Hermel, Richard; Herms, Atilà; Herten, Gregor; Hesselbach, Stefan; Heuer, Rolf-Dieter; Heusch, Clemens A.; Hewett, Joanne; Higashi, Norio; Higashi, Takatoshi; Higashi, Yasuo; Higo, Toshiyasu; Hildreth, Michael D.; Hiller, Karlheinz; Hillert, Sonja; Hillier, Stephen James; Himel, Thomas; Himmi, Abdelkader; Hinchliffe, Ian; Hioki, Zenro; Hirano, Koichiro; Hirose, Tachishige; Hisamatsu, Hiromi; Hisano, Junji; Hlaing, Chit Thu; Hock, Kai Meng; Hoeferkamp, Martin; Hohlfeld, Mark; Honda, Yousuke; Hong, Juho; Hong, Tae Min; Honma, Hiroyuki; Horii, Yasuyuki; Horvath, Dezso; Hosoyama, Kenji; Hostachy, Jean-Yves; Hou, Mi; Hou, Wei-Shu; Howell, David; Hronek, Maxine; Hsiung, Yee B.; Hu, Bo; Hu, Tao; Huang, Jung-Yun; Huang, Tong Ming; Huang, Wen Hui; Huedem, Emil; Huggard, Peter; Hugonie, Cyril; Hu-Guo, Christine; Huitu, Katri; Hwang, Youngseok; Idzik, Marek; Ignatenko, Alexandr; Ignatov, Fedor; Ikeda, Hirokazu; Ikematsu, Katsumasa; Ilicheva, Tatiana; Imbault, Didier; Imhof, Andreas; Incagli, Marco; Ingbir, Ronen; Inoue, Hitoshi; Inoue, Youichi; Introzzi, Gianluca; Ioakeimidi, Katerina; Ishihara, Satoshi; Ishikawa, Akimasa; Ishikawa, Tadashi; Issakov, Vladimir; Ito, Kazutoshi; Ivanov, V.V.; Ivanov, Valentin; Ivanyushenkov, Yury; Iwasaki, Masako; Iwashita, Yoshihisa; Jackson, David; Jackson, Frank; Jacobsen, Bob; Jaganathan, Ramaswamy; Jamison, Steven; Janssen, Matthias Enno; Jaramillo-Echeverria, Richard; Jaros, John; Jauffret, Clement; Jawale, Suresh B.; Jeans, Daniel; Jedziniak, Ron; Jeffery, Ben; Jehanno, Didier; Jenner, Leo J.; Jensen, Chris; Jensen, David R.; Jiang, Hairong; Jiang, Xiao Ming; Jimbo, Masato; Jin, Shan; Keith Jobe, R.; Johnson, Anthony; Johnson, Erik; Johnson, Matt; Johnston, Michael; Joireman, Paul; Jokic, Stevan; Jones, James; Jones, Roger M.; Jongewaard, Erik; Jönsson, Leif; Joshi, Gopal; Joshi, Satish C.; Jung, Jin-Young; Junk, Thomas; Juste, Aurelio; Kado, Marumi; Kadyk, John; Käfer, Daniela; Kako, Eiji; Kalavase, Puneeth; Kalinin, Alexander; Kalinowski, Jan; Kamitani, Takuya; Kamiya, Yoshio; Kamiya, Yukihide; Kamoshita, Jun-ichi; Kananov, Sergey; Kanaya, Kazuyuki; Kanazawa, Ken-ichi; Kanemura, Shinya; Kang, Heung-Sik; Kang, Wen; Kanjial, D.; Kapusta, Frédéric; Karataev, Pavel; Karchin, Paul E.; Karlen, Dean; Karyotakis, Yannis; Kashikhin, Vladimir; Kashiwagi, Shigeru; Kasley, Paul; Katagiri, Hiroaki; Kato, Takashi; Kato, Yukihiro; Katzy, Judith; Kaukher, Alexander; Kaur, Manjit; Kawagoe, Kiyotomo; Kawamura, Hiroyuki; Kazakov, Sergei; Kekelidze, V.D.; Keller, Lewis; Kelley, Michael; Kelly, Marc; Kelly, Michael; Kennedy, Kurt; Kephart, Robert; Keung, Justin; Khainovski, Oleg; Khan, Sameen Ahmed; Khare, Prashant; Khovansky, Nikolai; Kiesling, Christian; Kikuchi, Mitsuo; Kilian, Wolfgang; Killenberg, Martin; Kim, Donghee; Kim, Eun San; Kim, Eun-Joo; Kim, Guinyun; Kim, Hongjoo; Kim, Hyoungsuk; Kim, Hyun-Chui; Kim, Jonghoon; Kim, Kwang-Je; Kim, Kyung Sook; Kim, Peter; Kim, Seunghwan; Kim, Shin-Hong; Kim, Sun Kee; Kim, Tae Jeong; Kim, Youngim; Kim, Young-Kee; Kimmitt, Maurice; Kirby, Robert; Kircher, François; Kisielewska, Danuta; Kittel, Olaf; Klanner, Robert; Klebaner, Arkadiy L.; Kleinwort, Claus; Klimkovich, Tatsiana; Klinkby, Esben; Kluth, Stefan; Knecht, Marc; Kneisel, Peter; Ko, In Soo; Ko, Kwok; Kobayashi, Makoto; Kobayashi, Nobuko; Kobel, Michael; Koch, Manuel; Kodys, Peter; Koetz, Uli; Kohrs, Robert; Kojima, Yuuji; Kolanoski, Hermann; Kolodziej, Karol; Kolomensky, Yury G.; Komamiya, Sachio; Kong, Xiang Cheng; Konigsberg, Jacobo; Korbel, Volker; Koscielniak, Shane; Kostromin, Sergey; Kowalewski, Robert; Kraml, Sabine; Krammer, Manfred; Krasnykh, Anatoly; Krautscheid, Thorsten; Krawczyk, Maria; James Krebs, H.; Krempetz, Kurt; Kribs, Graham; Krishnagopal, Srinivas; Kriske, Richard; Kronfeld, Andreas; Kroseberg, Jürgen; Kruchonak, Uladzimir; Kruecker, Dirk; Krüger, Hans; Krumpa, Nicholas A.; Krumshtein, Zinovii; Kuang, Yu Ping; Kubo, Kiyoshi; Kuchler, Vic; Kudoh, Noboru; Kulis, Szymon; Kumada, Masayuki; Kumar, Abhay; Kume, Tatsuya; Kundu, Anirban; Kurevlev, German; Kurihara, Yoshimasa; Kuriki, Masao; Kuroda, Shigeru; Kuroiwa, Hirotoshi; Kurokawa, Shin-ichi; Kusano, Tomonori; Kush, Pradeep K.; Kutschke, Robert; Kuznetsova, Ekaterina; Kvasnicka, Peter; Kwon, Youngjoon; Labarga, Luis; Lacasta, Carlos; Lackey, Sharon; Lackowski, Thomas W.; Lafaye, Remi; Lafferty, George; Lagorio, Eric; Laktineh, Imad; Lal, Shankar; Laloum, Maurice; Lam, Briant; Lancaster, Mark; Lander, Richard; Lange, Wolfgang; Langenfeld, Ulrich; Langeveld, Willem; Larbalestier, David; Larsen, Ray; Lastovicka, Tomas; Lastovicka-Medin, Gordana; Latina, Andrea; Latour, Emmanuel; Laurent, Lisa; Le, Ba Nam; Le, Duc Ninh; Le Diberder, Francois; Dû, Patrick Le; Lebbolo, Hervé; Lebrun, Paul; Lecoq, Jacques; Lee, Sung-Won; Lehner, Frank; Leibfritz, Jerry; Lenkszus, Frank; Lesiak, Tadeusz; Levy, Aharon; Lewandowski, Jim; Leyh, Greg; Li, Cheng; Li, Chong Sheng; Li, Chun Hua; Li, Da Zhang; Li, Gang; Li, Jin; Li, Shao Peng; Li, Wei Ming; Li, Weiguo; Li, Xiao Ping; Li, Xue-Qian; Li, Yuanjing; Li, Yulan; Li, Zenghai; Li, Zhong Quan; Liang, Jian Tao; Liao, Yi; Lilje, Lutz; Guilherme Lima, J.; Lintern, Andrew J.; Lipton, Ronald; List, Benno; List, Jenny; Liu, Chun; Liu, Jian Fei; Liu, Ke Xin; Liu, Li Qiang; Liu, Shao Zhen; Liu, Sheng Guang; Liu, Shubin; Liu, Wanming; Liu, Wei Bin; Liu, Ya Ping; Liu, Yu Dong; Lockyer, Nigel; Logan, Heather E.; Logatchev, Pavel V.; Lohmann, Wolfgang; Lohse, Thomas; Lola, Smaragda; Lopez-Virto, Amparo; Loveridge, Peter; Lozano, Manuel; Lu, Cai-Dian; Lu, Changguo; Lu, Gong-Lu; Lu, Wen Hui; Lubatti, Henry; Lucotte, Arnaud; Lundberg, Björn; Lundin, Tracy; Luo, Mingxing; Luong, Michel; Luth, Vera; Lutz, Benjamin; Lutz, Pierre; Lux, Thorsten; Luzniak, Pawel; Lyapin, Alexey; Lykken, Joseph; Lynch, Clare; Ma, Li; Ma, Lili; Ma, Qiang; Ma, Wen-Gan; Macfarlane, David; Maciel, Arthur; MacLeod, Allan; MacNair, David; Mader, Wolfgang; Magill, Stephen; Magnan, Anne-Marie; Maiheu, Bino; Maity, Manas; Majchrzak, Millicent; Majumder, Gobinda; Makarov, Roman; Makowski, Dariusz; Malaescu, Bogdan; Mallik, C.; Mallik, Usha; Malton, Stephen; Malyshev, Oleg B.; Malysheva, Larisa I.; Mammosser, John; Mamta; Mamuzic, Judita; Manen, Samuel; Manghisoni, Massimo; Manly, Steven; Marcellini, Fabio; Marcisovsky, Michal; Markiewicz, Thomas W.; Marks, Steve; Marone, Andrew; Marti, Felix; Martin, Jean-Pierre; Martin, Victoria; Martin-Chassard, Gisèle; Martinez, Manel; Martinez-Rivero, Celso; Martsch, Dennis; Martyn, Hans-Ulrich; Maruyama, Takashi; Masuzawa, Mika; Mathez, Hervé; Matsuda, Takeshi; Matsumoto, Hiroshi; Matsumoto, Shuji; Matsumoto, Toshihiro; Matsunaga, Hiroyuki; Mättig, Peter; Mattison, Thomas; Mavromanolakis, Georgios; Mawatari, Kentarou; Mazzacane, Anna; McBride, Patricia; McCormick, Douglas; McCormick, Jeremy; McDonald, Kirk T.; McGee, Mike; McIntosh, Peter; McKee, Bobby; McPherson, Robert A.; Meidlinger, Mandi; Meier, Karlheinz; Mele, Barbara; Meller, Bob; Melzer-Pellmann, Isabell-Alissandra; Mendez, Hector; Mercer, Adam; Merkin, Mikhail; Meshkov, I.N.; Messner, Robert; Metcalfe, Jessica; Meyer, Chris; Meyer, Hendrik; Meyer, Joachim; Meyer, Niels; Meyners, Norbert; Michelato, Paolo; Michizono, Shinichiro; Mihalcea, Daniel; Mihara, Satoshi; Mihara, Takanori; Mikami, Yoshinari; Mikhailichenko, Alexander A.; Milardi, Catia; Miller, David J.; Miller, Owen; Miller, Roger J.; Milstene, Caroline; Mimashi, Toshihiro; Minashvili, Irakli; Miquel, Ramon; Mishra, Shekhar; Mitaroff, Winfried; Mitchell, Chad; Miura, Takako; Miyamoto, Akiya; Miyata, Hitoshi; Mjörnmark, Ulf; Mnich, Joachim; Moenig, Klaus; Moffeit, Kenneth; Mokhov, Nikolai; Molloy, Stephen; Monaco, Laura; Monasterio, Paul R.; Montanari, Alessandro; Moon, Sung Ik; Moortgat-Pick, Gudrid A.; Mora de Freitas, Paulo; Morel, Federic; Moretti, Stefano; Morgunov, Vasily; Mori, Toshinori; Morin, Laurent; Morisseau, François; Morita, Yoshiyuki; Morita, Youhei; Morita, Yuichi; Morozov, Nikolai; Morozumi, Yuichi; Morse, William; Moser, Hans-Guenther; Moultaka, Gilbert; Mtingwa, Sekazi; Mudrinic, Mihajlo; Mueller, Alex; Mueller, Wolfgang; Muennich, Astrid; Muhlleitner, Milada Margarete; Mukherjee, Bhaskar; Mukhopadhyaya, Biswarup; Müller, Thomas; Munro, Morrison; Murayama, Hitoshi; Muto, Toshiya; Myneni, Ganapati Rao; Nabhiraj, P.Y.; Nagaitsev, Sergei; Nagamine, Tadashi; Nagano, Ai; Naito, Takashi; Nakai, Hirotaka; Nakajima, Hiromitsu; Nakamura, Isamu; Nakamura, Tomoya; Nakanishi, Tsutomu; Nakao, Katsumi; Nakao, Noriaki; Nakayoshi, Kazuo; Nam, Sang; Namito, Yoshihito; Namkung, Won; Nantista, Chris; Napoly, Olivier; Narain, Meenakshi; Naroska, Beate; Nauenberg, Uriel; Nayyar, Ruchika; Neal, Homer; Nelson, Charles; Nelson, Janice; Nelson, Timothy; Nemecek, Stanislav; Neubauer, Michael; Neuffer, David; Newman, Myriam Q.; Nezhevenko, Oleg; Ng, Cho-Kuen; Nguyen, Anh Ky; Nguyen, Minh; Van Nguyen Thi,Hong; Niebuhr, Carsten; Niehoff, Jim; Niezurawski, Piotr; Nishitani, Tomohiro; Nitoh, Osamu; Noguchi, Shuichi; Nomerotski, Andrei; Noonan, John; Norbeck, Edward; Nosochkov, Yuri; Notz, Dieter; Nowak, Grazyna; Nowak, Hannelies; Noy, Matthew; Nozaki, Mitsuaki; Nyffeler, Andreas; Nygren, David; Oddone, Piermaria; O'Dell, Joseph; Oh, Jong-Seok; Oh, Sun Kun; Ohkuma, Kazumasa; Ohlerich, Martin; Ohmi, Kazuhito; Ohnishi, Yukiyoshi; Ohsawa, Satoshi; Ohuchi, Norihito; Oide, Katsunobu; Okada, Nobuchika; Okamura, Takahiro; Okugi, Toshiyuki; Okumi, Shoji; Okumura, Ken-ichi; Olchevski, Alexander; Oliver, William; Olivier, Bob; Olsen, James; Olsen, Jeff; Olsen, Stephen; Olshevsky, A.G.; Olsson, Jan; Omori, Tsunehiko; Onel, Yasar; Onengut, Gulsen; Ono, Hiroaki; Onoprienko, Dmitry; Oreglia, Mark; Oren, Will; Orimoto, Toyoko J.; Oriunno, Marco; Orlandea, Marius Ciprian; Oroku, Masahiro; Orr, Lynne H.; Orr, Robert S.; Oshea, Val; Oskarsson, Anders; Osland, Per; Ossetski, Dmitri; Österman, Lennart; Ostiguy, Francois; Otono, Hidetoshi; Ottewell, Brian; Ouyang, Qun; Padamsee, Hasan; Padilla, Cristobal; Pagani, Carlo; Palmer, Mark A.; Pam, Wei Min; Pande, Manjiri; Pande, Rajni; Pandit, V.S.; Pandita, P.N.; Pandurovic, Mila; Pankov, Alexander; Panzeri, Nicola; Papandreou, Zisis; Paparella, Rocco; Para, Adam; Park, Hwanbae; Parker, Brett; Parkes, Chris; Parma, Vittorio; Parsa, Zohreh; Parsons, Justin; Partridge, Richard; Pasquinelli, Ralph; Pásztor, Gabriella; Paterson, Ewan; Patrick, Jim; Patteri, Piero; Ritchie Patterson, J.; Pauletta, Giovanni; Paver, Nello; Pavlicek, Vince; Pawlik, Bogdan; Payet, Jacques; Pchalek, Norbert; Pedersen, John; Pei, Guo Xi; Pei, Shi Lun; Pelka, Jerzy; Pellegrini, Giulio; Pellett, David; Peng, G.X.; Penn, Gregory; Penzo, Aldo; Perry, Colin; Peskin, Michael; Peters, Franz; Petersen, Troels Christian; Peterson, Daniel; Peterson, Thomas; Petterson, Maureen; Pfeffer, Howard; Pfund, Phil; Phelps, Alan; Van Phi, Quang; Phillips, Jonathan; Phinney, Nan; Piccolo, Marcello; Piemontese, Livio; Pierini, Paolo; Thomas Piggott, W.; Pike, Gary; Pillet, Nicolas; Jayawardena, Talini Pinto; Piot, Phillippe; Pitts, Kevin; Pivi, Mauro; Plate, Dave; Pleier, Marc-Andre; Poblaguev, Andrei; Poehler, Michael; Poelker, Matthew; Poffenberger, Paul; Pogorelsky, Igor; Poirier, Freddy; Poling, Ronald; Poole, Mike; Popescu, Sorina; Popielarski, John; Pöschl, Roman; Postranecky, Martin; Potukochi, Prakash N.; Prast, Julie; Prat, Serge; Preger, Miro; Prepost, Richard; Price, Michael; Proch, Dieter; Puntambekar, Avinash; Qin, Qing; Qu, Hua Min; Quadt, Arnulf; Quesnel, Jean-Pierre; Radeka, Veljko; Rahmat, Rahmat; Rai, Santosh Kumar; Raimondi, Pantaleo; Ramberg, Erik; Ranjan, Kirti; Rao, Sista V.L.S.; Raspereza, Alexei; Ratti, Alessandro; Ratti, Lodovico; Raubenheimer, Tor; Raux, Ludovic; Ravindran, V.; Raychaudhuri, Sreerup; Re, Valerio; Rease, Bill; Reece, Charles E.; Regler, Meinhard; Rehlich, Kay; Reichel, Ina; Reichold, Armin; Reid, John; Reid, Ron; Reidy, James; Reinhard, Marcel; Renz, Uwe; Repond, Jose; Resta-Lopez, Javier; Reuen, Lars; Ribnik, Jacob; Rice, Tyler; Richard, François; Riemann, Sabine; Riemann, Tord; Riles, Keith; Riley, Daniel; Rimbault, Cécile; Rindani, Saurabh; Rinolfi, Louis; Risigo, Fabio; Riu, Imma; Rizhikov, Dmitri; Rizzo, Thomas; Rochford, James H.; Rodriguez, Ponciano; Roeben, Martin; Rolandi, Gigi; Roodman, Aaron; Rosenberg, Eli; Roser, Robert; Ross, Marc; Rossel, François; Rossmanith, Robert; Roth, Stefan; Rougé, André; Rowe, Allan; Roy, Amit; Roy, Sendhunil B.; Roy, Sourov; Royer, Laurent; Royole-Degieux, Perrine; Royon, Christophe; Ruan, Manqi; Rubin, David; Ruehl, Ingo; Jimeno, Alberto Ruiz; Ruland, Robert; Rusnak, Brian; Ryu, Sun-Young; Sabbi, Gian Luca; Sadeh, Iftach; Sadygov, Ziraddin Y; Saeki, Takayuki; Sagan, David; Sahni, Vinod C.; Saini, Arun; Saito, Kenji; Saito, Kiwamu; Sajot, Gerard; Sakanaka, Shogo; Sakaue, Kazuyuki; Salata, Zen; Salih, Sabah; Salvatore, Fabrizio; Samson, Joergen; Sanami, Toshiya; Levi Sanchez, Allister; Sands, William; Santic, John; Sanuki, Tomoyuki; Sapronov, Andrey; Sarkar, Utpal; Sasao, Noboru; Satoh, Kotaro; Sauli, Fabio; Saunders, Claude; Saveliev, Valeri; Savoy-Navarro, Aurore; Sawyer, Lee; Saxton, Laura; Schäfer, Oliver; Schälicke, Andreas; Schade, Peter; Schaetzel, Sebastien; Scheitrum, Glenn; Schibler, Emilie; Schindler, Rafe; Schlösser, Markus; Schlueter, Ross D.; Schmid, Peter; Schmidt, Ringo Sebastian; Schneekloth, Uwe; Schreiber, Heinz Juergen; Schreiber, Siegfried; Schroeder, Henning; Peter Schüler, K.; Schulte, Daniel; Schultz-Coulon, Hans-Christian; Schumacher, Markus; Schumann, Steffen; Schumm, Bruce A.; Schwienhorst, Reinhard; Schwierz, Rainer; Scott, Duncan J.; Scuri, Fabrizio; Sefkow, Felix; Sefri, Rachid; Seguin-Moreau, Nathalie; Seidel, Sally; Seidman, David; Sekmen, Sezen; Seletskiy, Sergei; Senaha, Eibun; Senanayake, Rohan; Sendai, Hiroshi; Sertore, Daniele; Seryi, Andrei; Settles, Ronald; Sever, Ramazan; Shales, Nicholas; Shao, Ming; Shelkov, G.A.; Shepard, Ken; Shepherd-Themistocleous, Claire; Sheppard, John C.; Shi, Cai Tu; Shidara, Tetsuo; Shim, Yeo-Jeong; Shimizu, Hirotaka; Shimizu, Yasuhiro; Shimizu, Yuuki; Shimogawa, Tetsushi; Shin, Seunghwan; Shioden, Masaomi; Shipsey, Ian; Shirkov, Grigori; Shishido, Toshio; Shivpuri, Ram K.; Shrivastava, Purushottam; Shulga, Sergey; Shumeiko, Nikolai; Shuvalov, Sergey; Si, Zongguo; Siddiqui, Azher Majid; Siegrist, James; Simon, Claire; Simrock, Stefan; Sinev, Nikolai; Singh, Bhartendu K.; Singh, Jasbir; Singh, Pitamber; Singh, R.K.; Singh, S.K.; Singini, Monito; Sinha, Anil K.; Sinha, Nita; Sinha, Rahul; Sinram, Klaus; Sissakian, A.N.; Skachkov, N.B.; Skrinsky, Alexander; Slater, Mark; Slominski, Wojciech; Smiljanic, Ivan; Smith, A J Stewart; Smith, Alex; Smith, Brian J.; Smith, Jeff; Smith, Jonathan; Smith, Steve; Smith, Susan; Smith, Tonee; Neville Snodgrass, W.; Sobloher, Blanka; Sohn, Young-Uk; Solidum, Ruelson; Solyak, Nikolai; Son, Dongchul; Sonmez, Nasuf; Sopczak, Andre; Soskov, V.; Spencer, Cherrill M.; Spentzouris, Panagiotis; Speziali, Valeria; Spira, Michael; Sprehn, Daryl; Sridhar, K.; Srivastava, Asutosh; St. Lorant, Steve; Stahl, Achim; Stanek, Richard P.; Stanitzki, Marcel; Stanley, Jacob; Stefanov, Konstantin; Stein, Werner; Steiner, Herbert; Stenlund, Evert; Stern, Amir; Sternberg, Matt; Stockinger, Dominik; Stockton, Mark; Stoeck, Holger; Strachan, John; Strakhovenko, V.; Strauss, Michael; Striganov, Sergei I.; Strologas, John; Strom, David; Strube, Jan; Stupakov, Gennady; Su, Dong; Sudo, Yuji; Suehara, Taikan; Suehiro, Toru; Suetsugu, Yusuke; Sugahara, Ryuhei; Sugimoto, Yasuhiro; Sugiyama, Akira; Suh, Jun Suhk; Sukovic, Goran; Sun, Hong; Sun, Stephen; Sun, Werner; Sun, Yi; Sun, Yipeng; Suszycki, Leszek; Sutcliffe, Peter; Suthar, Rameshwar L.; Suwada, Tsuyoshi; Suzuki, Atsuto; Suzuki, Chihiro; Suzuki, Shiro; Suzuki, Takashi; Swent, Richard; Swientek, Krzysztof; Swinson, Christina; Syresin, Evgeny; Szleper, Michal; Tadday, Alexander; Takahashi, Rika; Takahashi, Tohru; Takano, Mikio; Takasaki, Fumihiko; Takeda, Seishi; Takenaka, Tateru; Takeshita, Tohru; Takubo, Yosuke; Tanaka, Masami; Tang, Chuan Xiang; Taniguchi, Takashi; Tantawi, Sami; Tapprogge, Stefan; Tartaglia, Michael A.; Tassielli, Giovanni Francesco; Tauchi, Toshiaki; Tavian, Laurent; Tawara, Hiroko; Taylor, Geoffrey; Telnov, Alexandre V.; Telnov, Valery; Tenenbaum, Peter; Teodorescu, Eliza; Terashima, Akio; Terracciano, Giuseppina; Terunuma, Nobuhiro; Teubner, Thomas; Teuscher, Richard; Theilacker, Jay; Thomson, Mark; Tice, Jeff; Tigner, Maury; Timmermans, Jan; Titov, Maxim; Toge, Nobukazu; Tokareva, N.A.; Tollefson, Kirsten; Tomasek, Lukas; Tomovic, Savo; Tompkins, John; Tonutti, Manfred; Topkar, Anita; Toprek, Dragan; Toral, Fernando; Torrence, Eric; Traversi, Gianluca; Trimpl, Marcel; Mani Tripathi, S.; Trischuk, William; Trodden, Mark; Trubnikov, G.V.; Tschirhart, Robert; Tskhadadze, Edisher; Tsuchiya, Kiyosumi; Tsukamoto, Toshifumi; Tsunemi, Akira; Tucker, Robin; Turchetta, Renato; Tyndel, Mike; Uekusa, Nobuhiro; Ueno, Kenji; Umemori, Kensei; Ummenhofer, Martin; Underwood, David; Uozumi, Satoru; Urakawa, Junji; Urban, Jeremy; Uriot, Didier; Urner, David; Ushakov, Andrei; Usher, Tracy; Uzunyan, Sergey; Vachon, Brigitte; Valerio, Linda; Valin, Isabelle; Valishev, Alex; Vamra, Raghava; Van der Graaf, Harry; Van Kooten, Rick; Van Zandbergen, Gary; Vanel, Jean-Charles; Variola, Alessandro; Varner, Gary; Velasco, Mayda; Velte, Ulrich; Velthuis, Jaap; Vempati, Sundir K.; Venturini, Marco; Vescovi, Christophe; Videau, Henri; Vila, Ivan; Vincent, Pascal; Virey, Jean-Marc; Visentin, Bernard; Viti, Michele; Vo, Thanh Cuong; Vogel, Adrian; Vogt, Harald; von Toerne, Eckhard; Vorozhtsov, S.B.; Vos, Marcel; Votava, Margaret; Vrba, Vaclav; Wackeroth, Doreen; Wagner, Albrecht; Wagner, Carlos E.M.; Wagner, Stephen; Wake, Masayoshi; Walczak, Roman; Walkowiak, Wolfgang; Wallon, Samuel; Walsh, Roberval; Walston, Sean; Waltenberger, Wolfgang; Walz, Dieter; Wang, Chao En; Wang, Chun Hong; Wang, Dou; Wang, Faya; Wang, Guang Wei; Wang, Haitao; Wang, Jiang; Wang, Jiu Qing; Wang, Juwen; Wang, Lanfa; Wang, Lei; Wang, Min-Zu; Wang, Qing; Wang, Shu Hong; Wang, Xiaolian; Wang, Xue-Lei; Wang, Yi Fang; Wang, Zheng; Wanzenberg, Rainer; Ward, Bennie; Ward, David; Warmbein, Barbara; Warner, David W.; Warren, Matthew; Washio, Masakazu; Watanabe, Isamu; Watanabe, Ken; Watanabe, Takashi; Watanabe, Yuichi; Watson, Nigel; Wattimena, Nanda; Wayne, Mitchell; Weber, Marc; Weerts, Harry; Weiglein, Georg; Weiland, Thomas; Weinzierl, Stefan; Weise, Hans; Weisend, John; Wendt, Manfred; Wendt, Oliver; Wenzel, Hans; Wenzel, William A.; Wermes, Norbert; Werthenbach, Ulrich; Wesseln, Steve; Wester, William; White, Andy; White, Glen R.; Wichmann, Katarzyna; Wienemann, Peter; Wierba, Wojciech; Wilksen, Tim; Willis, William; Wilson, Graham W.; Wilson, John A.; Wilson, Robert; Wing, Matthew; Winter, Marc; Wirth, Brian D.; Wolbers, Stephen A.; Wolff, Dan; Wolski, Andrzej; Woodley, Mark D.; Woods, Michael; Woodward, Michael L.; Woolliscroft, Timothy; Worm, Steven; Wormser, Guy; Wright, Dennis; Wright, Douglas; Wu, Andy; Wu, Tao; Wu, Yue Liang; Xella, Stefania; Xia, Guoxing; Xia, Lei; Xiao, Aimin; Xiao, Liling; Xie, Jia Lin; Xing, Zhi-Zhong; Xiong, Lian You; Xu, Gang; Xu, Qing Jing; Yajnik, Urjit A.; Yakimenko, Vitaly; Yamada, Ryuji; Yamaguchi, Hiroshi; Yamamoto, Akira; Yamamoto, Hitoshi; Yamamoto, Masahiro; Yamamoto, Naoto; Yamamoto, Richard; Yamamoto, Yasuchika; Yamanaka, Takashi; Yamaoka, Hiroshi; Yamashita, Satoru; Yamazaki, Hideki; Yan, Wenbiao; Yang, Hai-Jun; Yang, Jin Min; Yang, Jongmann; Yang, Zhenwei; Yano, Yoshiharu; Yazgan, Efe; Yeh, G.P.; Yilmaz, Hakan; Yock, Philip; Yoda, Hakutaro; Yoh, John; Yokoya, Kaoru; Yokoyama, Hirokazu; York, Richard C.; Yoshida, Mitsuhiro; Yoshida, Takuo; Yoshioka, Tamaki; Young, Andrew; Yu, Cheng Hui; Yu, Jaehoon; Yu, Xian Ming; Yuan, Changzheng; Yue, Chong-Xing; Yue, Jun Hui; Zacek, Josef; Zagorodnov, Igor; Zalesak, Jaroslav; Zalikhanov, Boris; Zarnecki, Aleksander Filip; Zawiejski, Leszek; Zeitnitz, Christian; Zeller, Michael; Zerwas, Dirk; Zerwas, Peter; Zeyrek, Mehmet; Zhai, Ji Yuan; Zhang, Bao Cheng; Zhang, Bin; Zhang, Chuang; Zhang, He; Zhang, Jiawen; Zhang, Jing; Zhang, Jing Ru; Zhang, Jinlong; Zhang, Liang; Zhang, X.; Zhang, Yuan; Zhang, Zhige; Zhang, Zhiqing; Zhang, Ziping; Zhao, Haiwen; Zhao, Ji Jiu; Zhao, Jing Xia; Zhao, Ming Hua; Zhao, Sheng Chu; Zhao, Tianchi; Zhao, Tong Xian; Zhao, Zhen Tang; Zhao, Zhengguo; Zhou, De Min; Zhou, Feng; Zhou, Shun; Zhu, Shou Hua; Zhu, Xiong Wei; Zhukov, Valery; Zimmermann, Frank; Ziolkowski, Michael; Zisman, Michael S.; Zomer, Fabian; Zong, Zhang Guo; Zorba, Osman; Zutshi, Vishnu

    2007-01-01

    The International Linear Collider (ILC) is a 200-500 GeV center-of-mass high-luminosity linear electron-positron collider, based on 1.3 GHz superconducting radio-frequency (SCRF) accelerating cavities. The ILC has a total footprint of about 31 km and is designed for a peak luminosity of 2x10^34 cm^-2s^-1. This report is the Executive Summary (Volume I) of the four volume Reference Design Report. It gives an overview of the physics at the ILC, the accelerator design and value estimate, the detector concepts, and the next steps towards project realization.

  10. Executive Summary High-Yield Scenario Workshop Series Report

    Energy Technology Data Exchange (ETDEWEB)

    Leslie Park Ovard; Thomas H. Ulrich; David J. Muth Jr.; J. Richard Hess; Steven Thomas; Bryce Stokes

    2009-12-01

    To get a collective sense of the impact of research and development (R&D) on biomass resource availability, and to determine the feasibility that yields higher than baseline assumptions used for past assessments could be achieved to support U.S. energy independence, an alternate “High-Yield Scenario” (HYS) concept was presented to industry experts at a series of workshops held in December 2009. The workshops explored future production of corn/agricultural crop residues, herbaceous energy crops (HECs), and woody energy crops (WECs). This executive summary reports the findings of that workshop.

  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. Flat-plate solar array project. Volume 1: Executive summary

    Science.gov (United States)

    Callaghan, W.; Mcdonald, R.

    1986-01-01

    In 1975, the U.S. Government contracted the Jet Propulsion Lab. to develop, by 1985, in conjunction with industry, the photovoltaics (PV) module and array technology required for widespread use of photovoltaics as a significant terrestrial energy source. As a result, a project that eventually became known as the Flat Plate Solar Array (FSA) Project was formed to manage an industry, university, and Government team to perform the necessary research and development. The original goals were to achieve widespread commercial use of PV modules and arrays through the development of technology that would allow them to be profitably sold for $1.07/peak watts (1985 dollars). A 10% module conversion efficiency and a 20 year lifetime were also goals. It is intended that the executive summary provide the means by which one can gain a perspective on 11 years of terrestrial photovoltaic research and development conducted by the FSA Project.

  13. NanoByg - a survey of nanoinnovation in Danish construction. Executive summary in English

    DEFF Research Database (Denmark)

    Andersen, Maj Munch; Molin, Måns J.

    This is an executive summary of the Risoe report, Risø-R-1602 (EN), with the title ''NanoByg - A survey of nanoinnovation in Danish construction''.......This is an executive summary of the Risoe report, Risø-R-1602 (EN), with the title ''NanoByg - A survey of nanoinnovation in Danish construction''....

  14. NanoByg - a survey of nanoinnovation in Danish construction. Executive summary, dansk

    DEFF Research Database (Denmark)

    Andersen, Maj Munch; Molin, Måns J.

    Denne tekst er et Executive summary af Risø rapporten, ''NanoByg - A survey of nanoinnovation in Danish construction''. (Risø-R-1602 (EN), 72 p.)......Denne tekst er et Executive summary af Risø rapporten, ''NanoByg - A survey of nanoinnovation in Danish construction''. (Risø-R-1602 (EN), 72 p.)...

  15. How Many Dentists Are Needed in 2040: Executive Summary.

    Science.gov (United States)

    Bailit, Howard L

    2017-08-01

    Five background articles in Section 2 of the "Advancing Dental Education in the 21 st Century" project examined some of the factors likely to impact the number of dentists needed in 2040: 1) the oral health of the population, 2) changes in the utilization of dental services, 3) new technologies, 4) the growth of large capitated dental group practices, and 5) the demand for dental care. With this information, a sixth background article estimated the number of dentists needed in 2040 compared to the number expected if current trends continue. This executive summary provides an overview of findings from these six articles. The data indicate major improvements in oral health, especially in upper income groups that account for 65% of practice revenues. At the same time, per capita utilization of restorative and prosthetic services has declined dramatically. No major new technologies are likely to impact the need for dentists by 2040. In a large capitated group practice, full-time general dentists treated an average of 2,100 patients per year; solo general dentists averaged 1,350. Based on the examined factors, growth in demand for traditional forms of care may slow substantially, raising the potential for a surplus of dentists in 2040. If these trends continue, the key national policy issue then would be: should schools reduce the number of graduates before market forces require them to downsize or close, or are other alternatives available?

  16. What Should Oral Health Professionals Know in 2040: Executive Summary.

    Science.gov (United States)

    Weintraub, Jane A

    2017-08-01

    The "Advancing Dental Education in the 21 st Century" project assesses current status and trends to prepare for the future. Section 3 of the project asks what knowledge and skills should dental and advanced dental education learners have to provide dental care in 2040 and how should educators be preparing them. This executive summary of five background articles in this section focuses on predoctoral education, advanced dental education, the provision of medical services within dental practice, the incorporation of oral health services into primary care and medical practice, and interprofessional education and practice. The changing environment and external forces are presented along with their implications for advancing dental education. These forces include changes in population characteristics (e.g., demographics, disease prevalence, health disparities, consumerism), treatment needs and modalities, care delivery, science and technology, educational methods, and medical and dental integration. Future oral health professionals (OHPs) will care for more diverse patient populations, older patients with complex medical and dental needs, and relatively dentally healthy younger cohorts who require fewer complex restorative and prosthodontic treatments. Increasing integration of medical and oral health education and patient care will require OHPs to have more medical knowledge and to practice in intra- and interprofessional teams. OHPs increasingly will be providing patient-centered care as employees in large group practices, health care settings, and safety net clinics with expanded types of OHPs and improved materials and technology. Educators need to implement innovative curricula and educational methods to prepare for and adapt to the disruptive changes that lie ahead.

  17. The Oral Health Care Delivery System in 2040: Executive Summary.

    Science.gov (United States)

    Bailit, Howard L

    2017-09-01

    This executive summary for Section 4 of the "Advancing Dental Education in the 21 st Century" project examines the projected oral health care delivery system in 2040 and the likely impact of system changes on dental education. Dental care is at an early stage of major changes with the decline in solo practice and increase in large group practices. These groups are not consolidated at the state level, but further consolidation is expected as they try to increase their negotiating leverage with dental insurers. At this time, there is limited integration of medical and dental care in terms of financing, regulation, education, and delivery. This pattern may change as health maintenance organizations and integrated medical systems begin to offer dental care to their members. By 2040, it is expected that many dentists will be employed in large group practices and working with allied dental staff with expanded duties and other health professionals, and more dental graduates will seek formal postdoctoral training to obtain better positions in group practices.

  18. Environmental assessment of exploration drilling off Nova Scotia: executive summary

    International Nuclear Information System (INIS)

    2000-01-01

    The environmental assessment project of drilling offshore Nova Scotia covers year-around drilling conducted from jackup rigs, semi-submersible rigs, and drill ships that use the methods described in the project description on the Scotian Shelf, the Laurentian Channel and St, Pierre Bank. The assessment was sponsored by all the oil companies active in the area, namely Mobil Oil Canada, Shell Canada, Imperial Oil Resources, Gulf Canada Resources, Chevron Canada Resources, PanCanadian Petroleum, Murphy Oil Company and Norsk Hydro Canada Oil and Gas. This summary describes the impact assessment methodology used, provides a description of the project, reviews the cumulative impact, and the impacts of discrete activities such as noise and disturbances, operational discharges of oil, disruption of the benthos, garbage and waste disposal, and accidental oil spills, and outlines mitigation and monitoring activities to deal with the impacts. Mitigation measures encompass routine discharges, accidental oil spills, spill response, monitoring activities, contingency plans and an overall environmental protection plan. In addition to this generic assessment, the consultants recommend that individual exploration drilling programs that fall outside of the parameters outlined in the generic environmental assessment document, be required to undergo a program-specific assessment that focuses on those aspects of the proposed program that differ from the parameters prescribed in the present document. 9 refs

  19. Constellation Program: Lessons Learned. Volume 1; Executive Summary

    Science.gov (United States)

    Rhatigan, Jennifer L. (Editor)

    2011-01-01

    This document (Volume I) provides an executive summary of the lessons learned from the Constellation Program. A companion Volume II provides more detailed analyses for those seeking further insight and information. In this volume, Section 1.0 introduces the approach in preparing and organizing the content to enable rapid assimilation of the lessons. Section 2.0 describes the contextual framework in which the Constellation Program was formulated and functioned that is necessary to understand most of the lessons. Context of a former program may seem irrelevant in the heady days of new program formulation. However, readers should take some time to understand the context. Many of the lessons would be different in a different context, so the reader should reflect on the similarities and differences in his or her current circumstances. Section 3.0 summarizes key findings developed from the significant lessons learned at the program level that appear in Section 4.0. Readers can use the key findings in Section 3.0 to peruse for particular topics, and will find more supporting detail and analyses in Section 4.0 in a topical format. Appendix A contains a white paper describing the Constellation Program formulation that may be of use to readers wanting more context or background information. The reader will no doubt recognize some very similar themes from previous lessons learned, blue-ribbon committee reviews, National Academy reviews, and advisory panel reviews for this and other large-scale human spaceflight programs; including Apollo, Space Shuttle, Shuttle/Mir, and the ISS. This could represent an inability to learn lessons from previous generations; however, it is more likely that similar challenges persist in the Agency structure and approach to program formulation, budget advocacy, and management. Perhaps the greatest value of these Constellation lessons learned can be found in viewing them in context with these previous efforts to guide and advise the Agency and its

  20. Oral Health Research and Scholarship in 2040: Executive Summary.

    Science.gov (United States)

    Polverini, Peter J

    2017-09-01

    This executive summary for Section 6 of the "Advancing Dental Education in the 21 st Century" project provides an overview of five background articles that address the role of research and scholarship in dental education in the year 2040. Beginning with a historical account of research and discovery science in dentistry's evolution as a profession, the article then reviews the role of early thought leaders and organized dentistry in establishing research as a cornerstone of dental education and dental practice. The dental research workforce faces an uncertain future fueled by a volatile funding environment and inadequate mentoring and training of research faculty. Dental schools must forge stronger academic and scientific ties to their university and academic health centers and will be challenged to develop sustainable research and patient care collaborations with other health professions. The changing health care environment will create new opportunities for oral health care providers to expand their scope of practice and focus on prevention and screening for non-communicable chronic diseases. Dental practitioners in the future are likely to place greater emphasis on managing the overall health of their patients while promoting closer integration with other health professionals. All dental schools must develop a sustainable research mission if they hope to graduate dentists who function effectively in a collaborative health care environment. The changing scientific and health care landscape will dramatically alter dental education and dental practice. Dental schools need to reconsider their research and educational priorities and clinical practice objectives. Until dental schools and the practicing community come to grips with these challenges, a persistent attitude of complacency will likely be at the dental profession's peril.

  1. AASHTO transportation asset management guide : a focus on implementation executive summary.

    Science.gov (United States)

    2013-06-01

    This AASHTO Transportation Asset Management Executive Summary serves as a companion to the AASHTO Transportation : Asset Management GuideA Focus on Implementation, which takes as a starting point the Transportation : Asset Management Guide publish...

  2. Executive summary of the energy balance from Sao Paulo State, Brazil, 1996. Base year: 1995

    International Nuclear Information System (INIS)

    1996-01-01

    This document presents a executive summary of the energy balance in the year 1995, reporting the energy consumption considering the energy market dynamics and increasing ratio in the residential, public, commercial, agricultural, cattle breeding, transportation and industry areas

  3. Aircraft Battle Damage Assessment and Repair (ABDAR). Volume 1: Executive Summary

    National Research Council Canada - National Science Library

    Dierker, Ron

    2000-01-01

    .... This volume provides an executive summary and describes the overall program goals, the methodology used to develop the ABDAR technology and a demonstration system, and the results of a field test...

  4. Executive summaries of reports leading to the construction of the Baca Geothermal Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Sherwood, P.B.; Newman, K.L.; Westermeier, J.F.; Giroux, H.D.; Lowe, G.D.; Nienberg, M.W.

    1980-05-01

    Executive summaries have been written for 61 reports and compilations of data which, in part, have led to the construction of the Baca 50 MW Geothermal Demonstration Project (GDP). The reports and data include environmental research, reservoir and feasibility studies, the project proposal to DOE and the Final Environmental Impact Statement. These executive summaries are intended to give the reader a general overview of each report prior to requesting the report from the GDP Data Manager.

  5. Executive summaries of reports leading to the construction of the Baca Geothermal Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Sherwood, P.B.; Newman, K.L.; Westermeier, J.F.; Giroux, H.D.; Lowe, G.D.; Nienberg, M.W.

    1980-05-01

    Executive summaries have been written for 61 reports and compilations of data which in part, have led to the construction of the Baca 50 MW Geothermal Demonstration Project (GDP). The reports and data include environmental research, reservoir and feasibility studies, the project proposal to DOE and the Final Environmental Impact Statement. These executive summaries are intended to give the reader a general overview of each report prior to requesting the report from the GDP Data Manager.

  6. Performance assessment of the direct disposal in unsaturated tuff of spent nuclear fuel and high-level waste owned by U.S. Department of Energy. Volume 1: Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P. [ed.] [Sandia National Labs., Albuquerque, NM (United States). WIPP Performance Assessment Dept.

    1995-03-01

    This assessment studied the performance of high-level radioactive waste and spent nuclear fuel in a hypothetical repository in unsaturated tuff. The results of this 10-month study are intended to help guide the Office of Environment Management of the US Department of Energy (DOE) on how to prepare its wastes for eventual permanent disposal. The waste forms comprised spent fuel and high-level waste currently stored at the Idaho National Engineering Laboratory (INEL) and the Hanford reservation. About 700 metric tons heavy metal (MTHM) of the waste under study is stored at INEL, including graphite spent nuclear fuel, highly enriched uranium spent fuel, low enriched uranium spent fuel, and calcined high-level waste. About 2,100 MTHM of weapons production fuel, currently stored on the Hanford reservation, was also included. The behavior of the waste was analyzed by waste form and also as a group of waste forms in the hypothetical tuff repository. When the waste forms were studied together, the repository was assumed also to contain about 9,200 MTHM high-level waste in borosilicate glass from three DOE sites. The addition of the borosilicate glass, which has already been proposed as a final waste form, brought the total to about 12,000 MTHM. A source term model was developed to study the wide variety of waste forms, which included radionuclides residing in 10 different matrices and up to 8 nested layers of material that might react with water. The possibility and consequences of critical conditions occurring in or near containers of highly enriched uranium spent nuclear fuel were also studied.

  7. Compendium of Executive Summaries from the Maglev System Concept Definition. Final Reports.

    Science.gov (United States)

    1993-03-01

    This report contains the Executive Summaries from the four System Concept Definition (SCD) studies awarded under the National Maglev Initiative...These summaries present the technical feasibility, performance, capital, operating and maintenance costs for a maglev system that would be available by

  8. "AfterZone:" Outcomes for Youth Participating in Providence's Citywide After-School System. Executive Summary

    Science.gov (United States)

    Kauh, Tina J.

    2011-01-01

    This executive summary highlights the main findings from our participation and outcomes analysis of the "AfterZone" initiative--a citywide system-building effort in Providence, Rhode Island, that aims to provide high-quality, accessible out-of-school-time services to middle school youth. The summary briefly defines the AfterZone's unique…

  9. Housing Operations Management System (HOMES). Volume 1. Executive Summary

    Science.gov (United States)

    1984-08-01

    output products become available. One of these products is the Reimburs - able Order and Contract Ledger. By entering a Reimbursable Order (RO) Number or...Development Products Menu 108 G8 HOMES Budget Execution Menu 109 G9 Budget Execution Flow 110 G1O Commitments and Obligations Ledger il1 Gil Reimbursable ...are in a specified percentage range liquidated. Figure ClI shows the format of the Reimbursable Order and Contract Ledger. Figure 012 shows the

  10. Federal Facility Compliance Act, Proposed Site Treatment Plan: Background Volume. Executive Summary

    International Nuclear Information System (INIS)

    1995-01-01

    This Federal Facility Compliance Act Site Treatment Plan discusses the options of radioactive waste management for Ames Laboratory. This is the background volume which discusses: site history and mission; framework for developing site treatment plans; proposed plan organization and related activities; characterization of mixed waste and waste minimization; low level mixed waste streams and the proposed treatment approach; future generation of TRU and mixed wastes; the adequacy of mixed waste storage facilities; and a summary of the overall DOE activity in the area of disposal of mixed waste treatment residuals

  11. 1995 Solid Waste 30-year volume summary

    International Nuclear Information System (INIS)

    Valero, O.J.; DeForest, T.J.; Templeton, K.J.

    1995-06-01

    This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford's Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford

  12. 1994 Solid waste forecast container volume summary

    International Nuclear Information System (INIS)

    Templeton, K.J.; Clary, J.L.

    1994-09-01

    This report describes a 30-year forecast of the solid waste volumes by container type. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste. These volumes and their associated container types will be generated or received at the US Department of Energy Hanford Site for storage, treatment, and disposal at Westinghouse Hanford Company's Solid Waste Operations Complex (SWOC) during a 30-year period from FY 1994 through FY 2023. The forecast data for the 30-year period indicates that approximately 307,150 m 3 of LLMW and TRU/TRUM waste will be managed by the SWOC. The main container type for this waste is 55-gallon drums, which will be used to ship 36% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of 55-gallon drums is Past Practice Remediation. This waste will be generated by the Environmental Restoration Program during remediation of Hanford's past practice sites. Although Past Practice Remediation is the primary generator of 55-gallon drums, most waste generators are planning to ship some percentage of their waste in 55-gallon drums. Long-length equipment containers (LECs) are forecasted to contain 32% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of LECs is the Long-Length Equipment waste generator, which is responsible for retrieving contaminated long-length equipment from the tank farms. Boxes are forecasted to contain 21% of the waste. These containers are primarily forecasted for use by the Environmental Restoration Operations--D ampersand D of Surplus Facilities waste generator. This waste generator is responsible for the solid waste generated during decontamination and decommissioning (D ampersand D) of the facilities currently on the Surplus Facilities Program Plan. The remaining LLMW and TRU/TRUM waste volume is planned to be shipped in casks and other miscellaneous containers

  13. Media Campaigns and Crime Prevention: An Executive Summary.

    Science.gov (United States)

    Mendelsohn, Harold; O'Keefe, Garrett J.

    This summary report highlights the results of a study that examined the effects of the first phase of a nationwide, multimedia, crime prevention campaign featuring a trench-coated, animated dog named McGruff. Following an introduction explaining the purpose of the two surveys that comprised the study, the eight remaining sections of the report…

  14. Solid waste 30-year volume summary

    International Nuclear Information System (INIS)

    Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

    1994-06-01

    A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

  15. Nuclear Waste Management Program summary document, FY 1981

    International Nuclear Information System (INIS)

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel

  16. Nuclear Waste Management Program summary document, FY 1981

    Energy Technology Data Exchange (ETDEWEB)

    Meyers, Sheldon

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel.

  17. 1995 Solid Waste 30-year volume summary

    Energy Technology Data Exchange (ETDEWEB)

    Valero, O.J. [Westinghouse Hanford Co., Richland, WA (United States); DeForest, T.J.; Templeton, K.J. [Pacific Northwest Lab., Richland, WA (United States)

    1995-06-01

    This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), provides a description of the annual low-level mixed waste (LLMW) and transuranic/transuranic mixed solid waste (TRU-TRUM) volumes expected to be managed by Hanford`s Solid Waste Central Waste Complex (CWC) over the next 30 years. The waste generation sources and waste categories are also described. This document is intended to be used as a reference for short- and long-term planning of the Hanford treatment, storage, and disposal (TSD) activities over the next several decades. By estimating the waste volumes that will be generated in the future, facility planners can determine the timing of key waste management activities, evaluate alternative treatment strategies, and plan storage and disposal capacities. In addition, this document can be used by other waste sites and the general public to gain a better understanding of the types and volumes of waste that will be managed at Hanford.

  18. Biofuels Program Plan, FY 1992--FY 1996. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    This five-year program plan describes the goals and philosophy of the US Department of Energy`s (DOE) Biofuels Systems Division (BSD) program and the BSD`s major research and development (R&D) activities for fiscal years (FY) 1992 through 1996. The plan represents a consensus among government and university researchers, fuel and automotive manufacturers, and current and potential users of alternative fuels and fuel additives produced from biomass. It defines the activities that are necessary to produce versatile, domestic, economical, renewable liquid fuels from biomass feedstocks. The BSD program focuses on the production of alternative liquid fuels for transportation-fuels such as ethanol, methanol, biodiesel, and fuel additives for reformulated gasoline. These fuels can be produced from many plant materials and from a significant portion of the wastes generated by municipalities and industry. Together these raw materials and wastes, or feedstocks, are called biomass.

  19. ANDRA - R and D programme 2013-2016. Executive summary

    International Nuclear Information System (INIS)

    2014-03-01

    As the ANDRA has defined three strategic orientations for the years to come (period 2013-2016), respectively to prepare the decisions and the construction for the storage of high-level, intermediate-level-long-lived and low-level-long-lived wastes, to guarantee a high level of safety and to improve customer's satisfaction regarding the storage of their ultimate very-low-level and low-and-intermediate-level-short-lived wastes, and to provide and valorise innovating solutions for an optimised management of radioactive wastes, this report presents the different fields of research and development aimed at operational objectives associated with this strategic orientations. This R and D programme is herein presented in five main themes: to preserve the rare source of storage sites, to define requirements and needs-related technical specifications and to adapt them to knowledge progress, to support storage construction and exploitation operations, to define and exploit techniques and networks of control and information, and to optimise materials used in storage

  20. Summary: special waste form lysimeters - arid program

    International Nuclear Information System (INIS)

    Skaggs, R.L.; Walter, M.B.

    1987-01-01

    The purpose of the Special Waste Form Lysimeters - Arid Program is to determine the performance of solidified commercial low-level waste forms using a field-scale lysimeter facility constructed for measuring the release and migration of radionuclides from the waste forms. The performance of these waste forms, as measured by radionuclide concentrations in lysimeter effluent, will be compared to that predicted by laboratory characterization of the waste forms. Waste forms being tested include nuclear power reactor waste streams that have been solidified in cement, Dow polymer, and bitumen. To conduct the field leaching experiments a lysimeter facility was built to measure leachate under actual environmental conditions. Field-scale samples of waste were buried in lysimeters equipped to measure water balance components, effluent radionuclide concentrations, and to a limited extent, radionuclide concentrations in lysimeter soil samples. The waste forms are being characterized by standard laboratory leach tests to obtain estimates of radionuclide release. These estimates will be compared to leach rates observed in the field. Adsorption studies are being conducted to determine the amount of contaminant available for transport after the release. Theoretical solubility calculations will also be performed to investigate whether common solid phases could be controlling radionuclide release. 4 references, 8 figures, 1 table

  1. Coordination of Decision Making in Spain. The 'COWAM Spain' Initiative and the Current Project Under Consideration for a National Interim Storage Facility for Spent Fuel and High Level Waste. The Sixth Workshop of the Forum on Stakeholder Confidence. Executive Summary and International Perspective

    International Nuclear Information System (INIS)

    2006-01-01

    speakers introduced the COWAM Spain initiative and expounded its three main themes: (i) democracy and participatory systems for the local level; (ii) the interplay between the national and local level; and (iii) long-term governance. Presentations provided a background to subsequent round table discussions that included both local stakeholders and international delegates. Day 3 afternoon was devoted to the feedback by two thematic rapporteurs. They evaluated the meeting from two distinct perspectives: that of the policy making approach, and of participatory decision making. The present Summary gives an overview of the presentations and discussions that took place at the workshop and the community visit. 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 the NEA Secretariat's reflection highlighting from an international perspective some of the lessons to be learnt

  2. Site management system executive summary report -- March 1995

    International Nuclear Information System (INIS)

    Schultz, E.A.

    1995-03-01

    Performance data for March 1995 reflects a continued unfavorable schedule variance and favorable cost variance. The March fiscal-year-to-date (FYTD) schedule variance is an unfavorable $105.5M. EM-30 (Office of Waste Management) is the biggest contributor ($81.9 million) to the behind-schedule condition. The majority of the EM-30 schedule variance is associated with the Tank Waste Remediation System (TWRS) program. A breakdown of individual program performance is listed on page 6. The TWRS schedule variance totals a negative $63.0 million and is attributed to the delay in receiving key decision 0 (KD-0) for Project W-314, open-quotes Tank Farm Restoration and Safe Operationsclose quotes; the delay in receiving KD-3 for Project W-320, open-quotes 106-C Sluicingclose quotes; late deployment of the rotary and push mode sampling trucks due to equipment and operational issues; late placement of melter contracts; and the Multi-Function Waste Tank Facility (MWTF) workscope still being a part of the baseline. Class I change requests are in process to rebaseline the activities associated with KDs. An aggressive sampling schedule has been developed for the rotary and push mode sampling activity. Thirty-seven enforceable agreement milestones were schedule FYTD. Thirty-six (97 percent) of the thirty-seven were completed on or ahead of schedule and one (3 percent) is delinquent. The Department of Energy, Richland Operations Office entered into dispute resolution on April 7, 1995, for the delinquent milestone. Six (13 percent) of the 39 remaining enforceable agreement milestones scheduled for FY 1995 are forecast to be late. Additional information on these milestones can be found on pages 13 through 15. Performance data reflects a significant favorable $25.7 million (4 percent) cost variance. The majority of the cost variance is attributed to progress towards achievement of productivity commitment goals and is expected to continue for the remainder of this fiscal year

  3. AVLIS production plant waste management plan

    International Nuclear Information System (INIS)

    1984-01-01

    Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables

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

    International Nuclear Information System (INIS)

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

    1996-03-01

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

  5. Iodine waste form summary report (FY 2007)

    International Nuclear Information System (INIS)

    Krumhansl, James Lee; Nenoff, Tina Maria; McMahon, Kevin A.; Gao, Huizhen; Rajan, Ashwath Natech

    2007-01-01

    This new program at Sandia is focused on Iodine waste form development for GNEP cycle needs. Our research has a general theme of 'Waste Forms by Design' in which we are focused on silver loaded zeolite waste forms and related metal loaded zeolites that can be validated for chosen GNEP cycle designs. With that theme, we are interested in materials flexibility for iodine feed stream and sequestration material (in a sense, the ability to develop a universal material independent on the waste stream composition). We also are designing the flexibility to work in a variety of repository or storage scenarios. This is possible by studying the structure/property relationship of existing waste forms and optimizing them to our current needs. Furthermore, by understanding the properties of the waste and the storage forms we may be able to predict their long-term behavior and stability. Finally, we are working collaboratively with the Waste Form Development Campaign to ensure materials durability and stability testing

  6. Workers in an Integrating World. World Development Report, 1995. Executive Summary.

    Science.gov (United States)

    World Bank, Washington, DC.

    This executive summary examines the rapid changes occurring in economic markets and employment around the world. The report concludes that problems of low incomes, poor working conditions, and insecurity affecting many of the world's workers can be tackled effectively in ways that reduce poverty and regional inequality. Sound domestic policy and a…

  7. Building Management Information Systems to Coordinate Citywide Afterschool Programs: A Toolkit for Cities. Executive Summary

    Science.gov (United States)

    Kingsley, Chris

    2012-01-01

    This executive summary describes highlights from the report, "Building Management Information Systems to Coordinate Citywide Afterschool Programs: A Toolkit for Cities." City-led efforts to build coordinated systems of afterschool programming are an important strategy for improving the health, safety and academic preparedness of children…

  8. Reviving the Rural Factory: Automation and Work in the South. Executive Summary.

    Science.gov (United States)

    Rosenfeld, Stuart A.; And Others

    This document is the executive summary for a two volume report on technological innovation and southern rural industrial development. The first volume examines public and private factors that influence investment decisions in new technologies and the outcomes of those decisions; effects of automation on employment and the workplace; outcomes of…

  9. FWP executive summaries: basic energy sciences materials sciences and engineering program (SNL/NM).

    Energy Technology Data Exchange (ETDEWEB)

    Samara, George A.; Simmons, Jerry A.

    2006-07-01

    This report presents an Executive Summary of the various elements of the Materials Sciences and Engineering Program which is funded by the Division of Materials Sciences and Engineering, Office of Basic Energy Sciences, U.S. Department of Energy at Sandia National Laboratories, New Mexico. A general programmatic overview is also presented.

  10. Diagnosis, evaluation, and management of the hypertensive disorders of pregnancy: executive summary

    NARCIS (Netherlands)

    Magee, Laura A.; Pels, Anouk; Helewa, Michael; Rey, Evelyne; von Dadelszen, Peter; Audibert, Francois; Bujold, Emmanuel; Côté, Anne-Marie; Douglas, Myrtle Joanne; Eastabrook, Genevieve; Firoz, Tabassum; Gibson, Paul; Gruslin, Andrée; Hutcheon, Jennifer; Koren, Gideon; Lange, Ian; Leduc, Line; Logan, Alexander G.

    2014-01-01

    This executive summary presents in brief the current evidence assessed in the clinical practice guideline prepared by the Canadian Hypertensive Disorders of Pregnancy Working Group and published by Pregnancy Hypertension (http://www.pregnancyhypertension.org/article/S2210-7789(14)00004-X/fulltext)

  11. Executive summary of European Task Force document on diagnostic tools in rhinology

    NARCIS (Netherlands)

    Hellings, P. W.; Scadding, G.; Alobid, I.; Bachert, C.; Fokkens, W. J.; Gerth van Wijk, R.; Gevaerts, P.; Guilemany, J.; Kalogjera, L.; Lund, V. J.; Mullol, J.; Passalacqua, G.; Toskala, E.; van Drunen, C. M.

    2012-01-01

    This Executive Summary of the EAACI Task Force document on Diagnostic Tools in Rhinology provides the readers with an over- view of the currently available tools for diagnosis of nasal and sino-nasal disease, published in full version in the first issue of Clini- cal and Translational Allergy. A

  12. A Second Year Evaluation Study of Promethean ActivClassroom. Executive Summary

    Science.gov (United States)

    Marzano Research Laboratory, 2010

    2010-01-01

    During the 2009-2010 school year, Marzano Research Laboratory (MRL) was commissioned by Promethean Ltd. to conduct a second year evaluation study of the effects of Promethean ActivClassroom on student academic achievement. This executive summary highlights the key findings. [For "A Second Year Evaluation Study of Promethean ActivClassroom. Final…

  13. The Irreplaceables: Understanding the Real Retention Crisis in America's Urban Schools. Executive Summary

    Science.gov (United States)

    TNTP, 2012

    2012-01-01

    Discussions of teacher turnover usually focus on "how many" teachers leave schools each year, without regard for their performance in the classroom. This oversimplification masks the real teacher retention crisis: not only a failure to retain enough teachers, but a failure to retain the "right" teachers. This executive summary presents findings of…

  14. Global Strategy for the Diagnosis, Management and Prevention of Chronic Obstructive Pulmonary Disease, GOLD Executive Summary

    DEFF Research Database (Denmark)

    Vestbo, Jørgen; Hurd, Suzanne S; Agusti, Alvar G

    2013-01-01

    Chronic obstructive pulmonary disease (COPD) is a global health problem and since 2001 the Global Initiative for Chronic Obstructive Lung Disease (GOLD) has published its strategy document for the diagnosis and management of COPD. This executive summary presents the main contents of the second 5...

  15. HRS Clinical Document Development Methodology Manual and Policies: Executive summary.

    Science.gov (United States)

    Indik, Julia H; Patton, Kristen K; Beardsall, Marianne; Chen-Scarabelli, Carol A; Cohen, Mitchell I; Dickfeld, Timm-Michael L; Haines, David E; Helm, Robert H; Krishnan, Kousik; Nielsen, Jens Cosedis; Rickard, John; Sapp, John L; Chung, Mina

    2017-10-01

    The Heart Rhythm Society (HRS) has been developing clinical practice documents in collaboration and partnership with other professional medical societies since 1996. The HRS formed a Scientific and Clinical Documents Committee (SCDC) with the sole purpose of managing the development of these documents from conception through publication. The SCDC oversees the process for developing clinical practice documents, with input and approval from the HRS Executive Committee and the Board of Trustees. As of May 2017, the HRS has produced more than 80 publications with other professional organizations. This process manual is produced to publicly and transparently declare the standards by which the HRS develops clinical practice documents, which include clinical practice guidelines, expert consensus statements, scientific statements, clinical competency statements, task force policy statements, and proceedings statements. The foundation for this process is informed by the Institute of Medicine's standards for developing trustworthy clinical practice guidelines; the new criteria from the National Guidelines Clearinghouse, effective June 2014; SCDC member discussions; and a review of guideline policies and methodologies used by other professional organizations. Copyright © 2017 Heart Rhythm Society. Published by Elsevier Inc. All rights reserved.

  16. Nuclear Power Options Viability Study. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    Trauger, D.B.; White, J.D.; Booth, R.S.

    1986-09-01

    Innovative reactor concepts are described and evaluated in accordance with criteria established in the study. The reactors to be studied were selected on the basis of three ground rules: (1) the potential for commercialization between 2000 to 2010, (2) economic competitiveness with coal, and (3) the degree of passive safety in the design. The concepts, classified by coolants, were light water reactors, liquid metal reactors, and high-temperature reactors, and most were of modular design. Although the information available is not adequate for a definitive evaluation of economic competitiveness, all of the concepts appear to be potentially viable in the time frame selected. Public and institutional acceptance of nuclear power was found to be affected primarily by four issues: (1) operational safety, (2) waste handling and disposal, (3) construction and operating costs, and (4) the adequacy of management and regulatory controls

  17. Weapons-grade plutonium dispositioning. Volume 1: Executive summary

    International Nuclear Information System (INIS)

    Parks, D.L.; Sauerbrun, T.J.

    1993-06-01

    The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate dispositioning options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) assisted NAS in this evaluation by investigating the technical aspects of the dispositioning options and their capability for achieving plutonium annihilation levels greater than 90%. Additionally, the INEL investigated the feasibility of using plutonium fuels (without uranium) for disposal in existing light water reactors and provided a preconceptual analysis for a reactor specifically designed for destruction of weapons-grade plutonium. This four-volume report was prepared for NAS to document the findings of these studies. Volume 2 evaluates 12 plutonium dispositioning options. Volume 3 considers a concept for a low-temperature, low-pressure, low-power-density, low-coolant-flow-rate light water reactor that quickly destroys plutonium without using uranium or thorium. This reactor concept does not produce electricity and has no other mission than the destruction of plutonium. Volume 4 addresses neutronic performance, fabrication technology, and fuel performance and compatibility issues for zirconium-plutonium oxide fuels and aluminum-plutonium metallic fuels. This volumes gives summaries of Volumes 2--4

  18. Fuego/Scefire MPMD Coupling L2 Milestone Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, Flint [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Tencer, John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Pautz, Shawn D. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Drumm, Clifton R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-01

    This milestone campaign was focused on coupling Sandia physics codes SIERRA low Mach module Fuego and RAMSES Boltzmann transport code Sceptre(Scefire). Fuego enables simulation of low Mach, turbulent, reacting, particle laden flows on unstructured meshes using CVFEM for abnormal thermal environments throughout SNL and the larger national security community. Sceptre provides simulation for photon, neutron, and charged particle transport on unstructured meshes using Discontinuous Galerkin for radiation effects calculations at SNL and elsewhere. Coupling these ”best of breed” codes enables efficient modeling of thermal/fluid environments with radiation transport, including fires (pool, propellant, composite) as well as those with directed radiant fluxes. We seek to improve the experience of Fuego users who require radiation transport capabilities in two ways. The first is performance. We achieve this through leveraging additional computational resources for Scefire, reducing calculation times while leaving unaffected resources for fluid physics. This approach is new to Fuego, which previously utilized the same resources for both fluid and radiation solutions. The second improvement enables new radiation capabilities, including spectral (banded) radiation, beam boundary sources, and alternate radiation solvers (i.e. Pn). This summary provides an overview of these achievements.

  19. Summary of third international executive conference on photovoltaic power systems

    Energy Technology Data Exchange (ETDEWEB)

    Gillett, W.

    2001-07-01

    In December 1990, the International Energy Agency (IEA) invited photovoltaic manufacturers, electrical utilities, and government leaders to a groundbreaking First Congress of Executives conference in Taormina, Italy. The purpose was to develop a strategic approach to PV market development. The Taormina Congress focused on the diffusion of applications based on cost-effectiveness. A second IEA International Conference was held in Sun Valley, Idaho, in September 1995, focusing on the implementation of physical markets based on profit opportunities. Discussions in Sun Valley included the integration of utility and PV businesses into new partnerships in the developing world. By 1995, the strategic interaction of utility activity with photovoltaic technology was recognised and a number of new business opportunities were identified in both industrialised and developing countries. The November 1999 conference, held in Venice, Italy, has taken things a step further. It focused on communicating the 'value of the sun', as well as bringing in the developing business interests and expanding roles of the building construction industries and finance institutions. This theme was considered as being the most important issue of the conference and led to the conclusion that just selling kilowatt-hours is not enough, as the market needs complete products and better concepts. Further, all of the relevant stakeholders, including PV industry, project developers, architects, local, regional and national governments, and the IEA should collaborate in a world-wide effort to accelerate the growth of markets for photovoltaic electricity. The conference was designed to provide a unique forum for senior executives from the energy and building sectors, the photovoltaic industry, financial institutions and governments. The aim was to discuss and jointly develop strategic business opportunities for photovoltaics in a rapidly changing energy market and to take the growing movement

  20. MIxed Waste Integrated Program (MWIP): Technology summary

    International Nuclear Information System (INIS)

    1994-02-01

    The mission of the Mixed Waste Integrated Program (MWIP) is to develop and demonstrate innovative and emerging technologies for the treatment and management of DOE's mixed low-level wastes (MLLW) for use by its customers, the Office of Waste Operations (EM-30) and the Office of Environmental Restoration (EM-40). The primary goal of MWIP is to develop and demonstrate the treatment and disposal of actual mixed waste (MMLW and MTRU). The vitrification process and the plasma hearth process are scheduled for demonstration on actual radioactive waste in FY95 and FY96, respectively. This will be accomplished by sequential studies of lab-scale non-radioactive testing followed by bench-scale radioactive testing, followed by field-scale radioactive testing. Both processes create a highly durable final waste form that passes leachability requirements while destroying organics. Material handling technology, and off-gas requirements and capabilities for the plasma hearth process and the vitrification process will be established in parallel

  1. The Role of Nuclear Power in Europe (Executive Summary)

    International Nuclear Information System (INIS)

    World Energy Council

    2007-01-01

    Energy is and will remain one of the major global concerns of the 21st century and Europe is no exception. With global energy demand expected to grow strongly in the coming years, burning questions are now being raised over the future of energy supplies, the economic competitiveness of different energy sources and the associated environmental impacts. The European policy makers and the energy industry currently face three major challenges: ensuring security of energy supply, stabilizing or reducing greenhouse gas emissions and maintaining economic competitiveness by keeping energy prices at an affordable level. The final costs of kWh depend on local legislation and taxes, which impact the discount rate, given that nuclear plants are highly capital intensive. As nuclear power generation does not produce greenhouse gases and emissions, the key sources in creating global climate change and air pollution, it would undoubtedly help tackle growing environmental concerns. The actual amount of spent nuclear fuel produced globally every year is relatively small. Given nuclear power's excellent operational safety record in Europe during past five decades, public concern in many countries today is shifting from operational risks to nuclear waste management. The future contribution of nuclear power to society will depend on innovation, such as development of new reactor and fuel cycle technologies

  2. Nuclear Energy Center Site Survey, 1975. Executive summary

    International Nuclear Information System (INIS)

    1976-01-01

    The Nuclear Energy Center Site Survey is a study of a potential alternative siting approach for nuclear power and fuel-cycle facilities, an approach that would cluster sizable groups of such facilities on a relatively small number of sites. The largest aggregation of reactors on a single site being planned today is four, and this quad is assumed (for comparative study purposes) to be the typical dispersed site by the year 2000. Three basic types of nuclear energy centers are considered: power-plant centers, consisting of 10 to 40 nuclear electric generating units of 1200-megawatt electric capacity each; fuel-cycle centers, consisting of fuel reprocessing plants, mixed-oxide fuel fabrication facilities, and radioactive waste management facilities; and combined centers, containing both power plants and fuel-cycle facilities. The results of the general site-location screening efforts are shown on a United States map that shows the locations of large areas identified as likely to contain suitable candidate sites for power NECs, on the basis of four coarse screening criteria: water resources, seismic activity, population density, and statutory excluded lands

  3. General Public Space Travel and Tourism. Volume 1; Executive Summary

    Science.gov (United States)

    ONeil, Daniel (Compiler); Bekey, Ivan; Mankins, John; Rogers, Thomas F.; Stallmer, Eric W.

    1998-01-01

    risk. A two-year cooperative Space Act agreement study has been conducted by our National Aeronautics and Space Administration and the Space Transportation Association. It was conducted by NASA and STA study leaders drawing upon the competence, experience and hard-nosed imagination of a national Steering Group and scores of attendees at a multi-day Workshop. The study has involved scores of professionals and business people from various areas: astronauts; space booster technology and operations professionals; a hotel architect and a hotel operator; an airline planner; insurance underwriters; space sickness experts; space theme park designers; space and travel and tourism association and business executives; a space-related financier; university tourism and space policy experts; present and former space-responsible government officials; space entrepreneurs; space writers; This study concludes that serious national attention should now be given to activities that would enable the expansion of today's terrestrial space tourism businesses, and the creation of in-space travel and tourism businesses. Indeed, it concludes that, in time, it should become a very important part of our Country's overall commercial and civil space business-program structure.

  4. Sodium waste technology: A summary report

    International Nuclear Information System (INIS)

    Abrams, C.S.; Witbeck, L.C.

    1987-01-01

    The Sodium Waste Technology (SWT) Program was established to resolve long-standing issues regarding disposal of sodium-bearing waste and equipment. Comprehensive SWT research programs investigated a variety of approaches for either removing sodium from sodium-bearing items, or disposal of items containing sodium residuals. The most successful of these programs was the design, test, and the production operation of the Sodium Process Demonstration Facility at ANL-W. The technology used was a series of melt-drain-evaporate operations to remove nonradioactive sodium from sodium-bearing items and then converting the sodium to storable compounds

  5. Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Britt, Phillip F [ORNL

    2015-03-01

    Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions based on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.

  6. Program summary. Nuclear waste management and fuel cycle programs

    International Nuclear Information System (INIS)

    1982-07-01

    This Program Summary Document describes the US Department of Energy (DOE) Nuclear Waste Management and Fuel Cycle Programs. Particular emphasis is given to near-term, specifically Fiscal Year (FY) 1982, activities. The overall objective of these programs will be achieved by the demonstration of: (1) safe radioactive waste management practices for storage and disposal of high-level waste and (2) advanced technologies necessary to close the nuclear fuel cycle on a schedule which would assure a healthy future for the development of nuclear power in this country

  7. Summary report on the 1985 United Kingdom radioactive waste inventory

    International Nuclear Information System (INIS)

    Fletcher, A.M.; Wear, F.J.; Haselden, H.; Shepherd, J.; Tymons, B.J.

    1986-04-01

    Stocks of radioactive waste in the United Kingdom which have arisen, or are projected to arise, from commercial nuclear power reactors and fuel cycle facilities, research, medical and industrial uses of radioactive nuclides are given in the form of summary tables. Projected future arisings from operation and decommissioning of facilities and notional nuclear power generation programmes to 2030 are also given. (author)

  8. Tank waste remediation system technical baseline summary description

    International Nuclear Information System (INIS)

    Raymond, R.E.

    1998-01-01

    This document is one of the tools used to develop and control the mission work as depicted in the included figure. This Technical Baseline Summary Description document is the top-level tool for management of the Technical Baseline for waste storage operations

  9. TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETRIEVAL AND PROCESSING

    Energy Technology Data Exchange (ETDEWEB)

    SAMS TL; MENDOZA RE

    2010-08-11

    This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

  10. TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETREIVAL AND PROCESSING

    Energy Technology Data Exchange (ETDEWEB)

    SAMS TL

    2010-07-07

    This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

  11. CSNF WASTE FORM DEGRADATION: SUMMARY ABSTRACTION

    Energy Technology Data Exchange (ETDEWEB)

    J.C. CUNNANE

    2004-08-31

    The purpose of this model report is to describe the development and validation of models that can be used to calculate the release of radionuclides from commercial spent nuclear fuel (CSNF) following a hypothetical breach of the waste package and fuel cladding in the repository. The purpose also includes describing the uncertainties associated with modeling the radionuclide release for the range of CSNF types, exposure conditions, and durations for which the radionuclide release models are to be applied. This document was developed in accordance with Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package (BSC 2004 [DIRS 169944]). This document considers radionuclides to be released from CSNF when they are available for mobilization by gas-phase mass transport, or by dissolution or colloid formation in water that may contact the fuel. Because other reports address limitations on the dissolved and colloidal radionuclide concentrations (BSC 2004 [DIRS 169944], Table 2-1), this report does not address processes that control the extent to which the radionuclides released from CSNF are mobilized and transported away from the fuel either in the gas phase or in the aqueous phase as dissolved and colloidal species. The scope is limited to consideration of degradation of the CSNF rods following an initial breach of the cladding. It considers features of CSNF that limit the availability of individual radionuclides for release into the gaseous or aqueous phases that may contact the fuel and the processes and events expected to degrade these CSNF features. In short, the purpose is to describe the characteristics of breached fuel rods and the degradation processes expected to influence radionuclide release.

  12. CSNF WASTE FORM DEGRADATION: SUMMARY ABSTRACTION

    International Nuclear Information System (INIS)

    CUNNANE, J.C.

    2004-01-01

    The purpose of this model report is to describe the development and validation of models that can be used to calculate the release of radionuclides from commercial spent nuclear fuel (CSNF) following a hypothetical breach of the waste package and fuel cladding in the repository. The purpose also includes describing the uncertainties associated with modeling the radionuclide release for the range of CSNF types, exposure conditions, and durations for which the radionuclide release models are to be applied. This document was developed in accordance with Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package (BSC 2004 [DIRS 169944]). This document considers radionuclides to be released from CSNF when they are available for mobilization by gas-phase mass transport, or by dissolution or colloid formation in water that may contact the fuel. Because other reports address limitations on the dissolved and colloidal radionuclide concentrations (BSC 2004 [DIRS 169944], Table 2-1), this report does not address processes that control the extent to which the radionuclides released from CSNF are mobilized and transported away from the fuel either in the gas phase or in the aqueous phase as dissolved and colloidal species. The scope is limited to consideration of degradation of the CSNF rods following an initial breach of the cladding. It considers features of CSNF that limit the availability of individual radionuclides for release into the gaseous or aqueous phases that may contact the fuel and the processes and events expected to degrade these CSNF features. In short, the purpose is to describe the characteristics of breached fuel rods and the degradation processes expected to influence radionuclide release

  13. Planning manual for energy resource development on Indian lands. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    1978-03-01

    This report is the Executive Summary for the other 5 volumes of the Study Report--see TID-28526/1-5. Information is provided here that the tribes can use to make energy-development decisions. The report is particularly concerned with management responsibilities and financial commitments that development will require on the part of the tribes and with the types of information and skilled personnel the tribes will need in the future to make informed decisions.

  14. Executive Summary - Natural Gas and the Transformation of the U.S. Energy Sector: Electricity

    Energy Technology Data Exchange (ETDEWEB)

    Logan, J.; Heath, G.; Macknick, J.; Paranhos, E.; Boyd, W.; Carlson, K.

    2013-01-01

    In November 2012, the Joint Institute for Strategic Energy Analysis (JISEA) released a new report, 'Natural Gas and the Transformation of the U.S. Energy Sector: Electricity.' The study provides a new methodological approach to estimate natural gas related greenhouse gas (GHG) emissions, tracks trends in regulatory and voluntary industry practices, and explores various electricity futures. The Executive Summary provides key findings, insights, data, and figures from this major study.

  15. Guidelines for the Prevention of Infections Associated With Combat-Related Injuries: 2011 Update (Executive Summary)

    Science.gov (United States)

    2011-08-01

    employed at all deployed medical treatment facilities (MTF). These should include hand hygiene . with compli- ance monitoring. Infection control and...established infections where nosocomial pathogens, including multidrug~resistant. may be the in~ fecting agents (Table 3). 7. Selected agents should be dosed...REVIEW ARTICLE Executive Summary: Guidelines for the Prevention of Infections Associated With Combat-Related Injuries: 2011 Update Endorsed by the

  16. A solar regenerative thermoelectrochemical converter (RTEC). Executive summary of final subcontract report

    Energy Technology Data Exchange (ETDEWEB)

    Townsend, C.W.; McHardy, J. [Hughes Aircraft Co., El Segundo, CA (United States)

    1992-02-01

    This is an executive summary of a final subcontract report that describes the successful completion of a closed-loop demonstration of a regenerative thermoelectromechanical device using solar heat input for the production of electricity. The full report, which contains a detailed description of the two-year effort, is currently subject to a government secrecy order which precludes public release of the information. Copies of the full report will be made available for general release whenever the secrecy order is lifted.

  17. Executive summary

    International Nuclear Information System (INIS)

    Besmann, T.M.

    2015-01-01

    The State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels describes the state of fundamental materials models that can represent fuel behaviour, the methodologies for obtaining material properties, and modelling principles as they can be implemented in fuel performance codes. This report, while far from being a detailed assessment of nuclear fuel modelling, provides a recognition of the approaches to the significant aspects of fuel modelling and examples of their application. Fuel behaviour phenomena are discussed that are applicable across the spectrum of fuel forms, from conventional LWR oxide pellets to MOX, carbide, and metal SFR fuel, to coated particle fuel for gas-cooled reactors. A key issue is microstructural evolution during burn-up, and the state of understanding of that phenomenon is considered at length. Covered in the discussions are the basic material properties of heat capacity, free energy, and thermal conductivity and diffusion. Also included are the more functional effects of restructuring, bubble formation, constituent redistribution, fuel and clad oxidation, and fuel clad and environmental interactions. Fuel fabrication is considered as are many material modelling challenges, such as representing injection casting of metallic fuels, as seen in the preparation of nuclear fuel. The last set of contributions covered the basic principles for modelling phenomena and determining fundamental materials properties, a look at the state of fuel performance codes and a last note about integrating across multiple scales. The state-of-the-art of modelling phenomena related to nuclear fuel has advanced significantly in recent years. The representation of atomic level behaviour is increasingly becoming more accurate as capabilities to utilise larger sets of atoms evolve and empirical potentials improve. At the mesoscale, models for transport and microstructure evolution have also progressed with new techniques that well represent restructuring. At the macro-scale, the lower scale representations inform models that reproduce observed fuel behaviour. Significant challenges do remain in both improving the models and in their multi-scale integration, and thus there is still much to be done. However, it is the expectation that as the problems of fuel modelling and simulation are solved, predictive models will increasingly find their way into advanced fuel performance codes and allow the eventual realistic simulation of nuclear fuel behaviour under normal and accident conditions that goes beyond empirical correlations. (author)

  18. Executive summary

    Science.gov (United States)

    Susan H. Julius; Jordan M. West; Geoffrey M. Blate; Jill S. Baron; Brad Griffith; Linda A. Joyce; Peter Kareiva; Brian D. Keller; Margaret A. Palmer; Charles H. Peterson; J. Michael. Scott

    2008-01-01

    This report provides a preliminary review of adaptation options for climate-sensitive ecosystems and resources in the United States. The term “adaptation” in this document refers to adjustments in human social systems (e.g., management) in response to climate stimuli and their effects. Since management always occurs in the context of desired ecosystem conditions or...

  19. Executive summary

    DEFF Research Database (Denmark)

    Bangsbo, Jens; Junge, A; Dvorak, J

    2014-01-01

    and women with type 2 diabetes. Furthermore, muscle mass and bone mineral density increases in a number of participant groups, including 65-75-year-old men. The functional capacity is elevated with increases in VO2 max of 10-15%, and 50-100% improvements in the capacity to perform intermittent work within...... structure and improves its function. Blood pressure is markedly reduced with the mean arterial blood pressure being lowered by ~10 mmHg for hypertensive men and women training 2-3 times/week for 12-26 weeks. Triglycerides and cholesterol are lowered and body fat declines, especially in middle-aged men...

  20. Executive summary

    Science.gov (United States)

    Peter Backlund; Anthony Janetos; David Schimel; J. Hatfield; M. Ryan; S. Archer; D. Lettenmaier

    2008-01-01

    This report is an assessment of the effects of climate change on U.S. land resources, water resources, agriculture, and biodiversity. It is one of a series of 21 Synthesis and Assessment Products being produced under the auspices of the U.S. Climate Change Science Program (CCSP), which coordinates the climate change research activities of U.S. government agencies. The...

  1. Executive summary

    International Nuclear Information System (INIS)

    Christy, Robert F.; Tajima, Eizo

    1987-01-01

    The Historical Review describes the events leading up to the present reassessment of the dosimetry of the atomic bombs at Hiroshima and Nagasaki. To make that reassessment, working groups were set up in Japan and in the United States. These groups organized their efforts into ten major areas: yields of the bombs, radiation leakage from the bombs, transport of radiation in air over ground, thermoluminescence measurements of gamma rays, measurements of neutrons, residual radioactivity, house and terrain shielding, organ dosimetry, preparation of a dosimetry system, and uncertainty analysis. In this report on the reassessment, one chapter is devoted to each of the first nine areas; a future will deal with the last area, uncertainty analysis. The chapters were prepared by writing groups, listed as the authors of the chapters. The chapters are based on a large number of individual papers, some of which are included in this report as appendixes to the relevant chapters

  2. Executive summary

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    This is a report on studies that value the environmental impacts resulting from generation and conservation of electric power. The purpose is to review the literature on the methodologies used to assign monetary costs to environmental externalities and to present the results of studies which have applied these methodologies. For those environmental damages for which the literature has not established a value, the report identifies the indicated ranges of adverse effects and provides a road map of issues that require research. The report is intended to assist utilities, government regulators, legislators, policy analysts and public interest groups in estimating the costs of the environmental impacts of electricity. It should be useful, as well, to assist in valuing the environmental impacts of pollutants from other industries, for setting environmental control standards, and in establishing pollution taxes or fees

  3. Executive summary

    International Nuclear Information System (INIS)

    2014-01-01

    The workshop included an opening session, six sessions with participant presentations followed by short discussion, and two facilitated discussion sessions. The contributions presented were devoted to new methodological developments, projects with external hazards analysis activities, interesting aspects of external hazards analysis and expected challenges for future analyses. The contributions presented and the discussions organized during the workshop provided valuable input for strengthening the role of WGRISK in supporting the development and application of probabilistic safety assessment and risk-oriented decision making methods in the area of external hazards. The workshop supported the key general objectives of collecting and exchanging information from OECD member states on the methods and approaches used in probabilistic safety assessment in this area. The focus of the workshop was on external events PSA for nuclear power plants, including all modes of operation. The workshop scope was generally limited to external, natural hazards, including those hazards where the distinction between natural and man-made hazards is not sharp (e.g., external floods caused by dam failures). The participation was open to experts from regulatory authorities and their technical support organizations, research organizations, utilities, nuclear power plant (NPP) designers and vendors, industry associations and observers from OECD NEA member countries. The Background, Objectives, Organization, and Topics of the Workshop are presented in chapter 1. The WGRISK activities preceding the workshop and leading to the decision to organize it are described in Chapter 2. The detailed information about the presentations, discussions, and results of the workshop is presented in Chapter 3. Detailed information about the conclusions made during the workshop is presented in Chapter 4. The list of participants, the workshop agenda and the papers/presentations are attached in the appendixes

  4. Executive Summary

    DEFF Research Database (Denmark)

    Elf, Nikolaj Frydensbjerg

    2017-01-01

    Rekvireret forskningsrapport for Undervisningsministeriet (UVM) som afrapporterer forundersøgelsesfasen for danskfagets vedkommende i projekt Kvalitet i dansk og matematik. Har været til gennemsyn inden udgivelse hos UVM....

  5. Executive summary

    International Nuclear Information System (INIS)

    2015-01-01

    Since 2007, the OECD Nuclear Energy Agency has been organising a series of workshops on Structural Materials for Innovative Nuclear Systems. The third meeting was held on 7-9 October 2013 in Idaho Falls (United States). The main objectives of this workshop are to stimulate an exchange of information on current materials R and D programmes for different innovative nuclear systems. The main topics of the workshop covered fundamental studies, modelling and experiments on innovative structural materials including cladding materials for the range of advanced nuclear systems such as thermal/fast systems, sub-critical systems, as well as fusion systems. During the workshop, the following topics were discussed: - Fundamental studies; - Metallic materials; - Ceramic materials; - Novel materials pathways; - Ion vs neutron irradiation. Fundamental studies focused on the identification of mechanisms driving the response of materials under the conditions expected in innovative nuclear systems. These mechanisms may have acted at the atomic or higher scale with the application of multi-scale approaches, together with related problems of scale-bridging or numerical methods, were of special interest. Moreover, irradiation experiments and subsequent characterisation of materials with analytical techniques were included in the session if aimed at better understanding the acting mechanisms or drawing physics-based correlations. Metal alloys, ceramic and ceramic composites included in- and out-of-core applications which took into account the scope of: data availability and gaps (considering also licensing issues); experimental and modelling needs for specific components or degradation modes; the link between R and D, standardisation and experimental protocols; coolant effects and mechanical properties. Code development and implementation plans were also discussed. Application of SiC composites to LWR systems was of interest as an advanced concept. Novel materials pathways considered routes to fabricate materials and components for innovative nuclear systems. The 'ions vs. neutron irradiation' topic focused on specific irradiation comparisons including mechanical properties and microstructural effects caused by ion or neutron irradiation. Comparative irradiation studies on a common material were also welcome. Fuel-cladding interaction was not covered in this edition of the workshop. The workshop received 74 abstracts, and was scheduled with 5 invited talks, 27 oral presentations and 2 poster sessions (42 posters) from 75 registered participants. However, it was necessary to reorganise the programme at extremely short notice to take into account the effects of the unexpected US government shutdown and the constraints this imposed on the workshop. In total, 38 participants from 12 countries and 2 international organisations attended, and the final number of presentations amounted to 51 (22 oral presentations and 29 posters). The re-scheduled workshop opened with the welcome address by S. Cornet on behalf of the OECD Nuclear Energy Agency followed by technical sessions: Session I: Overview on programmes and metal alloys. Session II: Metal alloys. Session III: Novel pathways. Session IV: Ceramic composites, ions vs. neutrons and general

  6. Tank waste remediation system retrieval and disposal mission initial updated baseline summary

    International Nuclear Information System (INIS)

    Swita, W.R.

    1998-01-01

    This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

  7. Draft low level waste technical summary

    International Nuclear Information System (INIS)

    Powell, W.J.; Benar, C.J.; Certa, P.J.; Eiholzer, C.R.; Kruger, A.A.; Norman, E.C.; Mitchell, D.E.; Penwell, D.E.; Reidel, S.P.; Shade, J.W.

    1995-09-01

    The purpose of this document is to present an outline of the Hanford Site Low-Level Waste (LLW) disposal program, what it has accomplished, what is being done, and where the program is headed. This document may be used to provide background information to personnel new to the LLW management/disposal field and to those individuals needing more information or background on an area in LLW for which they are not familiar. This document should be appropriate for outside groups that may want to learn about the program without immediately becoming immersed in the details. This document is not a program or systems engineering baseline report, and personnel should refer to more current baseline documentation for critical information

  8. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Harmon, K.M.; Lakey, L.T.; Silviera, D.J.; Leigh, I.W.

    1987-09-01

    This report is a compilation of publicly-available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 20 nations and three international agencies that have publicized their activities in this field. The information in this document is compiled to provide summary information on radioactive waste management activities in other countries. This document indicates what is occurring in other countries with regard to strategies, activities, and facilities. This document first presents a short overview of the activities and trends for managing low- to high-level radioactive waste and spent fuel by the entities covered in this review. This is followed by information for each country for nuclear power; fuel cycle and waste management strategy/policy; highlights and major milestones; institutional considerations/organizations; nuclear fuel production; fuel recycle; spent fuel storage and transport; waste conditioning, storage and transport; surface and near-surface waste disposal; geologic waste disposal; management of uranium mine and mill wastes; decommissioning; international; and references. 406 refs

  9. Solid waste and materials systems alternatives study summary

    International Nuclear Information System (INIS)

    Kasper, J.R.; Smith, S.T.

    1996-01-01

    The Hanford Site is a 560-sq.-mi. area in southeastern Washington State owned and operated by the U.S. Department of Energy (DOE). Previous weapons program activities and recent environmental cleanup activities at the Hanford Site have resulted in an accumulation of large quantities of solid wastes and materials. Future Decontamination and Decommissioning (D ampersand D) and Environmental Remediation activities will generate additional wastes. This paper provides a summary of a recently completed analysis of the Hanford Site Solid Wastes and Materials. The analysis involved development and compilation of waste stream and material information including type, classification. location current and project volumes, and curie content. Current program plans for treatment, storage, and disposal/disposition (TSD) have also been included in this analysis

  10. Radioactive waste management: a summary of state laws and administration

    International Nuclear Information System (INIS)

    1983-09-01

    This is the second update of Radioactive Waste Management: A Summary of State Laws and Administration. It completely replaces the first update (15 April 1983). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. Included under the compacts is a description of what the state has done or currently plans to do, as well as the compact status of other eligible states in the region. The Administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. In a number of states, Boards of Health or similar boards are lead agencies, so they have been listed in that section. Each board's administrative agency is listed under it. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs, and a legislative contact. Many legislatures do not set a date for session adjournment, so the date listed represents a combination of information provided by the states and by the history of past sessions. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and this disposition. In general, the information in this report is accurate as of July 15, 1983

  11. Strategies and Decision Support Systems for Integrating Variable Energy Resources in Control Centers for Reliable Grid Operations. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Lawrence E. [Alstom Grid, Inc., Washington, DC (United States)

    2011-11-01

    This is the executive summary for a report that provides findings from the field regarding the best ways in which to guide operational strategies, business processes and control room tools to support the integration of renewable energy into electrical grids.

  12. International consensus statement on allergy and rhinology: allergic rhinitis-executive summary.

    Science.gov (United States)

    Wise, Sarah K; Lin, Sandra Y; Toskala, Elina

    2018-02-01

    The available allergic rhinitis (AR) literature continues to grow. Critical evaluation and understanding of this literature is important to appropriately utilize this knowledge in the care of AR patients. The International Consensus statement on Allergy and Rhinology: Allergic Rhinitis (ICAR:AR) has been produced as a multidisciplinary international effort. This Executive Summary highlights and summarizes the findings of the comprehensive ICAR:AR document. The ICAR:AR document was produced using previously described methodology. Specific topics were developed relating to AR. Each topic was assigned a literature review, evidence-based review (EBR), or evidence-based review with recommendations (EBRR) format as dictated by available evidence and purpose within the ICAR:AR document. Following iterative reviews of each topic, the ICAR:AR document was synthesized and reviewed by all authors for consensus. Over 100 individual topics related to AR diagnosis, pathophysiology, epidemiology, disease burden, risk factors, allergy testing modalities, treatment, and other conditions/comorbidities associated with AR were addressed in the comprehensive ICAR:AR document. Herein, the Executive Summary provides a synopsis of these findings. In the ICAR:AR critical review of the literature, several strengths were identified. In addition, significant knowledge gaps exist in the AR literature where current practice is not based on the best quality evidence; these should be seen as opportunities for additional research. The ICAR:AR document evaluates the strengths and weaknesses of the AR literature. This Executive Summary condenses these findings into a short summary. The reader is also encouraged to consult the comprehensive ICAR:AR document for a thorough description of this work. © 2018 ARS-AAOA, LLC.

  13. National briefing summaries: Nuclear fuel cycle and waste management

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

    1988-12-01

    The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities.

  14. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Lakey, L.T.; Silviera, D.J.

    1988-12-01

    The National Briefing Summaries is a compilation of publicly available information concerning the nuclear fuel cycle and radioactive waste management strategies and programs of 21 nations, including the United States and three international agencies that have publicized their activities in this field. It presents available highlight information with references that may be used by the reader for additional information. The information in this document is compiled primarily for use by the US Department of Energy and other US federal agencies and their contractors to provide summary information on radioactive waste management activities in other countries. This document provides an awareness to managers and technical staff of what is occurring in other countries with regard to strategies, activities, and facilities. The information may be useful in program planning to improve and benefit United States' programs through foreign information exchange. Benefits to foreign exchange may be derived through a number of exchange activities

  15. Technology Summary Advancing Tank Waste Retreival And Processing

    International Nuclear Information System (INIS)

    Sams, T.L.

    2010-01-01

    This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them. Hanford's underground waste storage tanks hold approximately 57 million gallons of radiochemical waste from nuclear defense production - more tank waste than any other site in the United States. In addition, the waste is uniquely complicated since it contains constituents from at least six major radiochemical processes and several lesser processes. It is intermixed and complexed more than any other waste collection known to exist in the world. The multi-faceted nature of Hanford's tank waste means that legally binding agreements in the Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement) and between the Department of Energy (DOE) and its contractors may not be met using current vitrification schedules, plans and methods. WRPS and the DOE are therefore developing, testing, and deploying technologies to ensure that they can meet the necessary commitments and complete the DOE's River Protection Project (RPP) mission within environmentally acceptable requirements. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

  16. Summary statement on fundamental geochemistry needs for nuclear waste isolation

    International Nuclear Information System (INIS)

    Giletti, B.J.

    1985-01-01

    A summary of basic geochemical research needs for high-level nuclear waste isolation is given. The focus of the paper is on the transport of alkalis and alkaline earths, particularly, Sr 90 and Cs 137 . The discussion addresses: 1)diffusion kinetics of different elements in crystalline solids; 2)transport kinetics along mineral grain boundaries; 3)natural rock systems that have undergone water circulation and isotope exchange; and 4)the techniques, feasibility, and promise of experimental efforts

  17. Session 1984-85. Radioactive waste. Minutes of evidence, Monday 17 June 1985. Nuclear Industry Radioactive Waste Executive

    International Nuclear Information System (INIS)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from the Nuclear Industry Radioactive Waste Executive, on the management and disposal of radioactive waste arising in the UK, under the headings: introduction; the structure of NIREX; the nature of radioactive waste; plans for the disposal of low and intermediate level wastes. Representatives of NIREX were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

  18. National briefing summaries: Nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

    1991-04-01

    Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy

  19. National briefing summaries: Nuclear fuel cycle and waste management

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, K.J.; Bradley, D.J.; Fletcher, J.F.; Konzek, G.J.; Lakey, L.T.; Mitchell, S.J.; Molton, P.M.; Nightingale, R.E.

    1991-04-01

    Since 1976, the International Program Support Office (IPSO) at the Pacific Northwest Laboratory (PNL) has collected and compiled publicly available information concerning foreign and international radioactive waste management programs. This National Briefing Summaries is a printout of an electronic database that has been compiled and is maintained by the IPSO staff. The database contains current information concerning the radioactive waste management programs (with supporting information on nuclear power and the nuclear fuel cycle) of most of the nations (except eastern European countries) that now have or are contemplating nuclear power, and of the multinational agencies that are active in radioactive waste management. Information in this document is included for three additional countries (China, Mexico, and USSR) compared to the prior issue. The database and this document were developed in response to needs of the US Department of Energy.

  20. Preliminary technical data summary defense waste processing facility stage 2

    International Nuclear Information System (INIS)

    1980-12-01

    This Preliminary Technical Data Summary presents the technical basis for design of Stage 2 of the Staged Defense Waste Processing Facility (DWPF). Process changes incorporated in the staged DWPF relative to the Alternative DWPF described in PTDS No. 3 (DPSTD-77-13-3) are the result of ongoing research and development and are aimed at reducing initial capital investment and developing a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it is filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material and curie balances, material and curie balance bases, and other technical data for design of Stage 2 of the DWPF. Stage 1 technical data are presented in DPSTD-80-38

  1. IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

    International Nuclear Information System (INIS)

    1997-01-01

    This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

  2. IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

  3. Annual report of the Association EURATOM-Cea 2004 (executive summary)

    International Nuclear Information System (INIS)

    2004-01-01

    Progress in fusion technology is constant over the years and this report once again highlights a number of important steps that have been accomplished in this domain. This document is the executive summary of the full annual report, summarizing activities performed by the EURATOM-Cea association. This report has been organized into 10 issues: 1) physics integration, 2) reactor vessel, 3) plasma facing components, 4) remote handling, 5) magnets structures, 6) tritium breeding blankets, 7) structural material, 8) safety and environment, 9) system study, and 10) ITER site preparation

  4. Executive summary of safeguards systems concepts for nuclear material transportation. Final report

    International Nuclear Information System (INIS)

    Baldonado, O.C.; Kevany, M.; Rodney, D.; Pitts, D.; Mazur, M.

    1977-09-01

    The U.S. Nuclear Regulatory Commission contracted with System Development Corporation to develop integrated system concepts for the safeguard of special strategic nuclear materials (SSNM), which include plutonium, uranium 233 and uranium 235 of at least 20 percent enrichment, against malevolent action during interfacility transport. This executive summary outlines the conduct and findings of the project. The study was divided into three major subtasks: (1) The development of adversary action sequences; (2) The assessment of the vulnerability of the transport of nuclear materials to adversary action; (3) The development of conceptual safeguards system design requirements to reduce vulnerabilities

  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. Annual report of the Association EURATOM-Cea 2005 (executive summary)

    International Nuclear Information System (INIS)

    2005-01-01

    Progress in fusion technology is constant over the years and this report once again highlights a number of important steps that have been accomplished in this domain. This document is the executive summary of the full annual report, summarizing activities performed by the EURATOM-Cea association. This report has been organized into 10 issues: 1) physics integration, 2) reactor vessel, 3) plasma facing components, 4) remote handling, 5) magnets structures, 6) tritium breeding blankets, 7) structural material, 8) safety and environment, 9) system study, and 10) ITER site preparation

  7. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 1. Summary: alternatives for the back of the LWR fuel cycle types and properties of LWR fuel cycle wastes projections of waste quantities; selected glossary

    International Nuclear Information System (INIS)

    1976-05-01

    Volume I of the five-volume report contains executive and technical summaries of the entire report, background information of the LWR fuel cycle alternatives, descriptions of waste types, and projections of waste quantities. Overview characterizations of alternative LWR fuel cycle modes are also included

  8. Executive summary. Session summaries

    International Nuclear Information System (INIS)

    2011-01-01

    The possibility of stopping and/or delaying the progression of a core melt accident by the use of a recovered water source or by taking benefit of specific engineered systems is taken into account in a number of PSA (Probabilistic Safety Assessment) studies. The likelihood to stop the progression of a core melt-down accident by water injection is generally considered as high in the early phase of core degradation and depends on reactor specific features, nevertheless even in later sequences, e.g. during the relocation in the lower head, cooling still can be achieved but depends on reactor specific features and the accident scenario.. Ongoing, starting and planned experimental programmes address the coolability issues in the different relevant configurations, i.e. reflooding of bundles, debris beds, molten pools and Reactor Pressure Vessel external cooling. There is still a difficulty with present models to predict reliably if reflooding during the early core degradation would or not trigger a cladding oxidation runaway. Whether this is due to deficiencies in thermal-hydraulics description or problems for taking into account the oxidation of melts is a matter of discussion. The code developments are promisingly directed towards a more mechanistic approach using a porous medium modelling able to treat the different configurations of a degraded core. Secondly, the models to describe adequately the relocation of parts of the molten core to the lower head and the debris bed formation still need further development and qualification. Their validation is expected against the results of ongoing experimental programmes. The transposition of results to the reactor scale where multi-dimensional effects are expected needs to be evaluated, all the more as larger scale experiments are probably not feasible

  9. Summaries of Idaho National Engineering Laboratory Radioecology and Ecology Program's waste management related studies

    International Nuclear Information System (INIS)

    Markham, O.D.

    1985-10-01

    The research summaries briefly describe studies concerning the activities of small mammals on and in waste disposal sites, revegetation of waste disposal sites, and contamination of wildlife by radionuclides and the spread of radionuclides by wildlife

  10. Managing commercial high-level radioactive waste: summary

    International Nuclear Information System (INIS)

    1982-04-01

    This summary presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste - an issue that has been debated over the last decade and that now appears to be moving toward major congressional action. After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue. The continued lack of final isolation facilities has raised two key problems that underlie debates about radioactive waste policy. First, some question the continued use of nuclear power until it is shown that safe final isolation for the resulting wastes can and will be accomplished, and argue that the failure to develop final isolation facilities is evidence that it may be an insoluble problem. Second, because there are no reprocessing facilities or federal waste isolation facilities to accept spent fuel, existing reactors are running out of spent fuel storage space, and by 1986 some may face a risk of shutting down for some period. Most of the 72,000 metric tons of spent fuel expected to be generated by the year 2000 will still be in temporary storage at that time. While it is possible that utilities could provide all necessary additional storage at reactor sites before existing basins are filled, some supplemental storage may be needed if there are delays in their efforts

  11. US enrichment safeguards program development activities with potential International Atomic Energy Agency safeguards applications. Part 1. Executive summaries

    International Nuclear Information System (INIS)

    Swindle, D.W. Jr.

    1984-07-01

    The most recent progress, results, and plans for future work on the US Enrichment Safeguards Program's principal development activities are summarized. Nineteen development activities are reported that have potential International Atomic Energy Agency (IAEA) safeguards applications. Part 1 presents Executive Summaries for these, each of which includes information on (1) the purpose and scope of the development activity; (2) the potential IAEA safeguards application and/or use if adopted; (3) significant development work, results, and/or conclusions to date; and where appropriate (4) future activities and plans for continued work. Development activities cover: measurement technology for limited-frequency-unannounced-access stategy inspections; integrated data acquisition system; enrichment-monitoring system; load-cell-based weighing system for UF 6 cylinder mass verifications; vapor phase versus liquid phase sampling of UF 6 cylinders; tamper-safing hardware and systems; an alternative approach to IAEA nuclear material balance verifications resulting from intermittent inspections; UF 6 sample bottle enrichment analyzer; crated waste assay monitor; and compact 252 Cf shuffler for UF 6 measurements

  12. Reducing barriers to energy efficiency in the German higher education sector. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Schleich, J.; Boede, U.

    2000-12-01

    This report describes the empirical research into barriers to energy efficiency in the German higher education (HE) sector. It is one of nine such reports in the BARRIERS project. The report contains description and analysis of six case studies of energy management in German universities. The results are analysed using the theoretical framework developed for the BARRIERS project (Sorrell et al., 2000). The report also provides brief recommendations on how these barriers to the rational use of energy (RUE) may be overcome and how energy efficiency within the sector may be improved. The results of the study for the higher education sector in Germany are summarised in this executive summary under the following headings: - Characterising the higher education sector; - Case studies of energy management in the German higher education sector; - Evidence of barriers in the German higher education sector; - The role of energy service companies in the higher education sector; - Policy implications. (orig.)

  13. Definition of technology development missions for early Space Station satellite servicing. Volume 1: Executive summary

    Science.gov (United States)

    1984-01-01

    The Executive Summary volume 1, includes an overview of both phases of the Definition of Technology Development Missions for Early Space Station Satellite Servicing. The primary purpose of Phase 1 of the Marshall Space Flight Center (MSFC) Satellite Servicing Phase 1 study was to establish requirements for demonstrating the capability of performing satellite servicing activities on a permanently manned Space Station in the early 1990s. The scope of Phase 1 included TDM definition, outlining of servicing objectives, derivation of initial Space Station servicing support requirements, and generation of the associated programmatic schedules and cost. The purpose of phase 2 of the satellite servicing study was to expand and refine the overall understanding of how best to use the manned space station as a test bed for demonstration of satellite servicing capabilities.

  14. Reducing barriers to energy efficiency in the German mechanical engineering sector. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Schleich, J.; Boede, U.

    2000-12-01

    This report describes the empirical research into barriers to energy efficiency in the German mechanical engineering (ME) sector. It is one of nine such reports in the BARRIERS project. The report contains description and analysis of four case studies of energy management in German companies in the ME sector. The results are analysed using the theoretical framework developed for the BARRIERS project. The report also provides brief recommendations on how these barriers to the rational use of energy (RUE) may be overcome and how energy efficiency within the ME sector may be improved. The results of the study for the ME sector in Germany are summarised in this executive summary under the following headings: - Characterising the mechanical engineering sector; - Case studies of energy management in the German mechanical engineering sector; - Evidence of barriers in the German mechanical engineering sector; - The role of energy service companies in the mechanical engineering sector; - Policy implications. (orig.)

  15. Developing maintainability for tokamak fusion power systems. Phase II report. Volume I: executive summary

    International Nuclear Information System (INIS)

    Fuller, G.M.; Zahn, H.S.; Mantz, H.C.; Kaletta, G.R.; Waganer, L.M.; Carosella, L.A.; Conlee, J.L.

    1978-11-01

    The purpose of this report is to identify design features of fusion power reactors which contribute to the achievement of high levels of maintainability. Volume 1, the Executive Summary, presents the progress achieved toward this objective in this phase and includes a comparison with the results of the first phase study efforts. A series of maintainability design guidelines and an improved maintenance system are defined as initial steps in developing the requirements for a maintainable tokamak fusion power system. The principle comparative studies that are summarized include the determination of the benefits of various vacuum wall arrangements, the effect of unscheduled and scheduled maintenance of the first wall/blanket, some initial investigation of maintenance required for subsystems other than the first wall/blanket, and the impact of maintenance equipment failures

  16. Global Outlook on Sustainable Consumption and Production (SCP) Policies: Taking Action Together. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Beaton, Chris; Perera, Oshani [International Institute for Sustainable Development (IISD), Winnepeg, Ontario (Canada); Arden-Clarke, Charles; Farah, Adriana Zacarias; Polsterer, Nicole [UNEP, Paris (France)

    2012-03-21

    This executive summary, which will be complemented by the full report, was developed by the United Nations Environment Programme (UNEP) with the financial support of the European Commission, The study provides a non-exhaustive review of policies and initiatives that are promoting the shift towards Sustainable Consumption and Production (SCP) patterns. It is illustrated by 56 case studies ranging from global multilateral agreements and regional strategies to specific policies and initiatives being implemented by governments, businesses and civil society organizations. The main objectives are to provide information about existing activities promoting SCP, to identify best practices, and to provide recommendations to adapt, replicate and scale up SCP policies and initiatives contributing to the overarching goal of achieving sustainable development.

  17. Reducing barriers to energy efficiency in the German brewing sector. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Schleich, J.; Boede, U.; Ostertag, K.; Radgen, P.

    2000-12-01

    This report describes the empirical research into barriers to energy efficiency in the German brewing sector. It is one of nine such reports in the BARRIERS project. The report contains description and analysis of five case studies of energy management in German breweries. The results are analysed using the theoretical framework developed for the BARRIERS project. The report also provides brief recommendations on how these barriers to the rational use of energy (RUE) may be overcome and how energy efficiency within the brewing sector may be improved. The results of the study for the brewing sector in Germany are summarised in this executive summary under the following headings: - Characterising the brewing sector; - Case studies of energy management in the German brewing sector; - Evidence of barriers in the German brewing sector; - The role of energy service companies in the brewing sector; - Policy implications. (orig.)

  18. Executive summary of the consensus document on osteoporosis in HIV-infected individuals.

    Science.gov (United States)

    Negredo, Eugenia; Domingo, Pere; Gutiérrez, Félix; Galindo, María José; Knobel, Hernando; Lozano, Fernando; Martínez, Esteban; Masiá, Mar; Polo, Rosa; Estrada, Vicente

    2018-05-01

    Osteoporosis has become an emerging comorbid condition in people living with HIV (PLWH). The increase in survival and the progressive aging of PLWH will make this complication more frequent in the near future. In addition to the traditional risk factors affecting the general population, factors directly or indirectly associated with HIV infection, including antiretroviral therapy, can increase the risk of osteoporosis. The present article is an executive summary of the document that updates the previous recommendations on the prevention and treatment of osteoporosis in PLWH. This document is intended for all professionals who work in clinical practice in the field of HIV infection. Copyright © 2017 Elsevier España, S.L.U. and Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica. All rights reserved.

  19. Executive Summary: 30th Report on Physician Assistant Educational Programs in the United States.

    Science.gov (United States)

    Huang, Lindsey M

    2015-09-01

    The purpose of this executive summary was to provide an overview of key findings from By the Numbers: 30th Report on Physician Assistant Educational Programs in the United States. The 2014 Program Survey is a Web-based survey and is administered annually to all member physician assistant (PA) program directors. This executive summary will focus on 4 of the 7 sections of the survey instrument: general, financial, program personnel, and students. The typical PA program's sponsoring institution is private and in a nonacademic health center. Most PA programs (93.0%) offer a master's degree as the primary or highest credential. The average total program budget was $2,221,751 (SD=$2,426,852). The average total resident tuition was $64,961, and the average total nonresident tuition was $75,964. Overall, 181 programs reported 1843 program faculty. Of those, 1467 were identified as core faculty and 376 were identified as adjunct faculty. A typical first-year PA student is 26 years old (SD=2.51), female (70.3%, n=5898), non-Hispanic (89.3%, n=3631), White (79.9%, n=3712), and has an overall undergraduate and science grade point average (GPA) of 3.52 (SD=0.14) and 3.47 (SD=0.16), respectively. In 2014, there were approximately 7556 graduates from 164 responding programs. By gaining a better understanding of the characteristics of PA programs and their faculty and students, policy makers can be better informed. Physician assistant educators and stakeholders are encouraged to use this information to advance and advocate for the profession.

  20. Back from the Brink: How a Bold Vision and a Focus on Resources Can Drive System Improvement. Executive Summary

    Science.gov (United States)

    Education Resource Strategies, 2015

    2015-01-01

    This executive summary describes a case study that implemented the framework School System 20/20 to examine how Lawrence Public Schools (Massachusetts) is transforming its policies and structures to better align resources with student and teacher needs. Education Resource Strategies' (ERS') School System 20/20 is a set of conditions and practices…

  1. Performance assessment of geological isolation systems for radioactive waste. Summary

    International Nuclear Information System (INIS)

    Cadelli, N.; Cottone, G.; Orlowski, S.; Bertozzi, G.; Girardi, F.; Saltelli, A.

    1988-01-01

    The report summarizes the studies undertaken in the framework of the project PAGIS of the CEC Research Programme on radioactive waste. It concerns the analysis of the safety performances on the deep disposal of vitrified high level waste in four geological options: clay, granite, salt and the sub-seabed. The report describes the selection of sites and scenarios with the corresponding data base. It outlines the methodology adopted for determining the safety level which can be achieved with an underground disposal system for HLW. Two complementary approaches have been implemented: 1) a set of deterministic calculations for evaluating the dose rates as a function of time and for analysing local sensitivity on single parameters or components of the disposal system, 2) stochastic calculations for both uncertainty and global sensitivity analyses. For each option, the report presents the most significant results, obtained from the calculations at specific sites-from both the approaches. Apart the dose rates and their expectation values, the predominant radionuclides and pathways to man are identified as well as the most sensitive parameters and phenomena. The final chapter concludes stating the feasibility of safe disposal of HLW in underground repositories. This document is one of a set of 5 reports covering a relevant project of the European Community on a nuclear safety subject having very wide interest. The five volumes are: the summary (EUR 11775-EN), the clay (EUR 11776-EN), the granite (EUR 11777-FR), the salt (EUR 11778-EN) and the sub-seabed (EUR 11779-EN)

  2. Estimating the Cold War mortgage: The 1995 Baseline Environmental Management report. Executive summary, March 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This is the first annual report on the activities and potential costs required to address the waste, contamination, and surplus nuclear facilities that are the responsibility of DOE's Environmental Management program. Of the Base Case life-cycle cost estimate of $230 billion from 1995 to 2070, 49% is waste management, 28% environmental restoration, 10% nuclear material and facility stabilization, 5% technology development, and 8% other. The top 5 sites account for 70% of the costs: Hanford 21%, Savannah River Site 21%, Rocky Flats 10%, Oak Ridge 10%, and Idaho Laboratory 8%. Assumptions include significant productivity increases, meeting current compliance requirements, and use of existing technologies. Excluded were: cleanup where no feasible cleanup technology exists (eg, nuclear explosion sites and most contaminated groundwater), cleanup of currently active facilities, naval nuclear propulsion facilities (handled by US Navy), and first 5 years of program ($23 billion). Of the alternative cases evaluated, land use has the biggest potential cost impact. Total projected environmental costs are comparable to total U.S. nuclear weapons production costs. The makeup of Volumes I and II (the latter being site summaries) are outlined briefly

  3. Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010

    International Nuclear Information System (INIS)

    Beeman, Gordon H.

    2010-01-01

    The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL's '1831' use agreement and later PNNL's '1830' prime contract with DOE in support of the WTP. In March 2001, PNNL under its '1831' use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL's support to the WTP was moved under its '1830' prime contract with DOE. Documents numbered 'PNWD-XXXX' were issued under PNNL's '1831' use agreement. Documents numbered 'PNNL-XXXX' were issued under PNNL's '1830' prime contract with DOE. The documents are sorted by fiscal year and categorized as follows: (1) Characterization; (2) HLW (High Level Waste); (3) Material Characterization; (4) Pretreatment; (5) Simulant Development; (6) Vitrification; and (7) Waste Form Qualification. This report is intended to provide a compendium of reports issued by PNWD/PNNL in support of the Waste Treatment Plant. Copies of all reports can be obtained by clicking on http://www.pnl.gov/rpp-wtp/ and downloading the .pdf file(s) to your computer.

  4. Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

    International Nuclear Information System (INIS)

    Johnson, L.J.

    1980-10-01

    Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed

  5. Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, L.J. (comp.)

    1980-10-01

    Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed.

  6. The energy accounts for the Nova Scotia genuine progress index : executive summary

    International Nuclear Information System (INIS)

    Lipp, J.; Cain, S.; Colman, R.; Parmenter, R.; Milne, K.; Mullaly, H.; Wysocki, A.

    2005-10-01

    GPI Atlantic has developed a Genuine Progress Index (GPI) involving a new measure of sustainability, wellbeing and quality of life in order to better evaluate energy supply and demand by accounting for all benefits and costs including natural capital, social capital, human capital, and conventional produced capital. The executive summary provides an energy overview and presents indicators of energy sustainability including socio-economic, health and environmental and institutional indicators. Socio-economic indicators are organized across the following 6 areas of concern: reliability, affordability, employment; energy efficiency, energy consumption; and energy production and supply. Health and environmental trends examined include carbon monoxide; nitrogen oxide; sulphur dioxide; mercury; total particulate matter; volatile organic compounds; and greenhouse gas emissions. Trends over time are assessed to determine if energy use is becoming more or less sustainable. Institutional indicators are grouped according to several areas of concern, such as leading by example; creating societal change; reporting; and evaluation. The full cost of energy was then discussed using the underlying physical indicators. It was concluded that Nova Scotia is not making sufficient progress towards sustainability in its energy system, and that the production and use of energy are the leading causes of a number of serious environmental problems. Several recommendations are made for government to lead on a number of initiatives. 4 tabs

  7. 2007-2008 activity report of the Association EURATOM-CEA (Executive summary)

    International Nuclear Information System (INIS)

    Labasse, F.

    2008-01-01

    This document is the executive summary of the full report, summarizing activities performed by EURATOM-CEA association in 2007-2008. The activities are various and have involved different issues like the study of dust generation processes and measurement techniques, ICRH antenna design for heating, integration studies inside the port-plug for diagnostics and in-situ divertor thermography, or the helium cooled lithium lead (HCLL) breeding blanket concept. Activities have been made to study the properties of the line defects governing the plastic behavior of iron base materials. Different options have been investigated for the superconducting magnet system. The measurement of in-vessel tritium inventory by laser induced breakdown spectroscopy (LIBS) technique has been investigated. 2007-2008 were also dedicated to the manufacture and complete tests of the AIA (Articulated Inspection Arm). AIA is designed to inspect divertor cassettes and the vacuum vessel first wall. Activities based on safety analysis or tests of ITER safety open issues have been carried out using several CEA facilities and expertise

  8. A Market Assessment of Residential Grid-Tied PV Systems in Colorado: Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Farhar, B.; Coburn, T.

    2000-09-13

    This is the Executive Summary of a report that presents research done in response to a decision by the Colorado Governor's Office of Energy Conservation and Management (OEC) and Colorado utility companies to consider making residential grid-tied photovoltaic (PV) systems available in Colorado. The idea was to locate homeowners willing to pay the costs of grid-tied PV (GPV) systems without batteries--$8,000 or $12,000 for a 2- or 3-kilowatt (kW) system, respectively, in 1996. These costs represented two-thirds of the actual installed cost of $6 per watt at that time and assumed the remainder would be subsidized. The National Renewable Energy Laboratory (NREL) and OEC partnered to conduct a market assessment for GPV technology in Colorado. The study encompassed both qualitative and quantitative phases. The market assessment concluded that a market for residential GPV systems exists in Colorado today. That market is substantial enough for companies to successfully market PV systems to Colorado homeowners. These homeowners appear ready to learn more, inform themselves, and actively purchase GPV systems. The present situation is highly advantageous to Colorado's institutions--primarily its state government and its utility companies, and also its homebuilders--if they are ready to move forward on GPV technology.

  9. Wound, Ostomy, and Continence Nursing: Scope and Standards of Practice, 2nd Edition: An Executive Summary.

    Science.gov (United States)

    2018-04-25

    Wound, ostomy, and continence (WOC) nursing was recognized as a nursing specialty by the American Nurses Association in February 2010, and the Society published the original scope and standards of WOC nursing practice in May 2010. The Wound, Ostomy, and Continence Nursing: Scope and Standards of Practice, 2nd Edition is the definitive resource promoting excellence in professional practice, quality care, and improved patient outcomes in WOC specialty practice. It can be used to articulate the value of WOC nurses to administrators, legislators, payers, patients, and others. The second edition also provides an overview of the scope of WOC nursing practice including a description of the specialty, the history and evolution of WOC nursing, characteristics of WOC nursing practice, and description of the trispecialty. The document describes various WOC nurse roles, populations served, practice settings, care coordination, and collaboration. Educational preparation, levels of practice within WOC specialty nursing, certification, mandate for continuous professional development, ethics, current trends, future considerations and challenges, and standards of WOC nursing practice and professional performance with competencies for each standard are provided. The purpose of this Executive Summary is to describe the process for developing the scope and standards document, provide an overview of the scope of WOC nursing practice, and list the standards of practice and professional performance along with the competencies for each level of WOC nurse provider. The original document is available from the WOCN Society's online book store (www.wocn.org).

  10. Executive Summary to EDC-2: The Endocrine Society's Second Scientific Statement on Endocrine-Disrupting Chemicals.

    Science.gov (United States)

    Gore, A C; Chappell, V A; Fenton, S E; Flaws, J A; Nadal, A; Prins, G S; Toppari, J; Zoeller, R T

    2015-12-01

    This Executive Summary to the Endocrine Society's second Scientific Statement on environmental endocrine-disrupting chemicals (EDCs) provides a synthesis of the key points of the complete statement. The full Scientific Statement represents a comprehensive review of the literature on seven topics for which there is strong mechanistic, experimental, animal, and epidemiological evidence for endocrine disruption, namely: obesity and diabetes, female reproduction, male reproduction, hormone-sensitive cancers in females, prostate cancer, thyroid, and neurodevelopment and neuroendocrine systems. EDCs such as bisphenol A, phthalates, pesticides, persistent organic pollutants such as polychlorinated biphenyls, polybrominated diethyl ethers, and dioxins were emphasized because these chemicals had the greatest depth and breadth of available information. The Statement also included thorough coverage of studies of developmental exposures to EDCs, especially in the fetus and infant, because these are critical life stages during which perturbations of hormones can increase the probability of a disease or dysfunction later in life. A conclusion of the Statement is that publications over the past 5 years have led to a much fuller understanding of the endocrine principles by which EDCs act, including nonmonotonic dose-responses, low-dose effects, and developmental vulnerability. These findings will prove useful to researchers, physicians, and other healthcare providers in translating the science of endocrine disruption to improved public health.

  11. WOCN 2016 Guideline for Prevention and Management of Pressure Injuries (Ulcers): An Executive Summary.

    Science.gov (United States)

    This article provides an executive summary of recommendations from the 2016 Guideline for Prevention and Management of Pressure Ulcers (Injuries) published by the Wound, Ostomy and Continence Nurses Society (WOCN). It presents an overview of the process used to update and develop the guideline, and lists the specific recommendations from the guideline for assessment, prevention, and treatment of pressure injuries. The guideline is a resource for physicians, nurses, therapists, and other healthcare professionals who work with adults who have/or are at risk for pressure injuries. The full text of the published guideline, which includes the available evidence supporting the recommendations and a complete reference list, is available from the Wound, Ostomy and Continence Nurses Society, 1120 Rt 73, Ste 200, Mount Laurel, NJ 08054; Web site: www.wocn.org. Refer to the Supplemental Digital Content (http://links.lww.com/JWOCN/A38) associated with this article for a complete reference list for the guideline. The guideline has been accepted for inclusion in the National Guideline Clearinghouse (www.guideline.gov/).

  12. MOD-5A wind turbine generator program design report: Volume 1: Executive Summary

    Science.gov (United States)

    1984-01-01

    The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator covering work performed between July 1980 and June 1984 is discussed. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 1, the Executive Summary, summarizes all phases of the MOD-5A program. The performance and cost of energy generated by the MOD-5A are presented. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation, power generation, and control and instrumentation subsystems - is described briefly. The early phases of the MOD-5A program, during which the design was analyzed and optimized, and new technologies and materials were developed, are discussed. Manufacturing, quality assurance, and safety plans are presented. The volume concludes with an index of volumes 2 and 3.

  13. Lower Flathead System Fisheries Study, Executive Summary, Volume I, 1983-1987 Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Cross, David; DosSantos, Joseph M.

    1988-06-01

    This Executive Summary, Volume I, of the lower Flathead System Fisheries Study Final Report, was prepared to provide a study overview for persons who are not fisheries scientists. The contents provide an introduction to the study and its objectives, a short description of the study area, a discussion of the major findings and conclusions of the study, and the description of fisheries management alternatives available to managers of the lower Flathead system. Technical reports were prepared for those portions of the study dealing with the lower Flathead River and its tributaries, Volume II, and the South Bay of Flathead Lake, Volume III. The annual hydrographic regime of the Flathead system, consisting of upper rivers, lake and lower river, has been modified by the construction and operation of two major hydroelectric facilities, Hungry Horse Dam on the south fork Flathead River and Kerr Dam at the outlet of Flathead Lake. The modified hydrographic regime has resulted in significant impacts to kokanee (Oncorhynchus nerka) and several species of trout. Kerr Dam, closed in 1938, controls Flathead Lake levels between 878.7 m (2883 ft) and 881.8 m (2893 ft) and discharges into the lower Flathead River. Kerr Dam is a 63.4 m (208 ft) high concrete arch structure located 7.2 km (4.5 miles) downstream from the outlet of Flathead Lake. The facility is used by Montana Power Company primarily for system frequency load control with some use for low level base load. 77 refs., 5 figs.

  14. Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste

    Energy Technology Data Exchange (ETDEWEB)

    R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

    2010-02-01

    This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

  15. Radioactive waste disposal from Austria. Summary of experts' discussion

    International Nuclear Information System (INIS)

    Benischek, I.; Dincmen, T.; Ehrenstrasser, G.; Komurka, M.; Krejsa, P.; Kudlicza, P.; Schreiber, R.

    1992-06-01

    The aims of this report are: (1) A summary of relevant decision bases (2) A summary of comparative evaluation of ground-level and underground deposition (3) Recommendations for further investigations and on the acceptance. (authors, translated by Quittner)

  16. Pre-feasibility workbook for bioenergy projects in eastern Ontario : executive summary

    International Nuclear Information System (INIS)

    Rees, C.; Bradley, D.; DeYoe, D.

    2007-03-01

    This summary provided details of a pre-feasibility workbook designed to assist communities and developers in better understanding bioenergy challenges and opportunities in Ontario. The workbook examined issues related to the conversion of biomass through thermal conversion technologies and focused on combined heat and power projects that used forest and agricultural biomass in order to produce up to 10 MW of electricity under the Ontario Renewable Standard Offer Program. As part of the program, new generators of no more than 10 MW are paid a base rate of 11 cents per kWh and an additional 3.52 cents per kWh for on-peak production. The workbook was comprised of a review of biomass supply in the eastern Ontario region and included both forested and abandoned farm lands. A base-line financial analysis was included to assess the feasibility of projects using combustion, pyrolysis, and gasification technologies. Biomass sources in the region included mill residue, harvest waste, biomass mortality from natural events, stand management, and standing timber. Key elements required for parties interested in considering a bioenergy business initiative were also included

  17. Executive summary for the Weldon Spring Site Environmental Report for calendar year 1991

    International Nuclear Information System (INIS)

    1992-07-01

    This report is the sixth in a series of annual reports produced by the Weldon Spring Site Remedial Action Project (WSSRAP) since 1986. It reports the results of a comprehensive, year-round program to monitor the impact of the Weldon Spring site (WSS) on the surrounding region's groundwater and surface waters; air quality; vegetation and wildlife; and, through these multiple pathways, the potential for exposure to receptor human populations. Information is also presented on the environmental monitoring quality assurance program, waste management activities, audits and reviews, and special environmental studies. Data are included for both the Weldon Spring Chemical Plant and raffinate pits and the Weldon Spring Quarry. Based on the consistent exercise of quality assurance in both standard operating procedures and quality control sample collection, the WSSRAP asserts that the data presented in the WSS Environmental Report for Calendar Year 1991 accurately reflect the environmental conditions monitored at the WSS. This report presents narratives, summaries, and conclusions on environmental monitoring at the WSS and surrounding vicinity properties for the entire 1991 monitoring year. During 1991 the WSSRAP also published quarterly data reports, wherein all routine monitoring data were tabulated and presented quarterly to allow the public to review the data in a timely fashion prior to issuance of the annual report

  18. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Lee

    2005-09-15

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  19. DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

    International Nuclear Information System (INIS)

    Lee, T.A.

    2005-01-01

    The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

  20. Market surveillance panel monitoring report on the IMO-administered electricity markets : Executive summary

    International Nuclear Information System (INIS)

    2002-01-01

    The electricity market in Ontario was opened on May 1, 2002. This document provides the executive summary for the first monitoring report prepared by the Market Surveillance Panel covering the period May to August 2002. In the introductory chapter of the main report, explanations are provided on why competition, when effective, benefits consumers, as well as touching on the conditions for the design of an effective competitive electricity market with special emphasis on the electricity market in Ontario and its operations. For the period under review, the report presents a description and analysis of the activities and operations of the Independent Electricity Market Operator (IMO)-administered markets (focus on energy markets). Rising costs for hydroelectric power and very high temperatures combined in July and August resulting in record levels of demand. It became apparent that the province relies on imports to satisfy demand. The figures reveal that reliability in July and August depended on imports 21 per cent of the time. A serious shortage of generating capacity exists in Ontario and steps to rectify the situation should be initiated to ensure reliability of electricity supply for next summer. Prospective entrants in the electricity market in Ontario may not be receiving clear, credible and consistent signals. Effective use of existing or potential transmission capacity may not always be made by the system. The lowering of consumption by consumers is difficult since consumers are not properly equipped, resulting in their lack of power to discipline price increases from suppliers. The future evolution of the market must be planned and measures implemented to enhance the effectiveness of competition. The incentives effects for some aspects of the market design do not completely satisfy the Panel

  1. Executive summary of the Diagnostic Criteria for Temporomandibular Disorders for clinical and research applications.

    Science.gov (United States)

    Schiffman, Eric; Ohrbach, Richard

    2016-06-01

    In this executive summary, the authors describe a protocol for assessing patients with temporomandibular disorder (TMD). It is based on the Diagnostic Criteria for Temporomandibular Disorders (DC/TMD) for clinical and research applications. The DC/TMD was developed using published Axis I physical diagnoses for the most common TMDs. Axis I diagnostic criteria were derived from pertinent clinical TMD signs and symptoms. Axis II consists of psychosocial and behavioral questionnaires already in the public domain. A panel of experts vetted and modified the Axis I and Axis II diagnostic protocols. Recommended changes were assessed for diagnostic accuracy by using the Validation Project's data set, which formed the basis for the development of the DC/TMD. Axis I diagnostic criteria for TMD pain-related disorders have acceptable validity and provide definitive diagnoses for pain involving the temporomandibular joint (TMJ) and masticatory muscles. Axis I diagnostic criteria for the most common TMJ intra-articular disorders are appropriate for screening purposes only. A definitive diagnosis for TMJ intra-articular disorders requires computed tomography or magnetic resonance imaging. Axis II questionnaires provide valid assessment of psychosocial and behavioral factors that can affect management of TMD. The DC/TMD provides a questionnaire for the pain history in conjunction with validated clinical examination criteria for diagnosing the most common TMDs. In addition, it provides Axis II questionnaires for assessing psychosocial and behavioral factors that may contribute to the onset and perpetuation of the patient's TMD. The DC/TMD is appropriate for use in clinical and research settings to allow for a comprehensive assessment of patients with TMD. Copyright © 2016 American Dental Association. Published by Elsevier Inc. All rights reserved.

  2. DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization

    Energy Technology Data Exchange (ETDEWEB)

    T.A. Lee

    2006-02-06

    This data quality objective (DQO) summary report provides the results of the DQO process conducted for waste characterization activities for the 324 and 327 Building hot cells decommission, deactivate, decontaminate, and demolish activities. This DQO summary report addresses the systems and processes related to the hot cells, air locks, vaults, tanks, piping, basins, air plenums, air ducts, filters, an adjacent elements that have high dose rates, high contamination levels, and/or suspect transuranic waste, which will require nonstandard D4 techniques.

  3. Summary of BNL studies regarding commercial mixed waste

    International Nuclear Information System (INIS)

    Bowerman, B.S.; Kempf, C.R.; MacKenzie, D.R.; Siskind, B.; Piciulo, P.L.

    1986-09-01

    Based on BNL's study it was concluded that there are low-level radioactive wastes (LLWs) which contain chemically hazardous components. Scintillation liquids may be considered an EPA listed hazardous waste and are, therefore, potential mixed wastes. Since November 1985, no operating LLW disposal site will accept these wastes for disposal. Unless such wastes contain de minimis quantities of radionuclides, they cannot be disposed of at an EPA permitted site. Currently generators of liquid scintillation wastes can ship de minimis wastes to be burned at commercial facilities. Oil wastes may also eventually be an EPA listed waste and thus will have to be considered a potential radioactive mixed waste unless NRC establishes de minimis levels of radionuclides below which oils can be managed as hazardous wastes. Regarding wastes containing lead metal there is some question as to the extent of the hazard posed by lead disposed in a LLW burial trench. Chromium-containing wastes would have to be tested to determine whether they are potential mixed wastes. There may be other wastes that are mixed wastes; the responsibility for determining this rests with the waste generator. While management options for handling potential mixed wastes are available, there is limited regulatory guidance for generators. BNL has identified and evaluated a variety of treatment options for the management of potential radioactive mixed wastes. The findings of that study showed that application of a management option with the purpose of addressing EPA concerns can, at the same time, address stabilization and volume reduction concerns of NRC. 6 refs., 1 tab

  4. 1995 solid waste 30-year characteristics volume summary

    International Nuclear Information System (INIS)

    Templeton, K.J.; DeForest, T.J.; Rice, G.I.; Valero, O.J.

    1995-10-01

    The Hanford Site has been designated by the US Department of Energy (DOE) to store, treat, and dispose of solid waste received from both onsite and offsite generators. This waste is currently or planned to be generated from ongoing operations, maintenance and deactivation activities, decontamination and decommissioning (D ampersand D) of facilities, and environmental restoration (ER) activities. This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), describes the characteristics of the waste to be shipped to Hanford's SWOC. The physical waste forms and hazardous constituents are described for the low-level mixed waste (LLMW) and the transuranic - transuranic mixed waste (TWunderscoreTRUM)

  5. Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

    International Nuclear Information System (INIS)

    Hladek, K.L.

    1996-01-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995

  6. Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

    Energy Technology Data Exchange (ETDEWEB)

    Hladek, K.L.

    1996-06-06

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995.

  7. Waste Treatment Plant Support Program: Summaries of Reports Produced During Fiscal Years 1999-2010

    Energy Technology Data Exchange (ETDEWEB)

    Beeman, Gordon H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2010-08-01

    The Waste Treatment Plant (WTP) being built on the U.S. Department of Energy (DOE) Hanford Site will be the largest chemical processing plant in the United States. Bechtel National Inc. (BNI) is the designer and constructor for the WTP. The Pacific Northwest National Laboratory (PNNL) has provided significant research and testing support to the WTP. This report provides a summary of reports developed initially under PNNL’s “1831” use agreement and later PNNL’s “1830” prime contract with DOE in support of the WTP. In March 2001, PNNL under its “1831” use agreement entered into a contract with BNI to support their research and testing activities. However, PNNL support to the WTP predates BNI involvement. Prior to March 2001, PNNL supported British Nuclear Fuels Ltd. in its role as overall designer and constructor. In February 2007, execution of PNNL’s support to the WTP was moved under its “1830” prime contract with DOE.

  8. Tank waste remediation system retrieval and disposal mission initial updated baseline summary

    International Nuclear Information System (INIS)

    Swita, W.R.

    1998-01-01

    This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

  9. Hanford Site Environment Safety and Health (ES and H) FY 1999 and FY 2000 Execution Commitment Summary

    Energy Technology Data Exchange (ETDEWEB)

    REEP, I.E.

    1999-12-01

    All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the S&H resources that support these activities. The fiscal year (FY) 1999 and 2000 information (Sieracki 1999) and data contained in the ''Hanford Site Environment, Safety and Health Fiscal Year 2001 Budget-Risk Management Summary'' (RL 1999) were the basis for preparing this report. Fiscal year 2000 finding of Office of Environmental Management (EM) and Office of Nuclear Energy, Science and Technology (NE) activities is based on the President's budget of $1,065.1 million and $28.0 million, plus $2.7 million carryover finding, respectively, as of October 31, 1999. Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2002 ES&H Budget-Risk Management Summary to be issued in May 2000. This report provides the end-of-year status of FY 1999 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2000 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H ''Guidance for FY200l Budget Formulations and Execution'' (DOE 1999).

  10. On the development of a theory of traveler attitude-behavior interrelationships. Volume 3 : executive summary : overview of methods, results, and conclusions

    Science.gov (United States)

    1978-08-01

    The executive summary of this Final Report offers an overview of : methods, results, and conclusions which support the development of a : theory of traveler attitude-behavior interrelationships. Such a theory : will be useful in the design of transpo...

  11. Energy Audit for Moncrief Army Community Hospital, Oliver Dental Clinic, Caldwell Dental Clinic, and Hagen Dental Clinic, Volume 1 - Executive Summary

    National Research Council Canada - National Science Library

    1987-01-01

    This is the Executive Summary of an Energy Engineering Analysis Program (EEAP) Study that was conducted at Moncrief Army Community Hospital, Fort Jackson, South Carolina, by the firm of BENATECH, INC. The Scope of Work...

  12. Waste management for Shippingport Station Decommissioning Project: Extended summary

    International Nuclear Information System (INIS)

    Mullee, G.R.; Schulmeister, A.R.

    1987-01-01

    The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP

  13. Clinical Practice Guideline: Improving Nasal Form and Function after Rhinoplasty Executive Summary.

    Science.gov (United States)

    Ishii, Lisa E; Tollefson, Travis T; Basura, Gregory J; Rosenfeld, Richard M; Abramson, Peter J; Chaiet, Scott R; Davis, Kara S; Doghramji, Karl; Farrior, Edward H; Finestone, Sandra A; Ishman, Stacey L; Murphy, Robert X; Park, John G; Setzen, Michael; Strike, Deborah J; Walsh, Sandra A; Warner, Jeremy P; Nnacheta, Lorraine C

    2017-02-01

    Objective Rhinoplasty, a surgical procedure that alters the shape or appearance of the nose while preserving or enhancing the nasal airway, ranks among the most commonly performed cosmetic procedures in the United States, with >200,000 procedures reported in 2014. While it is difficult to calculate the exact economic burden incurred by rhinoplasty patients following surgery with or without complications, the average rhinoplasty procedure typically exceeds $4000. The costs incurred due to complications, infections, or revision surgery may include the cost of long-term antibiotics, hospitalization, or lost revenue from hours/days of missed work. The resultant psychological impact of rhinoplasty can also be significant. Furthermore, the health care burden from psychological pressures of nasal deformities/aesthetic shortcomings, surgical infections, surgical pain, side effects from antibiotics, and nasal packing materials must also be considered for these patients. Prior to this guideline, limited literature existed on standard care considerations for pre- and postsurgical management and for standard surgical practice to ensure optimal outcomes for patients undergoing rhinoplasty. The impetus for this guideline is to utilize current evidence-based medicine practices and data to build unanimity regarding the peri- and postoperative strategies to maximize patient safety and to optimize surgical results for patients. Purpose The primary purpose of this guideline executive summary is to provide evidence-based recommendations for clinicians who either perform rhinoplasty or are involved in the care of a rhinoplasty candidate, as well as to optimize patient care, promote effective diagnosis and therapy, and reduce harmful or unnecessary variations in care. The target audience is any clinician or individual, in any setting, involved in the management of these patients. The target patient population is all patients aged ≥15 years. The guideline is intended to focus on

  14. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Mangement Program

    International Nuclear Information System (INIS)

    1983-05-01

    This is the first quarterly update of Radioactive Waste Management: A Summary of State Laws and Administration. Because states have been very active on waste management issues, the whole report is being reissued in this update. It covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. The administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs and a legislative contact. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and their disposition. In general, the information in this report is accurate as of 15 April 1983

  15. Baseline tests for arc melter vitrification of INEL buried wastes. Volume 1: Facility description and summary data report

    International Nuclear Information System (INIS)

    Oden, L.L.; O'Connor, W.K.; Turner, P.C.; Soelberg, N.R.; Anderson, G.L.

    1993-01-01

    This report presents field results and raw data from the Buried Waste Integrated Demonstration (BWID) Arc Melter Vitrification Project Phase 1 baseline test series conducted by the Idaho National Engineering Laboratory (INEL) in cooperation with the U.S. Bureau of Mines (USBM). The baseline test series was conducted using the electric arc melter facility at the USBM Albany Research Center in Albany, Oregon. Five different surrogate waste feed mixtures were tested that simulated thermally-oxidized, buried, TRU-contaminated, mixed wastes and soils present at the INEL. The USBM Arc Furnace Integrated Waste Processing Test Facility includes a continuous feed system, the arc melting furnace, an offgas control system, and utilities. The melter is a sealed, 3-phase alternating current (ac) furnace approximately 2 m high and 1.3 m wide. The furnace has a capacity of 1 metric ton of steel and can process as much as 1,500 lb/h of soil-type waste materials. The surrogate feed materials included five mixtures designed to simulate incinerated TRU-contaminated buried waste materials mixed with INEL soil. Process samples, melter system operations data and offgas composition data were obtained during the baseline tests to evaluate the melter performance and meet test objectives. Samples and data gathered during this program included (a) automatically and manually logged melter systems operations data, (b) process samples of slag, metal and fume solids, and (c) offgas composition, temperature, velocity, flowrate, moisture content, particulate loading and metals content. This report consists of 2 volumes: Volume I summarizes the baseline test operations. It includes an executive summary, system and facility description, review of the surrogate waste mixtures, and a description of the baseline test activities, measurements, and sample collection. Volume II contains the raw test data and sample analyses from samples collected during the baseline tests

  16. Mixed waste characterization, treatment, and disposal focus area. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning

  17. Mixed waste characterization, treatment, and disposal focus area. Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning.

  18. Summary of tank waste physical properties at the Hanford Site

    International Nuclear Information System (INIS)

    Nguyen, Q.H.

    1994-04-01

    This report summarizes the physical parameters measured from Hanford Site tank wastes. Physical parameters were measured to determine the physical nature of the tank wastes to develop simulants and design in-tank equipment. The physical parameters were measured mostly from core samples obtained directly below tank risers. Tank waste physical parameters were collected through a database search, interviewing and selecting references from documents. This report shows the data measured from tank waste but does not describe how the analyses wee done. This report will be updated as additional data are measured or more documents are reviewed

  19. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Management Program. Revision 6

    International Nuclear Information System (INIS)

    1985-12-01

    This is the sixth update of ''Radioactive Waste Management: A Summary of State Laws and Administration.'' It completely replaces the fifth update (15 September 1984). The updated report covers low-level radioactive waste compacts, and the administration, the legislature and the laws related to radioactive waste management in each of the fifty states. The report is organized by low-level waste compact regions. Each section begins with a description of the low-level waste compact, followed by reports on each state within the region. There are also sections for states which have made plans to dispose of waste independently of a compact, and for those states which have not yet declared their intentions. The report on each compact is divided into four sections: Cover Page, Chair Organization, State Delegations, and Compact

  20. Richland Operations (DOE-RL) Environmental Safety Health (ES and H) FY 2000 and FY 2001 Execution Commitment Summary

    Energy Technology Data Exchange (ETDEWEB)

    REEP, I.E.

    2000-12-01

    All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the Safety and Health (S&H) resources that support these activities. The fiscal year (FY) 2000 and 2001 information and data contained in the Richland Operations Environment, Safefy and Health Fiscal Year 2002 Budget-Risk Management Summary (RL 2000a) were the basis for preparing this report. Fiscal year 2001 activities are based on the President's Amended Congressional Budget Request of $689.6 million for funding Ofice of Environmental Management (EM) $44.0 million for Fast Flux Test Facility standby less $7.0 million in anticipated DOE, Headquarters holdbacks for Office of Nuclear Energy, Science and Technology (NE); and $55.3 million for Safeguards and Security (SAS). Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2003 ES&H Budget-Risk Management Summary to be issued in May 2001. This report provides the end-of-year status of FY 2000 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2001 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H guidance contained in the FY 2002 Field Budget Call (DOE 2000).

  1. Waste isolation safety assessment program. Summary of FY-77 progress

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Greenborg, J.; Stottlemyre, J.A.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.

    1977-11-01

    Objective is to provide long-term safety information for the National Waste Terminal Storage Program. Work in FY 77 supported the development of the generic assessment method (release scenario analysis, release consequence analysis) and of the generic data base (waste form release rate data, radionuclide geochemical interaction data)

  2. Waste dislodging and conveyance testing summary and conclusions to date

    International Nuclear Information System (INIS)

    Rinker, M.W.; Hatchell, B.K.; Mullen, O.D.

    1994-09-01

    This document summarizes recent work performed by the Waste Dislodging and Conveyance technology development program to provide assistance with the retrieval of wastes from the Hanford single-shell tanks (SSTs). This work is sponsored by the Underground Storage Tank-Integrated Demonstration (UST-ID) Office with the U.S. Department of Energy (DOE) Office of Technology Development. A baseline technology of high-pressure water-jet dislodging and pneumatic conveyance integrated as a scarifier is proposed as a means of retrieval. The tests and studies described were performed to demonstrate that at least one robust technology exists that could be effectively used with low water-addition arm-based systems. These results are preliminary and do not represent an optimized baseline. The Waste Dislodging and Conveyance work thus far has demonstrated that waterjet mobilization and air conveyance can mobilize and convey SST waste simulants at the target rates while operating within the space envelope and the dynamic loading constraints of deployment devices. The recommended technologies are well proven in industrial applications and are quite robust, yet lightweight and relatively benign to the retrieval environment. The baseline approach has versatility to continuously dislodge and convey a broad range of waste forms, from hard wastes to soft sludge wastes. The approach also has the major advantage of being noncontact with the waste surface under normal operation

  3. Waste Tank Summary Report for Month Ending February 28 2001

    International Nuclear Information System (INIS)

    HANLON, B.M.

    2001-01-01

    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 63 smaller miscellaneous underground storage tanks and special 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 435.I (DOE-RL, July 1999, Radioactive Waste Management, U.S. Department of Energy-Richland Operations Office, Richland, Washington) requiring the reporting of waste inventories and space utilization for Hanford Tank Farm tanks

  4. WASTE TANK SUMMARY REPORT FOR MONTH ENDING 01/2004

    International Nuclear Information System (INIS)

    HANLON, B.M.

    2004-01-01

    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 60 smaller miscellaneous underground storage tanks and special 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 Order 435.1 (DOE-HQ, August 28,2001, Radioactive Waste Management, U.S. Department of Energy-Washington, D.C.) requiring the reporting of waste inventories and space utilization for the Hanford Site Tank Farm tanks

  5. Assessment of research needs for advanced heterogeneous catalysts for energy applications. Final report: Volume 1, Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Mills, G.A.

    1994-04-01

    This report assesses the direction, technical content, and priority of research needs judged to provide the best chance of yielding new and improved heterogeneous catalysts for energy-related applications over a period of 5--20 years. It addresses issues of energy conservation, alternate fuels and feedstocks, and the economics and applications that could alleviate pollution from energy processes. Recommended goals are defined in 3 major, closely linked research thrusts: catalytic science, environmental protection by catalysis, and industrial catalytic applications. This volume provides a comprehensive executive summary, including research recommendations.

  6. Inventory of Federal energy-related environment and safety research for FY 1978. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1979-12-01

    The FY 1978 Federal Inventory is a compilation of 3225 federally funded energy-related environmental and safety reserch projects. It consists of three volumes: an executive summary providing an overview of the data (Volume I), a catalog listing each Inventory project followed by series of indexes (Volume II), and an interactive terminal guide giving instructions for on-line data retrieval (Volume III). Volume I reviews the inventory data as a whole and also within each of three major categories: biomedical and environmental research, environmental control technology research, and operational safety research

  7. Large Deployable Reflector (LDR) system concept and technology definition study. Volume 1: Executive summary, analyses and trades, and system concepts

    Science.gov (United States)

    Agnew, Donald L.; Jones, Peter A.

    1989-01-01

    A study was conducted to define reasonable and representative large deployable reflector (LDR) system concepts for the purpose of defining a technology development program aimed at providing the requisite technological capability necessary to start LDR development by the end of 1991. This volume includes the executive summary for the total study, a report of thirteen system analysis and trades tasks (optical configuration, aperture size, reflector material, segmented mirror, optical subsystem, thermal, pointing and control, transportation to orbit, structures, contamination control, orbital parameters, orbital environment, and spacecraft functions), and descriptions of three selected LDR system concepts. Supporting information is contained in appendices.

  8. CanVasc recommendations for the management of antineutrophil cytoplasm antibody (ANCA)-associated vasculitides - Executive summary.

    Science.gov (United States)

    McGeoch, Lucy; Twilt, Marinka; Famorca, Leilani; Bakowsky, Volodko; Barra, Lillian; Benseler, Susan; Cabral, David A; Carette, Simon; Cox, Gerald P; Dhindsa, Navjot; Dipchand, Christine; Fifi-Mah, Aurore; Goulet, Michele; Khalidi, Nader; Khraishi, Majed M; Liang, Patrick; Milman, Nataliya; Pineau, Christian A; Reich, Heather; Samadi, Nooshin; Shojania, Kam; Taylor-Gjevre, Regina; Towheed, Tanveer E; Trudeau, Judith; Walsh, Michael; Yacyshyn, Elaine; Pagnoux, Christian

    2015-01-01

    The Canadian Vasculitis research network (CanVasc) is composed of physicians from different medical specialties, including rheumatology and nephrology and researchers with expertise in vasculitis. One of its aims was to develop recommendations for the diagnosis and management of antineutrophil cytoplasm antibody (ANCA)-associated vasculitides in Canada. This executive summary features the 19 recommendations and 17 statements addressing general AAV diagnosis and management, developed by CanVasc group based on a synthesis of existing international guidelines, other published supporting evidence and expert consensus considering the Canadian healthcare context.

  9. CanVasc Recommendations for the Management of Antineutrophil Cytoplasm Antibody (ANCA-Associated Vasculitides – Executive Summary

    Directory of Open Access Journals (Sweden)

    Lucy McGeoch

    2015-11-01

    Full Text Available The Canadian Vasculitis research network (CanVasc is composed of physicians from different medical specialties, including rheumatology and nephrology and researchers with expertise in vasculitis. One of its aims was to develop recommendations for the diagnosis and management of antineutrophil cytoplasm antibody (ANCA-associated vasculitides in Canada. This executive summary features the 19 recommendations and 17 statements addressing general AAV diagnosis and management, developed by CanVasc group based on a synthesis of existing international guidelines, other published supporting evidence and expert consensus considering the Canadian healthcare context.

  10. A summary of available information on ferrocyanide tank wastes

    International Nuclear Information System (INIS)

    Burger, L.L.; Strachan, D.M.; Reynolds, D.A.; Schulz, W.W.

    1991-10-01

    Ferrocyanide wastes were generated at the Hanford site during the mid to late 1950s to make more tank space available for the storage of high level nuclear waste. The ferrocyanide process was developed as a method of removing 137 Cs from existing waste solutions and from process solutions that resulted from the recovery of valuable uranium in waste tanks. During the coarse of the research associated with the ferrocyanide process, it was discovered that ferrocyanide materials when mixed with NaNO 3 and/or NaNO 2 exploded. This chemical reactivity became an issue in the 1980s when the safety associated with the storage of ferrocyanide wastes in Hanford tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety associated with these wastes and the current research and waste management programs. Over the past three years, numerous explosive test have been carried out using milligram quantities of cyanide compounds. These tests provide information on the nature of possible tank reactions. On heating a mixture of ferrocyanide and nitrate or nitrite, an explosive reaction normally begins at about 240 degrees C, but may occur well below 200 degrees C in the presence of catalysts or organic compounds that may act as initiators. The energy released is highly dependent on the course of the reaction. Three attempts to model hot spots in local areas of the tanks indicate a very low probability of having a hot spot large enough and hot enough to be of concern. The main purpose of this document is to inform the members of the Tank Waste Science Panel of the background and issues associated with the ferrocyanide wastes. Hopefully, this document fulfills similar needs outside of the framework of the Tank Waste Science Panel. 50 refs., 9 figs., 7 tabs

  11. Assessment of display performance for medical imaging systems: Executive summary of AAPM TG18 report

    International Nuclear Information System (INIS)

    Samei, Ehsan; Badano, Aldo; Chakraborty, Dev

    2005-01-01

    Digital imaging provides an effective means to electronically acquire, archive, distribute, and view medical images. Medical imaging display stations are an integral part of these operations. Therefore, it is vitally important to assure that electronic display devices do not compromise image quality and ultimately patient care. The AAPM Task Group 18 (TG18) recently published guidelines and acceptance criteria for acceptance testing and quality control of medical display devices. This paper is an executive summary of the TG18 report. TG18 guidelines include visual, quantitative, and advanced testing methodologies for primary and secondary class display devices. The characteristics, tested in conjunction with specially designed test patterns (i.e., TG18 patterns), include reflection, geometric distortion, luminance, the spatial and angular dependencies of luminance, resolution, noise, glare, chromaticity, and display artifacts. Geometric distortions are evaluated by linear measurements of the TG18-QC test pattern, which should render distortion coefficients less than 2%/5% for primary/secondary displays, respectively. Reflection measurements include specular and diffuse reflection coefficients from which the maximum allowable ambient lighting is determined such that contrast degradation due to display reflection remains below a 20% limit and the level of ambient luminance (L amb ) does not unduly compromise luminance ratio (LR) and contrast at low luminance levels. Luminance evaluation relies on visual assessment of low contrast features in the TG18-CT and TG18-MP test patterns, or quantitative measurements at 18 distinct luminance levels of the TG18-LN test patterns. The major acceptable criteria for primary/secondary displays are maximum luminance of greater than 170/100 cd/m 2 , LR of greater than 250/100, and contrast conformance to that of the grayscale standard display function (GSDF) of better than 10%/20%, respectively. The angular response is tested to

  12. Rainwater Wildlife Area Management Plan Executive Summary : A Columbia Basin Wildlife Mitigation Project.

    Energy Technology Data Exchange (ETDEWEB)

    Childs, Allen B.

    2002-02-01

    This Executive Summary provides an overview of the Draft Rainwater Wildlife Area Management Plan. The comprehensive plan can be viewed on the Confederated Tribes of the Umatilla Indian Reservation (CTUIR) website at: www.umatilla.nsn.us or requested in hard copy from the CTUIR at the address below. The wildlife area was established in September 1998 when the CTUIR purchased the Rainwater Ranch through Bonneville Power Administration (BPA) for purposes of fish and wildlife mitigation for the McNary and John Day dams. The Management Plan has been developed under a standardized planning process developed by BPA for Columbia River Basin Wildlife Mitigation Projects (See Guiding Policies Section below). The plan outlines the framework for managing the project area, provides an assessment of existing conditions and key resource issues, and presents an array of habitat management and enhancement strategies. The plan culminates into a 5-Year Action Plan that will focus management actions and prioritize funding during the 2002-2006 planning period. Since acquisition of the property in late 1998, the CTUIR has conducted an extensive baseline resource assessment in preparation for the management plan, initiated habitat restoration in the Griffin Fork drainage to address road-related resource damage caused by roads constructed for forest practices and an extensive flood event in 1996, and initiated infrastructure developments associated with the Access and Travel Management Plan (i.e., installed parking areas, gates, and public information signs). In addition to these efforts, the CTUIR has worked to set up a long-term funding mechanism with BPA through the NPPC Fish and Wildlife Program. The CTUIR has also continued to coordinate closely with local and state government organizations to ensure consistency with local land use laws and maintain open lines of communication regarding important issues such as big game hunting, tribal member exercise of treaty rights, and public

  13. FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Templeton, K.J.

    1996-05-23

    For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

  14. FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

    International Nuclear Information System (INIS)

    Templeton, K.J.

    1996-01-01

    For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company's Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division's treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

  15. 2nd FSC Workshop - Executive Summary and International Perspective, Stakeholder Involvement and Confidence in the Process of Decision-making for the Disposal of Spent Nuclear Fuel in Finland, 15-16 November 2001, Turku, Finland

    International Nuclear Information System (INIS)

    2002-01-01

    The 2. FSC workshop examined 'Stakeholder Involvement and Confidence in the Process of Decision-making for the Disposal of Spent Nuclear Fuel in Finland'. By gathering Finnish Stakeholders, those who expressed favour and opposition, as well as observer-participants from the other NEA/FSC countries, a joint reflection on a complex reality was achieved from which general conclusions can also be drawn concerning stakeholder involvement in the long-term management of radioactive waste. 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 Executive 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

  16. Summary and evaluation of nuclear waste forms. Chapter 12

    International Nuclear Information System (INIS)

    Lutze, W.; Ewing, R.C.

    1988-01-01

    In this chapter data are compiled from the foregoing contributed chapters into tables. In a few cases additional more recent data not found in the chapters have been included in the tables. The following waste form data are summarized: physical properties, chemical durability, radiation effects and the status of processing techniques. In addition important aspects of the comparison of waste forms and the response of waste forms (glass and ceramic) to corrosion and radiation effects are discussed. (author). 119 refs.; 6 figs.; 5 tabs

  17. Summary of 4th general plan of radioactive wastes

    International Nuclear Information System (INIS)

    Veganzones, A.

    1995-01-01

    The last 9th of December 1994 the Council of Ministries approved the Fourth General Plan of Radioactive Waste (PGRR). The Fourth Plan actualizes former texts taking into into account new circumstances, both technical and economical, affecting radioactive waste. Some of the steps that conform the global waste management process have been revised on the light of the Spanish experience but also considering the evolution and trends in other countries. In this work some of the most important aspects included in the Fourth general Plan are overviewed. (Author)

  18. Compendium of Executive Summaries from the Maglev System Concept Definition. Final Reports

    National Research Council Canada - National Science Library

    1993-01-01

    ...) studies awarded under the National Maglev Initiative. These summaries present the technical feasibility, performance, capital, operating and maintenance costs for a maglev system that would be available by the year 2000...

  19. Recycle of contaminated scrap metal, comprehensive executive summary. Final report, September 30, 1993--March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    R&D activities have demonstrated Catalytic Extraction Processing (CEP) to be a robust, one-step process process that is relatively insensitive to wide variations in waste composition and is applicable to a broad spectrum of DOE wastes. The feed size and composition compatible with CEP have been increased in a short period of time, and additional R&D should lead to the ability to accept a drum (and larger?) size feed of completely uncharacterized waste. Experiments have validated the CPU (Catalytic Processing Unit). Two commercial facilities have been commissioned and are currently processing mixed low level wastes. Expansion of CEP to transuranic and high level wastes should be the next step in the development and deployment of CEP for recycle, reuse, and disposal of materials from DOE decontamination and decommissioning activities.

  20. Guideline for the management of wounds in patients with lower-extremity venous disease: an executive summary.

    Science.gov (United States)

    Kelechi, Teresa J; Johnson, Jan J

    2012-01-01

    This article provides an executive summary of the lower extremity venous disease (LEVD) evidence-based guideline produced by the WOCN Wound Guidelines Task Force. The target audience for this guideline is health care professionals who specialize in, direct, or provide wound care for patients at risk for or with lower-extremity venous disease. The full guideline opens with an overview of definitions of LEVD, its prevalence, clinical relevance, etiology, related physiology and pathophysiology, and overall management goals for patients at risk for developing venous leg ulcers. A detailed assessment section describes how to conduct a full clinical history and physical examination. Two approaches to interventions are provided: one addresses prevention strategies to reduce the risk of developing LEVD with ulcers. Methods to prevent ulcer recurrence are summarized including compression therapy, adjunctive therapies, medications, and patient education. A second approach presents treatment interventions including wound cleansing, debridement, infection control, antibiotic use, along with management of the periwound skin, nutrition, pain, and edema. This section also discusses limb elevation, surgical options, adjunctive therapies, patient education, and health care provider follow-up. A comprehensive reference list, glossary of terms, and appendices on cellulitis and venous eczema, types of edema, and compression therapy are available at the end of the guideline. This article provides an executive summary of the essential features of the guideline.

  1. Executive Summary: Enhanced Recovery After Surgery: Best Practice Guideline for Care of Patients With a Fecal Diversion.

    Science.gov (United States)

    Miller, Debbie; Pearsall, Emily; Johnston, Debra; Frecea, Monica; McKenzie, Marg

    Enhanced Recovery After Surgery (ERAS) is a multimodal program developed to decrease postoperative complications, improve patient safety and satisfaction, and promote early discharge. In the province of Ontario, Canada, a standardized approach to the care of adult patients undergoing elective colorectal surgery (including benign and malignant diseases) was adopted by 15 hospitals in March 2013. All colorectal surgery patients with or without an ostomy were included in the ERAS program targeting a length of stay of 3 days for colon surgery and 4 days for rectal surgery. To ensure the individual needs of patients requiring an ostomy in an ERAS program were being met, a Provincial ERAS Enterostomal Therapy Nurse Network was established. Our goal was to develop and implement an evidence-based, ostomy-specific best practice guideline addressing the preoperative, postoperative, and discharge phases of care. The guideline was developed over a 3-year period. It is based on existing literature, guidelines, and expert opinion. This article serves as an executive summary for this clinical resource; the full guideline is available as Supplemental Digital Content 1 (available at: http://links.lww.com/JWOCN/A36) to this executive summary.

  2. Data summary of municipal solid waste management alternatives

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    This appendix on Mass Burn Technologies is the first in a series designed to identify, describe and assess the suitability of several currently or potentially available generic technologies for the management of municipal solid waste (MSW). These appendices, which cover eight core thermoconversion, bioconversion and recycling technologies, reflect public domain information gathered from many sources. Representative sources include: professional journal articles, conference proceedings, selected municipality solid waste management plans and subscription technology data bases. The information presented is intended to serve as background information that will facilitate the preparation of the technoeconomic and life cycle mass, energy and environmental analyses that are being developed for each of the technologies. Mass burn has been and continues to be the predominant technology in Europe for the management of MSW. In the United States, the majority of the existing waste-to-energy projects utilize this technology and nearly 90 percent of all currently planned facilities have selected mass burn systems. Mass burning generally refers to the direct feeding and combustion of municipal solid waste in a furnace without any significant waste preprocessing. The only materials typically removed from the waste stream prior to combustion are large bulky objects and potentially hazardous or undesirable wastes. The technology has evolved over the last 100 or so years from simple incineration to the most highly developed and commercially proven process available for both reducing the volume of MSW and for recovering energy in the forms of steam and electricity. In general, mass burn plants are considered to operate reliably with high availability.

  3. Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project

    International Nuclear Information System (INIS)

    Duncan, David

    2011-01-01

    This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

  4. Annual Waste Minimization Summary Report Calendar Year 2007

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2008-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year (CY) 2007. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit (number NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by the NNSA/NSO and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  5. Annual Waste Minimization Summary Report, Calendar Year 2008

    International Nuclear Information System (INIS)

    2009-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2008. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit (No. NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  6. Annual Waste Minimization Summary Report, Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC, for the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2009. This report was developed in accordance with the requirements of the Nevada Test Site Resource Conservation and Recovery Act Permit (No. NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by NNSA/NSO.

  7. Defense-waste vitrification studies during FY-1981. Summary report

    International Nuclear Information System (INIS)

    Bjorklund, W.J.

    1982-09-01

    Both simulated alkaline defense wastes and simulated acidic defense wastes (formed by treating alkaline waste with formic acid) were successfully vitrified in direct liquid-fed melter experiments. The vitrification process was improved while using the formate-treated waste. Leach resistance was essentially the same. Off-gas entrainment was the primary mechanism for material exiting the melter. When formate waste was vitrified, the flow behavior of the off gas from the melter changed dramatically from an erratic surging behavior to a more quiet, even flow. Hydrogen and CO were detectable while processing formate feed; however, levels exceeding the flamability limits in air were never approached. Two types of melter operation were tested during the year, one involving boost power. Several boosting methods located within the melter plenum were tested. When lid heating was being used, water spray cooling in the off gas was required. Countercurrent spray cooling was more effective than cocurrent spray cooling. Materials of construction for the off-gas system were examined. Inconel-690 is preferred in the plenum area. Inspection of the pilot-scale melter found that corrosion of the K-3 refractory and Inconel-690 electrodes was minimal. An overheating incident occurred with the LFCM in which glass temperatures up to 1480 0 C were experienced. Lab-scale vitrification tests to study mercury behavior were also completed this year. 53 figures, 63 tables

  8. Radioactive waste management: a summary of state laws and adminstration. Revision 4

    International Nuclear Information System (INIS)

    1984-06-01

    This is the fourth update of Radioactive Waste Management: a summary of State Laws and Administration. It completely replaces the third update (January 15, 1984). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: cover page; administrative; legislative; and applicable legislation. In general, the information in this report is accurate as of April 30, 1984

  9. Oak Ridge Low Level Waste Management Task Force summary

    International Nuclear Information System (INIS)

    Van Hoesen, S.D.

    1985-01-01

    New facilities are required in the next five years to manage low level radioactive wastes (LLW) produced on the Oak Ridge Reservation (ORR). The Central Waste Disposal Facility (CWDF) was planned to provide the needed additional facilities beginning in late 1985. The CWDF was planned as a shallow land burial facility to dispose of non-stabilized LLW. However, comments on the CWDF Draft Environmental Impact Statement (DEIS) received from the State of Tennessee, the Environmental Protection Agency, and the Nuclear Regulatory Commission identified major issues related to the treatment of alternatives as required by the National Environmental Policy Act, and the potential for unacceptable groundwater contamination resulting from shallow land burial of non-stabilized waste. A series of initial and detailed evaluations are being conducted to develop the basic environmental performance and cost information needed to compare several LLW management approaches and arrive at a proposed system for development. The evaluations are targeted for completion by October

  10. Effluent Information System (EIS) / Onsite Discharge Information System (ODIS): 1986 executive summary

    International Nuclear Information System (INIS)

    Watanabe, T.

    1987-09-01

    Department of Energy (DOE) data base systems aid DOE-Headquarters and Field Offices in managing the radioactive air and liquid effluents from DOE facilities. Data on effluents released offsite are entered into effluent information system (EIS) and data on effluents discharged onsite and retained onsite are entered into Onsite Discharge Information System (ODIS). This document is a summary of information obtained from the CY 1986 effluent data received from all DOE and DOE contractor facilities and entered in the data bases. Data from previous years are also included. The summary consists of information for effluents released offsite, and information for effluents retained onsite

  11. Radioactive waste and recoverable material in France. Summary of the National Inventory 2006

    International Nuclear Information System (INIS)

    2006-01-01

    Thorough knowledge is needed if the various types of radioactive waste are to be managed openly, consistently and in a safe manner. All French radioactive material users have subscribed to this process for many years. Under the terms of the French Act of Parliament of 30 December 1991, the Government commissioned the French National Agency for Radioactive Waste Management (or ANDRA) to carry out a survey of all the radioactive waste present on French Territory. Through its efforts to collect and confirm information from many sources over the years, that is mainly from statements made by waste producers and handlers, ANDRA has built up a database on existing waste and its geographical location. This constantly updated resource has been regularly circulated. At the beginning of the century the Government decided to extend the areas covered by this database, in response to the recommendations made by the National Review Board (CNE) and the Parliamentary Office for Evaluating Scientific and Technology Options (OPECST). This is how the first edition of the National Inventory, published in 2004, came about. The National Inventory of Radioactive Waste and Recoverable Material, presents a full panorama of radioactive waste that it groups into waste families that present homogenous characteristics. It describes the state of the waste that may be conditioned (that is, in its final form) or may not be conditioned (that is, has not been put through sufficient treatments to arrive at its final form) at the end of 2004. Furthermore it presents not only a statistical and geographical summary, but a predictive summary, as it provides waste quantity forecasts for 2010, 2020 and beyond. The Inventory also includes recoverable materials that contain radioactivity. They are always accounted for separately because of their special nature. The data is presented in a synthesis report. This summary is the general public version of the report. The synthesis report offers more in

  12. Radioactive waste and recoverable material in France. Summary of the National Inventory 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    Thorough knowledge is needed if the various types of radioactive waste are to be managed openly, consistently and in a safe manner. All French radioactive material users have subscribed to this process for many years. Under the terms of the French Act of Parliament of 30 December 1991, the Government commissioned the French National Agency for Radioactive Waste Management (or ANDRA) to carry out a survey of all the radioactive waste present on French Territory. Through its efforts to collect and confirm information from many sources over the years, that is mainly from statements made by waste producers and handlers, ANDRA has built up a database on existing waste and its geographical location. This constantly updated resource has been regularly circulated. At the beginning of the century the Government decided to extend the areas covered by this database, in response to the recommendations made by the National Review Board (CNE) and the Parliamentary Office for Evaluating Scientific and Technology Options (OPECST). This is how the first edition of the National Inventory, published in 2004, came about. The National Inventory of Radioactive Waste and Recoverable Material, presents a full panorama of radioactive waste that it groups into waste families that present homogenous characteristics. It describes the state of the waste that may be conditioned (that is, in its final form) or may not be conditioned (that is, has not been put through sufficient treatments to arrive at its final form) at the end of 2004. Furthermore it presents not only a statistical and geographical summary, but a predictive summary, as it provides waste quantity forecasts for 2010, 2020 and beyond. The Inventory also includes recoverable materials that contain radioactivity. They are always accounted for separately because of their special nature. The data is presented in a synthesis report. This summary is the general public version of the report. The synthesis report offers more in

  13. Effective Classroom Management and Instruction: An Exploration of Models. Executive Summary of Final Report.

    Science.gov (United States)

    Evertson, Carolyn M.; And Others

    A summary is presented of the final report, "Effective Classroom Management and Instruction: An Exploration of Models." The final report presents a set of linked investigations of the effects of training teachers in effective classroom management practices in a series of school-based workshops. Four purposes were addressed by the study: (1) to…

  14. 'Literacy Octopus' Dissemination Trial: Evaluation Report and Executive Summary

    Science.gov (United States)

    Lord, Pippa; Rabiasz, Adam; Styles, Ben

    2017-01-01

    The "'Literacy Octopus' Dissemination Trial" aimed to test the impact on pupil outcomes of disseminating research summaries and evidence-based resources to schools. The materials aimed to support teaching and learning of Key Stage 2 literacy and were created by leading organisations with experience of engaging schools in evidence use.…

  15. Physical protection of special nuclear material in the commercial fuel cycle. Volume I. Executive summary

    International Nuclear Information System (INIS)

    1976-04-01

    This is the summary of the work and recommendations resulting from Sandia's participation in the Special Safeguards Study, which covered three areas: protection of SNM at fixed facilities, protection of SNM while in transit, and relocation and recovery of lost SNM. The results are published in full in five other volumes. 6 tables, 4 fig

  16. Preserving heritage resources through responsible use of southern Nevada’s lands [Chapter 9] (Executive Summary)

    Science.gov (United States)

    Carol B. Raish

    2013-01-01

    Southern Nevada’s cultural resources (heritage resources) include archeological remains, sacred sites, historic sites, and cultural landscapes of significance to Native Americans and many other cultural groups. Locating, maintaining, and protecting these special places are part of the mandate of Nevada’s Federal and state agencies. This summary addresses Sub-goal 2.2...

  17. Hanford Waste Vitrification Plant Project advanced conceptual design summary report

    International Nuclear Information System (INIS)

    Anderson, T.D.

    1988-11-01

    The Hanford Waste Vitrification Plant (HWVP) will immobilize Hanford defense liquid high-level waste in borosilicate glass in preparation for shipment to a geologic repository. The shipment of the waste to the repository will satisfy an objective in the President's Defense Waste Management Plan. The glass product will be cast into stainless steel canisters, which will be sealed and stored at Hanford until they are shipped. This document summarizes work performed during the Advance Conceptual Design (ACD) of the HWVP. In the Reference Conceptual Design phase, which preceded the ACD, a number of design issues were identified with the potential to improve cost effectiveness, safety, constructibility, and operability. The ACD addressed and evaluated these design issues. Implementation of recommendations derived from ACD work will occur in subsequent design phases. The next design phase is preliminary design which will be followed by detailed design and construction. Net potential cost improvements of more than $36.9M were identified along with improvements in safety, constructibility, and operability. No negative schedule impacts will result from implementation of the improvements. 11 refs., 5 figs., 3 tabs

  18. Data summary of municipal solid waste management alternatives

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    This appendix contains the alphabetically indexed bibliography for the complete group of reports on municipal waste management alternatives. The references are listed for each of the following topics: mass burn technologies, RDF technologies, fluidized-bed combustion, pyrolysis and gasification of MSW, materials recovery- recycling technologies, sanitary landfills, composting, and anaerobic digestion of MSW.

  19. Data summary of municipal solid waste management alternatives

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    This appendix contains the numerically indexed bibliography for the complete group of reports on municipal solid waste management alternatives. The list references information on the following topics: mass burn technologies, RDF technologies, fluidized bed combustion, pyrolysis and gasification of MSW, materials recovery- recycling technologies, sanitary landfills, composting and anaerobic digestion of MSW.

  20. Solid Waste Information Management System (SWIMS) data summary, fiscal year 1982

    International Nuclear Information System (INIS)

    Watanabe, T.

    1983-06-01

    The Solid Waste Information Management System (SWIMS) is a Department of Energy (DOE) information system for radioactive solid waste. This document is a summary of the FY 1982 data and the forecast data for FY 1983 reported by DOE sites. Detailed data are included in the appendices. The SWIMS data base contains data on the solid transuranic and solid low-level waste generated, buried, or stored at DOE sites. The burial and storage data include the period from site initiation through FY 1982

  1. EMERGING TECHNOLOGY SUMMARY: VITRIFICATION OF SOILS CONTAMINATED BY HAZARDOUS AND/OR RADIOACTIVE WASTES

    Science.gov (United States)

    A performance summary of an advanced multifuel-capable combustion and melting system (CMS) for the vitrification of hazardous wastes is presented. Vortex Corporation has evaluated its patented CMS for use in the remediation of soils contaminated with heavy metals and radionuclid...

  2. Household Hazardous Waste Disposal Project. Summary Report. Metro Toxicant Program Report No. 1A.

    Science.gov (United States)

    Ridgley, Susan M.; Galvin, David V.

    The Household Hazardous Waste Disposal Project was established as an interagency effort to reduce the level of toxicants entering the environment by developing a control plan for the safe disposal of small quantities of household chemicals. This summary report provides an overview of the aspects of this problem that were examined, and the steps…

  3. Summary of the Swedish report Waste-to-energy, an inventory and review about dioxins

    Energy Technology Data Exchange (ETDEWEB)

    Hagelin, A. [RVF - The Swedish Association of Waste Management (Sweden)

    2002-10-01

    Continuous efforts are being made to further improve waste incineration as a means of dealing with household waste and other combustible material, while also producing valuable energy. The main aims are to further reduce the already low emissions to air, and to ensure effective long-term deposition of ashes and other residues from the flue-gas treatment of the waste incineration process. In order to increase knowledge in this area, the Swedish Association of Waste Management (RVF) has taken the initiative for the biggest study to date into dioxins and waste incineration in Sweden. RVF is a trade association working within the areas of waste management and recycling. The owners of Sweden's 22 waste incineration plants are all members of RVF. The study has been carried out by engineer Nils Ahlgren, an independent consultant in energy and the environment, and Professor Stellan Marklund of the University of Umeae, who has a doctorate in dioxins and conducts research into incineration technology and environmental effects. A summary of the report of this study is presented here. The order of the text in this summary follows that of the respective sections in the main report, see below for further explanation.

  4. Summary of national and international radioactive waste management programs

    International Nuclear Information System (INIS)

    Harmon, K.M.

    1979-03-01

    This report summarizes information collected on the status of fuel cycle and waste management programs in Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, Democratic Republic of Germany, Federal Republic of Germany, India, Iran, Italy, Japan, Mexico, the Netherlands, Pakistan, Spain, Sweden, Switzerland, United Kingdom, United States, and USSR. This compilation attempts to provide current information as of the end of January 1979

  5. Summary review of rock mechanics workshop on radioactive waste disposal

    International Nuclear Information System (INIS)

    Carter, N.L.; Goodman, R.E.; Merrill, R.H.

    1977-01-01

    Presentations, critiques and recommendations for the disposal of commercial radioactive waste based upon an analysis of the information presented at the Rock Mechanics Review/Workshop, Denver, Colorado, December 16-17, 1976 are summarized. The workshop, comprised of both formal and informal sessions, with about 50 participants, was hosted by RE/SPEC Inc. and Dr. Paul F. Gnirk, President and was sponsored by the Office of Waste Isolation (OWI), led by Dr. William C. McClain. The panel of reviewers, responsible for this report, consisted of Neville L. Carter, Richard E. Goodman, and Robert H. Merrill. These panel members were selected not only on the basis of their experience in various aspects of Rock Mechanics and Mining Engineering but also because they have had no previous active participation in problems concerning disposal of radioactive waste. By way of a general comment, the review panel was very favorably impressed with the Rock Mechanics research efforts, supported by OWI, on this problem and with the level of technical competence of those carrying out the research. Despite the rather preliminary nature of the results presented and the youth of the program itself, it is clear that the essential ingredients for a successful program are at hand, especially as regards disposal in natural salt formations. These include laboratory studies of appropriate rock deformation, numerical analyses of thermal and mechanical stresses around openings, and in situ field tests. We shall comment on each of these three major areas in turn. We shall then offer recommendations for their improvement, and, finally, we shall make more general recommendations for future considerations of the OWI radioactive waste disposal program

  6. Summary of scientific investigations for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Weart, W.D.

    1996-01-01

    The scientific issues concerning disposal of radioactive wastes in salt formations have received 40 years of attention since the National Academy of Sciences (NAS) first addressed this issue in the mid-50s. For the last 21 years, Sandia National Laboratories (SNL) have directed site specific studies for the Waste Isolation Pilot Plant (WIPP). This paper will focus primarily on the WIPP scientific studies now in their concluding stages, the major scientific controversies regarding the site, and some of the surprises encountered during the course of these scientific investigations. The WIPP project's present understanding of the scientific processes involved continues to support the site as a satisfactory, safe location for the disposal of defense-related transuranic waste and one which will be shown to be in compliance with Environmental Protection Agency (EPA) standards. Compliance will be evaluated by incorporating data from these experiments into Performance Assessment (PA) models developed to describe the physical and chemical processes that could occur at the WIPP during the next 10,000 years under a variety of scenarios. The resulting compliance document is scheduled to be presented to the EPA in October 1996 and all relevant information from scientific studies will be included in this application and the supporting analyses. Studies supporting this compliance application conclude the major period of scientific investigation for the WIPP. Further studies will be of a ''confirmatory'' and monitoring nature

  7. Notice of inquiry on waste acceptance issues: Response summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    On May 25, 1994, the Department of Energy published a Notice of Inquiry on Waste Acceptance Issues in the Federal Register. Through this Notice of Inquiry, the Department sought to implement the Secretary`s initiative to explore with affected parties various options and methods for sharing the costs related to the financial burden associated with continued on-site storage by eliciting the views of affected parties on: (1) The Department`s preliminary view that it does not have a statutory obligation to begin accepting spent nuclear fuel in 1998 in the absence of an operational repository or other suitable storage facility constructed under the Nuclear Waste Policy Act of 1982, as amended; (2) The need for an interim, away-from-reactor storage facility prior to repository operations; and (3) Options for offsetting, through the Nuclear Waste Fund, a portion of the financial burden that may be incurred by utilities in continuing to store spent nuclear fuel at reactor sites beyond 1998. The Department received a total of 1,111 responses representing 1,476 signatories to this Notice of Inquiry. The responses included submittals from utilities (38 responses); public utility/service commissions and utility regulators (26 responses); Federal, state, and local governments, agencies, and representatives (23 responses); industry and companies (30 responses); public interest groups and other organizations (19 responses); and members of the general public (975 responses).

  8. Radioactive Tank Waste Remediation Focus Area. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    In February 1991, DOE's Office of Technology Development created the Underground Storage Tank Integrated Demonstration (UST-ID), to develop technologies for tank remediation. Tank remediation across the DOE Complex has been driven by Federal Facility Compliance Agreements with individual sites. In 1994, the DOE Office of Environmental Management created the High Level Waste Tank Remediation Focus Area (TFA; of which UST-ID is now a part) to better integrate and coordinate tank waste remediation technology development efforts. The mission of both organizations is the same: to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. The TFA has focused on four DOE locations: the Hanford Site in Richland, Washington, the Idaho National Engineering Laboratory (INEL) near Idaho Falls, Idaho, the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site (SRS) in Aiken, South Carolina

  9. Notice of inquiry on waste acceptance issues: Response summary

    International Nuclear Information System (INIS)

    1995-03-01

    On May 25, 1994, the Department of Energy published a Notice of Inquiry on Waste Acceptance Issues in the Federal Register. Through this Notice of Inquiry, the Department sought to implement the Secretary's initiative to explore with affected parties various options and methods for sharing the costs related to the financial burden associated with continued on-site storage by eliciting the views of affected parties on: (1) The Department's preliminary view that it does not have a statutory obligation to begin accepting spent nuclear fuel in 1998 in the absence of an operational repository or other suitable storage facility constructed under the Nuclear Waste Policy Act of 1982, as amended; (2) The need for an interim, away-from-reactor storage facility prior to repository operations; and (3) Options for offsetting, through the Nuclear Waste Fund, a portion of the financial burden that may be incurred by utilities in continuing to store spent nuclear fuel at reactor sites beyond 1998. The Department received a total of 1,111 responses representing 1,476 signatories to this Notice of Inquiry. The responses included submittals from utilities (38 responses); public utility/service commissions and utility regulators (26 responses); Federal, state, and local governments, agencies, and representatives (23 responses); industry and companies (30 responses); public interest groups and other organizations (19 responses); and members of the general public (975 responses)

  10. Impact of geothermal development on the state of Hawaii. Executive summary. Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Siegel, B.Z.

    1980-06-01

    Questions regarding the sociological, legal, environmental, and geological concerns associated with the development of geothermal resources in the Hawaiian Islands are addressed in this summary report. Major social changes, environmental degradation, legal and economic constraints, seismicity, subsidence, changes in volcanic activity, accidents, and ground water contamination are not major problems with the present state of development, however, the present single well does not provide sufficient data for extrapolation. (ACR)

  11. Effluent information system (EIS)/onsite discharge information system (ODIS) 1985 executive summary

    International Nuclear Information System (INIS)

    Watanabe, T.

    1986-09-01

    The Effluent Information System (EIS) and Onsite Discharge Information System (ODIS) are Department of Energy (DOE) data base systems that aid DOE-Headquarters and Field Offices in managing the radioactive air and liquid effluents from DOE facilities. Data on effluents released offsite are entered into EIS and data on effluents discharged onsite and retained onsite are entered into ODIS. This document is a summary of information obtained from the CY 1985 effluent data received from all DOE and DOE contractor facilities and entered in the data bases. Data from previous years are also included. The summary consists of two parts. The first part summarizes information for effluents released offsite, and the second part summarizes information for effluents retained onsite. These summaries are taken from the routine annual reports sent to each DOE Operations Office. Special tabulations or specific data can be supplied upon request. Explanations of the significant changes are included in the EIS and ODIS graphic sections. Only those changes in activity greater than a factor of two and having a magnitude greater than 0.1 Ci are considered significant and are addressed in the explanation

  12. LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-10-01

    The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

  13. Institut de recherche sur la fusion par confinement magnetique. Association EURATOM-CEA. Annual report 2008 (executive summary)

    International Nuclear Information System (INIS)

    2008-01-01

    The 2008 experimental campaign on Tore-Supra has been especially fruitful with the completion of multi-annual programmes bringing important answers, notably on operational aspects of long duration discharges. Concerning JET, particular effort have been devoted to: -) hydrogen isotopes retention studies, -) advanced scenarios studies such as JT60-JET physics identity experiments in ITB regimes, -) the commissioning of the ITER-like ICRH antenna, and -) high power level commissioning of the LHCD antenna and long distance coupling studies. Concerning integrated modelling, the development of the CRONOS code suite has been carried on, with particular emphasis on increasing its reliability and international coverage. CRONOS has been extensively used to investigate steady-state scenarios for ITER and DEMO. Most of the technological developments carried out by the Association concentrates on key domains that apply to ITER: superconducting conductors, actively cooled PFC (plasma facing components), or diagnostics. This document is an executive summary

  14. Executive summary: Prevention and treatment of opportunistic infections and other coinfections in HIV-infected patients: May 2015.

    Science.gov (United States)

    Iribarren, José Antonio; Rubio, Rafael; Aguirrebengoa, Koldo; Arribas, Jose Ramón; Baraia-Etxaburu, Josu; Gutiérrez, Félix; Lopez Bernaldo de Quirós, Juan Carlos; Losa, Juan Emilio; Miró, José Ma; Moreno, Santiago; Pérez Molina, José; Podzamczer, Daniel; Pulido, Federico; Riera, Melchor; Rivero, Antonio; Sanz Moreno, José; Amador, Concha; Antela, Antonio; Arazo, Piedad; Arrizabalaga, Julio; Bachiller, Pablo; Barros, Carlos; Berenguer, Juan; Caylá, Joan; Domingo, Pere; Estrada, Vicente; Knobel, Hernando; Locutura, Jaime; López Aldeguer, José; Llibre, Josep Ma; Lozano, Fernando; Mallolas, Josep; Malmierca, Eduardo; Miralles, Celia; Miralles, Pilar; Muñoz, Agustín; Ocampo, Agustín; Olalla, Julián; Pérez, Inés; Pérez Elías, Ma Jesús; Pérez Arellano, José Luis; Portilla, Joaquín; Ribera, Esteban; Rodríguez, Francisco; Santín, Miguel; Sanz Sanz, Jesús; Téllez, Ma Jesús; Torralba, Miguel; Valencia, Eulalia; Von Wichmann, Miguel Angel

    2016-10-01

    Opportunistic infections continue to be a cause of morbidity and mortality in HIV-infected patients. They often arise because of severe immunosuppression resulting from poor adherence to antiretroviral therapy, failure of antiretroviral therapy, or unawareness of HIV infection by patients whose first clinical manifestation of AIDS is an opportunistic infection. The present article is an executive summary of the document that updates the previous recommendations on the prevention and treatment of opportunistic infections in HIV-infected patients, namely, infections by parasites, fungi, viruses, mycobacteria, and bacteria, as well as imported infections. The article also addresses immune reconstitution inflammatory syndrome. This document is intended for all professionals who work in clinical practice in the field of HIV infection. Copyright © 2016 Elsevier España, S.L.U. and Sociedad Española de Enfermedades Infecciosas y Microbiología Clínica. All rights reserved.

  15. Energy from the desert. Very large scale photovoltaic systems: socio-economic, financial, technical and environmental aspects. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Kurokawa, K.; Ito, M.; Komoto, K.; Vleuten, P. van der; Faiman, D. (eds.)

    2009-05-15

    This executive summary report for the International Energy Agency (IEA) summarises the objectives and concepts of very large scale photovoltaic power generation (VLS-PV) systems and takes a look at the socio-economic, financial and technical aspects involved as well as the environmental impact of such systems. Potential benefits for desert communities, agricultural development and desalination of water are topics that are looked at. The potential of VLS-PV, its energy payback time and CO{sub 2} emission rates are discussed. Case studies for the Sahara and the Gobi Dessert areas are discussed. A VLS-PV roadmap is proposed and scenarios are discussed. Finally, conclusions are drawn and recommendations are made.

  16. Executive summary and conclusions from the European Hydration Institute Expert Conference on human hydration, health, and performance.

    Science.gov (United States)

    Benton, D; Braun, H; Cobo, J C; Edmonds, C; Elmadfa, I; El-Sharkawy, A; Feehally, J; Gellert, R; Holdsworth, J; Kapsokefalou, M; Kenney, W L; Leiper, J B; Macdonald, I A; Maffeis, C; Maughan, R J; Shirreffs, S M; Toth-Heyn, P; Watson, P

    2015-09-01

    On April 7-8, 2014, the European Hydration Institute hosted a small group of experts at Castle Combe Manor House, United Kingdom, to discuss a range of issues related to human hydration, health, and performance. The meeting included 18 recognized experts who brought a wealth of experience and knowledge to the topics under review. Eight selected topics were addressed, with the key issues being briefly presented before an in-depth discussion. Presented here is the executive summary and conclusions from this meeting. © The Author(s) 2015. Published by Oxford University Press on behalf of the International Life Sciences Institute. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

  17. Regulation, characterization and treatment of discharge waters from pipelines. Volume 1. Topical report, January 1989-April 1992. Executive summary

    International Nuclear Information System (INIS)

    Tallon, J.T.; Fillo, J.P.

    1992-04-01

    The report examines environmental issues related to hydrostatic testing of discharge waters generated from integrity testing of natural gas pipelines. Hydrostatic testing, and proper environmental management of the discharge waters, can be required by DOT regulations. However, disposal of water used to conduct a hydrostatic pipeline test is regulated on a state-by-state basis. State-specific requirements vary widely, ranging from an authorization letter to a complete NPDES permit. Monitoring may be required before and during discharge, include a variety of analyses, have varying protocols for obtaining samples, and may be required either to obtain data or to ascertain compliance with stipulated discharge limits. The composition of the discharge and state-specific discharge limitations dictate treatment needs on a case-by-case basis. The volume consists of the Executive Summary of a five-volume report series

  18. Global Strategy for the Diagnosis, Management, and Prevention of Chronic Obstructive Lung Disease 2017 Report: GOLD Executive Summary.

    Science.gov (United States)

    Vogelmeier, Claus F; Criner, Gerard J; Martinez, Fernando J; Anzueto, Antonio; Barnes, Peter J; Bourbeau, Jean; Celli, Bartolome R; Chen, Rongchang; Decramer, Marc; Fabbri, Leonardo M; Frith, Peter; Halpin, David M G; López Varela, M Victorina; Nishimura, Masaharu; Roche, Nicolas; Rodriguez-Roisin, Roberto; Sin, Don D; Singh, Dave; Stockley, Robert; Vestbo, Jørgen; Wedzicha, Jadwiga A; Agusti, Alvar

    2017-03-01

    This Executive Summary of the Global Strategy for the Diagnosis, Management, and Prevention of COPD (GOLD) 2017 Report focuses primarily on the revised and novel parts of the document. The most significant changes include: 1) the assessment of chronic obstructive pulmonary disease has been refined to separate the spirometric assessment from symptom evaluation. ABCD groups are now proposed to be derived exclusively from patient symptoms and their history of exacerbations; 2) for each of the groups A to D, escalation strategies for pharmacological treatments are proposed; 3) the concept of de-escalation of therapy is introduced in the treatment assessment scheme; 4) nonpharmacologic therapies are comprehensively presented and; 5) the importance of comorbid conditions in managing COPD is reviewed. Copyright ©2017 the American Thoracic Society. Published with permission from the American Thoracic Society. Design and branding are copyright ©ERS 2017.

  19. Alternative Electrochemical Salt Waste Forms, Summary of FY2010 Results

    International Nuclear Information System (INIS)

    Riley, Brian J.; Rieck, Bennett T.; Crum, Jarrod V.; Matyas, Josef; McCloy, John S.; Sundaram, S.K.; Vienna, John D.

    2010-01-01

    In FY2009, PNNL performed scoping studies to qualify two waste form candidates, tellurite (TeO2-based) glasses and halide minerals, for the electrochemical waste stream for further investigation. Both candidates showed promise with acceptable PCT release rates and effective incorporation of the 10% fission product waste stream. Both candidates received reprisal for FY2010 and were further investigated. At the beginning of FY2010, an in-depth literature review kicked off the tellurite glasses study. The review was aimed at ascertaining the state-of-the-art for chemical durability testing and mixed chloride incorporation for tellurite glasses. The literature review led the authors to 4 unique binary and 1 unique ternary systems for further investigation which include TeO2 plus the following: PbO, Al2O3-B2O3, WO3, P2O5, and ZnO. Each system was studied with and without a mixed chloride simulated electrochemical waste stream and the literature review provided the starting points for the baseline compositions as well as starting points for melting temperature, compatible crucible types, etc. The most promising glasses in each system were scaled up in production and were analyzed with the Product Consistency Test, a chemical durability test. Baseline and PCT glasses were analyzed to determine their state, i.e., amorphous, crystalline, phase separated, had undissolved material within the bulk, etc. Conclusions were made as well as the proposed direction for FY2011 plans. Sodalite was successfully synthesized by the sol-gel method. The vast majority of the dried sol-gel consisted of sodalite with small amounts of alumino-silicates and unreacted salt. Upon firing the powders made by sol-gel, the primary phase observed was sodalite with the addition of varying amounts of nepheline, carnegieite, lithium silicate, and lanthanide oxide. The amount of sodalite, nepheline, and carnegieite as well as the bulk density of the fired pellets varied with firing temperature, sol

  20. Alternative Electrochemical Salt Waste Forms, Summary of FY2010 Results

    Energy Technology Data Exchange (ETDEWEB)

    Riley, Brian J.; Rieck, Bennett T.; Crum, Jarrod V.; Matyas, Josef; McCloy, John S.; Sundaram, S. K.; Vienna, John D.

    2010-08-01

    In FY2009, PNNL performed scoping studies to qualify two waste form candidates, tellurite (TeO2-based) glasses and halide minerals, for the electrochemical waste stream for further investigation. Both candidates showed promise with acceptable PCT release rates and effective incorporation of the 10% fission product waste stream. Both candidates received reprisal for FY2010 and were further investigated. At the beginning of FY2010, an in-depth literature review kicked off the tellurite glasses study. The review was aimed at ascertaining the state-of-the-art for chemical durability testing and mixed chloride incorporation for tellurite glasses. The literature review led the authors to 4 unique binary and 1 unique ternary systems for further investigation which include TeO2 plus the following: PbO, Al2O3-B2O3, WO3, P2O5, and ZnO. Each system was studied with and without a mixed chloride simulated electrochemical waste stream and the literature review provided the starting points for the baseline compositions as well as starting points for melting temperature, compatible crucible types, etc. The most promising glasses in each system were scaled up in production and were analyzed with the Product Consistency Test, a chemical durability test. Baseline and PCT glasses were analyzed to determine their state, i.e., amorphous, crystalline, phase separated, had undissolved material within the bulk, etc. Conclusions were made as well as the proposed direction for FY2011 plans. Sodalite was successfully synthesized by the sol-gel method. The vast majority of the dried sol-gel consisted of sodalite with small amounts of alumino-silicates and unreacted salt. Upon firing the powders made by sol-gel, the primary phase observed was sodalite with the addition of varying amounts of nepheline, carnegieite, lithium silicate, and lanthanide oxide. The amount of sodalite, nepheline, and carnegieite as well as the bulk density of the fired pellets varied with firing temperature, sol

  1. Total-system performance assessment for Yucca Mountain -- SNL second iteration (TSPA-1993); Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, M.L.; Barnard, R.W. [Sandia National Labs., Albuquerque, NM (United States); Gauthier, J.H. [Sandia National Labs., Albuquerque, NM (United States)]|[Spectra Research, Inc. (United States)] [and others

    1994-04-01

    Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone. Probabilistic analyses are performed for aqueous and gaseous flow and transport, human intrusion, and basaltic magmatic activity. Results of the calculations lead to a number of recommendations concerning studies related to site characterization. Primary among these are the recommendations to obtain better information on percolation flux at Yucca Mountain, on the presence or absence of flowing fractures, and on physical and chemical processes influencing gaseous flow. Near-field thermal and chemical processes, and waste-container degradation are also areas where additional investigations may reduce important uncertainties. Recommendations for repository and waste-package design studies are: (1) to evaluate the performance implications of large-size containers, and (2) to investigate in more detail the implications of high repository thermal power output on the adjacent host rock and on the spent fuel.

  2. Trends in public perceptions and preferences on energy and environmental policy: Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Farhar, B.C.

    1993-03-01

    This is a summary of a report that presents selected results from a secondary analysis of public opinion surveys, taken at the national and state/local levels, relevant to energy and environmental policy choices. The data base used in the analysis includes about 2,000 items from nearly 600 separate surveys conducted between 1979 and 1992. Answers to word-for-word questions were traced over time, permitting trend analysis. Patterns of response were also identified for findings from similarly worded survey items. The analysis identifies changes in public opinion concerning energy during the past 10 to 15 years.

  3. EXECUTIVE SUMMARY OF THE SNOWMASS 2001 WORKING GROUP : ELECTROWEAK SYMMETRY BREAKING

    International Nuclear Information System (INIS)

    CARENA, M.; GERDES, D.W.; HABER, H.E.; TURCOT, A.S.; ZERWAS, P.M.

    2001-01-01

    In this summary report of the 2001 Snowmass Electroweak Symmetry Breaking Working Group, the main candidates for theories of electroweak symmetry breaking are surveyed, and the criteria for distinguishing among the different approaches are discussed. The potential for observing electroweak symmetry breaking phenomena at the upgraded Tevatron and the LHC is described. We emphasize the importance of a high-luminosity e + e - linear collider for precision measurements to clarify the underlying electroweak symmetry breaking dynamics. Finally, we note the possible roles of the μ + μ - collider and VLHC for further elucidating the physics of electroweak symmetry breaking

  4. Executive Summary of Ares V: Lunar Capabilities Concept Review Through Phase A-Cycle 3

    Science.gov (United States)

    Holladay, J. B.; Baggett, K. E.; Feldman, S. M.

    2011-01-01

    This Technical Memorandum (TM) was generated as an overall Ares V summary from the Lunar Capabilities Concept Review (LCCR) through Phase A-Cycle 3 (PA-C3) with the intent that it may be coupled with separately published appendices for a more detailed, integrated narrative. The Ares V has evolved from the initial point of departure (POD) 51.00.48 LCCR configuration to the current candidate POD, PA-C3D, and the family of vehicles concept that contains vehicles PA-C3A through H. The logical progression from concept to POD vehicles is summarized in this TM and captures the trade space and performance of each. The family-of-vehicles concept was assessed during PA-C3 and offered flexibility in the path forward with the ability to add options deemed appropriate. A description of each trade space is given in addition to a summary of each Ares V element. The Ares V contributions to a Mars campaign are also highlighted with the goal of introducing Ares V capabilities within the trade space. The assessment of the Ares V vehicle as it pertains to Mars missions remained locked to the architecture presented in Mars Design Reference Authorization 5.0 using the PA-C3D vehicle configuration to assess Mars transfer vehicle options, in-space EDS capabilities, docking adaptor and propellant transfer assessments, and lunar and Mars synergistic potential.

  5. Inventory of Federal energy-related environment and safety research for FY 1979. Volume 1. Executive summary

    International Nuclear Information System (INIS)

    1980-12-01

    The FY 1979 Federal Inventory contains information on 3506 federally funded energy-related environmental and safety research projects. The Inventory is published in two volumes: Volume I, an executive summary and overview of the data and Volume II, project listings, summaries, and indexes. Research and development (R and D) categories were reorganized into three main areas; environmental and safety control technology, technology impacts overview and assessments, and biological and environmental R and D and assessments. Federal offices submitting project data were: Council on Environmental Quality; Department of Agriculture; Department of Commerce; Department of Defense; Department of Energy; Department of Health, Education, and Welfare; Department of Housing and Urban Development; Department of the Interior; Department of Transportation; Environmental Protection Agency; National Aeronautics and Space Administration; Nuclear Regulatory Commission; National Science Foundation; Office of Technology Assessment; and Tennessee Valley Authority. The inventory also breaks out research sponsored by various federal agencies and the amount of funding provided by each in various research categories. The format and index system allows efficient access to information compiled. Users are able to identify projects by log agency, performing organization, principal investigator and subject

  6. Greening the Department of Energy through waste prevention, recycling, and Federal acquisition. Strategic plan to implement Executive Order 13101

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-11-01

    This Plan provides strategies and milestones to implement Executive Order 13101, Greening the Government Through Waste Prevention, Recycling, and Federal Acquisition, and to achieve the new Secretarial goals for 2005 and 2010. It serves as the principal Secretarial guidance to Department of Energy (DOE) Headquarters, Field Offices, and laboratory and contractor staff to improve sanitary waste prevention, recycling, and the purchase and use of recycled content and environmentally preferable products and services in the DOE.

  7. Workshop on using natural language processing applications for enhancing clinical decision making: an executive summary.

    Science.gov (United States)

    Pai, Vinay M; Rodgers, Mary; Conroy, Richard; Luo, James; Zhou, Ruixia; Seto, Belinda

    2014-02-01

    In April 2012, the National Institutes of Health organized a two-day workshop entitled 'Natural Language Processing: State of the Art, Future Directions and Applications for Enhancing Clinical Decision-Making' (NLP-CDS). This report is a summary of the discussions during the second day of the workshop. Collectively, the workshop presenters and participants emphasized the need for unstructured clinical notes to be included in the decision making workflow and the need for individualized longitudinal data tracking. The workshop also discussed the need to: (1) combine evidence-based literature and patient records with machine-learning and prediction models; (2) provide trusted and reproducible clinical advice; (3) prioritize evidence and test results; and (4) engage healthcare professionals, caregivers, and patients. The overall consensus of the NLP-CDS workshop was that there are promising opportunities for NLP and CDS to deliver cognitive support for healthcare professionals, caregivers, and patients.

  8. Executive summary: The health and fitness benefits of regular participation in small-sided football games

    DEFF Research Database (Denmark)

    Krustrup, Peter; Dvorak, J.; Junge, A.

    2010-01-01

    The present special issue of Scandinavian Journal of Medicine & Science in Sports deals with health and fitness benefits of regular participation in small-sided football games. One review article and 13 original articles were the result of a 2-year multi-center study in Copenhagen and Zurich...... and include studies of different age groups analyzed from a physiological, medical, social and psychological perspective. The main groups investigated were middle-aged, former untrained, healthy men and women who were followed for up to 16 months. In addition, elderly, children and hypertensive patients were...... studied. A summary and interpretations of the main findings divided into an analysis of the physical demands during training of various groups and the effect of a period of training on performance, muscle adaptations and health profile follow. In addition, social and psychological effects on participation...

  9. Rehabilitation Research at the National Institutes of Health: Moving the Field Forward (Executive Summary)

    Science.gov (United States)

    Frontera, Walter R.; Bean, Jonathan F.; Damiano, Diane; Ehrlich-Jones, Linda; Fried-Oken, Melanie; Jette, Alan; Jung, Ranu; Lieber, Rick L.; Malec, James F.; Mueller, Michael J.; Ottenbacher, Kenneth J.; Tansey, Keith E.; Thompson, Aiko

    2017-01-01

    Approximately 53 million Americans live with a disability. For decades, the National Institutes of Health (NIH) has been conducting and supporting research to discover new ways to minimize disability and enhance the quality of life of people with disabilities. After the passage of the Americans With Disabilities Act, NIH established the National Center for Medical Rehabilitation Research, with the goal of developing and implementing a rehabilitation research agenda. Currently, 17 institutes and centers at NIH invest more than $500 million per year in rehabilitation research. Recently, the director of NIH, Francis Collins, appointed a Blue Ribbon Panel to evaluate the status of rehabilitation research across institutes and centers. As a follow-up to the work of that panel, NIH recently organized a conference, “Rehabilitation Research at NIH: Moving the Field Forward.” This report is a summary of the discussions and proposals that will help guide rehabilitation research at NIH in the near future. PMID:28422639

  10. Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    David Duncan

    2011-05-01

    This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

  11. Revised draft Hanford remedial action environmental impact statement and comprehensive land-use plan: Executive summary

    International Nuclear Information System (INIS)

    1999-01-01

    This report evaluates the potential environmental impacts associated with implementing a comprehensive land-use plan for the Hanford Site for at least the next 50 years. With the exception of the required No-Action Alternative, each of the six alternatives presented represents a Tribal, Federal, state, or local agency's Preferred Alternative. Each alternative is presented separately. The DOE's Preferred Alternative anticipates multiple uses of the Hanford Site, including: consolidating waste management operations in the Central Plateau, allowing industrial development in the eastern and southern portions of the site, increasing recreational access to the Columbia River, and expanding the Saddle Mountain National Wildlife Refuge to include all of the Wahluke Slope (managed by the US Fish and Wildlife Service). The Hanford Site occupies 1,517 square kilometers (km 2 ) (586 square miles [mi 2 ]) in southeastern Washington. Today, the Hanford Site has diverse missions associated with environmental restoration, waste management, and science and technology. These missions have resulted in the growing need for a comprehensive, long-term approach to planning and development for the Site

  12. Radioactive waste management: a summary of state laws and administration. Revision 3

    International Nuclear Information System (INIS)

    1984-02-01

    This is the third update of Radioactive Waste Management: A Summary of State Laws and Administration. It completely replaces the second update (15 July 1983). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. Included under the compacts is a description of what the state has done or currently plans to do, as well as the compact status of other eligible states in the region. In general, the information in this report is accurate as of January 1, 1984

  13. Comprehensive risk reduction in patients with atrial fibrillation : Emerging diagnostic and therapeutic options Executive summary* of the report from the 3rd AFNET/EHRA consensus conference

    NARCIS (Netherlands)

    Kirchhof, Paulus; Lip, Gregory Y. H.; Van Gelder, Isabelle C.; Bax, Jeroen; Hylek, Elaine; Kaeaeb, Stefan; Schotten, Ulrich; Wegscheider, Karl; Boriani, Giuseppe; Ezekowitz, Michael; Diener, Hans; Heidbuchel, Hein; Lane, Deirdre; Mont, Luis; Willems, Stephan; Dorian, Paul; Vardas, Panos; Breithardt, Guenter; Camm, A. John

    2011-01-01

    There are exciting new developments in several areas of atrial fibrillation (AF) management that carry the hope of improving outcomes in AF patients. This paper is an executive summary that summarises the proceedings from the 3rd AFNET/EHRA consensus conference on atrial fibrillation, held in Sophia

  14. Findings from the Evaluation of the National Library Power Program. Executive Summary. An Initiative of the DeWitt Wallace-Reader's Digest Fund.

    Science.gov (United States)

    Zweizig, Douglas; Hopkins, Dianne McAfee

    This document presents the executive summary of an evaluation of Library Power, a program of the DeWitt Wallace-Reader's Digest Fund to enhance and elevate the role of libraries in public schools. The report begins with an examination of Library Power's core components (collection development, facilities refurbishing, flexible scheduling,…

  15. A Study of the Extent and Effect of English Language Training for Refugees. Phase One: Results of a Comprehensive Mail Survey. Executive Summary.

    Science.gov (United States)

    Northwest Regional Educational Lab., Portland, OR. Office of Research and Evaluation Services.

    Results of a national survey of regional, state, and local agencies administering English language training programs for refugees, the first phase of a larger study of the training programs, are reported. The executive summary outlines the responses from 8 regional, 36 state, and 232 local agencies on four topics: (1) the nature and extent of…

  16. Report to the Congress on the need for, and the feasibility of, establishing a security agency within the Office of Nuclear Material Safety and Safeguards. Executive summary

    International Nuclear Information System (INIS)

    1976-08-01

    The Executive Summary of a report written in response to the Congressional mandate Section 204(b)-(2) (c) of the Energy Reorganization Act of 1974, by the Director of the Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission (NRC) is given. It summarizes the main report, which assessed guard force effectiveness, and addressed public policy, administration and legal issues

  17. An Analysis of the Relationship between English Language Arts and Mathematics Achievement and Essential Learning Mastery in Grades 3 and 4. Executive Summary

    Science.gov (United States)

    Haystead, Mark W.

    2016-01-01

    Over several years, Clark Pleasant Community School Corporation (CPCSC) schools have dedicated significant professional development hours and time to develop Essential Learnings (ELs) along with proficiency scales that could guide the content of classroom assessments used to determine student mastery. This executive summary highlights key findings…

  18. Building Student Momentum from High School into College. Ready or Not: It's Time to Rethink the 12th Grade. Executive Summary

    Science.gov (United States)

    Barnett, Elisabeth

    2016-01-01

    This executive summary describes a paper that is part of a series intended to encourage the nation's secondary and postsecondary systems to take joint responsibility for substantially increasing the number of young people who are prepared for college and career success. In this report, author Elisabeth Barnett of the Community College Research…

  19. New Education Advocacy Organizations in the U.S. States: National Snapshot and a Case Study of Advance Illinois. Executive Summary

    Science.gov (United States)

    Manna, Paul; Moffitt, Susan

    2014-01-01

    This executive summary describes a Wallace-commissioned report that identifies the emergence of a new kind of education advocacy organization in the United States. The report also assesses how these groups influence education policy, provides an overview of their work across the country, and offers a case study of one, Advance Illinois. The report…

  20. Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, C.B.

    1999-11-29

    The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected.

  1. Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary

    International Nuclear Information System (INIS)

    Shedrow, C.B.

    1999-01-01

    The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected

  2. The multi-annual Energy Plan - Executive summary. The energy transition for the green growth

    International Nuclear Information System (INIS)

    2017-07-01

    The multi-annual energy plan aims at completing the transition towards an energy system which is more efficient, less wasteful, more diverse and therefore more resilient. It reaffirms our commitment to reducing energy consumption, particularly energy from fossil fuels. The future of France's energy sector lies in striking a harmonious balance between different energy sources. These strategic decisions will help us to meet our objectives to keep greenhouse gas emissions to a minimum in line with our commitments to the EU and to the Paris Climate Agreement, to protect human health and the environment and to ensure access to energy at a reasonable cost whilst stimulating economic activity and employment in France

  3. FWP executive summaries, Basic Energy Sciences Materials Sciences Programs (SNL/NM)

    Energy Technology Data Exchange (ETDEWEB)

    Samara, G.A.

    1997-05-01

    The BES Materials Sciences Program has the central theme of Scientifically Tailored Materials. The major objective of this program is to combine Sandia`s expertise and capabilities in the areas of solid state sciences, advanced atomic-level diagnostics and materials synthesis and processing science to produce new classes of tailored materials as well as to enhance the properties of existing materials for US energy applications and for critical defense needs. Current core research in this program includes the physics and chemistry of ceramics synthesis and processing, the use of energetic particles for the synthesis and study of materials, tailored surfaces and interfaces for materials applications, chemical vapor deposition sciences, artificially-structured semiconductor materials science, advanced growth techniques for improved semiconductor structures, transport in unconventional solids, atomic-level science of interfacial adhesion, high-temperature superconductors, and the synthesis and processing of nano-size clusters for energy applications. In addition, the program includes the following three smaller efforts initiated in the past two years: (1) Wetting and Flow of Liquid Metals and Amorphous Ceramics at Solid Interfaces, (2) Field-Structured Anisotropic Composites, and (3) Composition-Modulated Semiconductor Structures for Photovoltaic and Optical Technologies. The latter is a joint effort with the National Renewable Energy Laboratory. Separate summaries are given of individual research areas.

  4. Executive summary: Weldon Spring Site Environmental Report for calendar year 1992

    International Nuclear Information System (INIS)

    1993-06-01

    This report has been prepared to provide information about the public safety and environmental protection programs conducted by the Weldon Spring Site Remedial Action Project. The Weldon Spring site is located in southern St. Charles County, Missouri, approximately 48 km (30 mi) west of St. Louis. The site consists of two main areas, the Weldon Spring Chemical Plant and raffinate pits and the Weldon Spring Quarry. The objectives of the Site Environmental Report are to present a summary of data from the environmental monitoring program, to characterize trends and environmental conditions at the site, and to confirm compliance with environmental and health protection standards and requirements. The report also presents the status of remedial activities and the results of monitoring these activities to assess their impacts on the public and environment. The scope of the environmental monitoring program at the Weldon Spring site has changed since it was initiated. Previously, the program focused on investigations of the extent and level of contaminants in the groundwater, surface waters, buildings, and air at the site. In 1992, the level of remedial activities required monitoring for potential impacts of those activities, particularly on surface water runoff and airborne effluents. This report includes monitoring data from routine radiological and nonradiological sampling activities. These data include estimates of dose to the public from the Weldon Spring site; estimates of effluent releases; and trends in groundwater contaminant levels. Also, applicable compliance requirements, quality assurance programs, and special studies conducted in 1992 to support environmental protection programs are reviewed

  5. 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

  6. Executive summary: the health and fitness benefits of regular participation in small-sided football games.

    Science.gov (United States)

    Krustrup, P; Dvorak, J; Junge, A; Bangsbo, J

    2010-04-01

    The present special issue of Scandinavian Journal of Medicine & Science in Sports deals with health and fitness benefits of regular participation in small-sided football games. One review article and 13 original articles were the result of a 2-year multi-center study in Copenhagen and Zurich and include studies of different age groups analyzed from a physiological, medical, social and psychological perspective. The main groups investigated were middle-aged, former untrained, healthy men and women who were followed for up to 16 months. In addition, elderly, children and hypertensive patients were studied. A summary and interpretations of the main findings divided into an analysis of the physical demands during training of various groups and the effect of a period of training on performance, muscle adaptations and health profile follow. In addition, social and psychological effects on participation in recreational football are considered, the comparison of football training and endurance running is summarized and the effects of football practice on the elderly and children and youngsters are presented.

  7. Rehabilitation research at the National Institutes of Health moving the field forward (executive summary).

    Science.gov (United States)

    Frontera, Walter R; Bean, Jonathan F; Damiano, Diane; Ehrlich-Jones, Linda; Fried-Oken, Melanie; Jette, Alan; Jung, Ranu; Lieber, Rick L; Malec, James F; Mueller, Michael J; Ottenbacher, Kenneth J; Tansey, Keith E; Thompson, Aiko

    2017-08-01

    Approximately 53 million Americans live with a disability. For decades, the National Institutes of Health (NIH) has been conducting and supporting research to discover new ways to minimize disability and enhance the quality of life of people with disabilities. After the passage of the Americans With Disabilities Act, NIH established the National Center for Medical Rehabilitation Research, with the goal of developing and implementing a rehabilitation research agenda. Currently, 17 institutes and centers at NIH invest more than $500 million per year in rehabilitation research. Recently, the director of NIH, Francis Collins, appointed a Blue Ribbon Panel to evaluate the status of rehabilitation research across institutes and centers. As a follow-up to the work of that panel, NIH recently organized a conference, "Rehabilitation Research at NIH: Moving the Field Forward." This report is a summary of the discussions and proposals that will help guide rehabilitation research at NIH in the near future. (PsycINFO Database Record (c) 2017 APA, all rights reserved).

  8. Rehabilitation Research at the National Institutes of Health: Moving the Field Forward (Executive Summary).

    Science.gov (United States)

    Frontera, Walter R; Bean, Jonathan F; Damiano, Diane; Ehrlich-Jones, Linda; Fried-Oken, Melanie; Jette, Alan; Jung, Ranu; Lieber, Rick L; Malec, James F; Mueller, Michael J; Ottenbacher, Kenneth J; Tansey, Keith E; Thompson, Aiko

    Approximately 53 million Americans live with a disability. For decades, the National Institutes of Health (NIH) has been conducting and supporting research to discover new ways to minimize disability and enhance the quality of life of people with disabilities. After the passage of the Americans With Disabilities Act, NIH established the National Center for Medical Rehabilitation Research, with the goal of developing and implementing a rehabilitation research agenda. Currently, 17 institutes and centers at NIH invest more than $500 million per year in rehabilitation research. Recently, the director of NIH, Francis Collins, appointed a Blue Ribbon Panel to evaluate the status of rehabilitation research across institutes and centers. As a follow-up to the work of that panel, NIH recently organized a conference, "Rehabilitation Research at NIH: Moving the Field Forward." This report is a summary of the discussions and proposals that will help guide rehabilitation research at NIH in the near future. Copyright © 2017 by The Author(s). Published by Wolters Kluwer Health, Inc. This is an open access article distributed under the terms of the Creative Commons Attribution-Non Commercial-No Derivatives License 4.0 (CCBY-NC-ND), where it is permissible to download and share the work provided it is properly cited. The work cannot be changed in any way or used commercially without permission from the journal.

  9. Summary of LLNL's accomplishments for the FY93 Waste Processing Operations Program

    International Nuclear Information System (INIS)

    Grasz, E.; Domning, E.; Heggins, D.; Huber, L.; Hurd, R.; Martz, H.; Roberson, P.; Wilhelmsen, K.

    1994-04-01

    Under the US Department of Energy's (DOE's) Office of Technology Development (OTD)-Robotic Technology Development Program (RTDP), the Waste Processing Operations (WPO) Program was initiated in FY92 to address the development of automated material handling and automated chemical and physical processing systems for mixed wastes. The Program's mission was to develop a strategy for the treatment of all DOE mixed, low-level, and transuranic wastes. As part of this mission, DOE's Mixed Waste Integrated Program (MWIP) was charged with the development of innovative waste treatment technologies to surmount shortcomings of existing baseline systems. Current technology advancements and applications results from cooperation of private industry, educational institutions, and several national laboratories operated for DOE. This summary document presents the LLNL Environmental Restoration and Waste Management (ER and WM) Automation and Robotics Section's contributions in support of DOE's FY93 WPO Program. This document further describes the technological developments that were integrated in the 1993 Mixed Waste Operations (MWO) Demonstration held at SRTC in November 1993

  10. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, P. M.

    2013-02-21

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

  11. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-16

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  12. Effective summary evaluators for deep nuclear waste repositories: geohydrologic response function

    International Nuclear Information System (INIS)

    Nelson, R.W.; Dove, F.H.

    1981-03-01

    Useful insight has been gained over the past four years as hydrologic system modeling has been applied to evaluate hypothetical, waste-repository sites in various geologic media. The Geohydrologic Response Functions, described in this paper, are shown to: blend extensive results of technical analysis into simple summary relationships, and to potentially help the public and decision makers to evaluate the magnitude of any loss in repository integrity

  13. An investigation of transitional management problems for the NSTS at NASA, executive summary

    Science.gov (United States)

    Hunsucker, John

    1988-01-01

    A summary is given of the work of the University of Houston research team for the third quarter of effort in a yearly grant for the National Space Transportation System (NSTS). As such it serves as a resting place for the ideas and concepts developed this quarter with the collaboration of the Management Integration Offices of NASA. Another objective is the hope that the report will help to stimulate the healthy problem solving process already present at NASA. The main goal of the contractual work is to help NASA to find ways and means of moving into a truly operational era with the shuttle program. This work is a continuation of early work and the reader is encouraged to read the final reports of earlier years. Chapter One of the report is an introduction. Chapter Two deals with industrial adaptation and is in two parts: theory and application. In the theory section, impressions of the management system immediately after reflight are discussed. A key issue, in the author's opinion is the seeming lack of purpose of the program. The application section has six appendices: 1988 Demographic Survey, Field Notes of Interview with HL/P South Texas Nuclear Project, a comparison of the Agendas of the current manager with that of a previous manager, a note on compartmentalization to assist in manifesting, a study on launch prediction for STS-26, and a discussion of a statistical decision-making course for upper level managers. Chapter Three deals with theoretical results returned on flow shop scheduling which will be of use downstream. Chapter Four deals with a statistical model developed to predict the flight rate in future years and indicates the program will have trouble making its schedule. Chapter Five covers the constructural effort and shows the work to be on schedule.

  14. SAFIR. The Finnish research programme on nuclear power plant safety 2003-2006. Executive summary

    International Nuclear Information System (INIS)

    Puska, E.

    2006-12-01

    Major part of Finnish public research on nuclear power plant safety during the years 2003-2006 has been carried out in the SAFIR programme. The programme has been administrated by the steering group that was nominated by the Ministry of Trade and Industry (KTM). The steering group of SAFIR has consisted of representatives from Radiation and Nuclear Safety Authority (STUK), Ministry of Trade and Industry (KTM), Technical Research Centre of Finland (VTT), Teollisuuden Voima Oy (TVO), Fortum Power and Heat Oy, Fortum Nuclear Services Oy (Fortum), Finnish Funding Agency for Technology and Innovation (Tekes), Helsinki University of Technology (TKK) and Lappeenranta University of Technology (LTY). The key research areas of SAFIR have been (1) reactor fuel and core, (2) reactor circuit and structural safety, (3) containment and process safety functions, that was divided in 2005 into (3a) thermal hydraulics and (3b) severe accidents, (4) automation, control room and IT, (5) organisations and safety management and (6) risk-informed safety management. The research programme has included annually from 20 up to 24 research projects, whose volume has varied from a few person months to several person years. The total volume of the programme during the four year period 2003-2006 has been 19.7 million euros and 148 person years. The research in the programme has been carried out primarily by Technical Research Centre of Finland (VTT). Other research units responsible for the projects include Lappeenranta University of Technology, Fortum Nuclear Services Oy, Helsinki University of Technology and RAMSE Consulting Oy. In addition, there have been a few minor subcontractors in some projects. The programme management structure has consisted of the steering group, a reference group in each of the seven research areas and a number of ad hoc groups in the various research areas. This report gives a short summary of the results of the SAFIR programme for the period January 2003 - November

  15. The Nordic nuclear safety research 1990-93. Evalution and executive summary

    International Nuclear Information System (INIS)

    Marcus, F.

    1994-11-01

    A four-year Nordic research programme in the field of nuclear safety was carried through from 1990 through 1993, performed under the auspices of the Nordic Committee for Nuclear Safety Research, NKS. The aim has been to increase knowledge required to judge the safety of nuclear installations in and around the Nordic areas, and to improve and harmonize emergency preparedness. There were 19 individual projects within the four main section of the programme: Emergency preparedness, Waste and decommissioning, Radioecology, and Reactor safety. The programme was evaluated in 1994 by five evaluators, and the main emphasis was on general questions. The evaluators recommend that project plans are revised at mid-term, for updating. During the project period, NKS should use specified criteria to judge progress and success. Time tables must be adhered to. Recommendations deal with reporting and presentation of results, project leaders must disseminate information at the professional level and organize seminars. The NKS annual reports should be conceived so that they can also be used for external information. NKS should establish a policy aimed at enhanced information on its projects. Final reports should contain conclusions and recommendations which can subsequently be followed up. Directors of the competent authorities in the Nordic countries should be requested to give their views on the recommendations, and also industry, on the usefulness of results. It is proposed that NKS consider presentation of the outcome to responsible ministers and their staff. These recommendations were taken into account during 1994. (AB)

  16. Radioactive waste assessment using 'minimum waste generation' scenario - summary report March 1984

    International Nuclear Information System (INIS)

    Richardson, J.A.; Goodill, D.R.; Tymons, B.J.

    1984-11-01

    This report describes an assessment of radioactive waste management arisings from a defined nuclear power generation - Scheme 1. Scheme 1 assumes a minimum waste generation scenario with raw waste arisings from 3 main groups; (i) existing and committed commercial reactors; (ii) fuel reprocessing plants, (iii) research, industry and medicine. No decommissioning wastes are considered except for arisings from the final fuel cores from decommissioned reactors. The study uses the SIMULATION2 code which models waste material flows through the system. With a knowledge of the accumulations and average production rates of the raw wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data bases for the inventory calculations and the assumptions concerning future operation of nuclear facilities were those current in 1983. Both the inventory data and plans for the future of existing nuclear installations have been updated since these calculations were completed. Therefore the results from this assessment do not represent the most up-to-date information available. The report does, however, illustrate the methodology of assessment and indicates the type of information that can be generated. (author)

  17. Annual report of the Association EURATOM/CEA 2003 (executive summary)

    International Nuclear Information System (INIS)

    2003-01-01

    3 different materials (copper base, stainless steel and mono-crystalline molybdenum) have been selected for mirrors used in diagnostic purposes. A new diagnostic for thermographic analysis has been developed for JET. The EURATOM-Cea association is involved in the development of the first ITER neutral beam injector (in particular the source and the accelerator) and in the design of the ITER neutral beam test facility. The EURATOM-Cea association has contributed to the design of an ITER-relevant ICRH launcher that will be installed on JET during the 2004 shutdown. The development of an industrial cutting and welding laser tool for fabrication and maintenance of hydraulic connector parts of the ITER blanket module has been achieved in 2003. Work on the manufacture of the ITER primary first wall panel by HIP forming is ongoing. In the field 'plasma facing components' activities have focused on flat tile technology and particularly on the possibility of failure in cascade of these tiles. A full-scale prototype mock-up of the ITER divertor vertical target has been high flux tested. The hot isostatic pressing technique has been selected for the fabrication of lot of fusion reactor components. Concerning remote handling activities, the feasibility studies for the remote maintenance (cutting, welding and inspection) of the ITER divertor cooling pipe with bore tools have been achieved. In the field 'magnet', activities have focused on an extensive characterization of 3 types of NbTi strand candidate for ITER PF coils and on the thermohydraulic properties of cable-in-conduit conductors. The helium cooled lithium lead (HCLL) breeding blanket concept has been developed for the test blanket module. In the field 'structural materials', work has been dedicated to the development of reduced activation ferritic martensitic steel and of SiC-SiC ceramic composites and of tungsten alloys. In the framework of fusion waste management, different processes that could be used for tritium

  18. Land application uses for dry flue gas desulfurization by-products. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Dick, W.; Bigham, J.; Forster, R.; Hitzhusen, F.; Lal, R.; Stehouwer, R.; Traina, S.; Wolfe, W.; Haefner, R.; Rowe, G.

    1999-01-31

    Flue gas desulfurization (FGD) scrubbing technologies create several types of by-products. This project focused primarily on by-product materials obtained from what are commonly called ''dry scrubbers'' which produce a dry, solid material consisting of excess sorbent, reaction product that contains sulfate and sulfite, and coal fly ash. Prior to this project, dry FGD by-products were generally treated as solid wastes and disposed in landfills. However, landfill sites are becoming scarce and tipping fees are constantly increasing; The major objective of this project was to develop beneficial uses, via recycling, capable of providing economic benefits to both the producer and the end user of the FGD by-product. It is equally important, however, that the environmental impacts be carefully assessed so that the new uses developed are not only technically feasible but socially acceptable. Specific objectives developed for this project were derived over an 18-month period during extensive discussions with personnel from industry, regulatory agencies and research institutions. These were stated as follows: Objective 1: To characterize the material generated by dry FGD processes. Objective 2: To demonstrate the utilization of dry FGD by-product as a soil amendment on agricultural lands and on abandoned and active surface coal mines in Ohio. Objective 3: To demonstrate the use of dry FGD by-product as an engineering material for soil stabilization. Objective 4: To determine the quantities of dry FGD by-product that can be utilized in each of these applications. Objective 5. To determine the environmental and economic impacts of utilizing the material. Objective 6. To calibrate environmental, engineering, and economic models that can be used to determine the applicability and costs of utilizing these processes at other sites.

  19. 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

  20. High level waste vitrification at the SRP [Savannah River Plant] (DWPF [Defense Waste Processing Facility] summary)

    International Nuclear Information System (INIS)

    Weisman, A.F.; Knight, J.R.; McIntosh, D.L.; Papouchado, L.M.

    1988-01-01

    The Savannah River Plant has been operating a nuclear fuel cycle since the early 1950's. Fuel and target elements are fabricated and irradiated to produce nuclear materials. After removal from the reactors, the fuel elements are processed to extract the products, and waste is stored. During the thirty years of operation including evaporation, about 30 million gallons of high level radioactive waste has accumulated. The Defense Waste Processing Facility (DWPF) under construction at Savannah River will process this waste into a borosilicate glass for long-term geologic disposal. The construction of the DWPF is about 70% complete; this paper will describe the status of the project, including design demonstrations, with an emphasis on the melter system. 9 figs

  1. Solid Waste Information Management System (SWIMS). Data summary, Fiscal Year 1979

    International Nuclear Information System (INIS)

    Batchelder, H.M.

    1980-07-01

    The Solid Waste Information Management System (SWIMS) maintains computerized records on a master data base. It provides a comprehensive system for cataloging and assembling data into output reports. The system summarizes the solid radioactive waste generation, disposal, and storage information throughout the Department of Energy (DOE). The SWIMS data base contains the information on the transuranic (TRU) and Low-Level Waste (LLW) generated, buried, or stored by DOE facilities. The generation data covers the period from the FY 1976 transition quarter through FY 1979. The burial and storage data includes the period from site initiation through FY 1979. This document includes the DOE Summary Reports from the SWIMS, presenting the FY 1979 data and the FY 1980 forecasts. Each report is detailed by nuclide category. The categorization allows the user to separate TRU data from LLW data, etc

  2. Waste paper recycling opportunities for government action. Vol. 1 summary. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, J; Love, P

    1978-01-01

    This paper presents a summary of analyses of the current and expected waste paper market conditions in Canada with the objective of identifying government initiatives which could permanently increase recovery levels. Emphasis has been placed upon defining short-term, practical measures which take into account the variations in market conditions for each of the major types of secondary fiber: newsprint, fine paper, and corrugated cardboard. Demand, generation and recovery are analyzed for each of these types on a national and regional basis. The opportunities for increased recycling in each region are identified and recommendations are made regarding appropriate government actions. The principal benefits of increased waste paper reclamation and recycling are perceived as: reducing waste management costs, creating new industries, promoting the conserver ethic, conserving forest and energy resources, and reducing pollution. Includes glossary. 1 fig., 5 tabs.

  3. Preliminary technical data summary for the Defense Waste Processing Facility, Stage 1

    International Nuclear Information System (INIS)

    1980-09-01

    This Preliminary Technical Data Summary presents the technical basis for design of Stage 1 of the Staged Defense Waste Processing Facility (DWPF), a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material, and curie balances, material and curie balance bases, and other technical data for design of the Stage 1 DWPF

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

    International Nuclear Information System (INIS)

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

    1995-06-01

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

  5. WOCN Society Clinical Guideline: Management of the Adult Patient With a Fecal or Urinary Ostomy-An Executive Summary.

    Science.gov (United States)

    This article provides an executive summary of the recommendations from the Clinical Guideline: Management of the Adult Patient With a Fecal or Urinary Ostomy, published by the Wound, Ostomy and Continence Nurses Society (WOCN Society). It presents an overview of the process used to update and develop the guideline and lists specific recommendations from the guideline. We provide recommendations that include the following topics: stoma construction, preoperative education, stoma site marking, selection of an ostomy pouching system, postoperative education, postoperative management issues, follow-up care after discharge from the acute care setting, health-related quality of life, and stomal and peristomal complications. The intent of the guideline is to provide information that will assist healthcare providers to manage adult patients with ostomies, prevent or decrease complications, and improve patient outcomes. The full text of the published guideline, which includes available evidence supporting the recommendations and a complete reference list, is available in print and as a mobile application from the WOCN Society's online bookstore (http://www.wocn.org). Refer to Supplemental Digital Content 1 (available at: http://links.lww.com/JWOCN/A40) associated with this article for a complete reference list for the guideline.

  6. Forschende und ihre Daten: Ergebnisse einer österreichweiten Befragung. Report 2015 – Executive Summary und Empfehlungen

    Directory of Open Access Journals (Sweden)

    Bruno Bauer

    2015-01-01

    Full Text Available Der vorliegende Beitrag bringt Executive Summary und Empfehlungen aus „Forschende und ihre Daten: Ergebnisse einer österreichweiten Befragung. Report 2015“. Dieser Report gibt einen Überblick über die österreichweite Befragung zu Forschungsdaten, die im Rahmen des Projekts e-Infrastructures Austria 2015 durchgeführt wurde. Diese richtete sich an das wissenschaftliche und künstlerisch-wissenschaftliche Personal aller 21 öffentlichen Universitäten sowie an drei außeruniversitäre Forschungseinrichtungen in Österreich. Die Teilnehmenden wurden zu folgenden Themenbereichen befragt: Datentypen und Formate; Datenarchivierung, -sicherung und -verlust; ethische und rechtliche Aspekte; Zugänglichkeit und Nachnutzung; Infrastruktur und Services. Die in diesem Kontext erstmals auf nationaler Ebene durchgeführte Befragung diente der Erhebung des praktischen Umgangs mit Forschungsdaten in Österreich und ist somit die Basis für eine konsekutive Optimierung der zweckdienlichen Infrastruktur, für eine Anpassung der Serviceangebote sowie für eine Neuorientierung bei der Ermittlung von Ressourcen in diesem strategischen Bereich entsprechend der geäußerten Bedürfnisse der im Forschungsprozess Tätigen.

  7. Study of environmental impact assessment for Mochovce NPP Units 3 and 4. Executive summary. September 2007

    International Nuclear Information System (INIS)

    Anon

    2007-09-01

    Regional Authority in Nitra No. 97/02276-004 and further by Decision of the Regional Construction Authority in Nitra No. 2004/00402-007 dated 15 July 2004 (the current Construction Permit for Completion of MO34). Construction work on Units 3 and 4 was halted in 1992 and since that time attention has been paid to preservation and protection of components so that they will be immediately ready for further work when a decision was taken about the completion. On the basis of the valid construction permit and according to current legislation there is no legal obligation to follow an Environmental Impact Assessment (EIA) procedure for the completion of Units 3 and 4 of Mochovce NPP. The project consists of the completion of two units, Units 3 and 4, of an the existing nuclear power plant whose operation started in 1998 and 2000 for Unit 1 and Unit 2 respectively. In particular the Project includes the completion and the operation of Units 3 and 4 and the operations of all four units (4 x 440 MW) to generate overall 1,760 MW of electricity for distribution to the Slovak Republic grid. The Project includes management of used fuel and radioactive waste produced through the operating life of the power station. After 40 years of operation the power station would be decommissioned. Since the Mochovce NPP is an existing plant, previous EIA and environmental studies were carried out in order to assess the effects of the construction phase of the 4 units and related facilities. At the moment Units 3 and 4 are completed about 70% in civil part and about 40% in mechanical part. Therefore the present study focuses on likely additional environmental effects of an existing facility, as a result of the completion and operation of Units 3 and 4. The Environmental Impact Assessment has been divided into several basis sections, each comprising a number of chapters of the overall report

  8. Tank Waste Transport Stability: Summaries of Hanford Slurry and Salt-Solution Studies in FY 2000

    Energy Technology Data Exchange (ETDEWEB)

    Welch, T.D.

    2002-07-08

    This report is a collection of summary articles on FY 2000 studies of slurry transport and salt-well pumping related to Hanford tank waste transfers. These studies are concerned with the stability (steady, uninterrupted flow) of tank waste transfers, a subset of the Department of Energy (DOE) Tanks Focus Area Tank (TFA) Waste Chemistry effort. This work is a collaborative effort of AEA Technology plc, the Diagnostic Instrumentation and Analysis Laboratory at Mississippi State University (DIAL-MSU), the Hemispheric Center for Environmental Technology at Florida International University (HCET-FIU), Numatec Hanford Corporation (NHC), and the Oak Ridge National Laboratory (ORNL). The purpose of this report is to provide, in a single document, an overview of these studies to help the reader identify contacts and resources for obtaining more detailed information and to help promote useful interchanges between researchers and users. Despite over 50 years of experience in transporting radioactive tank wastes to and from equipment and tanks at the Department of Energy's Hanford, Savannah River, and Oak Ridge sites, waste slurry transfer pipelines and process piping become plugged on occasion. At Hanford, several tank farm pipelines are no longer in service because of plugs. At Savannah River, solid deposits in the outlet line of the 2H evaporator have resulted in an unplanned extended downtime. Although waste transfer criteria and guidelines intended to prevent pipeline plugging are in place, they are not always adequate. To avoid pipeline plugging in the future, other factors that are not currently embodied in the transfer criteria may need to be considered. The work summarized here is being conducted to develop a better understanding of the chemical and waste flow dynamics during waste transfer. The goal is to eliminate pipeline plugs by improving analysis and engineering tools in the field that incorporate this understanding.

  9. A summary of radiological waste disposal practices in the United States and the United Kingdom - 16379

    International Nuclear Information System (INIS)

    Maranville, Victoria M.; McGrath, Richard

    2009-01-01

    A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. The main focus of the review consisted of a literature search of available documents and other published sources on low level radioactive waste (LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by the United Kingdom's (UK) Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site. The review contained a summary of the US and UK radiological waste classification requirements including a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices. A regulatory overview and evolution of regulatory requirements in the US is presented. The UK regulatory environment is also discussed and contrasted to the US process. The public participation, as part of the US regulatory process, is provided and the mechanism for stakeholder identification and involvement is detailed. To demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies, in which remediation activities were carried out, were reviewed. The following information was compiled: type of wastes disposed of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is discussed within the case studies. Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are presented in this publication for

  10. Crystal accumulation in the Hanford Waste Treatment Plant high level waste melter: Summary of 2017 experiments

    Energy Technology Data Exchange (ETDEWEB)

    Fox, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fowley, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2018-01-11

    A full-scale, transparent mock-up of the Hanford Tank Waste Treatment and Immobilization Project High Level Waste glass melter riser and pour spout has been constructed to allow for testing with visual feedback of particle settling, accumulation, and resuspension when operating with a controlled fraction of crystals in the glass melt. Room temperature operation with silicone oil and magnetite particles simulating molten glass and spinel crystals, respectively, allows for direct observation of flow patterns and settling patterns. The fluid and particle mixture is recycled within the system for each test.

  11. Identification and management of cardiometabolic risk in Canada: a position paper by the cardiometabolic risk working group (executive summary).

    Science.gov (United States)

    Leiter, Lawrence A; Fitchett, David H; Gilbert, Richard E; Gupta, Milan; Mancini, G B John; McFarlane, Philip A; Ross, Robert; Teoh, Hwee; Verma, Subodh; Anand, Sonia; Camelon, Kathryn; Chow, Chi-Ming; Cox, Jafna L; Després, Jean-Pierre; Genest, Jacques; Harris, Stewart B; Lau, David C W; Lewanczuk, Richard; Liu, Peter P; Lonn, Eva M; McPherson, Ruth; Poirier, Paul; Qaadri, Shafiq; Rabasa-Lhoret, Rémi; Rabkin, Simon W; Sharma, Arya M; Steele, Andrew W; Stone, James A; Tardif, Jean-Claude; Tobe, Sheldon; Ur, Ehud

    2011-01-01

    With the objectives of clarifying the concepts related to "cardiometabolic risk," "metabolic syndrome" and "risk stratification" and presenting practical strategies to identify and reduce cardiovascular risk in multiethnic patient populations, the Cardiometabolic Working Group presents an executive summary of a detailed analysis and position paper that offers a comprehensive and consolidated approach to the identification and management of cardiometabolic risk. The above concepts overlap and relate to the atherogenic process and development of type 2 diabetes. However, there is confusion about what these terms mean and how they can best be used to improve our understanding of cardiovascular disease treatment and prevention. The concepts related to cardiometabolic risk, pathophysiology, and strategies for identification and management (including health behaviours, pharmacotherapy, and surgery) in the multiethnic Canadian population are presented. "Global cardiometabolic risk" is proposed as an umbrella term for a comprehensive list of existing and emerging factors that predict cardiovascular disease and/or type 2 diabetes. Health behaviour interventions (weight loss, physical activity, diet, smoking cessation) in people identified at high cardiometabolic risk are of critical importance given the emerging crisis of obesity and the consequent epidemic of type 2 diabetes. Vascular protective measures (health behaviours for all patients and pharmacotherapy in appropriate patients) are essential to reduce cardiometabolic risk, and there is growing consensus that a multidisciplinary approach is needed to adequately address cardiometabolic risk factors. Health care professionals must also consider ethnicity-related risk factors in order to appropriately evaluate all individuals in their diverse patient populations. Copyright © 2011 American College of Cardiology Foundation. Published by Elsevier Inc. All rights reserved.

  12. Executive summary 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    Blue Energy Canada is a company that focuses on ocean energy technology. Considered the world's most advanced such technology, it involves high-density seawater passing through advanced vertical axis hydro turbines that are used to convert the kinetic energy in ocean currents, tides and rivers to low-cost electric power. A ten-year collaboration effort with the National Research Council of Canada (NRC) led to the development of the successful prototypes. A privately funded prototype was successfully implemented which generated power from the Florida Gulf Stream. The NRC, as well as independent engineering assessments have proven that the technology is sound and ready for the next phase: commercialization. This low-cost technology compares favorably with hydro, thermal nuclear, and wind energy. Once fuel and maintenance costs are included, micro units will be cost competitive with diesel generators. The high density of the system is approximately 180 times greater than that of wind and solar technologies. Its environmental impact is minimal, generating no pollution or emitting no greenhouse gases, and does not affect the flow of silt, fish and aquatic life. Marine fences will be erected to protect marine mammals from the turbines, coupled with a backup auto-braking system controlled by sonar sensors. It is possible to reliably predict the energy output based on the cyclical tidal patterns. The design is modular, allowing for the production of power as soon as the first turbine is installed. The addition of turbines will provide incremental capacity. The multiple infrastructure design allows the structure to be used to carry water mains, fiber optics, power lines and phone lines, thereby sharing construction costs. The technology ensures a low maintenance since generator and gearbox are both located above water level, eliminating the requirement for seals and the associated risks. The commercialization plan was detailed, with phase I projected for the implementation of a 500 kW demonstration project off the coast of British Columbia. The implementation of phase II involves utilizing the technology developed by Blue Energy to electrolyse clean hydrogen to fuel a 250 kW stationary hydrogen fuel cell. The manufacturing process uses an automated assembly line, and the cost is competitive with other distributed power systems. Large scale power projects are being developed, with the focus placed on Taiwan, the Philippines, the United Kingdom and the United States in 2005. The funding was briefly discussed and the use of proceeds detailed. 1 fig.

  13. Executive Summary - Historical background

    International Nuclear Information System (INIS)

    2005-01-01

    The Institute of Nuclear Physics (INP) was established in Cracow in 1955. The post-war excitement of engaging in scientific activity, can certainly be credited to the talent, experience and unusual personality of Professor Henryk Niewodniczanski, the founder and first Director of the INP. In the 60's the INP research activity was concentrated around the Russian U120 Cyclotron, built in 1958 which provided deuteron beams up to 14.5 MeV and of alpha particles up to 29 MeV. A small 48 cm pole-piece cyclotron with was in-house constructed, and used for PIXE analyses and RBA material studies. In 1960's, the nuclear spectroscopy group began building several types of magnetic beta ray spectrometers to study excited levels of neutron-deficient isotopes provided by the 660 MeV cyclotron of the JINR. In parallel, studies of spin polarization of n and p emitted in the deuteron stripping reaction were performed. Studies of condensed matter using pulsed neutron beams from the IBR30 and Kjeller (Norway) reactors had also began. The NMR signal was first observed in Poland by physicists from the Jagiellonian University, and a well equipped NMR Laboratory was also created at the INP. A small theoretical physics department was established to support experimental research. Applied physics, based on the research performed in the INP was also developed. Following the interest in fast neutron radiotherapy, initiated by the Gray Laboratory in Hammersmith, a beam of fast neutrons was produced on a Be target by 13.5 MeV deuterons from the U120 and applied for cancer therapy, in a collaborative effort with the Centre of Oncology in Cracow. Over a period of 10 years, some 500 patients were treated, in selected types of salivary gland cancer and post-mastectomy recurrences. In the late 60's a technology of thermoluminescent dosimeters (TLD) was developed at the INP, based on specially activated LiF. The method was patented and TLDs, manufactured at the INP, are nowadays applied by in over 30 countries. The INP had an important role to play during and after the Chernobyl accident, by serving the population with measurements of radioactive contamination of air, soil and food. This work is being continued, with a permanent early-warning and monitoring station at the INP, an element of the national radiation monitoring system. After 38 years of operation the U-120 cyclotron was replaced by an inhouse constructed 144 cm pole-piece AIC-144 one able to accelerate protons up to 60 MeV, which is now used to produce short-lived beta-plus isotopes and will be able to provide a proton beam for treating ocular melanoma. The small 48-cm cyclotron was replaced by a 2.5 MeV Van de Graaff accelerator. With a microbeam capacity, it serves to continue and further develop the interdisciplinary research in cell biology, archaeology and material structure. The particle and high energy physics group, which joined the INP in 1970 (and had originated from the Cosmic Ray Studies group initiated in 1938 by Professor Marian Miesowicz at the Academy of Mining and Metallurgy) was initially connected with accelerators of the JINR and later was able to expand to CERN and DESY. The theoretical physics group had also expanded, engaging in particle theory and astrophysics. We take part in assembling the LHC. We entered the ATLAS, ALICE, and LHCb collaborations and may possibly join the CASTOR project. We took part in constructing the HERA collider and are collaborators in the large ZEUS and H1 projects. We joined the TESLA project. Within the ZEUS collaboration we built the luminosity detector. At the RHIC collider we constructed a large part of the PHOBOS detector and within this collaboration we made a contribution to the discovery of the new state of hadronic matter. Within the BELLE collaboration at KEK we took part in the measurements of the CP violation effects in the B mesons decay. Our scientists participate in experiments performed at GANIL, Legnaro and GSI. We carry out condensed matter physics experiments at the High Flux Reactor of The Laue Langevin Institute and the ISIS spallation source at Rutherford-Appleton. Recently, we very actively entered the ICARUS neutrino collaboration and were invited to the PIERRE AUGER collaboration which will search for the highest energies in the Universe. Having close ties with CERN we are very actively engaged in CROSS-GRID, a large computer network project. To better understand the historical background of the INP development, it is necessary to add a few comments on financing of science in Poland. During the 70's and the 80's, research was financed through the so-called Central Research Projects for Science and Technical Development. The advantage of this system was that state-allocated research funds were divided only by a few representatives of the scientific community, which allowed realistic allocation of money to a small number of projects. After 1989 we were able to purchase commercially available equipment, which led to the closure of our large and very experienced electronic workshop. We also considerably reduced our well equipped mechanical shop. During the 90's the reduced state financing of science was accompanied by a newly established Committee of Scientific Research which led to the creation of a system of small research projects. This precluded the development of more ambitious research projects and led to the dispersion of equipment among many smaller laboratories and universities. A large research establishment, such as our Institute, could not develop properly under such conditions. In all, between 1989 and 2004 we reduced our personnel from about 800 to 470 and our infrastructure became seriously undercapitalised. However, with energetic search for research funds, from European rather than national research programs, we hope to improve and modernize our laboratories and their infrastructure in the coming years

  14. Artificial intelligence executive summary

    International Nuclear Information System (INIS)

    Wamsley, S.J.; Purvis, E.E. III

    1984-01-01

    Artificial intelligence (AI) is a high technology field that can be used to provide problem solving diagnosis, guidance and for support resolution of problems. It is not a stand alone discipline, but can also be applied to develop data bases for retention of the expertise that is required for its own knowledge base. This provides a way to retain knowledge that otherwise may be lost. Artificial Intelligence Methodology can provide an automated construction management decision support system, thereby restoring the manager's emphasis to project management

  15. Course Correction: Executive Summary

    Science.gov (United States)

    Allen, Nicole

    2009-01-01

    Textbooks are an essential, but increasingly expensive part of obtaining a college degree. Digital textbooks are a promising way to lower costs for students. The digital format has the potential to cut production costs, increase options for students, and open up the market to more competition. Digital textbooks are now beginning to gain a more…

  16. Executive Summary - Our mission

    International Nuclear Information System (INIS)

    2007-01-01

    Full text: The Henryk Niewodniczanski Institute of Nuclear Physics (Instytut Fizyki Jadrowej im. Henryka Niewodniczanskiego, IFJ PAN) is currently the largest research institution of the Polish Academy of Sciences (Polska Akademia Nauk). The research activity of the Academy is financed mainly from the State budget via the Ministry of Science and Higher Education. The mission of IFJ PAN is stated in its Charter. According to Paragraphs 5, 6, and 7 of the 2004 Charter, the Institute's duty is to carry out research activities in the following areas: 1. High energy and elementary particle physics (including astrophysics), 2. Nuclear physics and strong interaction, 3. Condensed matter physics, 4. Interdisciplinary research, in particular: in radiation and environmental biology, environmental physics, medical physics, dosimetry, nuclear geophysics, radiochemistry and material engineering. The main tasks of the Institute are: 1. To perform research in the above disciplines, 2. To promote the development of scientists and of specialists qualified to carry out research in these disciplines, 3. To organize a Post-Graduate Study Course, 4. To permit, through agreements with national and foreign research institutions, external scholars to train and gain academic qualifications in the Institute's laboratories, 5. To collaborate with national and local authorities in providing them with expertise in the Institute's research topics, especially concerning radiation protection. These tasks are fulfilled by: 1. Performing individual and coordinated research through individual and collective research grant projects, 2. Initiating and maintaining cooperation with laboratories, organizations and institutions performing similar activities, in Poland and abroad, 3. Conferring scientific degrees and titles, 4. Distributing research results obtained, through peer-reviewed publications and other public media, 5. Organizing scientific meetings, conferences, symposia, training workshops, etc., 6. Providing expertise and analytic reports to government institutions and local authorities, 7. Carrying out other duties, within the statutory mandate of the Institute. In November 2004 the president of the Polish Academy of Sciences, Prof. A. Legocki, constituted the Scientific Advisory Board, SAB, to review the scientific activities of the Institute. The Board was asked to assess the present state of IFJ PAN, in particular the quality of its research as measured on an international scale and to provide recommendations in order for the Institute to strengthen its position and future research goals. The first review took place in February 2005 and in March 2005 SAB formulated its recommendations. SAB stressed the need to maintain and strengthen the role of fundamental research and to cultivate its strong links with the international scientific community, particularly with large laboratories such as CERN, DESY, GANIL, GSI, and ILL. In applied sciences IFJ PAN should remain attractive for Polish scientists, particularly to continue to make use of some of its unique facilities and laboratories. SAB also recommended to maintain the funding of the high level engineering and technical support, which gives a unique opportunity to support the new experiments in physics. It was also underlined that the role of young people in leading positions should be strengthened. (author)

  17. SCIL Executive Summaries.

    Science.gov (United States)

    Samuels, Alan R.; And Others

    1987-01-01

    These five papers by speakers at the Small Computers in Libraries 1987 conference include: "Acquiring and Using Shareware in Building Small Scale Automated Information systems" (Samuels); "A Software Lending Collection" (Talab); "Providing Subject Access to Microcomputer Software" (Mitchell); "Interfacing Vendor…

  18. Executive Summary - Our mission

    International Nuclear Information System (INIS)

    2005-01-01

    On September 1 st 2003, the Henryk Niewodniczanski Institute of Nuclear Physics in Cracow joined the Polish Academy of Sciences. The Polish Academy of Sciences (PAN), founded in 1952, is a state-sponsored scientific institution acting through an elected corporation of leading scholars, their research organizations and through numerous scientific establishments. PAN is a major national scientific advisory body acting via its scientific committees which represent all disciplines of science. There are currently 79 PAN research establishments (institutes and research centers, research stations, botanical gardens and other research units) and a number of auxiliary scientific units (such as archives, libraries, museums, and PAN stations abroad). Our Institute is currently one of the largest research institutions of the Polish Academy of Sciences. The research activity of the Academy is financed mainly from the State budget via the Ministry of Scientific Research and Information Technology. The mission of the Institute of Nuclear Physics, IFJ is stated in its Charter. According to Paragraphs 5, 6, and 7 of the 2004 Charter, the Institute's duty is to carry out research activities in the following areas:1. High energy and elementary particle physics (including astrophysics), 2. Nuclear physics and physics of mechanisms of nuclear interaction, 3. Condensed matter physics, 4. Interdisciplinary research, and in particular: in radiation and environmental biology, environmental physics, medical physics, dosimetry, nuclear geophysics, radiochemistry and material engineering. The main tasks of the Institute are: 1. To perform research in the above disciplines, 2. To promote the development of scientists and of specialists qualified to carry out research in these disciplines, 3. To organize a Post-Doctoral Study Course, 4. To permit, through agreements with national and foreign research institutions, external scholars to train and gain academic qualifications in the Institute's laboratories, 5. To collaborate with national and local authorities in providing them with expertise in the Institute's research topics, especially concerning radiation protection. These tasks are fulfilled by: 1. Performing individual and coordinated research through individual and collective research grant projects, 2. Initiating and maintaining cooperation with laboratories, organizations and institutions performing similar activities, in Poland and abroad, 3. Conferring scientific degrees and titles, 4. Distributing research results obtained, through peer-reviewed publications and other public media, 5. Organizing scientific meetings, conferences, symposia, training workshops, etc., 6. Providing expertise and analytic reports to government institutions and local authorities, 7. Carrying out other duties, within the statutory mandate of the Institute

  19. Preliminaries & Executive Summary

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

    jg

    2007-05-29

    May 29, 2007 ... and government officials struggling with designing an appropriate policy and/or ..... of production, such as labour, supporting them while they re-tool. ...... manufacturers of polythene pipes engaged in bid rigging claimed that ...

  20. Chapter 0: Executive summary

    International Nuclear Information System (INIS)

    1995-01-01

    This chapter deals with the background (Gabcikovo hydro power scheme was input in October 1992), project objective, project framework, equipment, establishment of the integrated modelling system, model setup, calibration and validation, definitions of scenarios for model application and with the results of model applications

  1. Executive Summary - Future plans

    International Nuclear Information System (INIS)

    2005-01-01

    Our Institute has sufficient scientific potential to play a key role in the field of particle physics, nuclear physics and in several aspects of solid state and applied physics, at least in our part of Europe. We believe the Institute should continue its present mode of operation, where basic research, closely coordinated through our collaboration with leading laboratories all over the world, stimulates our interdisciplinary research and technology transfer to the industry. If our present scientific potential is matched by suitably modernized infrastructure, we should be able to acquire the critical mass necessary for further effective development. In order to maintain our present world-level research, we have to continue and further extend our participation in large international collaborations, in the construction of large detectors and to seek further financial support from EU and international organizations. For experimental particle physics, our priorities remain in collaborating with major European and world laboratories such as CERN, DESY, Gran Sasso, Fermilab, KEK, SLAC and with laboratories developing astrophysics experiments, such as the PIERRE AUGER experiment. Collaboration in the field of nuclear physics, physics of condensed matter, theoretical physics and interdisciplinary research should be continued with leading European laboratories offering access to large accelerator facilities (such as GANIL or GSI), to synchrotron radiation or to unique polarized neutron beams, such as those available at ILL Grenoble. An exiting new frontier in research for our research teams will be opened by the X-ray Free Electron Laser (XFEL) in DESY and the future International Linear Collider. We will be able to further invest towards upgrading our small-scale facilities, such as the infrastructure around the Van de Graaff accelerator, in order to perform single-ion beam experiments, or around the AIC-144 cyclotron, to treat ocular melanoma, in close collaboration with ophthalmologists at the Collegium Medicum (Jagiellonian University) and radiotherapists at the Centre of Oncology. Our Institute is capable of providing PET isotopes to the local medical community. We will continue to upgrade our technical infrastructure and research equipment basing on Structural Funds of the European Commission. We are able to achieve this through our Centres of Excellence and Centres of Advanced Technologies. We will further continue to strongly support the application of methods of nuclear physics in biological and medical research, such as single-ion studies of the effects of low-radiation doses, Nuclear Magnetic Resonance research in physiology, the Atomic Force microscope for studying properties of cell and membranes, the chromosome aberration/DNA studies for biological dosimetry, or advanced dosimetry techniques for medical physics and space dosimetry. We shall also continue our obligation to serve the national and local authorities with our expertise in radiation protection and dosimetry. We intend to further support the development of geophysical methods for searching natural resources. In view of the current discussion on the future sources of energy in Poland, our Institute will actively engage in promoting nuclear energy, based on new-generation reactor technology. We will be actively seeking the opportunity of maintaining the tradition of our Institute being focused around its major accelerator facility. While the present AIC-144 cyclotron is no longer adequate for treatment of deep-seated tumors, a medium-sized synchrotron able to accelerate light ions to energies of some several hundred MeV/amu, capable of generating ion beams suitable for light-ion radiotherapy, could fulfill this role, stimulating a renewal of our past close collaboration with radiotherapists in fighting cancer. Such radiotherapy centres are currently under development in other parts of the European Community. We will actively seek the opportunities to obtain external funding for this purpose. However, we are fully aware of the difficulty of introducing cutting-edge medical technology to the Polish national health care system, in view of the immediate needs of this seriously undercapitalized service of our 40-million community. We need to devote special attention to further training our personnel. The present potential of the Institute allows our research group to participate in the most ambitious projects and collaborations. Availability of such highly educated and experienced technical staff is absolutely essential for performing this type of work. Such personnel is not usually available at universities, where the potential is spread-out to a much larger extent. We would like to maintain our group of engineers specialized in the development and construction of detectors, dedicated electronics and software needed for experimental physics. One of the principal goals of the Institute is to promote professional careers of young researchers in Poland. We would like to increase the participation of undergraduate and graduate (Ph.D.) students and short-term postdoctoral researchers, originating from Europe and outside, in activities of the research groups in the Institute. We plan to strengthen our cooperation with universities and technical universities in southern Poland (Cracow, Rzeszow, Kielce, Katowice and others) by teaching students and providing our laboratories and expertise to help them complete their theses. Further development of our International Post-Graduate Study Course, in collaboration with other institutions in the European Research Area, will be strongly supported

  2. Summary of the Environmental Impact Statement on the concept for disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    1994-01-01

    This is the Summary of the Environmental Impact Statement (EIS) prepared by Atomic Energy of Canada Limited (AECL) on the concept for disposal of Canada's nuclear fuel waste. The proposed concept is a method for geological disposal, based on a system of natural and engineered barriers. The EIS provides information requested by the Environmental Assessment Panel reviewing the disposal concept and presents AECL's case for the acceptability of the concept. The introductory chapter of this Summary provides background information on several topics related to nuclear fuel waste, including current storage practices for used fuel, the need for eventual disposal of nuclear fuel waste, the options for disposal, and the reasons for Canada's focus on geological disposal. Chapter 2 describes the concept for disposal of nuclear fuel waste. Because the purpose of implementing the concept would he to protect human health and the natural environment far into the future, we discuss the long-term performance of a disposal system and present a case study of potential effects on human health and the natural environment after the closure of a disposal facility. The effects and social acceptability of disposal would depend greatly on how the concept was implemented. Chapter 3 describes AECL's proposed approach to concept implementation. We discuss how the public would be involved in implementation; activities that would be undertaken to protect human health, the natural environment, and the socio-economic environment; and a case study of the potential effects of disposal before the closure of a disposal facility. The last chapter presents AECL's Conclusion, based on more than 15 years of research and development, that implementation of the disposal concept represents a means by which Canada can safely dispose of its nuclear fuel waste. This chapter also presents AECL's recommendation that Canada progress toward disposal of its nuclear fuel waste by undertaking the first stage of concept

  3. INFX guide: summary of US DOE plans and policies for international cooperation in the field of radioactive waste management

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.

    1981-01-01

    The purpose of this document is to provide, in one source, an overview and summary of major international cooperative activities such as long-term personnel exchanges, planning of complementary R and D programs, and testing programs like the one at Stripa for use by DOE and DOE contractor personnel responsible for planning such programs. The contents are as follows: waste management-general, high-level waste immobilization; transuranic wastes; low-level radioactive waste; airborne wastes; waste isolation in geologic repositories; marine disposal; spent fuel storage; transportation; uranium mill tailings; decontamination and decommissioning; and appendices which are for bilaterial waste management agreements; INFX policies and procedures, DOE contractor personnel and international agencies

  4. Executive summary of a draft report on the geology and salt deposits of the Salina Salt Basin

    International Nuclear Information System (INIS)

    1978-01-01

    The study discussed is the first phase of a program for the geologic evaluation of the Silurian-age bedded salt of the Salina Group. The Salina Salt Basin, as used in this study, includes those portions of the Appalachian and Michigan basins that are underlain by the Salina Group. The full draft report consists of a regional reconnaissance, identification of study areas in New York and Ohio which are deserving of a more thorough evaluation, and a program plan to accomplish that evaluation. The entire draft report is in two volumes, contains 1068 pages and 204 figures, and has a bibliography that consists of over 1100 separate entries. This summary has been prepared for the benefit of those who wish to review the results of this phase of the evaluation but who do not want to go through the exhaustive detail that is present in the full report. The regional reconnaissance was accomplished by a very thorough and extensive literature review, addressing the following topics: depth of salt, thickness, stratigraphy, tectonics, structure, seismicity, hydrology, erosion and denudation, and mineral resources. Before further technical evaluation proceeds, the draft report and the proposed program are being subjected to a thorough evaluation by a number of groups, including appropriate state agencies. This rather extensive review process is being conducted to ensure that the program is performed entirely in the open and subject to continuous public surveillance. This report does not represent the first work that has been done in this region with regard to evaluating the salt deposits for waste disposal. Previous efforts have been limited, however, and have been done by individual consultants. At the present time, the U.S. Geological Survey is also participating in the technical evaluation; their results will be issued separately. In addition to the technical evaluations, environmental surveys will also be conducted as an integral part of this thorough evaluation program

  5. ORNL long-range environmental and waste management plan: Program overview and summary

    International Nuclear Information System (INIS)

    Bates, L.D.; Berry, J.B.; Butterworth, G.E.

    1988-04-01

    The primary purpose of this report is to provide a thorough and systematic planning document to reflect the continuing process of site assessment, strategy development, and planning for the current and long-term control of environmental issues, waste management practices, and remedial action requirements. The docuemnt also provides an estimate of the resources required to implement the current plan. This document is not intended to be a budget document: it is, however, intended to provide guidance to both Martin Marietta Energy Systems, Inc., and the US Department of Energy (DOE) Management as to the near order of magnitude of the resources (primarily funding requirements) and the time frame required to execute the strategy in the present revision of the plan. The near-term (one to three years) part of the plan is a realistic assessment of the current program and ongoing capital projects and reflects the efforts preceived to be necessary to comply with all current state and federal regulations and DOE orders. It also should be in general agreement with current budget (funding) requests and obligations for these immediate years. Beyond the immediate time frame, the document reflects the strategy and the project and funding estimates as a snapshot at the time of publication. Annual revision will reflect the continuing evoltuion and development of environmental and waste management processes, characterizations, remedial actions, regulations, an strategies for the establishment and conduct of a comprehensive environmental and waste management program. 15 figs., 10 tabs

  6. Production development and utilization of Zimmer Station wet FGD by-products. Final report. Volume 1, Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Kevin [Dravo Technology Center, Pittsburgh, PA (United States); Beeghly, Joel H. [Dravo Technology Center, Pittsburgh, PA (United States)

    2000-11-30

    About 30 electric utility units with a combined total of 15,000 MW utilize magnesium enhanced lime flue gas desulfurization (FGD) systems. A disadvantage of this and other inhibited or natural oxidation wet FGD systems is the capital and operating cost associated with landfill disposal of the calcium sulfite based solids. Fixation to stabilize the solids for compaction in a landfill also consumes fly ash that otherwise may be marketable. This Executive Summary describes efforts to dewater the magnesium hydroxide and gypsum slurries and then process the solids into a more user friendly and higher value form. To eliminate the cost of solids disposal in its first generation Thiosorbic® system, the Dravo Lime Company developed the ThioClear® process that utilizes a magnesium based absorber liquor to remove S02 with minimal suspended solids. Magnesium enhanced lime is added to an oxidized bleed stream of thickener overflow (TOF) to produce magnesium hydroxide [Mg(OH)2] and gypsum (CaS04 • 2H20), as by-products. This process was demonstrated at the 3 to 5 MW closed loop FGD system pilot plant at the Miami Fort Station of Cinergy, near Cincinnati, Ohio with the help of OCDO Grant Agreement CDO/D-91-6. A similar process strictly for'recovery and reuse of Mg(OH)2 began operation at the Zimmer Station of Cinergy in late 1994 that can produce 900 pounds of Mg(OH)2 per hour and 2,600 pounds of gypsum per hour. This by-product plant, called the Zimmer Slipstream Magnesium Hydroxide Recovery Project Demonstration, was conducted with the help of OCDO Grant Agreement CDO/D-921-004. Full scale ThioClear® plants began operating in 1997 at the 130 MW Applied Energy Services plant, in Monaca, PA, and in year 2000 at the 1,330 MW Allegheny Energy Pleasants Station at St. Marys, WV.

  7. Summary of Laboratory Capabilities Fact Sheets Waste Sampling and Characterization Facility and 222-S Laboratory Complex

    International Nuclear Information System (INIS)

    HADLEY, R.M.

    2002-01-01

    This summary of laboratory capabilities is provided to assist prospective responders to the CH2M HILL Hanford Group, Inc. (CHG) Requests for Proposal (RFP) issued or to be issued. The RFPs solicit development of treatment technologies as categorized in the CHG Requests for Information (RFI): Solid-Liquid Separations Technology - SOL: Reference-Number-CHG01; Cesium and Technetium Separations Technology - SOL: Reference-Number-CHG02; Sulfate Removal Technology - SOL: Reference-Number-CHG03; Containerized Grout Technology - SOL: Reference-Number-CHG04; Bulk Vitrification Technology - SOL: Reference-Number-CHG05; and TRU Tank Waste Solidification for Disposal at the Waste Isolation Pilot Plant - SOL: Reference-Number-CHG06 Hanford Analytical Services, Technology Project Management (TPM), has the capability and directly related experience to provide breakthrough innovations and solutions to the challenges presented in the requests. The 222-S Complex includes the 70,000 sq ft 222-S Laboratory, plus several support buildings. The laboratory has 11 hot cells for handling and analyzing highly radioactive samples, including tank farm waste. Inorganic, organic, and radiochemical analyses are performed on a wide variety of air, liquid, soil, sludge, and biota samples. Capabilities also include development of process technology and analytical methods, and preparation of analytical standards. The TPM staff includes many scientists with advanced degrees in chemistry (or closely related fields), over half of which are PhDs. These scientists have an average 20 years of Hanford experience working with Hanford waste in a hot cell environment. They have hundreds of publications related to Hanford tank waste characterization and process support. These would include, but are not limited to, solid-liquid separations engineering, physical chemistry, particle size analysis, and inorganic chemistry. TPM has had revenues in excess of $1 million per year for the past decade in above

  8. Congressional-executive interaction and the nuclear waste repository site selection process

    International Nuclear Information System (INIS)

    Thurber, J.A.; Evanson, T.C.

    1993-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA) (P.L. 97-425) and the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) (Title V of P.L. 100-203) provide the framework for the DOE Office of Civilian Radioactive Waste Management (OCRWM) to find a permanent means for disposing of high-level nuclear waste in the US. The focus of this study is the congressional decision-making process associated with passage of the Nuclear Waste Policy Amendments Act of 1987. The passage of NWPAA was a direct result of the failure of the policy adopted in the Nuclear Waste Policy Act of 1982. This study analyzes the nature of congressional nuclear waste policy-making through the lens of subsystems theory. The data analysis is primarily based on confidential interviews with over fifty key actors in the nuclear waste policy subsystem as well as an analysis of primary source documents

  9. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Summary

    International Nuclear Information System (INIS)

    1997-05-01

    This Waste Management Programmatic Environmental Impact Statement (WM PEIS) is a nationwide study examining the environmental impacts of managing five types of radioactive and hazardous wastes generated by past and future nuclear defense and research activities at a variety of sites located around the United States. The five waste types are low-level mixed waste (LLMW), low-level waste (LLW), transuranic waste (TRUW), high-level waste (HLW), and hazardous waste (HW)

  10. Summary report of a seminar on geosphere modelling requirements of deep disposal of low and intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    Piper, D.; Paige, R.W.; Broyd, T.W.

    1989-02-01

    A seminar on the geosphere modelling requirements of deep disposal of low and intermediate level radioactive wastes was organised by WS Atkins Engineering Sciences as part of Her Majesty's Inspectorate of Pollution's Radioactive Waste Assessment Programme. The objectives of the seminar were to review geosphere modelling capabilities and prioritise, if possible, any requirements for model development. Summaries of the presentations and subsequent discussions are given in this report. (author)

  11. Tank waste remediation system privatization Phase 1 infrastructure, project W-519, project execution plan

    International Nuclear Information System (INIS)

    Parazin, R.J.

    1998-01-01

    This Project Execution Plan (PEP) defines the overall strategy, objectives, and contractor management requirements for the execution phase of Project W-519 (98-D403), Privatization Phase 1 Infrastructure Support, whose mission is to effect the required Hanford site infrastructure physical changes to accommodate the Privatization Contractor facilities. This plan provides the project scope, project objectives and method of performing the work scope and achieving objectives. The plan establishes the work definitions, the cost goals, schedule constraints and roles and responsibilities for project execution. The plan also defines how the project will be controlled and documented

  12. Critical human-factors issues in nuclear-power regulation and a recommended comprehensive human-factors long-range plan. Executive summary

    International Nuclear Information System (INIS)

    Hopkins, C.O.; Snyder, H.L.; Price, H.E.; Hornick, R.J.; Mackie, R.R.; Smillie, R.J.; Sugarman, R.C.

    1982-08-01

    This comprehensive long-range human factors plan for nuclear reactor regulation was developed by a Study Group of the Human Factors Society, Inc. This Study Group was selected by the Executive Council of the Society to provide a balanced, experienced human factors perspective to the applications of human factors scientific and engineering knowledge to nuclear power generation. The report is presented in three volumes. Volume 1 contains an Executive Summary of the 18-month effort and its conclusions. Volume 2 summarizes all known nuclear-related human factors activities, evaluates these activities wherever adequate information is available, and describes the recommended long-range (10-year) plan for human factors in regulation. Volume 3 elaborates upon each of the human factors issues and areas of recommended human factors involvement contained in the plan, and discusses the logic that led to the recommendations

  13. Geology summary of Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Anderson, J.E.

    1996-08-01

    During FY 1994, three multiport wells were installed in Waste Area Grouping (WAG) 5. The wells were instrumented with Westbay multiport systems. The purpose of the wells is (1) to characterize different flow systems and (2) to monitor for contaminants. The geology of the individual boreholes (WAG 5-12, WAG 5-13, WAG 5-14) is documented in Bechtel National, Inc., (BNI) et al. (1994). The Bechtel report does not explicitly show geologic relationships between these boreholes or integrate this information into the geology of WAG 5. The purpose of this report is to document and present a summary of the distribution of geologic formations in WAG 5. This information is presented in several ways: (1) stratigraphic correlation diagrams based on the natural gamma ray log, (2) geologic cross sections, and (3) a geologic map. This work provides a reference frame for interpreting flow, water, and contaminant chemistry data from multiport wells

  14. Composting of biological waste. Processes and utilisation. Summary report; Bioabfallkompostierung. Verfahren und Verwertung. Kurzfassung

    Energy Technology Data Exchange (ETDEWEB)

    Gronauer, A.; Claassen, N.; Ebertseder, T.; Fischer, P.; Gutser, R.; Helm, M.; Popp, L.; Schoen, H.

    1997-12-31

    The project investigated environmentally compatible concepts for processing and utilisation of biological waste by means of composting and spreading on agriculataural and gardening plots. The project comprised three parts: Composting techniques, applications of compost in agriculture and gardening, and applications in landscaping. This volume comprises the summaries of the three part-projects. (orig./SR) [Deutsch] Die umweltschonende Aufbereitung und Verwertung von Bioabfall durch Kompostierung und Rueckfuehrung auf landwirtschaftliche und gaertnerische Flaechen wurde untersucht. Dieses Projekt war dreigeteilt in die Bereiche der Kompostierung selbst, der Anwendung des Komposts in der Landwirtschaft und seiner Anwendung im Gartenbau sowie im Garten- und Landschaftsbau (GaLa-Bau). Die vorliegende Schrift enthaelt die Zusammenfassung der genannten drei Teilberichte. (orig./SR)

  15. Southern cone energy network coal gasification for SNG production and pipeline system. Feasibility study. Volume 1. Executive summary. Export trade information

    International Nuclear Information System (INIS)

    1992-01-01

    The Executive Summary document summarizes the study report on the economic and technical feasibility of gasifying coal to produce a substitute natural gas (SNG) for distribution to the industrial areas of Southern Brazil. The report includes data surveys, technology assessments, process evaluations, and conceptual designs and analyses. The study contributes to the Brazilian Government efforts to investigate feasible crude oil substitution programs that will meet the nation's energy needs by utilizing domestic resources, thereby reducing the severe negative impact of foreign crude oil importation on Brazil's balance of payments

  16. Final Generic Environmental Impact Statement. Handling and storage of spent light water power reactor fuel. Volume 1. Executive summary and text

    International Nuclear Information System (INIS)

    1979-08-01

    The Generic Environmental Impact Statement on spent fuel storage was prepared by the Nuclear Regulatory Commission staff in response to a directive from the Commissioners published in the Federal Register, September 16, 1975 (40 FR 42801). The Commission directed the staff to analyze alternatives for the handling and storage of spent light water power reactor fuel with particular emphasis on developing long range policy. Accordingly, the scope of this statement examines alternative methods of spent fuel storage as well as the possible restriction or termination of the generation of spent fuel through nuclear power plant shutdown. Volume 1 includes the executive summary and the text

  17. A REPRINT of a July 1991 Report to Congress, Executive Summary of Verification of Nuclear Warhead Dismantlement and Special Nuclear Material Controls

    International Nuclear Information System (INIS)

    Fuller, James L.

    2008-01-01

    With the renewed thinking and debate about deep reductions in nuclear weapons, including recent proposals about eliminating nuclear warheads altogether, republishing the general conclusions of the Robinson Committee Report of 1992 appears useful. The report is sometimes referred to as the 3151 Report, from Section 3151 of the National Defense Authorization Act for FY1991, from where its requirement originated. This report contains the Executive Summary only and the forwarding letters from the Committee, the President of the United States, the Secretary of Energy, and C Paul Robinson, the head of the Advisory Committee

  18. The execution by COVRA of the Dutch policy with regard to radioactive waste. Chapter 2

    International Nuclear Information System (INIS)

    Vrijen, J.

    1989-01-01

    Considerations for alteration of the radioactive-waste policy in the Netherlands resulted in the foundation in 1982 of the Central Organization For Radioactive Waste (COVRA). This chapter deals with the specifications of duty and the organization of COVRA and its management with regard to the interim storage and processing of radioactive waste in Zijpe and Borssele, and the final disposal. (H.W.). 3 figs

  19. Certification plan transuranic waste: Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    1992-06-01

    The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification

  20. 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

  1. SUMMARY OF 2010 DOE EM INTERNATIONAL PROGRAM STUDIES OF WASTE GLASS STRUCTURE AND PROPERTIES

    Energy Technology Data Exchange (ETDEWEB)

    Fox, K.; Choi, A.; Marra, J.; Billings, A.

    2011-02-07

    Collaborative work between the Savannah River National Laboratory (SRNL) and SIA Radon in Russia was divided among three tasks for calendar year 2010. The first task focused on the study of simplified high level waste glass compositions with the objective of identifying the compositional drivers that lead to crystallization and poor chemical durability. The second task focused on detailed characterization of more complex waste glass compositions with unexpectedly poor chemical durabilities. The third task focused on determining the structure of select high level waste glasses made with varying frit compositions in order to improve models under development for predicting the melt rate of the Defense Waste Processing Facility (DWPF) glasses. The majority of these tasks were carried out at SIA Radon. Selection and fabrication of the glass compositions, along with chemical composition measurements and evaluations of durability were carried out at SRNL and are described in this report. SIA Radon provided three summary reports based on the outcome of the three tasks. These reports are included as appendices to this document. Briefly, the result of characterization of the Task 1 glasses may indicate that glass compositions where iron is predominantly tetrahedrally coordinated have more of a tendency to crystallize nepheline or nepheline-like phases. For the Task 2 glasses, the results suggested that the relatively low fraction of tetrahedrally coordinated boron and the relatively low concentrations of Al{sub 2}O{sub 3} available to form [BO{sub 4/2}]{sup -}Me{sup +} and [AlO{sub 4/2}]{sup -}Me{sup +} tetrahedral units are not sufficient to consume all of the alkali ions, and thus these alkali ions are easily leached from the glasses. All of the twelve Task 3 glass compositions were determined to be mainly amorphous, with some minor spinel phases. Several key structural units such as metasilicate chains and rings were identified, which confirms the current modeling

  2. Studies of transuranic waste storage under conditions expected in the Waste Isolation Pilot Plant (WIPP). Interim summary report, October 1, 1977-June 15, 1979

    International Nuclear Information System (INIS)

    Kosiewicz, S.T.; Barraclough, B.L.; Zerwekh, A.

    1980-01-01

    The major focus of the program has been on the gas generation potential of organic wastes produced by radiolytic and thermal degradation under simulated WIPP storage conditions. The effects of TRU contamination level, temperature, waste type, pressure, and exposure time on radiolysis are presented. In addition, results from preliminary experiments on processed sludge dewatering are discussed. A summary is presented here of the results of a detailed study of all retrievably stored TRU wastes present at LASL before January 1, 1978. The data indicate a gross volume for the LASL inventory of 1610 m 3 with a total weight of nearly 1.24 x 10 6 kg (1240 metric tonnes). The dominant radionuclide contents of the waste are plutonium (primarily 238 Pu) and americium

  3. Organization, execution and evaluation of the 2014 Academic Emergency Medicine consensus conference on Gender-Specific Research in Emergency Care - an executive summary.

    Science.gov (United States)

    Safdar, Basmah; Greenberg, Marna R

    2014-12-01

    With the goal of reducing inequalities in patient care, the 2014 Academic Emergency Medicine (AEM) consensus conference, "Gender-Specific Research in Emergency Care: Investigate, Understand, and Translate How Gender Affects Patient Outcomes," convened a diverse group of researchers, clinicians, health care providers, patients, and representatives of federal agencies and policy-makers in Dallas, Texas, in May 2014. The executive and steering committees identified seven clinical domains as key to gender-specific emergency care: cardiovascular, neurological, trauma/injury, substance abuse, pain, mental health, and diagnostic imaging. The main aims of the conference were to: 1) summarize and consolidate current data related to sex- and gender-specific research for acute care and identify critical gender-related gaps in knowledge to inform an EM research agenda; 2) create a consensus-driven research agenda that advances sex- and gender-specific research in the prevention, diagnosis, and management of acute diseases and identify strategies to investigate them; and 3) build a multinational interdisciplinary consortium to disseminate and study the sex and gender medicine of acute conditions. Over a 2-year period, this collaborative network of stakeholders identified key areas where sex- and gender-specific research is most likely to improve clinical care and ultimately patient outcomes. The iterative consensus process culminated in a daylong conference on May 13, 2014, with a total of 133 registrants, with the majority being between ages 31 and 50 years (57%), females (71%), and whites (79%). Content experts led the consensus-building workshops at the conference and used the nominal group technique to consolidate consensus recommendations for priority research. In addition, panel sessions addressed funding mechanisms for gender-specific research as well as gender-specific regulatory challenges to product development and approval. This special issue of AEM reports the

  4. Definition of technology development missions for early space station, orbit transfer vehicle servicing. Volume 1: Executive summary

    Science.gov (United States)

    1983-01-01

    Orbital Transfer Vehicle (OTV) servicing study scope, propellant transfer, storage and reliquefaction technology development missions (TDM), docking and berthing TDM, maintenance TDM, OTV/payload integration TDM, combined TDMS design, summary space station accomodations, programmatic analysis, and TDM equipment operational usage are discussed.

  5. Senior expert symposium on electricity and the environment, Helsinki, Finland, 13-17 May 1991. Executive summary

    International Nuclear Information System (INIS)

    1991-07-01

    This document summarizes the key issues of the Senior Expert Symposium on Electricity and the Environment held in Helsinki, Finland in May 1991, and highlights the main findings. It is hoped that this summary will contribute to rational and objective discussion of different options and strategies aimed at ensuring the provision of adequate and economical electricity services while protecting health and the environment

  6. Executive Summary of the American College of Surgeons/Surgical Infection Society Surgical Site Infection Guidelines-2016 Update.

    Science.gov (United States)

    Ban, Kristen A; Minei, Joseph P; Laronga, Christine; Harbrecht, Brian G; Jensen, Eric H; Fry, Donald E; Itani, Kamal M F; Dellinger, E Patchen; Ko, Clifford Y; Duane, Therese M

    Guidelines regarding the prevention, detection, and management of surgical site infections (SSIs) have been published previously by a variety of organizations. The American College of Surgeons (ACS)/Surgical Infection Society (SIS) Surgical Site Infection (SSI) Guidelines 2016 Update is intended to update these guidelines based on the current literature and to provide a concise summary of relevant topics.

  7. Executive Dysfunction

    Science.gov (United States)

    Rabinovici, Gil D.; Stephens, Melanie L.; Possin, Katherine L.

    2015-01-01

    Purpose of Review: Executive functions represent a constellation of cognitive abilities that drive goal-oriented behavior and are critical to the ability to adapt to an ever-changing world. This article provides a clinically oriented approach to classifying, localizing, diagnosing, and treating disorders of executive function, which are pervasive in clinical practice. Recent Findings: Executive functions can be split into four distinct components: working memory, inhibition, set shifting, and fluency. These components may be differentially affected in individual patients and act together to guide higher-order cognitive constructs such as planning and organization. Specific bedside and neuropsychological tests can be applied to evaluate components of executive function. While dysexecutive syndromes were first described in patients with frontal lesions, intact executive functioning relies on distributed neural networks that include not only the prefrontal cortex, but also the parietal cortex, basal ganglia, thalamus, and cerebellum. Executive dysfunction arises from injury to any of these regions, their white matter connections, or neurotransmitter systems. Dysexecutive symptoms therefore occur in most neurodegenerative diseases and in many other neurologic, psychiatric, and systemic illnesses. Management approaches are patient specific and should focus on treatment of the underlying cause in parallel with maximizing patient function and safety via occupational therapy and rehabilitation. Summary: Executive dysfunction is extremely common in patients with neurologic disorders. Diagnosis and treatment hinge on familiarity with the clinical components and neuroanatomic correlates of these complex, high-order cognitive processes. PMID:26039846

  8. Canadian Thoracic Society 2012 Guideline Update: Diagnosis and Management of Asthma in Preschoolers, Children and Adults: Executive Summary

    Directory of Open Access Journals (Sweden)

    M Diane Lougheed

    2012-01-01

    Full Text Available BACKGROUND: In 2010, the Canadian Thoracic Society (CTS published a Consensus Summary for the diagnosis and management of asthma in children six years of age and older, and adults, including an updated Asthma Management Continuum. The CTS Asthma Clinical Assembly subsequently began a formal clinical practice guideline update process, focusing, in this first iteration, on topics of controversy and/or gaps in the previous guidelines.

  9. Assessment of the use of space technology in the monitoring of oil spills and ocean pollution: Executive summary

    Science.gov (United States)

    Alvarado, U. R. (Editor)

    1980-01-01

    The adequacy of current technology in terms of stage of maturity, of sensing, support systems, and information extraction was assessed relative to oil spills, waste pollution, and inputs to pollution trajectory models. Needs for advanced techniques are defined and the characteristics of a future satellite system are determined based on the requirements of U.S. agencies involved in pollution monitoring.

  10. A summary of the sources of input parameter values for the Waste Isolation Pilot Plant final porosity surface calculations

    International Nuclear Information System (INIS)

    Butcher, B.M.

    1997-08-01

    A summary of the input parameter values used in final predictions of closure and waste densification in the Waste Isolation Pilot Plant disposal room is presented, along with supporting references. These predictions are referred to as the final porosity surface data and will be used for WIPP performance calculations supporting the Compliance Certification Application to be submitted to the U.S. Environmental Protection Agency. The report includes tables and list all of the input parameter values, references citing their source, and in some cases references to more complete descriptions of considerations leading to the selection of values

  11. A summary of the sources of input parameter values for the Waste Isolation Pilot Plant final porosity surface calculations

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, B.M.

    1997-08-01

    A summary of the input parameter values used in final predictions of closure and waste densification in the Waste Isolation Pilot Plant disposal room is presented, along with supporting references. These predictions are referred to as the final porosity surface data and will be used for WIPP performance calculations supporting the Compliance Certification Application to be submitted to the U.S. Environmental Protection Agency. The report includes tables and list all of the input parameter values, references citing their source, and in some cases references to more complete descriptions of considerations leading to the selection of values.

  12. Project Execution Plan, Waste Management Division, Nevada Operations Office, U.S. Department of Energy, April 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This plan addresses project activities encompassed by the U.S. Department of Energy/Nevada Operations Office Waste Management Division and conforms to the requirements contained in the ''Life Cycle Asset Management,'' U.S. Department of Energy Order O430.1A; the Joint Program Office Policy on Project Management in Support of DOE Order O430.1, and the Project Execution and Engineering Management Planning Guide. The plan also reflects the milestone philosophies of the Federal Facility Agreement and Consent Order, as agreed to by the state of Nevada; and traditional project management philosophies such as the development of life cycle costs, schedules, and work scope; identification of roles and responsibilities; and baseline management and controls

  13. Joint Peru/United States report on Peru/United States cooperative energy assessment. Volume 1. Executive summary, main report and appendices

    Energy Technology Data Exchange (ETDEWEB)

    1979-08-01

    In 1978, the US and Peru conducted a comprehensive assessment of Peru's energy resources, needs, and uses and developed several alternative energy strategies that utilize the available resources to meet their energy requirements. This Volume I reports the findings of the assessment and contains the executive summary, the main report, and five appendices of information that support the integrated energy supply and demand analysis. The following chapters are included: The Energy Situation in Peru (economic context and background, energy resources and production, energy consumption patterns); Reference Supply and Demand Projection (approach, procedures, and assumptions; economic projections; energy demand and supply projections; supply/demand integration; uncertainties); and The Development of Strategies and Options (the analysis of options; strategies; increased use of renewables, hydropower, coal; increased energy efficiency; and financial analysis of strategies).

  14. Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: I-Master Plan and Executive Summary

    Science.gov (United States)

    Ohnuki, Akira; Kureta, Masatoshi; Yoshida, Hiroyuki; Tamai, Hidesada; Liu, Wei; Misawa, Takeharu; Takase, Kazuyuki; Akimoto, Hajime

    R&D project to investigate thermal-hydraulic performance in tight-lattice rod bundles for Innovative Water Reactor for Flexible Fuel Cycle has been progressed at Japan Atomic Energy Agency in collaboration with power utilities, reactor vendors and universities since 2002. In this series-study, we will summarize the R&D achievements using large-scale test facility (37-rod bundle with full-height and full-pressure), model experiments and advanced numerical simulation technology. This first paper described the master plan for the development of design technology and showed an executive summary for this project up to FY2005. The thermal-hydraulic characteristics in the tight-lattice configuration were investigated and the feasibility was confirmed based on the experiments. We have developed the design technology including 3-D numerical simulation one to evaluate the effects of geometry/scale on the thermal-hydraulic behaviors.

  15. Executive summary of the KDIGO Controversies Conference on Supportive Care in Chronic Kidney Disease: developing a roadmap to improving quality care.

    Science.gov (United States)

    Davison, Sara N; Levin, Adeera; Moss, Alvin H; Jha, Vivekanand; Brown, Edwina A; Brennan, Frank; Murtagh, Fliss E M; Naicker, Saraladevi; Germain, Michael J; O'Donoghue, Donal J; Morton, Rachael L; Obrador, Gregorio T

    2015-09-01

    Patients with advanced chronic kidney disease (CKD) have a high burden of physical and psychosocial symptoms, poor outcomes, and high costs of care. Current paradigms of care for this highly vulnerable population are variable, prognostic and assessment tools are limited, and quality of care, particularly regarding conservative and palliative care, is suboptimal. The KDIGO Controversies Conference on Supportive Care in CKD reviewed the current state of knowledge in order to define a roadmap to guide clinical and research activities focused on improving the outcomes of people living with advanced CKD, including those on dialysis. An international group of multidisciplinary experts in CKD, palliative care, methodology, economics, and education identified the key issues related to palliative care in this population. The conference led to a working plan to address outstanding issues in this arena, and this executive summary serves as an output to guide future work, including the development of globally applicable guidelines.

  16. A new approach to performance assessment of barriers in a repository. Executive summary, draft, technical appendices. Final report

    International Nuclear Information System (INIS)

    Mueller-Hoeppe, N.; Krone, J.; Niehues, N.; Poehler, M.; Raitz von Frentz, R.; Gauglitz, R.

    1999-06-01

    Multi-barrier systems are accepted as the basic approach for long term environmental safe isolation of radioactive waste in geological repositories. Assessing the performance of natural and engineered barriers is one of the major difficulties in producing evidence of environmental safety for any radioactive waste disposal facility, due to the enormous complexity of scenarios and uncertainties to be considered. This report outlines a new methodological approach originally developed basically for a repository in salt, but that can be transferred with minor modifications to any other host rock formation. The approach is based on the integration of following elements: (1) Implementation of a simple method and efficient criteria to assess and prove the tightness of geological and engineered barriers; (2) Using the method of Partial Safety Factors in order to assess barrier performance at certain reasonable level of confidence; (3) Integration of a diverse geochemical barrier in the near field of waste emplacement limiting systematically the radiological consequences from any radionuclide release in safety investigations and (4) Risk based approach for the assessment of radionuclide releases. Indicative calculations performed with extremely conservative assumptions allow to exclude any radiological health consequences from a HLW repository in salt to a reference person with a safety level of 99,9999% per year. (orig.)

  17. Radioactive wastes and valorizable materials in France: summary of the 2004 national inventory; Dechets radioactifs et matieres valorisables en France: resume de l'inventaire national 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The French national inventory of radioactive wastes is a reference document for professionals and scientists of the nuclear domain and also for any citizen interested in the management of radioactive wastes. This summary document contains: 1 - general introduction; 2 - classification of radioactive wastes: the 5 main categories; 3 - origin of the wastes; 4 - processing and conditioning; 5 - inventory of existing wastes: geographical inventory, inventory per category; 6 - prospective inventory: prospective scenarios, forecasting of waste production; 7 - valorizable radioactive materials; 8 - synthesis and perspective; 9 - glossary. (J.S.)

  18. Intermediate photovoltaic system application experiment operational performance executive summary. Volume 4. For Beverly High School, Beverly, MA

    Energy Technology Data Exchange (ETDEWEB)

    1982-02-01

    Performance data are given for a 100 kW grid-connected flat panel photovoltaic power supply at a Massachusetts high school for the month of January, 1982. Data given include daily and monthly electrical energy produced, daily and monthly plane-of-array solar energy incident, array efficiency, power conditioner efficiency, system efficiency, capacity factor, and average plane-of-array insolation. Also included are the data acquisition mode and recording interval plot and two site event report summaries involving the data acquisition system. (LEW)

  19. 75 FR 51678 - Hazardous Waste Management System; Identification and Listing of Hazardous Waste; Final Exclusion

    Science.gov (United States)

    2010-08-23

    ...: Environmental Protection Agency. ACTION: Final rule. SUMMARY: Environmental Protection Agency (EPA) is granting.... How much waste did OxyChem propose to delist? C. How did OxyChem sample and analyze the waste data in... proposed rule? V. Statutory and Executive Order Reviews I. Overview Information A. What action is EPA...

  20. Program summary for the Office of Remedial Action and Waste Technology

    International Nuclear Information System (INIS)

    1989-10-01

    The US Department of Energy is the lead Federal agency responsible for planning and implementing the programs that ensure safe and efficient management of nuclear wastes from both civilian and defense activities. Within the Department, three offices share this responsibility: the Office of Remedial Action and Waste Technology, the Office of Civilian Radioactive Waste Management, and the Office of Defense Waste and Transportation Management. This document summarizes the programs managed by the Office of Remedial Action and Waste Technology

  1. Radioactive waste management information, 1982 summary and record-to-date

    International Nuclear Information System (INIS)

    Cassidy, G.B.

    1983-07-01

    This document summarizes radioactive waste data records for the Idaho National Engineering Laboratory (INEL) compiled since 1952. Kinds of information include volume, radioactivity, isotopic identity, origin, and decay status. The radioactive waste data presented was obtained from the INEL Radioactive Waste Management Information System (RWMIS). This report is updated annually to incorporate waste management data for the current year and reflects changes in previous annual reports. Changes are made to more accurately reflect the current status of waste operations at the INEL

  2. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

    Energy Technology Data Exchange (ETDEWEB)

    Danny Anderson

    2014-07-01

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE

  3. Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

    International Nuclear Information System (INIS)

    Christensen, E.J.; Gordon, D.E.

    1983-12-01

    The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

  4. INTERNATIONAL PROGRAM: SUMMARY REPORT ON THE PROPERTIES OF CEMENTITIOUS WASTE FORMS

    International Nuclear Information System (INIS)

    Harbour, J

    2007-01-01

    This report provides a summary of the results on the properties of cementitious waste forms obtained as part of the International Program. In particular, this report focuses on the results of Task 4 of the Program that was initially entitled ''Improved Retention of Key Contaminants of Concern in Low Temperature Immobilized Waste Forms''. Task 4 was a joint program between Khlopin Radium Institute and the Savannah River National Laboratory. The task evolved during this period into a study of cementitious waste forms with an expanded scope that included heat of hydration and fate and transport modeling. This report provides the results for Task 4 of the International Program as of the end of FY06 at which time funding for Task 4 was discontinued due to the needs of higher priority tasks within the International Program. Consequently, some of the subtasks were only partially completed, but it was considered important to capture the results up to this point in time. Therefore, this report serves as the closeout report for Task 4. The degree of immobilization of Tc-99 within the Saltstone waste form was measured through monolithic and crushed grout leaching tests. An effective diffusion coefficient of 4.8 x 10 -12 (Leach Index of 11.4) was measured using the ANSI/ANS-16.1 protocol which is comparable with values obtained for tank closure grouts using a dilute salt solution. The leaching results show that, in the presence of concentrated salt solutions such as those that will be processed at the Saltstone Production Facility, blast furnace slag can effectively reduce pertechnetate to the immobile +4 oxidation state. Leaching tests were also initiated to determine the degree of immobilization of selenium in the Saltstone waste form. Results were obtained for the upper bound of projected selenium concentration (∼5 x 10 -3 M) in the salt solution that will be treated at Saltstone. The ANSI/ANS 16.1 leaching tests provided a value for the effective diffusivity of ∼5 x 10

  5. Comprehensive analysis and positioning of the energy and environmental industry in the GTA : final report and executive summary

    International Nuclear Information System (INIS)

    2004-06-01

    This report presented an outline of the energy and environment sectors in the Greater Toronto Area (GTA). The objective of the report was to present the GTA as an ideal relocation option for businesses in the environment and energy sectors. Details of the energy sector in Ontario were outlined, and an overview of the electricity market was provided. A regional distribution of the environment industry was presented, including details of hydrogen, renewable energy technologies, waste management, engineering and consulting companies and water and waste water. It was noted that 40 per cent of the Ontario environment industry is located in the Greater Toronto Area (GTA), and generates revenues of $4 billion per year. GTA issues and drivers include environmental issues such as air quality and climate change; finance and economics such as alternative financing mechanisms and infrastructure issues; resource adequacy and policy and regulation issues. New and emerging opportunities in the GTA were examined, including details of key enablers and an accompanying timeline. Competitive advantages of the GTA include strong technology innovation; skilled workforce; and world-wide recognition. An outline of facilities in the GTA was provided. The value of niche companies was assessed. The geographical proximity of the GTA to various large centres was assessed. It was concluded that the GTA value proposition includes a strong market demand; consistent policies and regulations; a business support framework; good quality of life; and many strong, well-positioned niche companies

  6. Electronic engagement on radioactive waste management: the experience of the Scottish executive

    International Nuclear Information System (INIS)

    Gray, E.

    2006-01-01

    The International Tele-democracy Centre (Napier University) carried out research between February and June 2004 to develop and test appropriate online tools and mechanisms to engage young people in dialogue on Radioactive Waste Management. The study found interest and enthusiasm in using information and communication technology (ICT) e-engagement tools, to take part in the debate on Radioactive Waste Management (RWM) through groups that also meet face-to-face, i.e. school classes or youth groups. The main barriers to young people's effective use of such tools are likely to be organisational: coordinating the provision and use of the tools and their content. The tools themselves should be designed with an emphasis on ease-of-use and accessibility. The active support of the education and community sectors is recommended. RWM specialists and decision-makers should be directly involved in the e-engagement. There is a need for non-government stakeholders including environmental organisations to provide their input

  7. Bleeding risk assessment and management in atrial fibrillation patients. Executive Summary of a Position Document from the European Heart Rhythm Association [EHRA], endorsed by the European Society of Cardiology [ESC] Working Group on Thrombosis

    NARCIS (Netherlands)

    Lip, Gregory Y. H.; Andreotti, Felicita; Fauchier, Laurent; Huber, Kurt; Hylek, Elaine; Knight, Eve; Lane, Deirdre; Levi, Marcel; Marín, Francisco; Palareti, Gualtiero; Kirchhof, Paulus

    2011-01-01

    In this executive summary of a Consensus Document from the European Heart Rhythm Association, endorsed by the European Society of Cardiology Working Group on Thrombosis, we comprehensively review the published evidence and propose a consensus on bleeding risk assessments in atrial fibrillation (AF)

  8. Position statement executive summary: guidelines and recommendations for laboratory analysis in the diagnosis and management of diabetes mellitus.

    Science.gov (United States)

    Sacks, David B; Arnold, Mark; Bakris, George L; Bruns, David E; Horvath, Andrea Rita; Kirkman, M Sue; Lernmark, Ake; Metzger, Boyd E; Nathan, David M

    2011-06-01

    Multiple laboratory tests are used in the diagnosis and management of patients with diabetes mellitus. The quality of the scientific evidence supporting the use of these assays varies substantially. An expert committee compiled evidence-based recommendations for the use of laboratory analysis in patients with diabetes. A new system was developed to grade the overall quality of the evidence and the strength of the recommendations. A draft of the guidelines was posted on the Internet, and the document was modified in response to comments. The guidelines were reviewed by the joint Evidence-Based Laboratory Medicine Committee of the AACC and the National Academy of Clinical Biochemistry and were accepted after revisions by the Professional Practice Committee and subsequent approval by the Executive Committee of the American Diabetes Association. In addition to the long-standing criteria based on measurement of venous plasma glucose, diabetes can be diagnosed by demonstrating increased hemoglobin A(1c) (HbA(1c)) concentrations in the blood. Monitoring of glycemic control is performed by the patients measuring their own plasma or blood glucose with meters and by laboratory analysis of HbA(1c). The potential roles of noninvasive glucose monitoring, genetic testing, and measurement of autoantibodies, urine albumin, insulin, proinsulin, C-peptide, and other analytes are addressed. The guidelines provide specific recommendations based on published data or derived from expert consensus. Several analytes are found to have minimal clinical value at the present time, and measurement of them is not recommended.

  9. Assessment of the use of space technology in the monitoring of oil spills and ocean pollution: Technical volume. Executive summary

    Science.gov (United States)

    Alvarado, U. R. (Editor); Chafaris, G.; Chestek, J.; Contrad, J.; Frippel, G.; Gulatsi, R.; Heath, A.; Hodara, H.; Kritikos, H.; Tamiyasu, K.

    1980-01-01

    The potential of space systems and technology for detecting and monitoring ocean oil spills and waste pollution was assessed as well as the impact of this application on communication and data handling systems. Agencies charged with responsibilities in this area were identified and their measurement requirements were ascertained in order to determine the spatial resolution needed to characterize operational and accidental discharges. Microwave and optical sensors and sensing techniques were evaluated as candidate system elements. Capabilities are described for the following: synthetic aperture radar, microwave scatterometer, passive microwave radiometer, microwave altimeter, electro-optical sensors currently used in airborne detection, existing space-based optical sensors, the thematic mapper, and the pointable optical linear array.

  10. Summary of radioactive solid waste received in the 200 areas during calendar year 1997

    International Nuclear Information System (INIS)

    Hagel, D.L.

    1998-01-01

    Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document

  11. Summary of radioactive solid waste received in the 200 Areas during calendar year 1992

    International Nuclear Information System (INIS)

    Anderson, J.D.; Hagel, D.L.

    1992-05-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document

  12. Summary of radioactive solid waste received in the 200 Areas during calendar year 1993

    International Nuclear Information System (INIS)

    Anderson, J.D.; Hagel, D.L.

    1994-09-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1993. This report does not include backlog waste, solid radioactive waste in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, ''Hanford Site Solid Waste Acceptance Criteria,'' (WHC 1988), liquid waste data are not included in this document

  13. Summary of radioactive solid waste received in the 200 areas during calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Hagel, D.L.

    1998-06-25

    Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document.

  14. Summary of radioactive solid waste received in the 200 Areas during calendar year 1994

    International Nuclear Information System (INIS)

    Anderson, J.D.; Hagel, D.L.

    1995-08-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document

  15. Summary of radioactive solid waste received in the 200 Areas during calendar year 1994

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, J.D.; Hagel, D.L.

    1995-08-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document.

  16. Summary of research and development activities in support of waste acceptance criteria for WIPP

    International Nuclear Information System (INIS)

    Hunter, T.O.

    1979-11-01

    The development of waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP) is summarized. Specifications for acceptable waste forms are included. Nine program areas are discussed. They are: TRU characterization, HLW interactions, thermal/structural interactions, nuclide migration, permeability, brine migration, borehole plugging, operation/design support, and instrumentation development. Recommendations are included

  17. Spent-Fuel Test - Climax: An evaluation of the technical feasibility of geologic storage of spent nuclear fuel in granite: Executive summary of final results

    International Nuclear Information System (INIS)

    Patrick, W.C.

    1986-01-01

    This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test - Climate project. The project was conducted between 1978 and 1983 in the granitic Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass. Storage of the spent-fuel affected the surrounding rock mass in measurable ways, but did not threaten the stability or safety of the facility at any time

  18. Executive summary: Weldon Spring Site Environmental Report for calendar year 1992. Weldon Spring Site Remedial Action Project, Weldon Spring, Missouri

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This report has been prepared to provide information about the public safety and environmental protection programs conducted by the Weldon Spring Site Remedial Action Project. The Weldon Spring site is located in southern St. Charles County, Missouri, approximately 48 km (30 mi) west of St. Louis. The site consists of two main areas, the Weldon Spring Chemical Plant and raffinate pits and the Weldon Spring Quarry. The objectives of the Site Environmental Report are to present a summary of data from the environmental monitoring program, to characterize trends and environmental conditions at the site, and to confirm compliance with environmental and health protection standards and requirements. The report also presents the status of remedial activities and the results of monitoring these activities to assess their impacts on the public and environment. The scope of the environmental monitoring program at the Weldon Spring site has changed since it was initiated. Previously, the program focused on investigations of the extent and level of contaminants in the groundwater, surface waters, buildings, and air at the site. In 1992, the level of remedial activities required monitoring for potential impacts of those activities, particularly on surface water runoff and airborne effluents. This report includes monitoring data from routine radiological and nonradiological sampling activities. These data include estimates of dose to the public from the Weldon Spring site; estimates of effluent releases; and trends in groundwater contaminant levels. Also, applicable compliance requirements, quality assurance programs, and special studies conducted in 1992 to support environmental protection programs are reviewed.

  19. Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

    International Nuclear Information System (INIS)

    2009-01-01

    On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

  20. Executive summary of NIH workshop on the Use and Biology of Energy Drinks: Current Knowledge and Critical Gaps.

    Science.gov (United States)

    Sorkin, Barbara C; Camp, Kathryn M; Haggans, Carol J; Deuster, Patricia A; Haverkos, Lynne; Maruvada, Padma; Witt, Ellen; Coates, Paul M

    2014-10-01

    Sales of energy drinks in the United States reached $12.5 billion in 2012. Emergency department visits related to consumption of these products have increased sharply, and while these numbers remain small relative to product sales, they raise important questions regarding biological and behavioral effects. Although some common ingredients of energy drinks have been extensively studied (e.g., caffeine, B vitamins, sugars, inositol), data on other ingredients (e.g., taurine) are limited. Summarized here are data presented elsewhere in this issue on the prevalence and patterns of caffeine-containing energy drink use, the effects of these products on alertness, fatigue, cognitive functions, sleep, mood, homeostasis, as well as on exercise physiology and metabolism, and the biological mechanisms mediating the observed effects. There are substantial data on the effects of some energy drink ingredients, such as caffeine and sugars, on many of these outcomes; however, even for these ingredients many controversies and gaps remain, and data on other ingredients in caffeine-containing energy drinks, and on ingredient interactions, are sparse. This summary concludes with a discussion of critical gaps in the data and potential next steps. Published 2014. This article is a U.S. Government work and is in the public domain in the USA.

  1. Southeast Regional Wastewater Treatment Plant Facilities Improvements Project and Geysers Effluent Pipeline Project. Draft EIR/EIS: Executive summary

    International Nuclear Information System (INIS)

    1994-01-01

    The Southeast Regional Wastewater Treatment Plant (SERWTP) Facilities Improvement Plan and Geysers Effluent Pipeline and Effluent Injection Project are proposed as a plan to provide expanded wastewater treatment capabilities and to dispose of the effluent by injection in The Geysers geothermal field for purposes of power production. The project is located predominantly in the County of Lake, California, and also in part of Sonoma County. The plan includes various conventional facilities improvements in wastewater treatment to a secondary level of treatment at the SWERWTP. The plan includes facilities to convey the treated effluent in a 26-mile, 24-inch inside diameter pipeline to the Southeast Geysers. The wastewater from the SERWTP would be supplemented by raw lake water diverted from nearby Clear Lake. At The Geysers, the effluent would be directed into a system of distribution lines to wells. In the geothermal reservoir, the water will be converted to steam and collected in production wells that will direct the steam to six existing power plants. This document is a summary of a combined full Environmental Impact Report (EIR) and Environmental Impact Statement (EIS). The EIR/EIS describes the environmental impacts of the various components of the project. Mitigation measures are suggested for reducing impacts to a less than significant level

  2. Executive summary - Geologic assessment of coal in the Gulf of Mexico coastal plain, U.S.A.

    Science.gov (United States)

    Warwick, Peter D.; Warwick, Peter D.; Karlsen, Alexander K.; Merrill, Matthew D.; Valentine, Brett J.

    2011-01-01

    The National Coal Resource Assessment (NCRA) project of the U.S. Geological Survey (USGS) has assessed the quantity and quality of the nation's coal deposits that potentially could be mined during the next few decades. For eight years, geologic, geochemical, and resource information was collected and compiled for the five major coal-producing regions of the United States: the Appalachian Basin, Illinois Basin, Northern Rocky Mountains and Great Plains, Colorado Plateau, and the western part of the Gulf of Mexico Coastal Plain (Gulf Coast) region (Figure 1). In particular, the NCRA assessed resource estimates, compiled coal-quality information, and characterized environmentally sensitive trace elements, such as arsenic and mercury, that are mentioned in the 1990 Clean Air Act Amendments (U.S. Environmental Protection Agency, 1990). The results of the USGS coal assessment efforts may be found at: http://energy.cr.usgs.gov/coal/coal-assessments/index.html and a summary of the results from all assessment areas can be found in Ruppert et al. (2002) and Dennen (2009).Detailed assessments of the major coal-producing areas for the Gulf Coast region along with reviews of the stratigraphy, coal quality, resources, and coalbed methane potential of the Cretaceous, Paleocene, and Eocene coal deposits are presented in this report (Chapters 5-10).

  3. Summary Record of the First Meeting of the Radioactive Waste Repository Metadata Management (RepMet) Initiative

    International Nuclear Information System (INIS)

    2014-01-01

    National radioactive waste repository programmes are collecting large amounts of data to support the long-term management of their nations' radioactive wastes. The data and related records increase in number, type and quality as programmes proceed through the successive stages of repository development: pre-siting, siting, characterisation, construction, operation and finally closure. Regulatory and societal approvals are included in this sequence. Some programmes are also documenting past repository projects and facing a challenge in allowing both current and future generations to understand actions carried out in the past. Metadata allows context to be stored with data and information so that it can be located, used, updated and maintained. Metadata helps waste management organisations better utilise their data in carrying out their statutory tasks and can also help verify and demonstrate that their programmes are appropriately driven. The NEA Radioactive Waste Repository Metadata Management (RepMet) initiative aims to bring about a better understanding of the identification and administration of metadata - a key aspect of data management - to support national programmes in managing their radioactive waste repository data, information and records in a way that is both harmonised internationally and suitable for long-term management and use. This is a summary record of the 1. meeting of the RepMet initiative. The actions and decisions from this meeting were sent separately to the group after the meeting, but are also included in this document (Annex A). The list of participants is attached as well (Annex B)

  4. Summary of radioactive solid waste received in the 200 Areas during calendar year 1990

    International Nuclear Information System (INIS)

    Anderson, J.D.; McCann, D.C.; Poremba, B.E.

    1991-04-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1990. This report does not include solid radioactive wastes in storage or disposal in other areas or facilities such as the underground tank farms. Unless packaged within the scope of Hanford Site radioactive solid waste acceptance criteria, liquid waste data are not included in this document. 10 refs., 1 tab

  5. Summary of radioactive solid waste received in the 200 areas during calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    Hladek, K.L.

    1997-05-21

    Rust Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1996. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document.

  6. Executive Summary of the NHLBI Workshop Report: Leveraging Current Scientific Advancements to Understand Sarcoidosis Variability and Improve Outcomes.

    Science.gov (United States)

    Maier, Lisa A; Crouser, Elliott D; Martin, William J; Eu, Jerry

    2017-12-01

    Sarcoidosis is a systemic granulomatous disease that primarily affects the lung; it is associated with significant disparities, more commonly impacting those in the prime of their lives (age 20-50 yr, with a second peak after age 60 yr), black individuals, and women. However, the burden of disease, the ability to diagnose and prognose organ involvement and course, as well as specific treatment options, management options, and disease pathogenesis remain poorly understood. As a result, the National Heart, Lung, and Blood Institute undertook a sarcoidosis workshop, "Leveraging Current Scientific Advancements to Understand Sarcoidosis Variability and Improve Outcomes," to help address these issues by defining the scientific and clinical priorities to improve sarcoidosis care. The overarching recommendations from this workshop are outlined in the following summary and detailed in the accompanying articles. The recommendations included establishing collaborations and networks to conduct research based on consensus definitions of disease phenotypes and standards of care, and to provide clinical outreach to areas with a burden of disease to improve care. These collaborative networks would also serve as the hub to conduct clinical trials of devastating phenotypes (e.g., cardiac, neurologic, and fibrotic disease) not only for treatment but to enhance our understanding of the burden of disease. In addition, the networks would be used to leverage state-of-the-art "omics" and systems biology research, as well as other studies to advance understanding of disease pathogenesis, and development of biomarkers and therapeutic targets, with a goal to translate this information to improve care of individuals with sarcoidosis.

  7. Summary of INEL research on the iron-enriched basalt waste form

    International Nuclear Information System (INIS)

    Reimann, G.A.; Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

    1992-01-01

    This report summarizes the knowledge base on the iron-enriched basalt (IEB) waste form developed at the Idaho National Engineering Laboratory (INEL) during 1979--1982. The results presented discuss the applicability of IEB in converting retrieved transuranic (TRU) waste from INEL's Radioactive Waste Management Complex (RWMC) into a vitreous/ceramic (glassy/rock) stable waste form suitable for permanent disposal in an appropriate repository, such as the Waste Isolation Pilot Plant (WIPP) in New Mexico. Borosilicate glass (BSG), the approved high-level waste form, appears unsuited for this application. Melting the average waste-soil mix from the RWMC produces the IEB composition and attempting to convert IEB to the BSG composition would require additions of substantial B 2 0 3 , Na, and SiO 2 (glass frit). IEB requires processing temperatures of 1400 to 1600 degrees C, depending upon the waste composition. Production of the IEB waste form, using Joule heated melters, has proved difficult in the past because of electrode and refractory corrosion problems associated with the high temperature melts. Higher temperature electric melters (arc and plasma) are available to produce this final waste form. Past research focused on extensive slag property measurements, waste form leachability tests, mechanical, composition, and microstructure evaluations, as well as a host of experiments to improve production of the waste form. Past INEL studies indicated that the IEB glass-ceramic is a material that will accommodate and stabilize a wide range of heterogeneous waste materials, including long lived radionuclides and scrap metals, while maintaining a superior level of chemical and physical performance characteristics. Controlled cooling of the molten IEB and subsequent heat treatment will produce a glass-ceramic waste form with superior leach resistance

  8. Execution techniques for high level radioactive waste disposal. 4. Design and manufacturing procedure of engineered barriers

    International Nuclear Information System (INIS)

    Ogata, Nobuhide; Kosaki, Akio; Ueda, Hiroyoshi; Asano, Hidekazu; Takao, Hajime

    1999-01-01

    Ensuring the physical integrity of engineered barriers for an extremely long time period is necessary for geological disposal of high-level radioactive wastes. This report describes the design process and the designed configurations of both overpack and buffer as engineered barriers. Manufacturing procedure, quality control and inspection methods are also summarized. Carbon steel was selected as a structural material of the overpack and the specification of the overpack was determined assuming disposal in the depths of 1000 m below surface of crystalline rock site. The mixture of bentonite and sand (80% sodium bentonite and 20% silica sand by mass) was selected as material for a buffer from mainly its permeability and characteristics of self-sealing of a gap occurred in construction work. Welding method of a lid onto the main body of the overpack, uniting method of a corrosion-resistance layer and the structural component in the case of a composite overpack and manufacturing procedures of both blocks-type and monolithic-type buffers are also investigated. (author)

  9. Summary of Uranium Solubility Studies in Concrete Waste Forms and Vadose Zone Environments

    Energy Technology Data Exchange (ETDEWEB)

    Golovich, Elizabeth C.; Wellman, Dawn M.; Serne, R. Jeffrey; Bovaird, Chase C.

    2011-09-30

    One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Concrete encasement would contain and isolate the waste packages from the hydrologic environment and act as an intrusion barrier. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages in concrete. These concrete-encased waste stacks are expected to vary in size with maximum dimensions of 6.4 m long, 2.7 m wide, and 4 m high. The waste stacks are expected to have a surrounding minimum thickness of 15 cm of concrete encasement. These concrete-encased waste packages are expected to withstand environmental exposure (solar radiation, temperature variations, and precipitation) until an interim soil cover or permanent closure cover is installed and to remain largely intact thereafter. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. This report presents the results of investigations elucidating the uranium mineral phases controlling the long-term fate of uranium within concrete waste forms and the solubility of these phases in concrete pore waters and alkaline, circum-neutral vadose zone environments.

  10. 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

  11. Photogrammetry and Laser Imagery Tests for Tank Waste Volume Estimates: Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Field, Jim G. [Washington River Protection Solutions, LLC, Richland, WA (United States)

    2013-03-27

    Feasibility tests were conducted using photogrammetry and laser technologies to estimate the volume of waste in a tank. These technologies were compared with video Camera/CAD Modeling System (CCMS) estimates; the current method used for post-retrieval waste volume estimates. This report summarizes test results and presents recommendations for further development and deployment of technologies to provide more accurate and faster waste volume estimates in support of tank retrieval and closure.

  12. 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

  13. Photogrammetry and Laser Imagery Tests for Tank Waste Volume Estimates: Summary Report

    International Nuclear Information System (INIS)

    Field, Jim G.

    2013-01-01

    Feasibility tests were conducted using photogrammetry and laser technologies to estimate the volume of waste in a tank. These technologies were compared with video Camera/CAD Modeling System (CCMS) estimates; the current method used for post-retrieval waste volume estimates. This report summarizes test results and presents recommendations for further development and deployment of technologies to provide more accurate and faster waste volume estimates in support of tank retrieval and closure

  14. Waste Isolation Pilot Plant disposal phase final supplemental environmental impact statement. Summary

    International Nuclear Information System (INIS)

    1997-09-01

    The purpose of the Waste Isolation Pilot Plant Disposal Final Supplemental Environmental Impact Statement (SEIS-II) is to provide information on environmental impacts regarding the Department of Energy''s (DOE) proposed disposal operations at WIPP. The Proposed Action describes the treatment and disposal of the Basic inventory of TRU waste over a 35-year period. The Action Alternatives proposed the treatment of the Basic Inventory and an Additional Inventory as well as the transportation of the treated waste to WIPP for disposal over a 150- to 190-year period. The three Action Alternatives include the treatment of TRU waste at consolidation sites to meet WIPP planning-basic Waste Acceptance Criteria, the thermal treatment of TRU waste to meet Land Disposal Restrictions, and the treatment of TRU waste by a shred and grout process. SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a combination of truck and dedicated rail service; and the disposal of this waste in the repository. Evaluated impacts include those to the general environment and to human health. Additional issues associated with the implementation of the alternatives are discussed to provide further understanding of the decisions to be reached and to provide the opportunity for public input on improving DOE''s Environmental Management Program

  15. Nuclear criticality safety analysis summary report: The S-area defense waste processing facility

    International Nuclear Information System (INIS)

    Ha, B.C.

    1994-01-01

    The S-Area Defense Waste Processing Facility (DWPF) can process all of the high level radioactive wastes currently stored at the Savannah River Site with negligible risk of nuclear criticality. The characteristics which make the DWPF critically safe are: (1) abundance of neutron absorbers in the waste feeds; (2) and low concentration of fissionable material. This report documents the criticality safety arguments for the S-Area DWPF process as required by DOE orders to characterize and to justify the low potential for criticality. It documents that the nature of the waste feeds and the nature of the DWPF process chemistry preclude criticality

  16. Executive summary. Summary of the workshop sessions

    International Nuclear Information System (INIS)

    2012-01-01

    The workshop played a great role in sharing the current state-of-the art on the PSA (Probabilistic Safety Assessment) of new and advanced reactors, and points of interest among member countries. The major concern expressed by the participants included passive safety system reliability, digital system reliability, new and advanced reactors-specific risk assessment methodology and relevant computational tool, and safety-security interface, etc). Main findings obtained from the workshop are as follows. For new reactors, the role of PSA is more important and more formalized comparing with exiting reactors. The PSAs are being used in the design of new reactors for purposes such as balance between accident prevention and mitigation features of the design, demonstration of safety, identification of design vulnerabilities and improvements, and comparison with the risk of existing plants, etc. For advanced reactors, the role of PSA is also being regarded as an essential tool for safety improvement and comparison of reactor designs at the conceptual or preliminary stages, but their practical use is at the early stage to gain the insights of risk into these reactors. This is due to the fact that the use of PSA for advanced reactors is mainly focused on identifying the PSA issues for designer and regulatory bodies, and developing the relevant methodologies and tools. Better guidance and peer review process on the PSA of new and advanced reactors was identified by both industry and regulatory as an important aspect

  17. Summary of TMX results: executive summary

    International Nuclear Information System (INIS)

    Simonen, T.C.

    1981-01-01

    This report summarizes results from the successful experimental operation of the Tandem Mirror Experiment (TMX) over the period October 1978 through September 1980. The experimental program, summarized by the DOE milestones given in Table 1, had three basic phases: (1) an 8-month checkout period, October 1978 through May 1979; (2) a 6-month initial period of operation, June through November 1979, during which the basic principles of the tandem configuration were demonstrated (i.e., plasma confinement was improved over that of a single-cell mirror); and (3) a 10-month period, December 1979 through September 1980, during which the initial TMX results were corroborated by additional diagnostic measurements and many detailed physics investigations were carried out. This report summarizes the early results, presents results of recent data analysis, and outlines areas of ongoing research

  18. Executive summary and recommendations from WHO/UNAIDS and AAVP consultation on: 'The inclusion of adolescents in HIV vaccine trials', 16-18 March 2006 in Gaborone, Botswana.

    Science.gov (United States)

    Osmanov, Saladin

    2007-09-12

    This report summarizes the discussions and recommendations from a consultation held in Gaborone, Botswana (16-19 March 2006), organized by the joint World Health Organization (WHO)/United Nations Programme on HIV/AIDS (UNAIDS) HIV Vaccine Initiative (HVI) and the African AIDS Vaccine Programme (AAVP). The consultation considered key challenges and strategies in enrolling adolescents into HIV vaccine clinical trials, relevant to developing countries, in particular in eastern and southern Africa. Approaches were identified that might address and resolve country-specific challenges related to scientific, legal, ethical, regulatory and community aspects of the involvement of adolescents in HIV vaccine trials. This executive summary is formulated for a broader dissemination of the outcomes of the meeting to the general clinical, scientific and regulatory community involved in the review, approval and monitoring of clinical trials and potential licensing of HIV vaccine candidates. Four major topics were discussed and recommendations developed with regard to: (i) criteria for products selection and clinical trial design; (ii) ethical and legal issues; (iii) community acceptance and participation; and (iv) regulatory considerations. The recommendations of this meeting were further discussed and endorsed by the WHO/UNAIDS HIV Vaccine Advisory Committee.

  19. Nuclear Dynamics Consequence Analysis (NDCA) for the Disposal of Spent Nuclear Fuel in an Underground Geologic Repository--Volume 1: Executive Summary

    International Nuclear Information System (INIS)

    Taylor, L.L.; Wilson, J.R.; Sanchez, L.Z.; Aguilar, R.; Trellue, H.R.; Cochrane, K.; Rath, J.S.

    1998-01-01

    The US Department of Energy Office of Environmental Management's (DOE/EM's) National Spent Nuclear Fuel Program (NSNFP), through a collaboration between Sandia National Laboratories (SNL) and Idaho National Engineering and Environmental Laboratory (INEEL), is conducting a systematic Nuclear Dynamics Consequence Analysis (NDCA) of the disposal of SNFs in an underground geologic repository sited in unsaturated tuff. This analysis is intended to provide interim guidance to the DOE for the management of the SNF while they prepare for final compliance evaluation. This report presents results from a Nuclear Dynamics Consequence Analysis (NDCA) that examined the potential consequences and risks of criticality during the long-term disposal of spent nuclear fuel owned by DOE-EM. This analysis investigated the potential of post-closure criticality, the consequences of a criticality excursion, and the probability frequency for post-closure criticality. The results of the NDCA are intended to provide the DOE-EM with a technical basis for measuring risk which can be used for screening arguments to eliminate post-closure criticality FEPs (features, events and processes) from consideration in the compliance assessment because of either low probability or low consequences. This report is composed of an executive summary (Volume 1), the methodology and results of the NDCA (Volume 2), and the applicable appendices (Volume 3)

  20. Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

    International Nuclear Information System (INIS)

    McLaughlin, T.J.

    1998-01-01

    This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

  1. Alternative Electrochemical Salt Waste Forms, Summary of FY/CY2011 Results

    Energy Technology Data Exchange (ETDEWEB)

    Riley, Brian J.; McCloy, John S.; Crum, Jarrod V.; Rodriguez, Carmen P.; Windisch, Charles F.; Lepry, William C.; Matyas, Josef; Westman, Matthew P.; Rieck, Bennett T.; Lang, Jesse B.; Pierce, David A.

    2011-12-01

    This report summarizes the 2011 fiscal+calendar year efforts for developing waste forms for a spent salt generated in reprocessing nuclear fuel with an electrochemical separations process. The two waste forms are tellurite (TeO2-based) glasses and sol-gel-derived high-halide mineral analogs to stable minerals found in nature.

  2. DOE systems approach to a low-level waste management information system: summary paper

    International Nuclear Information System (INIS)

    Esparza, V.

    1987-01-01

    The LLWMP is performing an assessment of waste information systems currently in use at each DOE site for recording LLW data. The assessment is being conducted to determine what changes to the waste information systems, if any, are desirable to support implementation of this systems approach to LLW management. Recommendations will be made to DOE from this assessment and what would be involved to modify current DOE waste generator information practices to support an appropriately structured overall DOE LLW data systems. In support of reducing the uncertainty of decision-making, DOE has selected a systems approach to keep pace with an evolving regulatory climate to low-level waste. This approach considers the effects of each stage of the entire low-level waste management process. The proposed systems approach starts with the disposal side of the waste management system and progresses towards the waste generation side of the waste management system. Using this approach provides quantitative performance to be achieved. In addition, a systems approach also provides a method for selecting appropriate technology based on engineering models

  3. Alternative Electrochemical Salt Waste Forms, Summary of FY/CY2011 Results

    International Nuclear Information System (INIS)

    Riley, Brian J.; McCloy, John S.; Crum, Jarrod V.; Rodriguez, Carmen P.; Windisch, Charles F.; Lepry, William C.; Matyas, Josef; Westman, Matthew P.; Rieck, Bennett T.; Lang, Jesse B.; Pierce, David A.

    2011-01-01

    This report summarizes the 2011 fiscal+calendar year efforts for developing waste forms for a spent salt generated in reprocessing nuclear fuel with an electrochemical separations process. The two waste forms are tellurite (TeO2-based) glasses and sol-gel-derived high-halide mineral analogs to stable minerals found in nature.

  4. Summary of non-US national and international radioactive waste management programs 1981

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.

    1981-06-01

    Many nations and international agencies are working to develop improved technology and industrial capability for neuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major efforts in these fields as of the end of May 1981

  5. 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

  6. 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

  7. 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

  8. 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

  9. Summary of non-US national and international radioactive waste management programs 1980

    International Nuclear Information System (INIS)

    Harmon, K.M.; Kelman, J.A.; Stout, L.A.; Hsieh, K.A.

    1980-03-01

    Many nations and international agencies are working to develop improved technology and industrial capability for nuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major efforts in these fields as of the end of January 1980

  10. 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

  11. Tank Waste Transport Stability: Summary of Slurry and Salt-Solution Studies for FY 2001

    Energy Technology Data Exchange (ETDEWEB)

    Welch, T.D.

    2002-06-07

    Despite over 50 years of experience in transporting radioactive tank wastes to and from equipment and tanks at the Department of Energy's Hanford, Savannah River, and Oak Ridge sites, waste slurry transfer pipelines and process piping become plugged on occasion. At Hanford, several tank farm pipelines are no longer in service because of plugs. At Savannah River, solid deposits in the outlet line of the 2H evaporator have resulted in an unplanned extended downtime. Although waste transfer criteria and guidelines intended to prevent pipeline plugging are in place, they are not always adequate. To avoid pipeline plugging in the future, other factors that are not currently embodied in the transfer criteria may need to be considered. The work summarized here is being conducted to develop a better understanding of the chemical and waste flow dynamics during waste transfer. The goal is to eliminate pipeline plugs by improving analysis and engineering tools in the field that incorporate this understanding.

  12. 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.

  13. 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.

  14. 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

  15. Waste Tank Summary Report for Month Ending 04/30/2002

    International Nuclear Information System (INIS)

    HANLON, B.M.

    2002-01-01

    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 60 smaller miscellaneous underground storage 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 Order 435.1 (DOE-HQ, August 28, 2001, Radioactive Waste Management, US. Department of Energy-Washington, D.C.) requiring the reporting of waste inventories and space utilization for the Hanford Site Tank Farm tanks

  16. 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

  17. 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

  18. 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.

  19. 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.

  20. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Management Program. Revision 5

    International Nuclear Information System (INIS)

    1984-09-01

    This updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. In general, the information in this report is accurate as of 31 August 1984

  1. 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

  2. System analysis of energy utilization from waste - evaluation of energy, environment and economy. Summary report

    International Nuclear Information System (INIS)

    Sundqvist, Jan-Olov; Granath, Jessica; Frostell, Bjoern; Bjoerklund, Anna; Eriksson, Ola; Carlsson, Marcus

    1999-12-01

    Energy, environmental, and economic consequences of different management systems for municipal solid waste have been studied in a systems analysis. In the systems analysis, different combinations of incineration, materials recycling of separated plastic and cardboard containers, and biological treatment (anaerobic digestion and composting) of easily degradable organic waste, were studied and also compared to landfilling. In the study a computer model (ORWARE) based on LCA methodology was used. Case studies were performed for three different municipalities: Uppsala, Stockholm, and Aelvdalen. The following parameters were used for evaluating the different waste management options: consumption of energy resources, global warming potential, acidification, eutrophication, photo oxidant formation, heavy metal flows, financial economy and welfare economy, where welfare economy is the sum of financial economy and environmental economy. The study shows that reduced landfilling to the benefit of an increased use of energy and material from waste is positive from an environmental and energy as well as economic aspect. This is mainly due to the fact that the choice of waste management method affects processes outside the waste management system, such as production of district heating, electricity, vehicle fuel, plastic, cardboard, and fertiliser. This means that landfilling of energy-rich waste should be avoided as far as possible, both because of the the environmental impact, and because of the low recovery of resources. Incineration should constitute a basis in the waste management systems of the three municipalities studied, even if the waste has to be transported to a regional facility. Once the waste is collected, longer regional transports are of little significance, as long as the transports are carried out in an efficient manner. Comparing materials recycling and incineration, and biological treatment and incineration, no unambiguous conclusions can be drawn. There are

  3. Test Summary Report INEEL Sodium-Bearing Waste Vitrification Demonstration RSM-01-1

    Energy Technology Data Exchange (ETDEWEB)

    Goles, Ronald W.; Perez, Joseph M.; Macisaac, Brett D.; Siemer, Darryl D.; Mccray, John A.

    2001-05-21

    The U.S. Department of Energy's Idaho National Engineering and Environmental Laboratory is storing large amounts of radioactive and mixed wastes. Most of the sodium-bearing wastes have been calcined, but about a million gallons remain uncalcined, and this waste does not meet current regulatory requirements for long-term storage and/or disposal. As a part of the Settlement Agreement between DOE and the State of Idaho, the tanks currently containing SBW are to be taken out of service by December 31, 2012, which requires removing and treatment the remaining SBW. Vitrification is the option for waste disposal that received the highest weighted score against the criteria used. Beginning in FY 2000, the INEEL high-level waste program embarked on a program for technology demonstration and development that would lead to conceptual design of a vitrification facility in the event that vitrification is the preferred alternative for SBW disposal. The Pacific Northwest National Laborator's Research-Scale Melter was used to conduct these initial melter-flowsheet evaluations. Efforts are underway to reduce the volume of waste vitrified, and during the current test, an overall SBW waste volume-reduction factor of 7.6 was achieved.

  4. 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

  5. Summary Of Cold Crucible Vitrification Tests Results With Savannah River Site High Level Waste Surrogates

    Energy Technology Data Exchange (ETDEWEB)

    Stefanovsky, Sergey; Marra, James; Lebedev, Vladimir

    2014-01-13

    The cold crucible inductive melting (CCIM) technology successfully applied for vitrification of low- and intermediate-level waste (LILW) at SIA Radon, Russia, was tested to be implemented for vitrification of high-level waste (HLW) stored at Savannah River Site, USA. Mixtures of Sludge Batch 2 (SB2) and 4 (SB4) waste surrogates and borosilicate frits as slurries were vitrified in bench- (236 mm inner diameter) and full-scale (418 mm inner diameter) cold crucibles. Various process conditions were tested and major process variables were determined. Melts were poured into 10L canisters and cooled to room temperature in air or in heat-insulated boxes by a regime similar to Canister Centerline Cooling (CCC) used at DWPF. The products with waste loading from ~40 to ~65 wt.% were investigated in details. The products contained 40 to 55 wt.% waste oxides were predominantly amorphous; at higher waste loadings (WL) spinel structure phases and nepheline were present. Normalized release values for Li, B, Na, and Si determined by PCT procedure remain lower than those from EA glass at waste loadings of up to 60 wt.%.

  6. Materials Characterization Center meeting on impact testing of waste forms. Summary report

    International Nuclear Information System (INIS)

    Merz, M.D.; Atteridge, D.; Dudder, G.

    1981-10-01

    A meeting was held on March 25-26, 1981 to discuss impact test methods for waste form materials to be used in nuclear waste repositories. The purpose of the meeting was to obtain guidance for the Materials Characterization Center (MCC) in preparing the MCC-10 Impact Test Method to be approved by the Materials Review Board. The meeting focused on two essential aspects of the test method, namely the mechanical process, or impact, used to effect rapid fracture of a waste form and the analysis technique(s) used to characterize particulates generated by the impact

  7. Integrated process analyses studies on mixed low level and transuranic wastes. Summary report

    International Nuclear Information System (INIS)

    1997-12-01

    Options for integrated thermal and nonthermal treatment systems for mixed low-level waste (MLLW) are compared such as total life cycle cost (TLCC), cost sensitivities, risk, energy requirements, final waste volume, and aqueous and gaseous effluents. The comparisons were derived by requiring all conceptual systems to treat the same composition of waste with the same operating efficiency. Thus, results can be used as a general guideline for the selection of treatment and disposal concepts. However, specific applications of individual systems will require further analysis. The potential for cost saving options and the research and development opportunities are summarized

  8. Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

    International Nuclear Information System (INIS)

    Stone, J.A.; Christensen, E.J.

    1983-12-01

    This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

  9. Integrated process analyses studies on mixed low level and transuranic wastes. Summary report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    Options for integrated thermal and nonthermal treatment systems for mixed low-level waste (MLLW) are compared such as total life cycle cost (TLCC), cost sensitivities, risk, energy requirements, final waste volume, and aqueous and gaseous effluents. The comparisons were derived by requiring all conceptual systems to treat the same composition of waste with the same operating efficiency. Thus, results can be used as a general guideline for the selection of treatment and disposal concepts. However, specific applications of individual systems will require further analysis. The potential for cost saving options and the research and development opportunities are summarized.

  10. The Integrated Data Base program: An executive-level data base of spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    Klein, J.A.

    1987-01-01

    The Integrated Data Base (IDB) is the official US Department of Energy (DOE) data base for spent fuel and radioactive waste inventories and projections. As such, it should be as convenient to utilize as is practical. Examples of summary-level tables and figures are presented, as well as more-detailed graphics describing waste-form distribution by site and line charts illustrating historical and projected volume (or mass) changes. This information is readily accessible through the annual IDB publication. Other presentation formats are also available to the DOE community through a simple request to the IDB Program

  11. Elimination of ammonium from waste water by means of chemical precipitation. Summary

    International Nuclear Information System (INIS)

    Boehnke, B.; Schulze-Rettmer, R.

    1990-07-01

    In the course of this research project, a process for precipitating ammonium salts contained in waste water was developed. The precipitate can be used as fertilizer. The purification process was tested in a pilot plant. (EF) [de

  12. Evaluating the use of waste-to-energy bottom ash as road construction materials : [summary].

    Science.gov (United States)

    2014-02-01

    Municipal solid waste incineration (MSWI) generates millions of tons of ash each year. In European and Asian countries, this ash has been recycled into road beds, asphalt paving, and concrete products encouraged and enforced by standards, managem...

  13. FY 1987 program summary document: Office of Defense Waste and Transportation Management

    International Nuclear Information System (INIS)

    1987-04-01

    This document describes the Office of Defense Waste and Transportation Management (DWTM) Program as supported by the President's Fiscal Year (FY) 1987 Budget Request to Congress. It specifically addresses the program's organization, objectives, strategies, and plans for FY 1987

  14. Foaming in Hanford River Protection Project Waste Treatment Plant LAW Evaporation Processes - FY01 Summary Report

    International Nuclear Information System (INIS)

    Calloway, T.B.

    2002-01-01

    The LAW evaporation processes currently being designed for the Hanford River Protection Project Waste Treatment Plant are subject to foaming. Experimental simulant studies have been conducted in an effort to achieve an effective antifoam agent suitable to mitigate such foaming

  15. Summary report on the development of a cement-based formula to immobilize Hanford facility waste

    International Nuclear Information System (INIS)

    Gilliam, T.M.; McDaniel, E.W.; Dole, L.R.; Friedman, H.A.; Loflin, J.A.; Mattus, A.J.; Morgan, I.L.; Tallent, O.K.; West, G.A.

    1987-09-01

    This report recommends a cement-based grout formula to immobilize Hanford Facility Waste in the Transportable Grout Facility (TGF). Supporting data confirming compliance with all TGF performance criteria are presented. 9 refs., 24 figs., 50 tabs

  16. Summary of the 2012 Wide Area Recovery and Resiliency Program (WARRP) Waste Management Workshop

    Science.gov (United States)

    Workshop advanced the planning of federal, state and local officials in the area of waste management following a chemical, biological or radiological wide-area incident in the Denver, Colorado urban area.

  17. Mixed Waste Management Facility Groundwater Monitoring Report, Fourth Quarter 1998 and 1998 Summary

    International Nuclear Information System (INIS)

    Chase, J.

    1999-01-01

    During fourth quarter 1998, ten constituents exceeded final Primary Drinking Water Standards (PDWS) in groundwater samples from downgradient monitoring wells at the Mixed Waste Management Facility. No constituents exceeded final PDWS in samples from the upgradient monitoring wells

  18. Summary report for the WIPP [Waste Isolation Pilot Plant] technology development program for isolation of radioactive waste

    International Nuclear Information System (INIS)

    Tyler, L.D.; Matalucci, R.V.; Molecke, M.A.; Munson, D.E.; Nowak, E.J.; Stormont, J.C.

    1988-04-01

    The technology experiments have been managed in three broad categories: Thermal/Structural Interactions (TSI), Plugging and Sealing Performance and Design (PandS), and Waste Package Performance (WPP). The history and major progress in each of these areas is summarized in this report. The TSI program has established the fact that the WIPP salt creep rate, and therefore closure of WIPP rooms, is about three times more rapid than our best models predicted prior to the tests. Studies to resolve this discrepancy are well advanced; in the interim, good agreement between predicitions and observation is obtained by empirical adjustment of the elastic constants. The closure of backfilled waste room to about five percent void volume is predicted to take less than 100 years, the time during which active controls may be assumed to prevent human intrusion. The waste package program has revealed that migration of interstitial brine to excavations in the WIPP salt occurs at a significantly greater rate than assumed by earlier investigations. A satisfactory model to explain the data utilizes darcy flow in very low permeability salt which is driven by a pore pressure gradient caused when the excavation creates an atmospheric pressure boundary. This model, coupled with room closure predictions and backfill design using a salt/bentonite clay mixture, indicates that the rate of brine seepage will not result in a fluid or slurry state in the room, but rather in a compacted solid. 373 refs., 20 figs., 9 tabs

  19. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories.

  20. Historically Black Colleges and Universities Radioactive Waste Management Research Program: Summary of activities, 1985-1986

    International Nuclear Information System (INIS)

    1986-01-01

    This report summarizes the 1985 to 1986 activities of the Historically Black Colleges and Universities (HBCUs) Radioactive Waste Management Research Program sponsored by the Office of Civilian Radioactive Waste Management of the US Department of Energy (DOE). The first set of three awards was made in September,1984. In September, 1985, two of these projects were renewed and a new proposal was funded. The program has been enthusiastically received by the community of HBCUs and the program sponsor

  1. A Summary of the Academic Symposium on the Treatment and Management of City Wastes

    Institute of Scientific and Technical Information of China (English)

    1991-01-01

    <正> With the continuous worsening of theproblems of urban wastes about 60 urbanscientific workers gathered in Guiyang to dis-cuss the present state of the treatment andmanagement of urban wastes and find rela-tive solutions to the problems.The“Guiyang Symposium on the Treat-ment and Management of City Wastes”jointly sponsored by the Chinese Urban Sci-entific Research Institute,the Urban Con-struction Department of the Ministry of Ur-

  2. Preliminary technical data summary No. 3 for the Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    Landon, L.F.

    1980-05-01

    This document presents an update on the best information presently available for the purpose of establishing the basis for the design of a Defense Waste Processing Facility. Objective of this project is to provide a facility to fix the radionuclides present in Savannah River Plant (SRP) high-level liquid waste in a high-integrity form (glass). Flowsheets and material balances reflect the alternate CAB case including the incorporation of low-level supernate in concrete

  3. Summary of national and international fuel cycle and radioactive waste management programs, 1984

    International Nuclear Information System (INIS)

    Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

    1984-07-01

    Worldwide activities related to nuclear fuel cycle and radioactive waste management programs are summarized. Several trends have developed in waste management strategy: All countries having to dispose of reprocessing wastes plan on conversion of the high-level waste (HLW) stream to a borosilicate glass and eventual emplacement of the glass logs, suitably packaged, in a deep geologic repository. Countries that must deal with plutonium-contaminated waste emphasize pluonium recovery, volume reduction and fixation in cement or bitumen in their treatment plans and expect to use deep geologic repositories for final disposal. Commercially available, classical engineering processing are being used worldwide to treat and immobilize low- and intermediate-level wastes (LLW, ILW); disposal to surface structures, shallow-land burial and deep-underground repositories, such as played-out mines, is being done widely with no obvious technical problems. Many countries have established extensive programs to prepare for construction and operation of geologic repositories. Geologic media being studied fall into three main classes: argillites (clay or shale); crystalline rock (granite, basalt, gneiss or gabbro); and evaporates (salt formations). Most nations plan to allow 30 years or longer between discharge of fuel from the reactor and emplacement of HLW or spent fuel is a repository to permit thermal and radioactive decay. Most repository designs are based on the mined-gallery concept, placing waste or spent fuel packages into shallow holes in the floor of the gallery. Many countries have established extensive and costly programs of site evaluation, repository development and safety assessment. Two other waste management problems are the subject of major R and D programs in several countries: stabilization of uranium mill tailing piles; and immobilization or disposal of contaminated nuclear facilities, namely reactors, fuel cycle plants and R and D laboratories

  4. Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results

    Energy Technology Data Exchange (ETDEWEB)

    Riley, Brian J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mccloy, John S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crum, Jarrod V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lepry, William C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rodriguez, Carmen P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Windisch, Charles F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Matyas, Josef [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westman, Matthew P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rieck, Bennett T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lang, Jesse B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Olszta, Matthew J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pierce, David A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-01-17

    The Fuel Cycle Research and Development Program, sponsored by the U.S. Department of Energy Office of Nuclear Energy, is currently investigating alternative waste forms for wastes generated from nuclear fuel processing. One such waste results from an electrochemical separations process, called the “Echem” process. The Echem process utilizes a molten KCl-LiCl salt to dissolve the fuel. This process results in a spent salt containing alkali, alkaline earth, lanthanide halides and small quantities of actinide halides, where the primary halide is chloride with a minor iodide fraction. Pacific Northwest National Laboratory (PNNL) is concurrently investigating two candidate waste forms for the Echem spent-salt: high-halide minerals (i.e., sodalite and cancrinite) and tellurite (TeO2)-based glasses. Both of these candidates showed promise in fiscal year (FY) 2009 and FY2010 with a simplified nonradioactive simulant of the Echem waste. Further testing was performed on these waste forms in FY2011 and FY2012 to assess the possibility of their use in a sustainable fuel cycle. This report summarizes the combined results from FY2011 and FY2012 efforts.

  5. Tank Waste Remediation System, Hanford Site, Richland, Washington. Final environmental impact statement. Summary

    International Nuclear Information System (INIS)

    1996-08-01

    This document analyzes the potential environmental consequences related to the Hanford Site Tank Waste Remediation System (TWRS) alternatives for management and disposal of radioactive, hazardous, and mixed waste, and the management and disposal of approximately 1,930 cesium and strontium capsules located at the Hanford Site. This waste is currently or projected to be stored in 177 underground storage tanks and approximately 60 miscellaneous underground storage tanks. This document analyzes the following alternatives for remediating the tank waste: No Action, Long-Term Management, In Situ Fill and Cap, In Situ Vitrification, Ex Situ Intermediate Separations, Ex Situ No Separations, Ex Situ Extensive Separations, Ex Situ/In Situ Combination 1, and Ex Situ/In Situ Combination 2. This document also addresses a Phased Implementation alternative (the DOE and Ecology preferred alternative for remediation of tank waste). Alternatives analyzed for the cesium and strontium capsules include: No Action, Onsite Disposal, Overpack and Ship, and Vitrify with Tank Waste. The DOE and Ecology preferred alternative for the cesium and strontium capsules is the No Action alternative

  6. CalTOX, a multimedia total exposure model for hazardous-waste sites; Part 1, Executive summary

    Energy Technology Data Exchange (ETDEWEB)

    McKone, T.E.

    1993-06-01

    CalTOX has been developed as a spreadsheet model to assist in health-risk assessments that address contaminated soils and the contamination of adjacent air, surface water, sediments, and ground water. The modeling effort includes a multimedia transport and transformation model, exposure scenario models, and efforts to quantify and reduce uncertainty in multimedia, multiple-pathway exposure models. This report provides an overview of the CalTOX model components, lists the objectives of the model, describes the philosophy under which the model was developed, identifies the chemical classes for which the model can be used, and describes critical sensitivities and uncertainties. The multimedia transport and transformation model is a dynamic model that can be used to assess time-varying concentrations of contaminants introduced initially to soil layers or for contaminants released continuously to air or water. This model assists the user in examining how chemical and landscape properties impact both the ultimate route and quantity of human contact. Multimedia, multiple pathway exposure models are used in the CalTOX model to estimate average daily potential doses within a human population in the vicinity of a hazardous substances release site. The exposure models encompass twenty-three exposure pathways. The exposure assessment process consists of relating contaminant concentrations in the multimedia model compartments to contaminant concentrations in the media with which a human population has contact (personal air, tap water, foods, household dusts soils, etc.). The average daily dose is the product of the exposure concentrations in these contact media and an intake or uptake factor that relates the concentrations to the distributions of potential dose within the population.

  7. Abandoned Mine Waste Working Group report

    International Nuclear Information System (INIS)

    1993-01-01

    The Mine Waste Working Group discussed the nature and possible contributions to the solution of this class of waste problem at length. There was a consensus that the mine waste problem presented some fundamental differences from the other classes of waste addresses by the Develop On-Site Innovative Technologies (DOIT) working groups. Contents of this report are: executive summary; stakeholders address the problems; the mine waste program; current technology development programs; problems and issues that need to be addressed; demonstration projects to test solutions; conclusion-next steps; and appendices

  8. Radioactive Waste in Perspective

    International Nuclear Information System (INIS)

    2011-01-01

    Large volumes of hazardous wastes are produced each year, however only a small proportion of them are radioactive. While disposal options for hazardous wastes are generally well established, some types of hazardous waste face issues similar to those for radioactive waste and also require long-term disposal arrangements. The objective of this NEA study is to put the management of radioactive waste into perspective, firstly by contrasting features of radioactive and hazardous wastes, together with their management policies and strategies, and secondly by examining the specific case of the wastes resulting from carbon capture and storage of fossil fuels. The study seeks to give policy makers and interested stakeholders a broad overview of the similarities and differences between radioactive and hazardous wastes and their management strategies. Contents: - Foreword; - Key Points for Policy Makers; - Executive Summary; - Introduction; - Theme 1 - Radioactive and Hazardous Wastes in Perspective; - Theme 2 - The Outlook for Wastes Arising from Coal and from Nuclear Power Generation; - Risk, Perceived Risk and Public Attitudes; - Concluding Discussion and Lessons Learnt; - Strategic Issues for Radioactive Waste; - Strategic Issues for Hazardous Waste; - Case Studies - The Management of Coal Ash, CO 2 and Mercury as Wastes; - Risk and Perceived Risk; - List of Participants; - List of Abbreviations. (authors)

  9. Executive Summary: European Heart Rhythm Association Consensus Document on the Management of Supraventricular Arrhythmias: Endorsed by Heart Rhythm Society (HRS), Asia-Pacific Heart Rhythm Society (APHRS), and Sociedad Latinoamericana de Estimulación Cardiaca y Electrofisiologia (SOLAECE).

    Science.gov (United States)

    Katritsis, Demosthenes G; Boriani, Giuseppe; Cosio, Francisco G; Jais, Pierre; Hindricks, Gerhard; Josephson, Mark E; Keegan, Roberto; Knight, Bradley P; Kuck, Karl-Heinz; Lane, Deirdre A; Lip, Gregory Yh; Malmborg, Helena; Oral, Hakan; Pappone, Carlo; Themistoclakis, Sakis; Wood, Kathryn A; Young-Hoon, Kim; Lundqvist, Carina Blomström

    2016-01-01

    This paper is an executive summary of the full European Heart Rhythm Association (EHRA) consensus document on the management of supraventricular arrhythmias, published in Europace . It summarises developments in the field and provides recommendations for patient management, with particular emphasis on new advances since the previous European Society of Cardiology guidelines. The EHRA consensus document is available to read in full at http://europace.oxfordjournals.org.

  10. Lipids and bariatric procedures part 1 of 2: Scientific statement from the National Lipid Association, American Society for Metabolic and Bariatric Surgery, and Obesity Medicine Association: EXECUTIVE SUMMARY.

    Science.gov (United States)

    Bays, Harold E; Jones, Peter H; Jacobson, Terry A; Cohen, David E; Orringer, Carl E; Kothari, Shanu; Azagury, Dan E; Morton, John; Nguyen, Ninh T; Westman, Eric C; Horn, Deborah B; Scinta, Wendy; Primack, Craig

    2016-01-01

    Bariatric procedures often improve lipid levels in patients with obesity. This 2-part scientific statement examines the potential lipid benefits of bariatric procedures and represents contributions from authors representing the National Lipid Association, American Society for Metabolic and Bariatric Surgery, and the Obesity Medicine Association. The foundation for this scientific statement was based on data published through June 2015. Part 1 of this 2-part scientific statement provides an overview of: (1) adipose tissue, cholesterol metabolism, and lipids; (2) bariatric procedures, cholesterol metabolism, and lipids; (3) endocrine factors relevant to lipid influx, synthesis, metabolism, and efflux; (4) immune factors relevant to lipid influx, synthesis, metabolism, and efflux; (5) bariatric procedures, bile acid metabolism, and lipids; and (6) bariatric procedures, intestinal microbiota, and lipids, with specific emphasis on how the alterations in the microbiome by bariatric procedures influence obesity, bile acids, and inflammation, which in turn, may all affect lipid levels. Included in part 2 of this comprehensive scientific statement will be a review of: (1) the importance of nutrients (fats, carbohydrates, and proteins) and their absorption on lipid levels; (2) the effects of bariatric procedures on gut hormones and lipid levels; (3) the effects of bariatric procedures on nonlipid cardiovascular disease risk factors; (4) the effects of bariatric procedures on lipid levels; (5) effects of bariatric procedures on cardiovascular disease; and finally (6) the potential lipid effects of vitamin, mineral, and trace element deficiencies that may occur after bariatric procedures. This document represents the executive summary of part 1. Copyright © 2016 National Lipid Association. All rights reserved.

  11. Data summary of municipal solid waste management alternatives. Volume 3, Appendix A: Mass burn technologies

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-10-01

    This appendix on Mass Burn Technologies is the first in a series designed to identify, describe and assess the suitability of several currently or potentially available generic technologies for the management of municipal solid waste (MSW). These appendices, which cover eight core thermoconversion, bioconversion and recycling technologies, reflect public domain information gathered from many sources. Representative sources include: professional journal articles, conference proceedings, selected municipality solid waste management plans and subscription technology data bases. The information presented is intended to serve as background information that will facilitate the preparation of the technoeconomic and life cycle mass, energy and environmental analyses that are being developed for each of the technologies. Mass burn has been and continues to be the predominant technology in Europe for the management of MSW. In the United States, the majority of the existing waste-to-energy projects utilize this technology and nearly 90 percent of all currently planned facilities have selected mass burn systems. Mass burning generally refers to the direct feeding and combustion of municipal solid waste in a furnace without any significant waste preprocessing. The only materials typically removed from the waste stream prior to combustion are large bulky objects and potentially hazardous or undesirable wastes. The technology has evolved over the last 100 or so years from simple incineration to the most highly developed and commercially proven process available for both reducing the volume of MSW and for recovering energy in the forms of steam and electricity. In general, mass burn plants are considered to operate reliably with high availability.

  12. The Undereducated American. Executive Summary

    Science.gov (United States)

    Carnavale, Anthony P.; Rose, Stephen J.

    2011-01-01

    The United States has been underproducing college-going workers since 1980. Supply has failed to keep pace with growing demand, and as a result, income inequality has grown precipitously. From 1915 to 1980, supply grew in tandem with demand. But, starting in 1990, the share of college-educated young people in the workforce rose very slowly. If the…

  13. Constellation Lessons Learned Executive Summary

    Science.gov (United States)

    Thomas, L. Dale; Neubek, Deb

    2011-01-01

    This slide presentation reviews the lessons learned from the Constellation Program (CxP) and identified several factors that contributed to the inability of the CxP to meet the cost and schedule commitments. The review includes a significant section on the context in which the CxP operated since new programs are likely to experience the same constraints.

  14. Executive summary of phase 2

    International Nuclear Information System (INIS)

    1989-02-01

    The second phase of the Stripa project included the continued development of methods and techniques for repository site investigations. The crosshole investigations demonstrated that it is possible to characterize fractures in crystralline rock with a reliability and realism not obtained before. At the investigated site at Stripa, it was shown that groundwater flow is concentrated within a few major fractures that were idenfified by geophysical methods. The work at Stripa has shown that it is possible to collect and analyze data that enable one to determine the type of distribution and its parameters for each of the essential geometrical and hydraulic properties of the fracture system, and hence compare one site with another as part of experience builing in safety assessment studies. The migration experiment demonstrated that the groundwater flow could be very unevenly distributed in the rock. The hydrogeochemical investigations at Stripa also indicated that a new type of solute source must be considered - fluid inclusions in the host rock. The age of the solutes may be entirely different from the age of the groundwater. Sealing and redirection of the groundwater flow away from man made openings in the rock was tested at Stripa and found to be feasible as shown in the various plugging and sealing experiments. The use of Na bentonite in the form of suitably shaped blocks of highly compacted powder has been found to be very practical for sealing off boreholes, shafts and tunnels in repositories

  15. Annual Waste Minimization Summary Report for the National Nuclear Security Administration Nevada Site Office

    International Nuclear Information System (INIS)

    Alfred J. Karns

    2007-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U. S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during CY06. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit ((number s ign)NEV HW0021) and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the DOE, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by the NNSA/NSO and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  16. ALARA in radioactive waste management- Summary and recommendations of the 11. European ALARA Network Workshop

    International Nuclear Information System (INIS)

    Shaw, P.; Crouail, P.; Drouet, F.

    2008-01-01

    The 11. European ALARA Network (E.A.N.) workshop on 'ALARA in radioactive waste management' took place in Athens (Greece) in April 2008. The aim of that workshop was to focus on the implementation of the ALARA principle with regard to occupational and public exposures arising from the management of radioactive waste in all sectors (nuclear, medical, industrial, etc.). This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. Individual presentations (papers and slides) are available to download from the E.A.N. web site (http://www.eu-alara.net). Based on report backs from the groups and discussions with all the participants, five formal recommendations have been formulated. These recommendations, addressed to international organisations (International Atomic Energy Agency, European Commission, Nuclear Energy Agency), national authorities, national and local stake holders and to E.A.N. itself, deal with the following themes: international guidance on ALARA in radioactive waste management, harmonization issues at the international level, ALARA approach in non-nuclear waste management, 'broader approach' in the radioactive waste management process, stake holder involvement. The objective of this paper is to present the main conclusions and the five recommendations produced during the workshop. (authors)

  17. Materials characterization center workshop on compositional and microstructural analysis of nuclear waste materials. Summary report

    International Nuclear Information System (INIS)

    Daniel, J.L.; Strachan, D.M.; Shade, J.W.; Thomas, M.T.

    1981-06-01

    The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented

  18. Data summary of municipal solid waste management alternatives. Volume 1, Report text

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-10-01

    This report provides data for use in evaluating the proven technologies and combinations of technologies that might be considered for managing municipal solid waste (MSW). It covers five major methods for MSW management in common use today: Landfilling; Mass combustion for energy recovery; Production of refuse-derived fuel (RDF); Collection/separation of recyclables; and Composting. It also provides information on three MSW management technologies that are not widely used at present: Anaerobic digestion; Cofiring of MSW with coal; and Gasification/pyrolysis. To the extent possible with available reliable data, the report presents information for each proven MSW technology on: Net energy balances; Environmental releases; and Economics. In addition to data about individual operations, the report presents net energy balances and inventories of environmental releases from selected combined MSW management strategies that use two or more separate operations. The scope of the report extends from the waste`s origin (defined as the point at which the waste is set out for collection), through transportation and processing operations, to its final disposition (e.g., recycling and remanufacturing, combustion, or landfilling operations). Data for all operations are presented on a consistent basis: one (1) ton of municipal (i.e., residential, commercial, and institutional) waste at the collection point. Selection of an MSW management plan may be influenced by many factors, in addition to the technical performance and economics of each option.

  19. Historical summary of the fuel and waste handling and disposition activities of the TMI-2 Information and Examination Program (1980-1988)

    International Nuclear Information System (INIS)

    Reno, H.W.; Schmitt, R.C.

    1988-10-01

    This report is a historical summary of the major activities conducted by the TMI-2 Information and Examination Program in managing fuel and special radioactive wastes resulting from the accident at the Unit 2 reactor of the Three Mile Island Nuclear Power Station (TMI-2). The activities often required the development and use of advanced handling, processing, and/or disposal technologies for those wastes

  20. Feasibility of space disposal of radioactive nuclear waste. 2: Technical summary

    Science.gov (United States)

    1974-01-01

    The feasibility of transporting radioactive waste produced in the process of generating electricity in nuclear powerplants into space for ultimate disposal was investigated at the request of the AEC as a NASA in-house effort. The investigation is part of a broad AEC study of methods for long-term storage or disposal of radioactive waste. The results of the study indicate that transporting specific radioactive wastes, particularly the actinides with very long half-lives, into space using the space shuttle/tug as the launch system, appears feasible from the engineering and safety viewpoints. The space transportation costs for ejecting the actinides out of the solar system would represent less than a 5-percent increase in the average consumer's electric bill.