Sample records for risk-informed safety margin

  1. RISK-INFORMED SAFETY MARGIN CHARACTERIZATION

    SciTech Connect (OSTI)

    Nam Dinh; Ronaldo Szilard

    2009-07-01T23:59:59.000Z

    The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system’s “loading” and its “capacity”, plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons.

  2. Risk Informed Margins Management as part of Risk Informed Safety Margin Characterization

    SciTech Connect (OSTI)

    Curtis Smith

    2014-06-01T23:59:59.000Z

    The ability to better characterize and quantify safety margin is important to improved decision making about Light Water Reactor (LWR) design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the Risk Informed Safety Margin Characterization (RISMC) Pathway provides methods and tools that enable mitigation options known as risk informed margins management (RIMM) strategies.

  3. A risk-informed approach to safety margins analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-07-01T23:59:59.000Z

    The Risk Informed Safety Margins Characterization (RISMC) Pathway is a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. The model has been tested on the Advanced Test Reactor (ATR) at Idaho National Lab.

  4. Risk-Informed Safety Margin Characterization Methods Development Work

    SciTech Connect (OSTI)

    Smith, Curtis L; Ma, Zhegang; Tom Riley; Mandelli, Diego; Nielsen, Joseph W; Alfonsi, Andrea; Rabiti, Cristian

    2014-09-01T23:59:59.000Z

    This report summarizes the research activity developed during the Fiscal year 2014 within the Risk Informed Safety Margin and Characterization (RISMC) pathway within the Light Water Reactor Sustainability (LWRS) campaign. This research activity is complementary to the one presented in the INL/EXT-??? report which shows advances Probabilistic Risk Assessment Analysis using RAVEN and RELAP-7 in conjunction to novel flooding simulation tools. Here we present several analyses that prove the values of the RISMC approach in order to assess risk associated to nuclear power plants (NPPs). We focus on simulation based PRA which, in contrast to classical PRA, heavily employs system simulator codes. Firstly we compare, these two types of analyses, classical and RISMC, for a Boiling water reactor (BWR) station black out (SBO) initiating event. Secondly we present an extended BWR SBO analysis using RAVEN and RELAP-5 which address the comments and suggestions received about he original analysis presented in INL/EXT-???. This time we focus more on the stochastic analysis such probability of core damage and on the determination of the most risk-relevant factors. We also show some preliminary results regarding the comparison between RELAP5-3D and the new code RELAP-7 for a simplified Pressurized Water Reactors system. Lastly we present some conceptual ideas regarding the possibility to extended the RISMC capabilities from an off-line tool (i.e., as PRA analysis tool) to an online-tool. In this new configuration, RISMC capabilities can be used to assist and inform reactor operator during real accident scenarios.

  5. Treatment of Passive Component Reliability in Risk-Informed Safety Margin Characterization FY 2010 Report

    SciTech Connect (OSTI)

    Robert W Youngblood

    2010-09-01T23:59:59.000Z

    The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, is founded on probabilistic characterizations of SSC performance.

  6. Integrating Safety Assessment Methods using the Risk Informed Safety Margins Characterization (RISMC) Approach

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-03-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of nuclear power plants (NPPs). As the current light water reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of systems, structures, and components (SSC) degradations or failures that initiate safety significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated primarily based on engineering judgment backed by a set of conservative engineering calculations. The ability to better characterize and quantify safety margin is important to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development (R&D) in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the RISMC Pathway provides methods and tools that enable mitigation options known as margins management strategies. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. As the lead Department of Energy (DOE) Laboratory for this Pathway, the Idaho National Laboratory (INL) is tasked with developing and deploying methods and tools that support the quantification and management of safety margin and uncertainty.

  7. Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

    SciTech Connect (OSTI)

    Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

    2012-08-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

  8. Risk-Informed Safety Margin Characterization (RISMC): Integrated Treatment of Aleatory and Epistemic Uncertainty in Safety Analysis

    SciTech Connect (OSTI)

    R. W. Youngblood

    2010-10-01T23:59:59.000Z

    The concept of “margin” has a long history in nuclear licensing and in the codification of good engineering practices. However, some traditional applications of “margin” have been carried out for surrogate scenarios (such as design basis scenarios), without regard to the actual frequencies of those scenarios, and have been carried out with in a systematically conservative fashion. This means that the effectiveness of the application of the margin concept is determined in part by the original choice of surrogates, and is limited in any case by the degree of conservatism imposed on the evaluation. In the RISMC project, which is part of the Department of Energy’s “Light Water Reactor Sustainability Program” (LWRSP), we are developing a risk-informed characterization of safety margin. Beginning with the traditional discussion of “margin” in terms of a “load” (a physical challenge to system or component function) and a “capacity” (the capability of that system or component to accommodate the challenge), we are developing the capability to characterize probabilistic load and capacity spectra, reflecting both aleatory and epistemic uncertainty in system response. For example, the probabilistic load spectrum will reflect the frequency of challenges of a particular severity. Such a characterization is required if decision-making is to be informed optimally. However, in order to enable the quantification of probabilistic load spectra, existing analysis capability needs to be extended. Accordingly, the INL is working on a next-generation safety analysis capability whose design will allow for much more efficient parameter uncertainty analysis, and will enable a much better integration of reliability-related and phenomenology-related aspects of margin.

  9. Risk-Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment to Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. P. Blanchard; R. W. Youngblood

    2014-06-01T23:59:59.000Z

    The Risk-Informed Safety Margin Characterization (RISMC) pathway of the DOE’s Light Water Reactor Sustainability (LWRS) program focuses on advancing the state of the art in safety analysis and risk assessment to support decision-making on nuclear power plant operation well beyond the originally designed lifetime of the plants (i.e., beyond 60 years). Among the issues being addressed in RISMC is the significance of SSC aging and how confident we are about our understanding of its impact on the margin between the loads SSCs are expected to see during normal operation and accident conditions, and the SSC capacities (their ability to resist those loads) as the SSCs age. In this paper, a summary is provided of a case study that examines SSC aging from an environmental qualification (EQ) perspective. The case study illustrates how the state of knowledge regarding SSC margin can be characterized given the overall integrated plant design, and was developed to demonstrate a method for deciding on which cables to focus, which cables are not so important from an environmental qualification margin standpoint, and what plant design features or operating characteristics determine the role that environmental qualification plays in establishing a safety case on which decisions regarding margin can be made. The selection of cables for which demonstration of margin with respect to aging and environmental challenges uses a technique known as Prevention Analysis. Prevention Analysis is a Boolean method for optimal selection of SSCs (that is, those combinations of SSCs both necessary and sufficient to meet a predetermined selection criterion) in a manner that allows demonstration that plant-level safety can be demonstrated by the collection of selected SSCs alone. Choosing the set of SSCs that is necessary and sufficient to satisfy the safety objectives, and demonstrating that the safety objectives can be met effectively, determines where resources are best allocated to assure SSC performance margin. The paper describes the resulting component types that were selected by Prevention Analysis and identifies the accident sequence characteristics that cause these component types to be important from an EQ and aging perspective (and, hence, worthwhile evaluating the extent of safety margin). In addition, component types not selected as needing significant margin from an EQ and aging perspective are discussed and an engineering rationale is developed justifying the lack of need to apply resources to demonstrating margin for these component types. This rationale is in terms of design features of the plant and operating characteristics that make these component types less important from an EQ and aging perspective. While the case study focuses on EQ and aging of equipment and cables located inside the containment of this PWR, the prevention analysis method is demonstrated to be an effective technique for identification of minimal collections of components that would be effective in managing safety for a variety of issues associated with aging and long-term operation of the fleet of plants.

  10. Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    R. Youngblood; D. Blanchard

    2011-09-01T23:59:59.000Z

    In general, the margins-based safety case helps the decision-maker manage plant margins most effectively. It tells the plant decision-maker such things as what margin is present (at the plant level, at the functional level, at the barrier level, at the component level), and where margin is thin or perhaps just degrading. If the plant is safe, it tells the decision-maker why the plant is safe and where margin needs to be maintained, and perhaps where the plant can afford to relax.

  11. Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. Blanchard; R. Youngblood

    2012-04-01T23:59:59.000Z

    In general, the margins-based safety case helps the decision-maker manage plant margins most effectively. It tells the plant decision-maker such things as what margin is present (at the plant level, at the functional level, at the barrier level, at the component level), and where margin is thin or perhaps just degrading. If the plant is safe, it tells the decision-maker why the plant is safe and where margin needs to be maintained, and perhaps where the plant can afford to relax.

  12. Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan

    SciTech Connect (OSTI)

    Curtis Smith; Cristian Rabiti; Richard Martineau

    2012-11-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”

  13. Robustness of RISMC Insights under Alternative Aleatory/Epistemic Uncertainty Classifications: Draft Report under the Risk-Informed Safety Margin Characterization (RISMC) Pathway of the DOE Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Eslinger, Paul W.; Johnson, Kenneth I.

    2012-09-20T23:59:59.000Z

    The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, would be founded on probabilistic characterizations of uncertainty in SSC performance. In the context of probabilistic risk assessment (PRA) technology, there has arisen a general consensus about the distinctive roles of two types of uncertainty: aleatory and epistemic, where the former represents irreducible, random variability inherent in a system, whereas the latter represents a state of knowledge uncertainty on the part of the analyst about the system which is, in principle, reducible through further research. While there is often some ambiguity about how any one contributing uncertainty in an analysis should be classified, there has nevertheless emerged a broad consensus on the meanings of these uncertainty types in the PRA setting. However, while RISMC methodology shares some features with conventional PRA, it will nevertheless be a distinctive methodology set. Therefore, the paradigms for classification of uncertainty in the PRA setting may not fully port to the RISMC environment. Yet the notion of risk-informed margin is based on the characterization of uncertainty, and it is therefore critical to establish a common understanding of uncertainty in the RISMC setting.

  14. Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy at Waste-to-Energy usingofRetrofittingFundA l i c e L i p p e r t S e n i

  15. Risk Informed Safety Margin Characterization Case Study: Selection of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy at Waste-to-Energy usingofRetrofittingFundA l i c e L i p p e r t S e n

  16. On the quantification of safety margins

    E-Print Network [OSTI]

    Pagani, Lorenzo P

    2004-01-01T23:59:59.000Z

    The nuclear industry has relied on the concept of Defense in Depth (DID) and traditional safety margins to deal with the uncertainties associated with the design and operation of nuclear facilities. These concepts were ...

  17. RISK-INFORMED BALANCING OF SAFETY, NONPROLIFERATION, AND ECONOMICS FOR THE SFR

    SciTech Connect (OSTI)

    Apostolakis, George; Driscoll, Michael; Golay, Michael; Kadak, Andrew; Todreas, Neil; Aldmir, Tunc; Denning, Richard; Lineberry, Michael

    2011-10-20T23:59:59.000Z

    A substantial barrier to the implementation of Sodium-cooled Fast Reactor (SFR) technology in the short term is the perception that they would not be economically competitive with advanced light water reactors. With increased acceptance of risk-informed regulation, the opportunity exists to reduce the costs of a nuclear power plant at the design stage without applying excessive conservatism that is not needed in treating low risk events. In the report, NUREG-1860, the U.S. Nuclear Regulatory Commission describes developmental activities associated with a risk-informed, scenario-based technology neutral framework (TNF) for regulation. It provides quantitative yardsticks against which the adequacy of safety risks can be judged. We extend these concepts to treatment of proliferation risks. The objective of our project is to develop a risk-informed design process for minimizing the cost of electricity generation within constraints of adequate safety and proliferation risks. This report describes the design and use of this design optimization process within the context of reducing the capital cost and levelized cost of electricity production for a small (possibly modular) SFR. Our project provides not only an evaluation of the feasibility of a risk-informed design process but also a practical test of the applicability of the TNF to an actual advanced, non-LWR design. The report provides results of five safety related and one proliferation related case studies of innovative design alternatives. Applied to previously proposed SFR nuclear energy system concepts We find that the TNF provides a feasible initial basis for licensing new reactors. However, it is incomplete. We recommend improvements in terms of requiring acceptance standards for total safety risks, and we propose a framework for regulation of proliferation risks. We also demonstrate methods for evaluation of proliferation risks. We also suggest revisions to scenario-specific safety risk acceptance standards, particularly concerning seismic and aircraft impactrelated risks. Most importantly, within the context of the TNF historical SFR safety concerns about energetic core disruptive accidents are seen to be unimportant, but those of rare scenarios mentioned above are seen to be of dominant concern. In terms of proliferation risks the SFR energy system is seen not to be of considerably greater concern than with other nuclear power technologies, providing that highly effective safeguards are employed. We find the economic performance of proposed SFRs likely, due to the problems of using sodium as a coolant, to be inferior to those of LWRs unless they can be credited for services to improve nuclear waste disposal, nuclear fuel utilization and proliferation risk reductions. None of the design innovations investigated offers the promise to reverse this conclusion. The most promising innovation investigated is that of improving the plant's thermodynamic efficiency via use of the supercritical CO{sub 2} (rather than steam Rankine) power conversion system. We were unable to reach conclusions about the economic and proliferation risk implications of competing nuclear fuel processing methods, as available designs are too little developed to justify any such results. Overall, we find the SFR to be a promising alternative to LWRs should the conditions governing the valuation change substantially from current ones.

  18. Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010

    Broader source: Energy.gov [DOE]

    On August 12, 2009, the Defense Nuclear Facilities Safety Board(DNFSB) issued Recommendation 2009?1, Risk Assessment Methodologies at Defense Nuclear Facilities. Thisrecommendation focused on the...

  19. Building a "Margin of Safety" Into Renewable Energy

    E-Print Network [OSTI]

    Building a "Margin of Safety" Into Renewable Energy Procurements: A Review of Experience purchasers and electricity regulators must confront the reality that signed renewable energy contracts will not always yield operational projects on the timeline given in the contracts themselves. Renewable energy

  20. Subsystem fragility: Seismic Safety Margins Research Program (Phase I)

    SciTech Connect (OSTI)

    Kennedy, R. P.; Campbell, R. D.; Hardy, G.; Banon, H.

    1981-10-01T23:59:59.000Z

    Seismic fragility levels of safety related equipment are developed for use in a seismic oriented Probabilistic Risk Assessment (PRA) being conducted as part of the Seismic Safety Margins Research Program (SSMRP). The Zion Nuclear Power Plant is being utilized as a reference plant and fragility descriptions are developed for specific and generic safety related equipment groups in Zion. Both equipment fragilities and equipment responses are defined in probabilistic terms to be used as input to the SSMRP event tree/fault tree models of the Zion systems. 65 refs., 14 figs., 11 tabs.

  1. Seismic Safety Margins Research Program: a concluding look

    SciTech Connect (OSTI)

    Cummings, G.E.

    1984-01-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) was started in 1978 with the goal of developing tools and data bases to compute the probability of earthquake - caused radioactive release from commercial nuclear power plants. These tools and data bases were to help NRC to assess seismic safety at nuclear plants. The methodology to be used was finalized in 1982 and applied to the Zion Nuclear Power Station. The SSMRP will be completed this year with the development of a more simplified method of analysis and a demonstration of its use on Zion. This simplified method is also being applied to a boiling-water-reactor, LaSalle.

  2. Seismic Safety Margins Research Program. Phase I, final report - overview

    SciTech Connect (OSTI)

    Smith, P. D.; Dong, R. G.; Bernreuter, D. L.; Bohn, M. P.; Chuang, T. Y.; Cummings, G. E.; Johnson, J. J.; Mensing, R. W.; Wells, J. E.

    1981-03-06T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a multiyear, multiphase program whose overall objective is to develop improved methods for seismic safety assessments of nuclear power plants, using a probabilistic computational procedure. The program is being carried out at the Lawrence Livermore National Laboratory and is sponsored by the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. Phase I of the SSMRP was successfully completed in January 1981: A probabilistic computational procedure for the seismic risk assessment of nuclear power plants has been developed and demonstrated. The methodology is implemented by three computer programs: HAZARD, which assesses the seismic hazard at a given site, SMACS, which computes in-structure and subsystem seismic responses, and SEISIM, which calculates system failure probabilities and radioactive release probabilities, given (1) the response results of SMACS, (2) a set of event trees, (3) a family of fault trees, (4) a set of structural and component fragility descriptions, and (5) a curve describing the local seismic hazard. The practicality of this methodology was demonstrated by computing preliminary release probabilities for Unit 1 of the Zion Nuclear Power Plant north of Chicago, Illinois. Studies have begun aimed at quantifying the sources of uncertainty in these computations. Numerous side studies were undertaken to examine modeling alternatives, sources of error, and available analysis techniques. Extensive sets of data were amassed and evaluated as part of projects to establish seismic input parameters and to produce the fragility curves. 66 refs., 29 figs., 10 tabs.

  3. Reliability Engineering and System Safety 92 (2007) 609618 The nuclear industry's transition to risk-informed regulation and

    E-Print Network [OSTI]

    2007-01-01T23:59:59.000Z

    improvement in safety based on Institute of Nuclear Power Operations (INPO) performance indicatorsReliability Engineering and System Safety 92 (2007) 609­618 The nuclear industry's transition a Nuclear Science and Engineering Department, Massachusetts Institute of Technology, Cambridge, MA 02139

  4. Margin of Safety Definition and Examples Used in Safety Basis Documents and the USQ Process

    SciTech Connect (OSTI)

    Beaulieu, R. A.

    2013-10-03T23:59:59.000Z

    The Nuclear Safety Management final rule, 10 CFR 830, provides an undefined term, margin of safety (MOS). Safe harbors listed in 10 CFR 830, Table 2, such as DOE?STD?3009 use but do not define the term. This lack of definition has created the need for the definition. This paper provides a definition of MOS and documents examples of MOS as applied in a U.S. Department of Energy (DOE) approved safety basis for an existing nuclear facility. If we understand what MOS looks like regarding Technical Safety Requirements (TSR) parameters, then it helps us compare against other parameters that do not involve a MOS. This paper also documents parameters that are not MOS. These criteria could be used to determine if an MOS exists in safety basis documents. This paper helps DOE, including the National Nuclear Security Administration (NNSA) and its contractors responsible for the safety basis improve safety basis documents and the unreviewed safety question (USQ) process with respect to MOS.

  5. Seismic Safety Margins Research Program. Phase I, final report. Major structure response (Project IV). Volume 5

    SciTech Connect (OSTI)

    Benda, B. J.; Johnson, J. J.; Lo, T. Y.

    1981-05-01T23:59:59.000Z

    Task of the Major Structure Response Project within the Seismic Safety Margins Research Program (SSMRP) was to develop detailed finite element models of the Zion Nuclear Power Plant's containment building and auxiliary-fuel-turbine (AFT) complex. The resulting models served as input to the seismic methodology analysis chain.

  6. Seismic Safety Margins Research Program. Phase I. Interim definition of terms

    SciTech Connect (OSTI)

    Smith, P.D.; Dong, R.G.

    1980-12-19T23:59:59.000Z

    This report documents interim definitions of terms in the Seismic Safety Margins Research Program (SSMRP). Intent is to establish a common-based terminology integral to the probabilistic methods that predict more realistically the behavior of nuclear power plants during an earthquake. These definitions are a response to a request by the Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards at its meeting held November 15-16, 1979.

  7. Development of the seismic input for use in the seismic safety margins research program

    SciTech Connect (OSTI)

    Bernreuter, D.L.; Chung, D.H.

    1980-01-29T23:59:59.000Z

    This paper briefly outlines the overall systems approach being developed for the Seismic Safety Margins Research Program. The unique features of the approach being taken to reduce the uncertainty in the seismic input for this program are discussed. These unique features will include extensive use of expert opinion, earthquake rupture simulation studies and the way in which the seismic hazard is incorporated into the overall systems analysis. Some very preliminary results are also given for the Zion site which is the power plant chosen for analysis in Phase I of the program.

  8. Seismic Safety Margins Research Program (Phase I). Project IV. Structural building response; Structural Building Response Review

    SciTech Connect (OSTI)

    Healey, J.J.; Wu, S.T.; Murga, M.

    1980-02-01T23:59:59.000Z

    As part of the Phase I effort of the Seismic Safety Margins Research Program (SSMRP) being performed by the University of California Lawrence Livermore Laboratory for the US Nuclear Regulatory Commission, the basic objective of Subtask IV.1 (Structural Building Response Review) is to review and summarize current methods and data pertaining to seismic response calculations particularly as they relate to the objectives of the SSMRP. This material forms one component in the development of the overall computational methodology involving state of the art computations including explicit consideration of uncertainty and aimed at ultimately deriving estimates of the probability of radioactive releases due to seismic effects on nuclear power plant facilities.

  9. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    SciTech Connect (OSTI)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.

  10. Seismic safety margins research program. Project I SONGS 1 AFWS Project

    SciTech Connect (OSTI)

    Chuang, T.Y.; Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Cummings, G.E.; Wells, J.E.

    1981-02-24T23:59:59.000Z

    The seismic qualification requirements of auxiliary feedwater systems (AFWS) of Pressurized Water Reactors (PWR) were developed over a number of years. These are formalized in the publication General Design Criteria (Appendix A to 10CFR50). The full recognition of the system as an engineered safety feature did not occur until publication of the Standard Review Plan (1975). Efforts to determine how to backfit seismic requirements to earlier plants has been undertaken primarily in the Systematic Evaluation Program (SEP) for a limited number of operating reactors. Nuclear Reactor Research (RES) and NRR have requested LLNL to perform a probabilistic study on the AFWS of San Onofre Nuclear Generating Station (SONGS) Unit 1 utilizing the tools developed by the Seismic Safety Margins Research Program (SSMRP). The main objectives of this project are to: identify the weak links of AFWS; compare the failure probabilities of SONGS 1 and Zion 1 AFWS: and compare the seismic responses due to different input spectra and design values.

  11. Structure/piping sensitivity studies for the US NRC Seismic Safety Margins Research Program. [PWR; BWR

    SciTech Connect (OSTI)

    Shieh, L.C.; O'Connell, W.J.; Johnson, J.J.

    1983-01-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a NRC-funded, multi-year program conducted by Lawrence Livermore National Laboratory (LLNL). One of the goals of the program is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis design process and explicitly includes the uncertainties inherent in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. In Phase I, a probabilistic computational procedure was developed for the seismic safety assessment. In Phase II, sensitivity studies were performed, codes and models were improved, and analysis of the Zion plant was completed.

  12. MNSR transient analyses and thermal-hydraulic safety margins for HEU and LEU cores using PARET

    SciTech Connect (OSTI)

    Olson, Arne P. [RERTR Program, Argonne National Laboratory, Argonne, IL 60439 (United States); Jonah, S.A. [Centre for Energy Research and Training, Ahmadu Bello University, Zaria, P.M.B. 1014 (Nigeria)

    2008-07-15T23:59:59.000Z

    Thermal-hydraulic performance characteristics of Miniature Neutron Source Reactors under long-term steady-state and transient conditions are investigated. Safety margins and limiting conditions attained during these events are determined. Modeling extensions are presented that enable the PARET/ANL code to realistically track primary loop heatup, heat exchange to the pool, and heat loss from the pool to air over the pool. Comparisons are made of temperature predictions for HEU and LEU fueled cores under transient conditions. Results are obtained using three different natural convection heat transfer correlations: the original (PARET/ANL version 5), Churchill-Chu, and an experiment- based correlation from the China Institute of Atomic Energy (CIAE). The MNSR, either fueled by HEU or by LEU, satisfies the design limits for long-term transient operation. (author)

  13. Seismic Safety Margins Research Program: Phase II program plan (FY 83-FY 84)

    SciTech Connect (OSTI)

    Bohn, M.P.; Bernreuter, D.L.; Cover, L.E.; Johnson, J.J.; Shieh, L.C.; Shukla, S.N.; Wells, J.E.

    1982-08-02T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is an NRC-funded, multiyear program conducted by Lawrence Livermore National Laboratory (LLNL). Its goal is to develop a complete, fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-caused radioactive release from a commercial nuclear power plant. The analysis procedure is based upon a state-of-the-art evaluation of the current seismic analysis and design process and explicitly includes the uncertainties inherent in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. As currently planned, the SSMRP will be completed in September, 1984. This document presents the program plan for work to be done during the remainder of the program. In Phase I of the SSMRP, the necessary tools (both computer codes and data bases) for performing a detailed seismic risk analysis were identified and developed. Demonstration calculations were performed on the Zion Nuclear Power Plant. In the remainder of the program (Phase II) work will be concentrated on developing a simplified SSMRP methodology for routine probabilistic risk assessments, quantitative validation of the tools developed and application of the simplified methodology to a Boiling Water Reactor. (The Zion plant is a pressurized water reactor.) In addition, considerable effort will be devoted to making the codes and data bases easily accessible to the public.

  14. Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

    SciTech Connect (OSTI)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01T23:59:59.000Z

    The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk – as a function of different configurations – in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

  15. Air Risk Information Support Center

    SciTech Connect (OSTI)

    Shoaf, C.R.; Guth, D.J. [Environmental Protection Agency, Washington, DC (United States)

    1990-12-31T23:59:59.000Z

    The Air Risk Information Support Center (Air RISC) was initiated in early 1988 by the US Environmental Protection Agency`s (EPA) Office of Health and Environmental Assessment (OHEA) and the Office of Air Quality Planning and Standards (OAQPS) as a technology transfer effort that would focus on providing information to state and local environmental agencies and to EPA Regional Offices in the areas of health, risk, and exposure assessment for toxic air pollutants. Technical information is fostered and disseminated by Air RISCs three primary activities: (1) a {open_quotes}hotline{close_quotes}, (2) quick turn-around technical assistance projects, and (3) general technical guidance projects. 1 ref., 2 figs.

  16. Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis

    SciTech Connect (OSTI)

    Smith, Curtis L; Mandelli, Diego; Zhegang Ma

    2014-11-01T23:59:59.000Z

    As part of the Light Water Sustainability Program (LWRS) [1], the purpose of the Risk Informed Safety Margin Characterization (RISMC) [2] Pathway research and development (R&D) is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” (SBO) wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario. We also describe our approach we are using to represent advanced flooding analysis.

  17. Integrated risk information system (IRIS)

    SciTech Connect (OSTI)

    Tuxen, L. [Environmental Protection Agency, Washington, DC (United States)

    1990-12-31T23:59:59.000Z

    The Integrated Risk Information System (IRIS) is an electronic information system developed by the US Environmental Protection Agency (EPA) containing information related to health risk assessment. IRIS is the Agency`s primary vehicle for communication of chronic health hazard information that represents Agency consensus following comprehensive review by intra-Agency work groups. The original purpose for developing IRIS was to provide guidance to EPA personnel in making risk management decisions. This original purpose for developing IRIS was to guidance to EPA personnel in making risk management decisions. This role has expanded and evolved with wider access and use of the system. IRIS contains chemical-specific information in summary format for approximately 500 chemicals. IRIS is available to the general public on the National Library of Medicine`s Toxicology Data Network (TOXNET) and on diskettes through the National Technical Information Service (NTIS).

  18. SSI sensitivity studies and model improvements for the US NRC Seismic Safety Margins Research Program. Rev. 1

    SciTech Connect (OSTI)

    Johnson, J.J.; Maslenikov, O.R.; Benda, B.J.

    1984-10-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a US NRC-funded program conducted by Lawrence Livermore National Laboratory. Its goal is to develop a complete fully coupled analysis procedure for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. In Phase II of the SSMRP, the methodology was applied to the Zion nuclear power plant. Three topics in the SSI analysis of Zion were investigated and reported here - flexible foundation modeling, structure-to-structure interaction, and basemat uplift. The results of these investigations were incorporated in the SSMRP seismic risk analysis. 14 references, 51 figures, 13 tables.

  19. SAFETY MARGINS CONFIDENCE ESTIMATION FOR A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM

    E-Print Network [OSTI]

    Boyer, Edmond

    , Italy enrico.zio@polimi.it 2 INET, Institute of Nuclear and New Energy Technology Tsinghua University, Beijing,100084, China ABSTRACT For licensing purposes, safety cases of Nuclear Power Plants (NPPs) must are traditionally performed for the verification of the safety performance of a Nuclear Power Plant (NPP) under

  20. Contributions to risk-informed decision making

    E-Print Network [OSTI]

    Elliott, Michael A. (Michael Alfred)

    2010-01-01T23:59:59.000Z

    Risk-informed decision-making (RIDM) is a formal process that assists stakeholders make decisions in the face of uncertainty. At MIT, a tool known as the Analytic Deliberative Decision Making Process (ADP) has been under ...

  1. Analyses to support development of risk-informed separation distances for hydrogen codes and standards.

    SciTech Connect (OSTI)

    LaChance, Jeffrey L.; Houf, William G. (Sandia National Laboratories, Livermore, CA); Fluer, Inc., Paso Robels, CA; Fluer, Larry (Fluer, Inc., Paso Robels, CA); Middleton, Bobby

    2009-03-01T23:59:59.000Z

    The development of a set of safety codes and standards for hydrogen facilities is necessary to ensure they are designed and operated safely. To help ensure that a hydrogen facility meets an acceptable level of risk, code and standard development organizations are tilizing risk-informed concepts in developing hydrogen codes and standards.

  2. Station Blackout: A case study in the interaction of mechanistic and probabilistic safety analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli; Cristian Rabiti

    2013-11-01T23:59:59.000Z

    The ability to better characterize and quantify safety margins is important to improved decision making about nuclear power plant design, operation, and plant life extension. As research and development (R&D) in the light-water reactor (LWR) Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway R&D is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario.

  3. New Methods and Tools to Perform Safety Analysis within RISMC

    SciTech Connect (OSTI)

    Diego Mandelli; Curtis Smith; Cristian Rabiti; Andrea Alfonsi; Robert Kinoshita; Joshua Cogliati

    2013-11-01T23:59:59.000Z

    The Risk Informed Safety Margins Characterization (RISMC) Pathway uses a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. What differentiates the RISMC approach from traditional probabilistic risk assessment (PRA) is the concept of safety margin. In PRA, a safety metric such as core damage frequency (CDF) is generally estimated using static fault-tree and event-tree models. However, it is not possible to estimate how close we are to physical safety limits (say peak clad temperature) for most accident sequences described in the PRA. In the RISMC approach, what we want to understand is not just the frequency of an event like core damage, but how close we are (or not) to this event and how we might increase our safety margin through margin management strategies in a Dynamic PRA (DPRA) fashion. This paper gives an overview of methods that are currently under development at the Idaho National Laboratory (INL) with the scope of advance the current state of the art of dynamic PRA.

  4. 7th Workshop on Risk Informed Regulation and Safety Culture ...

    Energy Savers [EERE]

    the plant was "built with China's own strength." It has a total of 9 units (1 300MWe PWR; 2 1,000MWe; 4 650MWe; and 2 700MWe Candu-6) in operation. It is stunning to learn how...

  5. MNSR transient analyses and thermal hydraulic safety margins for HEU and LEU cores using the RELAP5-3D code

    SciTech Connect (OSTI)

    Dunn, F.E.; Thomas, J.; Liaw, J.; Matos, J.E. [RERTR Program, Argonne National Laboratory, Argonne, IL 60439 (United States)

    2008-07-15T23:59:59.000Z

    For safety analyses to support conversion of MNSR reactors from HEU fuel to LEU fuel, a RELAP5-3D model was set up to simulate the entire MNSR system. This model includes the core, the beryllium reflectors, the water in the tank and the water in the surrounding pool. The MCNP code was used to obtain the power distributions in the core and to obtain reactivity feedback coefficients for the transient analyses. The RELAP5-3D model was validated by comparing measured and calculated data for the NIRR-1 reactor in Nigeria. Comparisons include normal operation at constant power and a 3.77 mk rod withdrawal transient. Excellent agreement was obtained for core coolant inlet and outlet temperatures for operation at constant power, and for power level, coolant inlet temperature, and coolant outlet temperature for the rod withdrawal transient. In addition to the negative reactivity feedbacks from increasing core moderator and fuel temperatures, it was necessary to calculate and include positive reactivity feedback from temperature changes in the radial beryllium reflector and changes in the temperature and density of the water in the tank above the core and at the side of the core. The validated RELAP5-3D model was then used to analyze 3.77 mk rod withdrawal transients for LEU cores with two UO{sub 2} fuel pin designs. The impact of cracking of oxide LEU fuel is discussed. In addition, steady-state power operation at elevated power levels was evaluated to determine steady-state safety margins for onset of nucleate boiling and for onset of significant voiding. (author)

  6. Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

    SciTech Connect (OSTI)

    NONE

    2000-08-01T23:59:59.000Z

    OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

  7. Risk-informed design changes for a passive cooling system

    E-Print Network [OSTI]

    Patalano, Giovanbattista

    2007-01-01T23:59:59.000Z

    The failure probability of a passive decay heat removal system after a LOCA is evaluated as part of a risk-informed design process for a helium-cooled fast reactor. The system was modeled using RELAP5-3D. The epistemic ...

  8. Needs for Risk Informing Environmental Cleanup Decision Making - 13613

    SciTech Connect (OSTI)

    Zhu, Ming; Moorer, Richard [U.S. Department of Energy, Washington, DC 20585 (United States)] [U.S. Department of Energy, Washington, DC 20585 (United States)

    2013-07-01T23:59:59.000Z

    This paper discusses the needs for risk informing decision making by the U.S. Department of Energy (DOE) Office of Environmental Management (EM). The mission of the DOE EM is to complete the safe cleanup of the environmental legacy brought about from the nation's five decades of nuclear weapons development and production and nuclear energy research. This work represents some of the most technically challenging and complex cleanup efforts in the world and is projected to require the investment of billions of dollars and several decades to complete. Quantitative assessments of health and environmental risks play an important role in work prioritization and cleanup decisions of these challenging environmental cleanup and closure projects. The risk assessments often involve evaluation of performance of integrated engineered barriers and natural systems over a period of hundreds to thousands of years, when subject to complex geo-environmental transformation processes resulting from remediation and disposal actions. The requirement of resource investments for the cleanup efforts and the associated technical challenges have subjected the EM program to continuous scrutiny by oversight entities. Recent DOE reviews recommended application of a risk-informed approach throughout the EM complex for improved targeting of resources. The idea behind this recommendation is that by using risk-informed approaches to prioritize work scope, the available resources can be best utilized to reduce environmental and health risks across the EM complex, while maintaining the momentum of the overall EM cleanup program at a sustainable level. In response to these recommendations, EM is re-examining its work portfolio and key decision making with risk insights for the major sites. This paper summarizes the review findings and recommendations from the DOE internal reviews, discusses the needs for risk informing the EM portfolio and makes an attempt to identify topics for R and D in integrated risk assessment that could assist in the EM prioritization efforts. (authors)

  9. Risk-Informed Assessment Methodology Development and Application

    SciTech Connect (OSTI)

    Sung Goo Chi; Seok Jeong Park; Chul Jin Choi [Korea Power Engineering Company Inc, 360 9 Mabuk Dong, Giheung-gu Yongin-si, Gyeonggi-do 449-713 (Korea, Republic of); Ritterbusch, S.E.; Jacob, M.C. [Westinghouse Electric Company LLC (United States)

    2002-07-01T23:59:59.000Z

    Westinghouse Electric Company (WEC) has been working with Korea Power Engineering Company (KOPEC) on a US Department of Energy (DOE) sponsored Nuclear Energy Research Initiative (NERI) project through a collaborative agreement established for the domestic NERI program. The project deals with Risk-Informed Assessment (RIA) of regulatory and design requirements of future nuclear power plants. An objective of the RIA project is to develop a risk-informed design process, which focuses on identifying and incorporating advanced features into future nuclear power plants (NPPs) that would meet risk goals in a cost-effective manner. The RIA design methodology is proposed to accomplish this objective. This paper discusses the development of this methodology and demonstrates its application in the design of plant systems for future NPPs. Advanced conceptual plant systems consisting of an advanced Emergency Core Cooling System (ECCS) and Emergency Feedwater System (EFWS) for a NPP were developed and the risk-informed design process was exercised to demonstrate the viability and feasibility of the RIA design methodology. Best estimate Loss-of-Coolant Accident (LOCA) analyses were performed to validate the PSA success criteria for the NPP. The results of the analyses show that the PSA success criteria can be met using the advanced conceptual systems and that the RIA design methodology is a viable and appropriate means of designing key features of risk-significant NPP systems. (authors)

  10. Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

    SciTech Connect (OSTI)

    Ritterbusch, S.E.

    2000-08-01T23:59:59.000Z

    The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

  11. Risk-informed incident management for nuclear power plants

    E-Print Network [OSTI]

    Smith, Curtis Lee, 1966-

    2002-01-01T23:59:59.000Z

    Decision making as a part of nuclear power plant operations is a critical, but common, task. Plant management is forced to make decisions that may have safety and economic consequences. Formal decision theory offers the ...

  12. RISMC ADVANCED SAFETY ANALYSIS WORKING PLAN – FY 2015 – FY 2019

    SciTech Connect (OSTI)

    Szilard, Ronaldo H; Smith, Curtis L

    2014-09-01T23:59:59.000Z

    SUMMARY In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: 1. A value proposition (“why is this important?”) that will make the case for stakeholder’s use of the ASAP research and development (R&D) products. 2. An identification of likely end users and pathway to adoption of enhanced tools by the end-users. 3. A proposed set of practical and achievable “use case” demonstrations. 4. A proposed plan to address ASAP verification and validation (V&V) needs. 5. A proposed schedule for the multi-year ASAP.

  13. Risk-informed applications and online maintenance in France and the United States

    E-Print Network [OSTI]

    Verdier, Edouard (Edouard Pierre Emmanuel)

    2012-01-01T23:59:59.000Z

    During the past twenty-five years, the US Nuclear Regulatory Commission has been progressing toward a more risk-informed, performance-based regulation. This regulatory framework has effectively supported the development ...

  14. 7th Workshop on Risk Informed Regulation and Safety Culture | Department of

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov. Are you sure you wantJoin us for|IdahotheWhatProposed - FINAL 30atProposed

  15. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants - Final Technical Report

    SciTech Connect (OSTI)

    Ritterbusch, Stanley; Golay, Michael; Duran, Felicia; Galyean, William; Gupta, Abhinav; Dimitrijevic, Vesna; Malsch, Marty

    2003-01-29T23:59:59.000Z

    OAK B188 Summary of methods proposed for risk informing the design and regulation of future nuclear power plants. All elements of the historical design and regulation process are preserved, but the methods proposed for new plants use probabilistic risk assessment methods as the primary decision making tool.

  16. Safety Issues for High Temperature Gas Reactors

    E-Print Network [OSTI]

    Risk Informed Safety Profile #12;LEVELS OF DEFENCE IN DEPTH (From INSAG-10) Control, limiting (reactivity insertion) ­ Loss of Load ­ Rod Ejection (more significant in block reactors) ­ Failure of reactor effects and chemical attack on graphite · Blow down loads and timing of accident event sequences

  17. 167 Prospectus California Margin

    E-Print Network [OSTI]

    . Each of the three transects across the California Current will compare deep-water sites near the core), for those sites that require it, can be obtained from the following World Wide Web site: http margin, Deep Sea Drilling Project (DSDP) Leg 63, occurred immediately before the first deployment

  18. contingency Nominal loading margin

    E-Print Network [OSTI]

    Member Member Fellow Electrical and Computer Engineering Department University of Wisconsin, Madison WI 53706 USA Abstract: The change in the loading margin to voltage collapse when line outages occur the line outages of the IEEE 118 bus system. The results show the effective ranking of contingencies

  19. Current Regulations and Guidance - New Approaches for Risk-Informed Low-Level Radioactive Waste Management

    SciTech Connect (OSTI)

    Ryan, M.T. Ph.D.; CHP [Advisory Committee on Nuclear Waste and Materials, U.S. Nuclear Regulatory Commission, Washington, D.C. (United States)

    2008-07-01T23:59:59.000Z

    This paper presents the historical foundations and future challenges for commercial low-level radioactive waste (LLRW) management in the United States. LLRW has been managed at government facilities since the beginning of the nuclear age and in the commercial sector since the early 1960's. Over the intervening years many technical, management and regulatory changes have occurred. Significant progress has been made in waste form, waste packaging and in recognizing radionuclides important to performance of disposal technologies and disposal facilities. This presentation will examine approaches using existing regulations and risk-informed approaches to improve guidance, licensing and management of LLRW. (authors)

  20. Margins up; consumption down

    SciTech Connect (OSTI)

    Mantho, M.

    1983-09-01T23:59:59.000Z

    The results of a survey of dealers in the domestic fuel oil industry are reported. Wholesale prices, reacting to oversupply, decreased as did retail prices; retail prices decreased at a slower rate so profit margins were larger. This trend produced competitive markets as price-cutting became the method for increasing a dealer's share of the profits. Losses to other fuels decreased, when the figures were compared to earlier y; and cash flow was very good for most dealers. In summary, profits per gallon of oil delivered increased, while the consumption of gasoline per customer decreased. 22 tables.

  1. Quantification of design margins/safety factors based on the prediction uncertainty in tritium production rate from fusion integral experiments of the USDOE/JAERI collaborative program on fusion blanket neutronics

    SciTech Connect (OSTI)

    Youssef, M.Z.; Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States)] [and others

    1994-12-31T23:59:59.000Z

    Various engineering-oriented fusion integral experiments were performed within the USDOE/JAERI Collaborative Program on Fusion Blanket Neutronics during the last decade. The objectives of this ten-year program were: (a) to establish new experimental techniques for design-related neutronics experiments, (b) to provide experimental data on local and integrated parameters such as tritium production rate, nuclear heating, and activation for the purpose of assessing the accuracies of present nuclear data and calculational methods, and (c) to provide designers with design margin for important responses. Tritium breeding rate (TPR) has the prime focus among other reactions. The program consisted of three phases in which local and integrated measurements inside a Li{sub 2}O test assembly that has various engineering features of a prototypical blanket (e.g. SS FW, H{sub 2}O coolant channels, beryllium multiplier). The analysis of the experiments were performed independently by the US and JAERI using their own codes/databases. A wide range of the calculated-to-experimental (C/E) values were observed in all these experiments for local TPR from Li-6 (T{sub 6}), from Li-7 (T{sub 7}), and from Li-natural (T{sub n}). In this paper, the experimental and calculational data sets of local TPR in each experiment were interpreted to give estimate to the prediction uncertainty, u{sub i}, of the line-integrated TPR and its standard deviation, {sigma}{sub i}.

  2. Risk-informed public safety policy for seismic events in the vicinity of a nuclear power plant

    E-Print Network [OSTI]

    Afolayan Jejeloye, Olubukola

    2002-01-01T23:59:59.000Z

    Nuclear Power Plants (NPPs) are potentially vulnerable to accidents, which can either be internally or externally initiated. External events include natural events like tornadoes, hurricanes, and earthquakes. The purpose ...

  3. Coastal ocean margins program

    SciTech Connect (OSTI)

    Not Available

    1988-12-01T23:59:59.000Z

    The marine research program supported by the Office of Energy Research, Ecological Research Division, is focused to provide scientific information on major environmental issues facing development and expansion of most energy technologies and energy policy. These issues include waste disposal, siting/operations, and possible long term effects on global systems. The research is concentrated along the United States coastal margins where marine waters provide abundant food and resources while assimilating discharges from atmospheric, terrestrial, and aquatic sources. The program focuses on the formation and transport of particles within the waters of the continental shelf and the fate of these particles, whether on the shelf, on the slope, or in the open ocean. The program is conducted with multidisciplinary teams of researchers who investigate water mass movements, biological productivity, and naturally forming particles, as well as contaminant transport, to develop a clear understanding of the exchanges of contaminants and other materials that take place between continental shelf and open ocean waters. Seventy-five percent of the projects are funded to university grantees and twenty-five percent to National Laboratories.

  4. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-10-24T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  5. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-11-16T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  6. Materials Reliability Program: Risk-Informed Revision of ASME Section XI Appendix G - Proof of Concept (MRP-143)

    SciTech Connect (OSTI)

    B. Bishop; et al

    2005-03-30T23:59:59.000Z

    This study indicates that risk-informed methods can be used to significantly relax the current ASME and NRC Appendix G requirements while still maintaining satisfactory levels of reactor vessel structural integrity. This relaxation in Appendix G requirements directly translates into significant improvements in operational flexibility.

  7. The safety valve and climate policy

    E-Print Network [OSTI]

    Jacoby, Henry D.; Ellerman, A. Denny.

    In discussions of a cap-and-trade system for implementation of Kyoto Protocol-type quantity targets, a "safety valve" was proposed where, by government sales of emissions permits at a fixed price, the marginal cost of the ...

  8. Feasibility of risk-informed regulation for Generation-IV reactors

    E-Print Network [OSTI]

    Matos, Craig H

    2005-01-01T23:59:59.000Z

    With the advent of new and innovative Generation-IV reactor designs, new regulations must be developed to assure the safety of these plants. In the past a purely deterministic way of developing design basis accidents was ...

  9. Risk-informing decisions about high-level nuclear waste repositories

    E-Print Network [OSTI]

    Ghosh, Suchandra Tina, 1973-

    2004-01-01T23:59:59.000Z

    Performance assessments (PAs) are important sources of information for societal decisions in high-level radioactive waste (HLW) management, particularly in evaluating safety cases for proposed HLW repository development. ...

  10. Sandia National Laboratories: critical marginal ice zone

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    marginal ice zone NASA Award for Marginal Ice Zone Observations and Process Experiment (MIZOPEX) On February 24, 2015, in Analysis, Climate, Modeling & Analysis, Monitoring, News,...

  11. RESEARCH SAFETY RADIATION SAFETY

    E-Print Network [OSTI]

    and Communications Manager (951) 827-6303 janette.ducut@ucr.edu Beiwei Tu, MS, CIH, CSP Safety and Industrial Hygiene

  12. Subsystem response review. Seismic Safety Margins Research Program

    SciTech Connect (OSTI)

    Kennedy, R. P.; Campbell, R. D.; Wesley, D. A.; Kamil, H.; Gantayat, A.; Vasudevan, R.

    1981-02-01T23:59:59.000Z

    A study was conducted to document the state of the art in seismic qualification of nuclear power plant components and subsystems by analysis and testing and to identify the sources and magnitude of the uncertainties associated with analysis and testing methods. The uncertainties are defined in probabilistic terms for use in probabilistic seismic risk studies. Recommendations are made for the most appropriate subsystem response analysis methods to minimize response uncertainties. Additional studies, to further quantify testing uncertainties, are identified. Although the general effect of non-linearities on subsystem response is discussed, recommendations and conclusions are based principally on linear elastic analysis and testing models.

  13. Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper

    SciTech Connect (OSTI)

    Pete Jordan

    2010-09-01T23:59:59.000Z

    This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

  14. Risk-Informed Monitoring, Verification and Accounting (RI-MVA). An NRAP White Paper Documenting Methods and a Demonstration Model for Risk-Informed MVA System Design and Operations in Geologic Carbon Sequestration

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Sadovsky, Artyom; Sullivan, E. C.; Anderson, Richard M.

    2011-09-30T23:59:59.000Z

    This white paper accompanies a demonstration model that implements methods for the risk-informed design of monitoring, verification and accounting (RI-MVA) systems in geologic carbon sequestration projects. The intent is that this model will ultimately be integrated with, or interfaced with, the National Risk Assessment Partnership (NRAP) integrated assessment model (IAM). The RI-MVA methods described here apply optimization techniques in the analytical environment of NRAP risk profiles to allow systematic identification and comparison of the risk and cost attributes of MVA design options.

  15. Ideas underlying quantification of margins and uncertainties(QMU): a white paper.

    SciTech Connect (OSTI)

    Helton, Jon Craig; Trucano, Timothy Guy; Pilch, Martin M.

    2006-09-01T23:59:59.000Z

    This report describes key ideas underlying the application of Quantification of Margins and Uncertainties (QMU) to nuclear weapons stockpile lifecycle decisions at Sandia National Laboratories. While QMU is a broad process and methodology for generating critical technical information to be used in stockpile management, this paper emphasizes one component, which is information produced by computational modeling and simulation. In particular, we discuss the key principles of developing QMU information in the form of Best Estimate Plus Uncertainty, the need to separate aleatory and epistemic uncertainty in QMU, and the risk-informed decision making that is best suited for decisive application of QMU. The paper is written at a high level, but provides a systematic bibliography of useful papers for the interested reader to deepen their understanding of these ideas.

  16. Seismic margins and calibration of piping systems

    SciTech Connect (OSTI)

    Shieh, L.C.; Tsai, N.C.; Yang, M.S.; Wong, W.L.

    1985-01-01T23:59:59.000Z

    The Seismic Safety Margins Research Program (SSMRP) is a US Nuclear Regulatory Commission-funded, multiyear program conducted by Lawrence Livermore National Laboratory (LLNL). Its objective is to develop a complete, fully coupled analysis procedure for estimating the risk of earthquake-induced radioactive release from a commercial nuclear power plant and to determine major contributors to the state-of-the-art seismic and systems analysis process and explicitly includes the uncertainties in such a process. The results will be used to improve seismic licensing requirements for nuclear power plants. In Phase I of SSMRP, the overall seismic risk assessment methodology was developed and assembled. The application of this methodology to the seismic PRA (Probabilistic Risk Assessment) at the Zion Nuclear Power Plant has been documented. This report documents the method deriving response factors. The response factors, which relate design calculated responses to best estimate values, were used in the seismic response determination of piping systems for a simplified seismic probablistic risk assessment. 13 references, 31 figures, 25 tables.

  17. Dynamics of the continental margins

    SciTech Connect (OSTI)

    Not Available

    1990-11-01T23:59:59.000Z

    On 18--20 June 1990, over 70 oceanographers conducting research in the ocean margins of North America attended a workshop in Virginia Beach, Virginia. The purpose of the workshop was to provide the Department of Energy with recommendations for future research on the exchange of energy-related materials between the coastal and interior ocean and the relationship between the ocean margins and global change. The workshop was designed to optimize the interaction of scientists from specific research disciplines (biology, chemistry, physics and geology) as they developed hypotheses, research questions and topics and implementation plans. The participants were given few restraints on the research they proposed other than realistic time and monetary limits. The interdisciplinary structure of the meeting promoted lively discussion and creative research plans. The meeting was divided into four working groups based on lateral, vertical, air/sea and sediment/water processes. Working papers were prepared and distributed before the meeting. During the meeting the groups revised the papers and added recommendations that appear in this report, which was reviewed by an Executive Committee.

  18. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-11-20T23:59:59.000Z

    The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

  19. Sandia National Laboratories: Marginal Ice Zone Observations...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Marginal Ice Zone Observations and Processes Experiment mission Sierra Unmanned Aerial Vehicle to Begin Flights Over Arctic Sea Ice On July 25, 2013, in Climate, Customers &...

  20. Marginal vitiligo: an unusual depigmenting disorder

    E-Print Network [OSTI]

    Trikha, Ritika; McCowan, Nancye; Brodell, Robert

    2015-01-01T23:59:59.000Z

    including marginal vitiligo, DLE, and hypopigmented MF.Direct immunofluorescence DLE: Discoid lupus erythematosusdiagnosis of IVRB includes DLE. In fact, the patches of

  1. Assessment of seismic margin calculation methods

    SciTech Connect (OSTI)

    Kennedy, R.P.; Murray, R.C.; Ravindra, M.K.; Reed, J.W.; Stevenson, J.D.

    1989-03-01T23:59:59.000Z

    Seismic margin review of nuclear power plants requires that the High Confidence of Low Probability of Failure (HCLPF) capacity be calculated for certain components. The candidate methods for calculating the HCLPF capacity as recommended by the Expert Panel on Quantification of Seismic Margins are the Conservative Deterministic Failure Margin (CDFM) method and the Fragility Analysis (FA) method. The present study evaluated these two methods using some representative components in order to provide further guidance in conducting seismic margin reviews. It is concluded that either of the two methods could be used for calculating HCLPF capacities. 21 refs., 9 figs., 6 tabs.

  2. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants (Cooperative Agreement DE-FC03-99SF21902, Am. M004) Final Technical Report

    SciTech Connect (OSTI)

    Stanley E. Ritterbusch, et. al.

    2003-01-29T23:59:59.000Z

    OAK-B135 Research under this project addresses the barriers to long term use of nuclear-generated electricity in the United States. It was agreed that a very basic and significant change to the current method of design and regulation was needed. That is, it was believed that the cost reduction goal could not be met by fixing the current system (i.e., an evolutionary approach) and a new, more advanced approach for this project would be needed. It is believed that a completely new design and regulatory process would have to be developed--a ''clean sheet of paper'' approach. This new approach would start with risk-based methods, would establish probabilistic design criteria, and would implement defense-in-depth only when necessary (1) to meet public policy issues (e.g., use of a containment building no matter how low the probability of a large release is) and (2) to address uncertainties in probabilistic methods and equipment performance. This new approach is significantly different from the Nuclear Regulatory Commission's (NRC) current risk-informed program for operating plants. For our new approach, risk-based methods are the primary means for assuring plant safety, whereas in the NRC's current approach, defense-in-depth remains the primary means of assuring safety. The primary accomplishments in the first year--Phase 1 were (1) the establishment of a new, highly risk-informed design and regulatory framework, (2) the establishment of the preliminary version of the new, highly risk-informed design process, (3) core damage frequency predictions showing that, based on new, lower pipe rupture probabilities, the design of the emergency core cooling system equipment can be simplified without reducing plant safety, and (4) the initial development of methods for including uncertainties in a new integrated structures-systems design model. Under the new regulatory framework, options for the use of ''design basis accidents'' were evaluated. It is expected that design basis accidents would be an inherent part of the Probabilistic Safety Assessment for the plant and their evaluation would be probabilistic. Other first year accomplishments include (1) the conversion of an NRC database for cross-referencing NRC criteria and industry codes and standards to Microsoft 2000 software, (2) an assessment of the NRC's hearing process which concluded that the normal cross-examination during public hearings is not actually required by the U.S. Administrative Procedures Act, (3) the identification and listing of reliability data sources, and (4) interfacing with other industry groups (e.g., NEI and IAEA) and NRC at workshops for risk-informing regulations. The major accomplishments during the second year consisted of (1) issuance of the final report for Subtask 1.1, ''Identify Current Applicable Regulatory Requirements [and Industry Standards],'' (2) issuance of the final report for Subtask 1.2,'' Identify Structures, Systems, and Components and Their Associate d Costs for a Typical Plant,'' (3) extension of the new, highly risk-informed design and regulatory framework to non-light-water-reactor technology, (4) completion of more detailed thermal-hydraulic and probabilistic analyses of advanced conceptual reactor system/component designs, (6) initial evaluation and recommendations for improvement of the NRC design review process, and (7) initial development of the software format, procedures and statistical routines needed to store, analyze and retrieve the available reliability data. Final reports for Subtasks 1.1 (regulatory and design criteria) and 1.2 (costs for structures, systems, and components) were prepared and issued. A final report for Subtask 1.3 (Regulatory Framework) was drafted with the aim to issue it in Phase 3 (Year 3). One technical report was produced for Subtask 1.4 (methods development) and two technical reports were produced for Subtask 1.6 (sample problem analysis). An interim report on the NRC design review process (Subtask 1.7) was prepared and issued. Finally, a report on Subtask 2.2 (database weaknesses) addressed the i

  3. Risk-informed design guidance for a Generation-IV gas-cooled fast reactor emergency core cooling system

    E-Print Network [OSTI]

    Delaney, Michael J. (Michael James), 1979-

    2004-01-01T23:59:59.000Z

    Fundamental objectives of sustainability, economics, safety and reliability, and proliferation resistance, physical protection and stakeholder relations must be considered during the design of an advanced reactor. However, ...

  4. Overview of New Tools to Perform Safety Analysis: BWR Station Black Out Test Case

    SciTech Connect (OSTI)

    D. Mandelli; C. Smith; T. Riley; J. Nielsen; J. Schroeder; C. Rabiti; A. Alfonsi; Cogliati; R. Kinoshita; V. Pasucci; B. Wang; D. Maljovec

    2014-06-01T23:59:59.000Z

    Dynamic Probabilistic Risk Assessment (DPRA) methodologies couple system simulator codes (e.g., RELAP, MELCOR) with simulation controller codes (e.g., RAVEN, ADAPT). While system simulator codes accurately model system dynamics deterministically, simulation controller codes introduce both deterministic (e.g., system control logic, operating procedures) and stochastic (e.g., component failures, parameter uncertainties) elements into the simulation. Typically, a DPRA is performed by: 1) sampling values of a set of parameters from the uncertainty space of interest (using the simulation controller codes), and 2) simulating the system behavior for that specific set of parameter values (using the system simulator codes). For complex systems, one of the major challenges in using DPRA methodologies is to analyze the large amount of information (i.e., large number of scenarios ) generated, where clustering techniques are typically employed to allow users to better organize and interpret the data. In this paper, we focus on the analysis of a nuclear simulation dataset that is part of the Risk Informed Safety Margin Characterization (RISMC) Boiling Water Reactor (BWR) station blackout (SBO) case study. We apply a software tool that provides the domain experts with an interactive analysis and visualization environment for understanding the structures of such high-dimensional nuclear simulation datasets. Our tool encodes traditional and topology-based clustering techniques, where the latter partitions the data points into clusters based on their uniform gradient flow behavior. We demonstrate through our case study that both types of clustering techniques complement each other in bringing enhanced structural understanding of the data.

  5. Large margin classification in infinite neural networks

    E-Print Network [OSTI]

    Saul, Lawrence K.

    Large margin classification in infinite neural networks Youngmin Cho and Lawrence K. Saul, CA 92093-0404 Abstract We introduce a new family of positive-definite kernels for large margin classi- fication in support vector machines (SVMs). These kernels mimic the computation in large neural networks

  6. MARGIN AND SENSITIVITY METHODS SECURITY ANALYSIS

    E-Print Network [OSTI]

    MARGIN AND SENSITIVITY METHODS FOR SECURITY ANALYSIS OF ELECTRIC POWER SYSTEMS by Scott Greene the amount by which system loads or power transfers can change before a security violation, such as an overloaded transmission line, is encountered. This thesis shows how to efficiently compute security margins

  7. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-12-22T23:59:59.000Z

    The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

  8. Biological Safety

    Broader source: Energy.gov [DOE]

    The DOE's Biological Safety Program provides a forum for the exchange of best practices, lessons learned, and guidance in the area of biological safety. This content is supported by the Biosurety Executive Team. The Biosurety Executive Team is a DOE-chartered group. The DOE Office of Worker Safety and Health Policy provides administrative support for this group. The group identifies biological safety-related issues of concern to the DOE and pursues solutions to issues identified.

  9. Analysis of gain margins and phase margins of a nonlinear reactor control system

    SciTech Connect (OSTI)

    Chang, C.H.; Chang, M.K. (Chung Cheng Inst. of Technology, Tao-Yuan (Taiwan, Province of China))

    1994-08-01T23:59:59.000Z

    By using the gain-phase margin tester, the parameter-plane method for the nonlinear control system is extended to frequency-domain related to gain margin and phase margin. The stability and self-excited oscillation are investigated with respect to the adjustable parameters. The useful information concerning the effect of adjustable parameters can be obtained, after the describing function curves and the boundaries of constant gain margin and constant phase margin are plotted in the parameter plane. Some interesting consequences are offered by employing the practical control system of a material testing reactor.

  10. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-10-13T23:59:59.000Z

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

  11. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-12-22T23:59:59.000Z

    This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

  12. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-12-04T23:59:59.000Z

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

  13. Gain margin and phase margin analysis of a nuclear reactor control system with multiple transport lags

    SciTech Connect (OSTI)

    Chang, C.H. (Institute of Electronics, National Chiao-Tung Univ. (TW)); Han, K.W. (Chung-Shan Institute and National Chiao-Tung Univ., Hsinchu (TW))

    1989-08-01T23:59:59.000Z

    In this paper a method for finding the boundaries of constant gain margin and phase margin of control systems with transport lags and adjustable parameters is presented. The considered systems are first modified by adding a gain-phase margin tester, then the characteristic equations are formulated, and finally the stability equations are used to find the boundaries of constant gain margin and phase margin. The main advantage of the proposed method is to obtain complete information about the effects of adjustable parameters on gain margin and phase margin and their corresponding crossover frequencies. In order to show the usefulness of the proposed method a nuclear reactor control system with multiple transport lags is chosen as one of the examples.

  14. When the Details Matter – Sensitivities in PRA Calculations That Could Affect Risk-Informed Decision-Making

    SciTech Connect (OSTI)

    Dana L. Kelly; Nathan O. Siu

    2010-06-01T23:59:59.000Z

    As the U.S. Nuclear Regulatory Commission (NRC) continues its efforts to increase its use of risk information in decision making, the detailed, quantitative results of probabilistic risk assessment (PRA) calculations are coming under increased scrutiny. Where once analysts and users were not overly concerned with figure of merit variations that were less than an order of magnitude, now factors of two or even less can spark heated debate regarding modeling approaches and assumptions. The philosophical and policy-related aspects of this situation are well-recognized by the PRA community. On the other hand, the technical implications for PRA methods and modeling have not been as widely discussed. This paper illustrates the potential numerical effects of choices as to the details of models and methods for parameter estimation with three examples: 1) the selection of the time period data for parameter estimation, and issues related to component boundary and failure mode definitions; 2) the selection of alternative diffuse prior distributions, including the constrained noninformative prior distribution, in Bayesian parameter estimation; and 3) the impact of uncertainty in calculations for recovery of offsite power.

  15. Modular HTGR Safety Basis and Approach

    SciTech Connect (OSTI)

    Thomas Hicks

    2011-08-01T23:59:59.000Z

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) process, as recommended in the NGNP Licensing Strategy - A Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy [DOE/NRC 2008]. Nuclear Regulatory Commission (NRC) licensing of the NGNP plant utilizing this process will demonstrate the efficacy for licensing future HTGRs for commercial industrial applications. This information paper is one in a series of submittals that address key generic issues of the priority licensing topics as part of the process for establishing HTGR regulatory requirements. This information paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach with the NRC staff and public stakeholders. The NGNP project does not expect to receive comments on this information paper because other white papers are addressing key generic issues of the priority licensing topics in greater detail.

  16. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01T23:59:59.000Z

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  17. Integral fast reactor safety features

    SciTech Connect (OSTI)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01T23:59:59.000Z

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents.

  18. Wholesale marginal prices in competitive generation markets

    SciTech Connect (OSTI)

    Perez-Arriaga, I.J. [National Electric Regulatory Commission, Madrid (Spain)] [National Electric Regulatory Commission, Madrid (Spain); Meseguer, C. [Univ. Pontificia Comillas, Madrid (Spain). Inst. de Investigacion Tecnologica] [Univ. Pontificia Comillas, Madrid (Spain). Inst. de Investigacion Tecnologica

    1997-05-01T23:59:59.000Z

    Wholesale marginal electricity prices are being used in several actual competitive generation markets worldwide, both to remunerate generators and to charge consumption. These prices must account not only for energy, but also for guarantee of supply in the long and the short term. This paper: (a) provides a sound conceptual and quantitative foundation for wholesale pricing based on generation services, where any existing restrictions in operation or planning in real power markets are accounted for, (b) clearly establishes the relationship between short term marginal costs, long term marginal costs and optimal wholesale electricity prices, and (c) identifies the reasons for mismatches in cost recovery with marginal generation prices. The theoretical results are verified with a detailed realistic power system model.

  19. Marginal, Erodible Land Retirement Policy (Minnesota)

    Broader source: Energy.gov [DOE]

    It is state policy to encourage the retirement of marginal, highly erodible land, particularly land adjacent to public waters and drainage systems, from crop production and to reestablish a cover...

  20. Estimation of Highway Maintenance Marginal Cost under Multiple Maintenance Activities

    E-Print Network [OSTI]

    Anani, Shadi B.; Madanat, Samer M

    2010-01-01T23:59:59.000Z

    Marginal costs for road maintenance and operation - a cost2010-01) Estimation of Highway Maintenance Marginal Costunder Multiple Maintenance Activities Shadi B. Anani and

  1. ITP Steel: Steel Industry Marginal Opportunity Study September...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Steel Industry Marginal Opportunity Study September 2005 ITP Steel: Steel Industry Marginal Opportunity Study September 2005 steelmarginalopportunity.pdf More Documents &...

  2. Improvement of the thermal margins in the Swedish Ringhals-3 PWR by introducing new fuel assemblies with thorium

    SciTech Connect (OSTI)

    Lau, C. W.; Demaziere, C. [Dept. of Applied Physics, Div. of Nuclear Engineering, Chalmers Univ. of Technology, 412 96 Gothenburg (Sweden); Nylen, H.; Sandberg, U. [Ringhals AB, 432 85 Vaeroebacka (Sweden)

    2012-07-01T23:59:59.000Z

    Thorium is a fertile material and most of the past research has focused on breeding thorium to fissile material. In this paper, the focus is on using thorium to improve the thermal margins by homogeneously distributing thorium in the fuel pellets. A proposed uranium-thorium-based fuel assembly is simulated for the Swedish Ringhals-3 PWR core in a realistic demonstration. All the key safety parameters, such as isothermal temperature coefficient of reactivity, Doppler temperature of reactivity, boron worth, shutdown margins and fraction of delayed neutrons are studied in this paper, and are within safety limits for the new core design using the uranium-thorium-based fuel assemblies. The calculations were performed by the two-dimensional transport code CASMO-4E and the two group steady-state three dimensional nodal code SIMULATE-3 from Studsvik Scandpower. The results showed that the uranium-thorium-based fuel assembly improves the thermal margins, both in the pin peak power and the local power (Fq). The improved thermal margins would allow more flexible core designs with less neutron leakage or could be used in power uprates to offer efficient safety margins. (authors)

  3. Physics-Based Stress Corrosion Cracking Component Reliability Model cast in an R7-Compatible Cumulative Damage Framework

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Lowry, Peter P.; Layton, Robert F.; Toloczko, Mychailo B.; Johnson, Kenneth I.; Sanborn, Scott E.

    2011-07-01T23:59:59.000Z

    This is a working report drafted under the Risk-Informed Safety Margin Characterization pathway of the Light Water Reactor Sustainability Program, describing statistical models of passives component reliabilities.

  4. Electromagnetic exploration of the Exmouth and Vøring rifted margins

    E-Print Network [OSTI]

    Myer, David Gerard

    2012-01-01T23:59:59.000Z

    continental margin; seismic interpretation, stratigraphy,CSEM, and seismic interpretation; (c) investigate the effect

  5. LASER SAFETY POLICY MANUAL ENVIRONMENTAL HEALTH & SAFETY

    E-Print Network [OSTI]

    Houston, Paul L.

    LASER SAFETY POLICY MANUAL ISSUED BY ENVIRONMENTAL HEALTH & SAFETY OFFICE OF RADIOLOGICAL SAFETY and GEORGIA TECH LASER SAFETY COMMITTEE July 1, 2010 Revised July 31, 2012 #12;Laser Safety Program 1-1 #12;Laser Safety Policy Manual TABLE OF CONTENTS 1. POLICY AND SCOPE

  6. ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL

    E-Print Network [OSTI]

    Maroncelli, Mark

    ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL May 10, 2002 #12;i Acknowledgements Environmental Health and Safety gratefully acknowledges the assistance provided by the University Safety Council extremely helpful. #12;ii Environmental Health and Safety General Safety Manual Table of Contents Section

  7. Safety Bulletin

    Broader source: Energy.gov (indexed) [DOE]

    in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and the...

  8. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2002-05-20T23:59:59.000Z

    To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

  9. Focus on Venezuelan heavy crude: refining margins

    SciTech Connect (OSTI)

    Not Available

    1984-01-25T23:59:59.000Z

    Of six crudes refined in the US Gulf Coast, heavy Venezuelan crude Lagunillas (15/sup 0/ API) provides the best margin per barrel. Data for end of December 1983 and the first three weeks of January show that margins on all crudes are on the rise in this market, due to a turnaround in product prices. The lighter crudes are showing the greatest increase in Gross Product Worth. This is having a modest shrinking effect on the margin differential between light and heavy crudes in this market. The domestic crude West Texas Intermediate, at 40/sup 0/ API, provides the highest GPW in this crude slate sample, over US $31 per barrel, compared to GPW of under US $28 per barrel for Lagunillas. Still, as Lagunillas cost about US $8 less than does WTI, refiners with sufficient residue conversion capacity can be earning about US $3.50 more in margin per barrel than they can with WTI. Although few refiners would be using a 15/sup 0/ API crude exclusively for any length of time, heavier oil's inclusion in modern refiners' diets is enhancing their competitive position more than any other single factor. This issue of Energy Detente presents the fuel price/tax series and industrial fuel prices for January 1984 for countries of the Western Hemisphere.

  10. Toolbox Safety Talk Ladder Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Health & Safety for recordkeeping. Slips, trips, and falls constitute the majority of general industry and construction worker injuries. Falls cause 15% of all accidental deaths, and are second only to motor vehicle

  11. Seismic margins assessment of the plutonium processing facility Los Alamos National Laboratory

    SciTech Connect (OSTI)

    Goen, L.K. [Los Alamos National Lab., NM (United States); Salmon, M.W. [EQE International, Irwine, CA (United States)

    1995-12-01T23:59:59.000Z

    Results of the recently completed seismic evaluation at the Los Alamos National Laboratory site indicate a need to consider seismic loads greater than design basis for many structures systems and components (SSCs). DOE Order 5480.28 requires that existing SSCs be evaluated to determine their ability to withstand the effects of earthquakes when changes in the understanding of this hazard results in greater loads. In preparation for the implementation of DOE Order 5480.28 and to support the update of the facility Safety Analysis Report, a seismic margin assessment of SSCs necessary for a monitored passive safe shutdown of the Plutonium Processing Facility (PF-4) was performed. The seismic margin methodology is given in EPRI NP-6041-SL, ``A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)``. In this methodology, high confidence of low probability of failure (HCLPF) capacities for SSCs are estimated in a deterministic manner. For comparison to the performance goals given in DOE Order 5480.28, the results of the seismic margins assessment were used to estimate the annual probability of failure for the evaluated SSCs. In general, the results show that the capacity for the SSCs comprising PF-4 is high. This is to be expected for a newer facility as PF-4 was designed in the early 1970`s. The methodology and results of this study are presented in this paper.

  12. Toolbox Safety Talk Welding & Metal Work Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Toolbox Safety Talk Welding & Metal Work Safety Environmental Health & Safety Facilities Safety or harmful emission giving metals. Welding Safety When welding outside of a designated welding booth, ensure injury. Avoid welding on materials such as galvanized or stainless steel in order to minimize toxic fume

  13. Shear measurements across the northern margin of Whillans Ice Stream

    E-Print Network [OSTI]

    Van Der Veen, C.J.; Jezek, K.; Stearns, Leigh

    2007-01-01T23:59:59.000Z

    Field measurements of surface deformation across the northern shear margin of Whillans Ice Stream, West Antarctica, were analyzed to better understand the processes controlling the position and migration of this margin. Four lines of poles extending...

  14. Nuclear Safety Regulatory Framework

    Broader source: Energy.gov (indexed) [DOE]

    overall Nuclear Safety Policy & ESH Goals Safety Basis Review and Approval In the DOE governance model, contractors responsible for the facility develop the safety basis and...

  15. Gas Pipeline Safety (Indiana)

    Broader source: Energy.gov [DOE]

    This section establishes the Pipeline Safety Division within the Utility Regulatory Commission to administer federal pipeline safety standards and establish minimum state safety standards for...

  16. Laser Safety Introduction

    E-Print Network [OSTI]

    McQuade, D. Tyler

    use Integrated Safety Management here at the lab to reduce risk and work to improve the quality and safety of the work? #12;Integrated Safety Management Use (greater in size than wavelength) #12;Integrated Safety Management Remember, we

  17. Hierarchical Marginal Land Assessment for Land Use Planning

    SciTech Connect (OSTI)

    Kang, Shujiang [ORNL; Post, Wilfred M [ORNL; Wang, Dali [ORNL; Nichols, Dr Jeff A [ORNL; Bandaru, Vara Prasad [ORNL

    2013-01-01T23:59:59.000Z

    Marginal land provides an alternative potential for food and bioenergy production in the face of limited land resources; however, effective assessment of marginal lands is not well addressed. Concerns over environmental risks, ecosystem services and sustainability for marginal land have been widely raised. The objective of this study was to develop a hierarchical marginal land assessment framework for land use planning and management. We first identified major land functions linking production, environment, ecosystem services and economics, and then classified land resources into four categories of marginal land using suitability and limitations associated with major management goals, including physically marginal land, biologically marginal land, environmental-ecological marginal land, and economically marginal land. We tested this assessment framework in south-western Michigan, USA. Our results indicated that this marginal land assessment framework can be potentially feasible on land use planning for food and bioenergy production, and balancing multiple goals of land use management. We also compared our results with marginal land assessment from the Conservation Reserve Program (CRP) and land capability classes (LCC) that are used in the US. The hierarchical assessment framework has advantages of quantitatively reflecting land functions and multiple concerns. This provides a foundation upon which focused studies can be identified in order to improve the assessment framework by quantifying high-resolution land functions associated with environment and ecosystem services as well as their criteria are needed to improve the assessment framework.

  18. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2013-06-21T23:59:59.000Z

    DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

  19. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C. (Malmoe, SE)

    1984-01-01T23:59:59.000Z

    The safety valve contains a resilient gland to be held between a valve seat and a valve member and is secured to the valve member by a sleeve surrounding the end of the valve member adjacent to the valve seat. The sleeve is movable relative to the valve member through a limited axial distance and a gap exists between said valve member and said sleeve.

  20. Caldera Rim Margins | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:EzfeedflagBiomassSustainableCSL Gas Recovery Biomass Facility80 Jump370Caldera Rim Margins

  1. Safety Share from National Safety Council

    Broader source: Energy.gov [DOE]

    Slide Presentation by Joe Yanek, Fluor Government Group. National Safety Council Safety Share. The Campbell Institute is the “Environmental, Health and Safety (EHS) Center of Excellence” at the National Safety Council and provides a Forum for Leaders in EHS to exchange ideas and collaborate across industry sectors and organizational types.

  2. Delivering safety

    SciTech Connect (OSTI)

    Baldwin, N.D.; Spooner, K.G.; Walkden, P. [British Nuclear Group Ltd, Daresbury, Warrington (United Kingdom)

    2007-07-01T23:59:59.000Z

    In the United Kingdom there have been significant recent changes to the management of civil nuclear liabilities. With the formation in April 2005 of the Nuclear Decommissioning Authority (NDA), ownership of the civil nuclear licensed sites in the UK, including the Magnox Reactor Stations, passed to this new organisation. The NDAs mission is to seek acceleration of the nuclear clean up programme and deliver increased value for money and, consequently, are driving their contractors to seek more innovative ways of performing work. British Nuclear Group manages the UK Magnox stations under contract to the NDA. This paper summarises the approach being taken within its Reactor Sites business to work with suppliers to enhance working arrangements at sites, improve the delivery of decommissioning programmes and deliver improvements in safety and environmental performance. The UK Magnox stations are 1. generation gas-graphite reactors, constructed in the 1950's and 1960's. Two stations are currently still operating, three are shut-down undergoing defueling and the other five are being decommissioned. Despite the distractions of industry restructuring, an uncompromising policy of demanding improved performance in conjunction with improved safety and environmental standards has been adopted. Over the past 5 years, this policy has resulted in step-changes in performance at Reactor Sites, with increased electrical output and accelerated defueling and decommissioning. The improvements in performance have been mirrored by improvements in safety (DACR of 0 at 5 sites); environmental standards (reductions in energy and water consumption, increased waste recycling) and the overall health of the workforce (20% reduction in sickness absence). These achievements have, in turn, been recognised by external bodies, resulting in several awards, including: the world's first ISRS and IERS level 10 awards (Sizewell, 2006), the NUMEX plant maintenance award (Bradwell, 2006), numerous RoSPA awards at site and sector level and nomination, at Company level, for the RoSPA George Earle trophy for outstanding performance in Health and Safety (Reactor Sites, 2006). After 'setting the scene' and describing the challenges that the company has had to respond to, the paper explains how these improvements have been delivered. Specifically it explains the process that has been followed and the parts played by sites and suppliers to deliver improved performance. With the experience of already having transitioned several Magnox stations from operations to defueling and then to decommissioning, the paper describes the valuable experience that has been gained in achieving an optimum change process and maintaining momentum. (authors)

  3. Safety, Security

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR EMaterialsSafety, Security

  4. CRAD, Nuclear Safety Delegations for Documented Safety Analysis...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Safety Delegations for Documented Safety Analysis Approval - January 8, 2015 (EA CRAD 31-09, Rev. 0) CRAD, Nuclear Safety Delegations for Documented Safety Analysis Approval -...

  5. MARGINAL EXPENSE OIL WELL WIRELESS SURVEILLANCE MEOWS

    SciTech Connect (OSTI)

    Mason M. Medizade; John R. Ridgely; Donald G. Nelson

    2004-11-01T23:59:59.000Z

    A marginal expense oil well wireless surveillance system to monitor system performance and production from rod-pumped wells in real time from wells operated by Vaquero Energy in the Edison Field, Main Area of Kern County in California has been successfully designed and field tested. The surveillance system includes a proprietary flow sensor, a programmable transmitting unit, a base receiver and receiving antenna, and a base station computer equipped with software to interpret the data. First, the system design is presented. Second, field data obtained from three wells is shown. Results of the study show that an effective, cost competitive, real-time wireless surveillance system can be introduced to oil fields across the United States and the world.

  6. Identification and Resolution of Safety Issues for the Advanced Integral Type PWR

    SciTech Connect (OSTI)

    Kim, Woong Sik; Jo, Jong Chull; Yune, Young Gill; Kim, Hho Jung [Korea Institute of Nuclear Safety, 19 Kusung-dong, Yusung-ku, Taejon, 305-338 (Korea, Republic of)

    2004-07-01T23:59:59.000Z

    This paper presents the interim results of a study on the identification and resolution of safety issues for the AIPWR licensing. The safety issues discussed in this paper include (1) policy issues for which decision-makings are needed for the procedural requirements of licensing system in the regulatory policy point of view, (2) technical issues for which either development of new requirements or amendment of some existing requirements is needed, or (3) other technical issues for which safety verifications are required. The study covers (a) the assessment of applicability of the issues identified from the previous studies to the case of the AIPWR, (b) identification of safety issues through analysis of the international experiences in the design and licensing of advanced reactors, and technical review of the AIPWR design, and (c) development of the resolutions of safety issues, and application of the resolutions to the amendment of regulatory requirements and the licensing review of the AIPWR. As the results of this study, a total of twenty eight safety issues was identified: fourteen issues from the previous studies, including the establishment of design safety goals; four issues from the foreign practices and experiences, including the risk-informed licensing; and ten issues by the AIPWR design review, including reliability of passive safety systems. Ten issues of them have been already resolved and the succeeding study is under way to resolve the remaining ones. (authors)

  7. african continental margin: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Palaeocene extension on the Lofoten and Vring margins, and the additional Eocene subsidence and faulting, implies that Nick Kusznir; Alan Roberts; Rob Hunsdale 183...

  8. Front and Center: Bringing Marginalized Girls into Focus in STEM...

    Office of Environmental Management (EM)

    federal government employees who are STEM professionals with teachers and middle school students to share their passion, including some of the most marginalized students....

  9. active continental margin: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    HMMs, On-line handwrit- ing recognition, Off Do,Trinh-Minh-Tri 336 Derivation of Locational Marginal Prices for Restructured Wholesale Power Markets Energy Storage, Conversion...

  10. Acceptable NSLS Safety Documentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Acceptable NSLS Safety Documentation Print NSLS users who have completed NSLS Safety Module must present a copy of one of the following documents to receive ALS 1001: Safety at the...

  11. RADIATION SAFETY TRAINING MANUAL Radiation Safety Office

    E-Print Network [OSTI]

    Sibille, Etienne

    protection and the potential risks of ionizing radiation. Radiation Safety Office personnel provide.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 II. OVERVIEW OF REGULATIONS, PROTECTION STANDARDS, AND RADIATION SAFETY ORGANIZATION.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 V. BASIC RADIATION PROTECTION PRINCIPLES

  12. Dam Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Pennsylvania Department of Environmental Protection's Division of Dam Safety provides for the regulation and safety of dams and reservoirs throughout the Commonwealth in order to protect the...

  13. Pipeline Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Pennsylvania legislature has empowered the Public Utility Commission to direct and enforce safety standards for pipeline facilities and to regulate safety practices of certificated utilities...

  14. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03T23:59:59.000Z

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly evaluated and identified. This document supersedes the seismic classifications, assignments, and computations in ''Seismic Analysis for Preclosure Safety'' (BSC 2004a).

  15. SHSD Manager Safety Engineering Group Manager

    E-Print Network [OSTI]

    Safety, Machine Shop Safety, Tier I Program, Traffic Safety S. Moss: Nuclear Criticality Safety G. Shepherd: Explosives Safety, Facility Authorization Basis, Nuclear Safety R. Travis: Readiness Evaluations

  16. Derivation of Locational Marginal Prices for Restructured Wholesale Power Markets

    E-Print Network [OSTI]

    Tesfatsion, Leigh

    Derivation of Locational Marginal Prices for Restructured Wholesale Power Markets Haifeng Liu restructured wholesale power markets, the detailed derivation of LMPs as actually used in industry practice Operator (MISO). Keywords: Locational marginal pricing, wholesale power market, AC optimal power flow, DC

  17. Assessment of Biomass Resources from Marginal Lands in APEC Economies

    SciTech Connect (OSTI)

    Milbrandt, A.; Overend, R. P.

    2009-08-01T23:59:59.000Z

    The goal of this study is to examine the marginal lands in Asia-Pacific Economic Cooperation (APEC) economies and evaluate their biomass productivity potential. Twelve categories of marginal lands are identified using the Global Agro-Ecological Zones system of the United Nations Food and Agriculture Organization.

  18. Automatic Model Complexity Control Using Marginalized Discriminative Growth Functions

    E-Print Network [OSTI]

    Hain, Thomas

    Automatic model complexity control . Most LVCSR systems are trained on large amounts of data. . ManyAutomatic Model Complexity Control Using Marginalized Discriminative Growth Functions X. Liu & M. J. J. F. Gales: Automatic Model Complexity Control Using Marginalized Discriminative Growth Functions

  19. Environmental Health and Safety Fire and Life Safety Laboratory Assessment

    E-Print Network [OSTI]

    Environmental Health and Safety Fire and Life Safety Laboratory Assessment PI or environmental concerns were identified. B. Items of safety or environmental concerns were identified. C. Uncorrected repeated safety or environmental items were identified. Safety Equipment # Compliance Items

  20. Light Water Reactor Sustainability Program FY13 Status Update for EPRI - RISMC Collaboration

    SciTech Connect (OSTI)

    Curtis Smith

    2013-09-01T23:59:59.000Z

    The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced "RISMC toolkit" that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory (INL) is collaborating with the Electric Power Research Institute (EPRI) in order to focus on applications of interest to the U.S. nuclear power industry. This report documents the collaboration activities performed between INL and EPRI during FY2013.

  1. PRA and Risk Informed Analysis

    SciTech Connect (OSTI)

    Bernsen, Sidney A.; Simonen, Fredric A.; Balkey, Kenneth R.

    2006-01-01T23:59:59.000Z

    The Boiler and Pressure Vessel Code (BPVC) of the American Society of Mechanical Engineers (ASME) has introduced a risk based approach into Section XI that covers Rules for Inservice Inspection of Nuclear Power Plant Components. The risk based approach requires application of the probabilistic risk assessments (PRA). Because no industry consensus standard existed for PRAs, ASME has developed a standard to evaluate the quality level of an available PRA needed to support a given risk based application. The paper describes the PRA standard, Section XI application of PRAs, and plans for broader applications of PRAs to other ASME nuclear codes and standards. The paper addresses several specific topics of interest to Section XI. Important consideration are special methods (surrogate components) used to overcome the lack of PRA treatments of passive components in PRAs. The approach allows calculations of conditional core damage probabilities both for component failures that cause initiating events and failures in standby systems that decrease the availability of these systems. The paper relates the explicit risk based methods of the new Section XI code cases to the implicit consideration of risk used in the development of Section XI. Other topics include the needed interactions of ISI engineers, plant operating staff, PRA specialists, and members of expert panels that review the risk based programs.

  2. Seismic Safety Margins Research Program. Phase I, Final report: subsystem response (Project V). Volume 6

    SciTech Connect (OSTI)

    Shieh, L. C.; Chuang, T. Y.; O'Connell, W. J.

    1981-07-01T23:59:59.000Z

    This document reports on (1) the computation of the responses of subsystems, given the input subsystem support motion for components and systems whose failure can lead to an accident sequence (radioactive release), and (2) the results of a sensitivity study undertaken to determine the contributions of the several links in the seismic methodology chain (SMC) - seismic input (SI), soil-structure interaction (SSI), structure response (STR), and subsystem response (SUB) - to the uncertainty in subsystem response.

  3. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01T23:59:59.000Z

    Management of Nuclear Safety, Industrial Safety, Industrial Hygiene, and Fire Protection programs, functions, and field support resources for Tank Waste Remediation Systems (TWRS) has, until recently, been centralized in TWRS Safety, under the Emergency, Safety, and Quality organization. Industrial hygiene technician services were also provided to support operational needs related to safety basis compliance. Due to WHC decentralization of safety and reengineering efforts in West Tank Farms, staffing and safety responsibilities have been transferred to the facilities. Under the new structure, safety personnel for TWRS are assigned directly to East Tank Farms, West Tank Farms, and a core Safety Group in TWRS Engineering. The Characterization Project Operations (CPO) safety organization will remain in tact as it currently exists. Personnel assigned to East Tank Farms, West Tank Farms, and CPO will perform facility-specific or project-specific duties and provide field implementation of programs. Those assigned to the core group will focus on activities having a TWRS-wide or programmatic focus. Hanford-wide activities will be the responsibility of the Safety Center of Expertise. In order to ensure an effective and consistent safety program for TWRS under the new organization program functions, goals, organizational structure, roles, responsibilities, and path forward must be clearly established. The purpose of the TWRS Safety Program Plan is to define the overall safety program, responsibilities, relationships, and communication linkages for safety personnel under the new structure. In addition, issues associated with reorganization transition are addressed, including training, project ownership, records management, and dissemination of equipment. For the purpose of this document ``TWRS Safety`` refers to all safety professionals and technicians (Industrial Safety, Industrial Hygiene, Fire Protection, and Nuclear Safety) within the TWRS organization, regardless of their location in the organization.

  4. Global-local Structural Optimization Using Response Surfaces of Local Optimization Margins

    E-Print Network [OSTI]

    Neumaier, Arnold

    1 Global-local Structural Optimization Using Response Surfaces of Local Optimization Margins Boyang optimization problems. First, a large number of component optimizations for maximization of margins are performed. Response surface approximations (RSA) for maximum margins of component optimization

  5. Implications of Monte Carlo Statistical Errors in Criticality Safety Assessments

    SciTech Connect (OSTI)

    Pevey, Ronald E.

    2005-09-15T23:59:59.000Z

    Most criticality safety calculations are performed using Monte Carlo techniques because of Monte Carlo's ability to handle complex three-dimensional geometries. For Monte Carlo calculations, the more histories sampled, the lower the standard deviation of the resulting estimates. The common intuition is, therefore, that the more histories, the better; as a result, analysts tend to run Monte Carlo analyses as long as possible (or at least to a minimum acceptable uncertainty). For Monte Carlo criticality safety analyses, however, the optimization situation is complicated by the fact that procedures usually require that an extra margin of safety be added because of the statistical uncertainty of the Monte Carlo calculations. This additional safety margin affects the impact of the choice of the calculational standard deviation, both on production and on safety. This paper shows that, under the assumptions of normally distributed benchmarking calculational errors and exact compliance with the upper subcritical limit (USL), the standard deviation that optimizes production is zero, but there is a non-zero value of the calculational standard deviation that minimizes the risk of inadvertently labeling a supercritical configuration as subcritical. Furthermore, this value is shown to be a simple function of the typical benchmarking step outcomes--the bias, the standard deviation of the bias, the upper subcritical limit, and the number of standard deviations added to calculated k-effectives before comparison to the USL.

  6. asian monsoonal margin: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    model (MRCM) in simulating the West African monsoon. The MRCM is built on the Regional Climate Model, ... Im, Eun-Soon 242 From Marginal Deformations to Confinement HEP - Theory...

  7. adeep ocean margin: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    portions of Volume 146, Part 1 (Cascadia Margin), of the Proceedings of the Ocean Drilling Program. References to page numbers in the Initial Reports are preceded by "A1 22...

  8. Large-margin Gaussian mixture modeling for automatic speech recognition

    E-Print Network [OSTI]

    Chang, Hung-An, Ph. D. Massachusetts Institute of Technology

    2008-01-01T23:59:59.000Z

    Discriminative training for acoustic models has been widely studied to improve the performance of automatic speech recognition systems. To enhance the generalization ability of discriminatively trained models, a large-margin ...

  9. asian marginal seas: Topics by E-print Network

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    which somewhat surprisingly turned out to be classically stable. This was called marginal stability, as moving along one of its zero-modes, two of the stable modes turn...

  10. Voltage Collapse Margin Sensitivity Methods applied to the Power System

    E-Print Network [OSTI]

    Greene Ian Dobson Electrical & Computer Engineering Department University of Wisconsin-Madison 1415 Outages causing at least 75 MW reduction in loading margin . . . . . . . . . . . . . . . . . . . . . . . . . . 24 4.2 Radial Line Outages . . . . . . . . . . . . . . . . . . . . . . . 24 4.3 Non-radial Line

  11. Geotechnical characterization of sediments from Hydrate Ridge, Cascadia Continental Margin

    E-Print Network [OSTI]

    Tan, Brian B. (Brian Bautista), 1979-

    2004-01-01T23:59:59.000Z

    Eight whole core sediment samples were obtained from ODP Site 1244, Hydrate Ridge, Cascadia Continental Margin with the goal of understanding the stress history, consolidation behavior and strength characteristics of the ...

  12. Design of miniature floating platform for marginal fields

    E-Print Network [OSTI]

    Miao, Sha, S.M. Massachusetts Institute of Technology

    2013-01-01T23:59:59.000Z

    This thesis presents the design of a novel type of miniature floating offshore platforms with a heave plate attached at the keel, suitable for developing deep-water marginal fields. This design features a small displacement, ...

  13. Victorian Queer: Marginality and Money in Nineteenth-Century Literature 

    E-Print Network [OSTI]

    Choi, Jung Sun

    2013-05-01T23:59:59.000Z

    ..................................... 66? Victorian Eccentricity: The Identity of the Extra-Ordinary ..... 72? Valentine Blyth?s Eccentricity and Respectability at Risk ...... 77? In Defense of Eccentricity I: Victorian Man?s Economic Ability... as extraordinary. Valentine Blyth is a figure of queer marginality that Collins takes an interest in for fostering his notion of social toleration of differences. Jane Eyre is also a representative marginal figure, in this case one used by Charlotte Bront...

  14. Coal Mine Safety Act (Virginia)

    Broader source: Energy.gov [DOE]

    This Act is the primary legislation pertaining to coal mine safety in Virginia. It contains information on safety rules, safety standards and required certifications for mine workers, prohibited...

  15. Nuclear Safety Research and Development...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of...

  16. Marginal Abatement Costs and Marginal Welfare Costs for Greenhouse Gas Emissions Reductions: Results from the EPPA Model

    E-Print Network [OSTI]

    Morris, Jennifer

    Marginal abatement cost (MAC) curves, relationships between tons of emissions abated and the CO2 (or GHG) price, have been widely used as pedagogic devices to illustrate simple economic concepts such as the benefits of ...

  17. Magnetic Field Safety Magnetic Field Safety

    E-Print Network [OSTI]

    McQuade, D. Tyler

    Magnetic Field Safety Training #12;Magnetic Field Safety Strong Magnetic Fields exist around energized magnets. High magnetic fields alone are a recognized hazard only for personnel with certain medical conditions such as pacemakers, magnetic implants, or embedded shrapnel. In addition, high magnetic

  18. Safety Issues Chemical Storage

    E-Print Network [OSTI]

    Cohen, Robert E.

    Safety Issues · Chemical Storage ·Store in compatible containers that are in good condition to store separately. #12;Safety Issues · Flammable liquid storage -Store bulk quantities in flammable storage cabinets -UL approved Flammable Storage Refrigerators are required for cold storage · Provide

  19. Office of Nuclear Safety

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety establishes nuclear safety requirements and expectations for the Department to ensure protection of workers and the public from the hazards associated with nuclear operations with all Department operations.

  20. Pipeline Safety Rule (Tennessee)

    Broader source: Energy.gov [DOE]

    The Pipeline Safety Rule simply states, "The Minimum Federal Safety Standards for the transportation of natural and other gas by pipeline (Title 49, Chapter 1, Part 192) as published in the Federal...

  1. Dam Safety Program (Maryland)

    Broader source: Energy.gov [DOE]

    The Dam Safety Division within the Department of the Environment is responsible for administering a dam safety program to regulate the construction, operation, and maintenance of dams to prevent...

  2. Dam Safety (Delaware)

    Broader source: Energy.gov [DOE]

    The Delaware Dam Safety Law was adopted in 2004 and provides the framework for proper design, construction, operation, maintenance, and inspection of dams in the interest of public health, safety,...

  3. Nuclear Explosive Safety Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14T23:59:59.000Z

    This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

  4. DOE handbook electrical safety

    SciTech Connect (OSTI)

    NONE

    1998-01-01T23:59:59.000Z

    Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  5. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  6. Department of Environmental Health & Safety Emergency Management

    E-Print Network [OSTI]

    O'Toole, Alice J.

    Management Fire & Life Safety Industrial Hygiene Laboratory Safety Occupational & General Safety Management Environmental Management Fire & Life Safety Industrial Hygiene Laboratory Safety Occupational Values A Note from the Director Environmental Management Fire & Life Safety Lab Safety & Industrial

  7. IEEE TRANSACTIONS ON POWER SYSTEMS, VOL. 29, NO. 1, JANUARY 2014 203 Distribution Locational Marginal Pricing for Optimal

    E-Print Network [OSTI]

    Oren, Shmuel S.

    (DSO) determines distribution locational marginal prices (DLMPs) by solving the social welfare, distribution locational marginal prices (DLMPs), distribution locational marginal pricing (DLMP), distribution at node . System locational marginal price (LMP) at time period for the node feeding the distribution grid

  8. Environmental Health & Safety

    E-Print Network [OSTI]

    Environmental Health & Safety Sub Department Name 480 Oak Rd, Stanford, CA 94305 T 650.723.0448 F 650.725.3468 DEPUTY DIRECTOR, ENVIRONMENTAL HEALTH AND SAFETY Exempt, Full-Time (100% FTE) Posted May 1, 2014 The Department of Environmental Health and Safety (EH&S) at Stanford University seeks

  9. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

    Report of Earth Sciences Departmental Safety Committee 2011 - 12 5 Chemical Safety 21 - 22 Chemical Waste Assessment Hire Vehicle Checklist Department Driving Protocol: Bullard vehicles 38 - 48 Electrical Safety 24 and outside adjacent to areas which present a particular fire hazard. Persons wishing to smoke are asked to do

  10. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

    Report of Earth Sciences Departmental Safety Committee 2012 - 13 5 Chemical Safety 21 - 22 Chemical Waste Assessment Hire Vehicle Checklist Department Driving Protocol: Bullard vehicles 38 - 48 Electrical Safety 24 and outside adjacent to areas which present a particular fire hazard. Persons wishing to smoke are asked to do

  11. September 2013 Laboratory Safety Manual Section 7 -Safety Training

    E-Print Network [OSTI]

    Wilcock, William

    September 2013 Laboratory Safety Manual Section 7 - Safety Training UW Environmental Health and Safety Page 7-1 Section 7 - Safety Training Contents A. SAFETY TRAINING REQUIREMENTS ......................................................7-1 B. EH&S SAFETY TRAINING AND RECORDS ..............................................7-1 C

  12. Center for Intermodal Transportation Safety

    E-Print Network [OSTI]

    Fernandez, Eduardo

    Center for Intermodal Transportation Safety and Security Panagiotis Scarlatos, Ph.D., Director Transportation Safety and Security #12;Center for Intermodal Transportation Safety and Security Partners #12 evacuations · Tracking systems for hazardous materials Center for Intermodal Transportation Safety

  13. Safety Manual Prepared by the

    E-Print Network [OSTI]

    Alpay, S. Pamir

    -3113 Emergency maintenance to report a water leak, electrical outage, non-working fume hood, etc. after normal Radiation and Laser Safety 19 Laser Safety 21 Compressed Gas and Cryogenic Safety 22 Electrical Safety 24

  14. Sandia National Laboratories: Transportation Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experimental Testing Phenomenological Modeling Risk and Safety Assessment Cyber-Based Vulnerability Assessments Uncertainty Analysis Transportation Safety Fire Science Human...

  15. Bioenergy crop productivity and potential climate change mitigation from marginal lands in the United States: An

    E-Print Network [OSTI]

    Zhuang, Qianlai

    ÀChampaign, Urbana, IL 61801, USA Abstract Growing biomass feedstocks from marginal lands is becoming an increasingly

  16. Total safety: A new safety culture to integrate nuclear safety and operational safety

    SciTech Connect (OSTI)

    Saji, G. [Japan Atomic Energy Research Institute, Ibaraki-ken (Japan); Murphy, G.A. [ed.

    1991-07-01T23:59:59.000Z

    The creation of a complete and thorough safety culture is proposed for the purpose of providing additional assurance about nuclear safety and improving the performance of nuclear power plants. The safety philosophy developed a combination of the former hardware-oriented nuclear safety approach and recent operational safety concepts. The improvement of the latter, after TMI-2 and Chernobyl, has been proven very effective in reducing the total risk associated with nuclear power plants. The first part of this article introduces a {open_quotes}total safety{close_quotes} concept. This extends the concept of {open_quotes}nuclear safety{close_quotes} and makes it closer to the public perception of safety. This concept is defined by means of a taxonomy of total safety. The second part of the article shows that total safety can be achieved by integrating it into a modern quality assurance (QA) system since it is tailored to make implementation into a framework of QA easier. The author believes that the outstanding success experienced by various industries as a result of introducing the modern QA system should lead to its application for ensuring the safety and performance of nuclear facilities. 15 refs., 3 figs.

  17. Quench margin measurement in Nb3Sn quadrupole magnet

    SciTech Connect (OSTI)

    Kashikhin, V.V.; Bossert, R.; Chlachidze, G.; Lamm, M.; Novitski, I.; Zlobin, A.V.; /Fermilab

    2008-08-01T23:59:59.000Z

    One of the possible practical applications of the Nb{sub 3}Sn accelerator magnets is the LHC luminosity upgrade that involves replacing the present NbTi focusing quadrupoles in two high-luminosity interaction regions (IR). The IR magnets are exposed to strong radiation from the interaction point that requires a detailed investigation of the magnet operating margins under the expected radiation-induced heat depositions. This paper presents the results of simulation and measurement of quench limits and temperature margins for a Nb{sub 3}Sn model magnet using a special midplane strip heater.

  18. Engineering index : a metric for assessing margin in engineered systems

    SciTech Connect (OSTI)

    Dolin, Ronald M.

    2002-01-01T23:59:59.000Z

    Inherent in most engineered products is some measure of margin or over design. Engineers often do not retain design and performance knowledge so they can quantify uncertainties and estimate how much margin their product possesses. When knowledge-capture and quantification is neither possible, nor permissible, engineers rely on cultural lore and institutionalised practices to assign nominal conditions and tolerances. Often what gets lost along the way is design intent, product requirements, and their relationship with the product's intended application. The Engineering Index was developed to assess the goodness or quality of a product.

  19. Distance Metric Learning for Large Margin Nearest Neighbor Classification

    E-Print Network [OSTI]

    Weinberger, Kilian

    Distance Metric Learning for Large Margin Nearest Neighbor Classification Kilian Q. Weinberger}@cis.upenn.edu Abstract We show how to learn a Mahanalobis distance metric for k-nearest neigh- bor (kNN) classification in kNN classification--for example, achieving a test error rate of 1.3% on the MNIST handwritten digits

  20. Contaminated identities: Mercury and marginalization in Ghana's artisanal mining sector

    E-Print Network [OSTI]

    Singha, Kamini

    mining; Political ecology; Ecohealth; Environmental justice; Ghana 1. Introduction Artisanal and smallContaminated identities: Mercury and marginalization in Ghana's artisanal mining sector Petra and multifaceted policy problem that underlies the current conflictual aspects in the small-scale mining sector

  1. Large Margin Taxonomy Embedding with an Application to Document Categorization

    E-Print Network [OSTI]

    Weinberger, Kilian

    Large Margin Taxonomy Embedding with an Application to Document Categorization Kilian Weinberger that the topics are not just discrete classes, but are nodes in a complex taxonomy with rich inter-topic relationships. For example, web pages can be categorized into the Yahoo! web taxonomy or medical journals can

  2. The world's offshore continental margins contain vast reserves of

    E-Print Network [OSTI]

    Texas at Austin, University of

    The world's offshore continental margins contain vast reserves of gas hydrate, a frozen form of nat-seafloor geology. Increasing use of marine multicomponent seismic technol- ogy by oil and gas companies now allows seafloor strata over distances of several kilometers across the Green Canyon area of the Gulf of Mexico

  3. RADIO EMISSION FROM INSTABILITIES IN SPACE PLASMAS: MARGINAL STABILITY,

    E-Print Network [OSTI]

    Melrose, Don

    I t RADIO EMISSION FROM INSTABILITIES IN SPACE PLASMAS: MARGINAL STABILITY, 4TOCHASTIC GROWTH emission, hich is an indirect emission process first discussed by Ginaburg and Zhe/eznyakoe, 9581, and electron cyclotron maser emission (ECME), which is a direct emission ess first discussed in the presently

  4. Mesozoic evolution of northeast African shelf margin, Libya and Egypt

    SciTech Connect (OSTI)

    Aadland, R.K.; Schamel, S.

    1989-03-01T23:59:59.000Z

    The present tectonic features of the northeast African shelf margin between the Nile delta and the Gulf of Sirte are products of (1) precursory late Paleozoic basement arches, (2) early Mesozoic rifting and plate separation, and (3) Late Cretaceous structural inversion. The 250 km-wide and highly differentiated Mesozoic passive margin in the Western Desert region of Egypt is developed above a broad northwest-trending Late Carboniferous basement arch. In northeastern Libya, in contrast, the passive margin is restricted to just the northernmost Cyrenaica platform, where subsidence was extremely rapid in the Jurassic and Early Cretaceous. The boundary between the Western Desert basin and the Cyrenaica platform is controlled by the western flank of the basement arch. In the middle Cretaceous (100-90 Ma), subsidence accelerated over large areas of the Western desert, further enhancing a pattern of east-west-trending subbasins. This phase of rapid subsidence was abruptly ended about 80 Ma by the onset of structural inversion that uplifted the northern Cyrenaica shelf margin and further differentiated the Western Desert subbasin along a northeasterly trend.

  5. Sustainable bioenergy production from marginal lands in the US Midwest

    SciTech Connect (OSTI)

    Gelfand, Ilya; Sahajpal, Ritvik; Zhang, Xuesong; Izaurralde, Roberto C.; Gross, Katherine L.; Robertson, G. P.

    2013-01-24T23:59:59.000Z

    Long-term measurements of global warming impact coupled with spatially explicit modeling suggests that both climate benefits and the production potential of cellulosic crops grown on marginal lands of the US North Central region are substantial but will be insufficient to meet long-term biofuel needs.

  6. The Marginalized Particle Filter for Automotive Tracking Applications

    E-Print Network [OSTI]

    Schön, Thomas

    The Marginalized Particle Filter for Automotive Tracking Applications Andreas Eidehall Thomas B surroundings (lane geometry and the position of other vehicles), which is needed for intelligent automotive in a nonlinear estimation problem. For automotive tracking systems, these problems are traditionally handled

  7. The Marginalized Particle Filter for Automotive Tracking Applications

    E-Print Network [OSTI]

    Gustafsson, Fredrik

    1 The Marginalized Particle Filter for Automotive Tracking Applications Andreas Eidehall Thomas Sch surroundings (lane geometry and the position of other vehicles), which is needed for intelligent automotive in a nonlinear estimation problem. For automotive tracking systems, these problems are traditionally handled

  8. Hydrogen Technologies Safety Guide

    SciTech Connect (OSTI)

    Rivkin, C.; Burgess, R.; Buttner, W.

    2015-01-01T23:59:59.000Z

    The purpose of this guide is to provide basic background information on hydrogen technologies. It is intended to provide project developers, code officials, and other interested parties the background information to be able to put hydrogen safety in context. For example, code officials reviewing permit applications for hydrogen projects will get an understanding of the industrial history of hydrogen, basic safety concerns, and safety requirements.

  9. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  10. Preliminary safety evaluation of the advanced burner test reactor.

    SciTech Connect (OSTI)

    Dunn, F. E.; Fanning, T. H.; Cahalan, J. E.; Nuclear Engineering Division

    2006-09-15T23:59:59.000Z

    Results of a preliminary safety evaluation of the Advanced Burner Test Reactor (ABTR) pre-conceptual design are reported. The ABTR safety design approach is described. Traditional defense-in-depth design features are supplemented with passive safety performance characteristics that include natural circulation emergency decay heat removal and reactor power reduction by inherent reactivity feedbacks in accidents. ABTR safety performance in design-basis and beyond-design-basis accident sequences is estimated based on analyses. Modeling assumptions and input data for safety analyses are presented. Analysis results for simulation of simultaneous loss of coolant pumping power and normal heat rejection are presented and discussed, both for the case with reactor scram and the case without reactor scram. The analysis results indicate that the ABTR pre-conceptual design is capable of undergoing bounding design-basis and beyond-design-basis accidents without fuel cladding failures. The first line of defense for protection of the public against release of radioactivity in accidents remains intact with significant margin. A comparison and evaluation of general safety design criteria for the ABTR conceptual design phase are presented in an appendix. A second appendix presents SASSYS-1 computer code capabilities and modeling enhancements implemented for ABTR analyses.

  11. Aviation Management and Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-15T23:59:59.000Z

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Cancels DOE O 440.2B.

  12. Dam Safety Program (Florida)

    Broader source: Energy.gov [DOE]

    Dam safety in Florida is a shared responsibility among the Florida Department of Environmental Protection (FDEP), the regional water management districts, the United States Army Corps of Engineers ...

  13. Battery Safety Testing

    Broader source: Energy.gov (indexed) [DOE]

    Battery Safety Testing Christopher J. Orendorff, Leigh Anna M. Steele, Josh Lamb, and Scott Spangler Sandia National Laboratories 2014 Energy Storage Annual Merit Review...

  14. BNL | ATF Laser Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    be continuously escorted by someone who has such training: The training consists of an eye exam, BNL general laser safety lecture, and formal ATF laser familiarization. Untrained...

  15. Coiled Tubing Safety Manual

    SciTech Connect (OSTI)

    Crow, W.

    1999-04-06T23:59:59.000Z

    This document addresses safety concerns regarding the use of coiled tubing as it pertains to the preservation of personnel, environment and the wellbore.

  16. Safety Hazards of Batteries

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Hazards of Batteries Battery technology is at the heart of much of our technological revolution. One of the most prevalent rechargeable batteries in use today is the...

  17. Pipeline Safety (Maryland)

    Broader source: Energy.gov [DOE]

    The Public Service Commission has the authority enact regulations pertaining to pipeline safety. These regulations address pipeline monitoring, inspections, enforcement, and penalties.

  18. Intrastate Pipeline Safety (Minnesota)

    Broader source: Energy.gov [DOE]

    These regulations provide standards for gas and liquid pipeline maintenance and operating procedures, per the Federal Hazardous Liquid and Natural Gas Pipeline Safety Acts, and give the...

  19. Pipeline Safety (South Dakota)

    Broader source: Energy.gov [DOE]

    The South Dakota Pipeline Safety Program, administered by the Public Utilities Commission, is responsible for regulating hazardous gas intrastate pipelines. Relevant legislation and regulations...

  20. Gas Safety Law (Florida)

    Broader source: Energy.gov [DOE]

    This law authorizes the establishment of rules and regulations covering the design, fabrication, installation, inspection, testing and safety standards for installation, operation and maintenance...

  1. DOE Explosives Safety Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-03-29T23:59:59.000Z

    This Manual describes DOE's explosives safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives.

  2. Audit Report The Procurement of Safety Class/Safety-Significant Items at the Savannah River Site

    SciTech Connect (OSTI)

    None

    2009-04-01T23:59:59.000Z

    The Department of Energy operates several nuclear facilities at its Savannah River Site, and several additional facilities are under construction. This includes the National Nuclear Security Administration's Tritium Extraction Facility (TEF) which is designated to help maintain the reliability of the U.S. nuclear stockpile. The Mixed Oxide Fuel Fabrication Facility (MOX Facility) is being constructed to manufacture commercial nuclear reactor fuel assemblies from weapon-grade plutonium oxide and depleted uranium. The Interim Salt Processing (ISP) project, managed by the Office of Environmental Management, will treat radioactive waste. The Department has committed to procuring products and services for nuclear-related activities that meet or exceed recognized quality assurance standards. Such standards help to ensure the safety and performance of these facilities. To that end, it issued Departmental Order 414.1C, Quality Assurance (QA Order). The QA Order requires the application of Quality Assurance Requirements for Nuclear Facility Applications (NQA-1) for nuclear-related activities. The NQA-1 standard provides requirements and guidelines for the establishment and execution of quality assurance programs during the siting, design, construction, operation, and decommissioning of nuclear facilities. These requirements, promulgated by the American Society of Mechanical Engineers, must be applied to 'safety-class' and 'safety-significant' structures, systems and components (SSCs). Safety-class SSCs are defined as those necessary to prevent exposure off site and to protect the public. Safety-significant SSCs are those whose failure could irreversibly impact worker safety such as a fatality, serious injury, or significant radiological or chemical exposure. Due to the importance of protecting the public, workers, and environment, we initiated an audit to determine whether the Department of Energy procured safety-class and safety-significant SSCs that met NQA-1 standards at the Savannah River Site. Our review disclosed that the Department had procured and installed safety-class and safety-significant SSCs that did not meet NQA-1 quality standards. Specifically, we identified multiple instances in which critical components did not meet required quality and safety standards. For example: (1) Three structural components were procured and installed by the prime contractor at Savannah River during construction of the MOX Facility that did not meet the technical specifications for items relied on for safety. These substandard items necessitated costly and time consuming remedial action to, among other things, ensure that nonconforming materials and equipment would function within safety margins; (2) In six instances, items used in the construction of TEF failed to satisfy quality standards. In one of these situations, operating procedures had to be modified to ensure that the problem item did not compromise safety; and (3) Finally, at the ISP, one component that did not meet quality standards was procured. The failure of the item could have resulted in a spill of up to 15,000 gallons of high-level radioactive waste. Based on an extensive examination of relevant internal controls and procurement practices, we concluded that these failures were attributable to inadequate attention to quality assurance at Savannah River. Simply put, Departmental controls were not adequate to prevent and/or detect quality assurance problems. For example, Federal and prime contractor officials did not expressly require that subcontractors or lower-tiered vendors comply with quality assurance requirements. Additionally, management did not effectively communicate quality assurance concerns between the several Departmental program elements operating at Savannah River. The procurement and installation of these nonconforming components resulted in cost increases. For example, as of October 2008, the MOX Facility had incurred costs of more than $680,000 due to problems associated with the procurement of $11 million of nonconforming safety-class reinforcing steel.

  3. Occupational Hygiene & Chemical Safety Division Department of Environmental Health & Safety

    E-Print Network [OSTI]

    Machel, Hans

    Occupational Hygiene & Chemical Safety Division Department of Environmental Health & Safety Risk all connections and fittings prior to start of anesthesia. Carefully pour Isoflurane from Environmental Health & Safety before re-entering the laboratory. REFERENCES 1. Procedure

  4. Sandia Energy - Risk and Safety Assessment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Risk and Safety Assessment Home Stationary Power Nuclear Fuel Cycle Nuclear Energy Safety Technologies Risk and Safety Assessment Risk and Safety AssessmentTara...

  5. Office of Nuclear Facility Safety Programs

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

  6. Facility Safety - DOE Directives, Delegations, and Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Change, Safety, The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety,...

  7. Integrated Safety Management Policy

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-04-25T23:59:59.000Z

    The policy establishes DOE's expectation for safety, including integrated safety management that will enable the Department’s mission goals to be accomplished efficiently while ensuring safe operations at all departmental facilities and activities. Cancels DOE P 411.1, DOE P 441.1, DOE P 450.2A, DOE P 450.4, and DOE P 450.7

  8. SECURITY AND FIRE SAFETY

    E-Print Network [OSTI]

    Barrash, Warren

    ANNUAL SECURITY AND FIRE SAFETY REPORT 2014 #12;2 Boise State University 2014 Annual Security and Fire Safety Report From the Vice President for Campus Operations and General Counsel At Boise State University, we are committed to providing a safe and secure environment for students, staff

  9. Safety of Accelerator Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2004-07-23T23:59:59.000Z

    To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2A. Certified 5-13-08. Canceled by DOE O 420.2C.

  10. Safety of Accelerator Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-07-21T23:59:59.000Z

    The order defines accelerators and establishes accelerator specific safety requirements and approval authorities which, when supplemented by other applicable safety and health requirements, promote safe operations to ensure protection of workers, the public, and the environment. Cancels DOE O 420.2B.

  11. Safety of Accelerator Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-01-08T23:59:59.000Z

    To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2. Canceled by DOE O 420.2B.

  12. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16T23:59:59.000Z

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  13. Occupational Hygiene & Chemical Safety Division Department of Environmental Health & Safety

    E-Print Network [OSTI]

    Machel, Hans

    Occupational Hygiene & Chemical Safety Division Department of Environmental Health & Safety Risk (most common ­ personal hygiene very important); d) storage ­ leaks; and e) waste ­ storage and disposal

  14. Impact of Passive Safety on FHR Instrumentation Systems Design and Classification

    SciTech Connect (OSTI)

    Holcomb, David Eugene [ORNL

    2015-01-01T23:59:59.000Z

    Fluoride salt-cooled high-temperature reactors (FHRs) will rely more extensively on passive safety than earlier reactor classes. 10CFR50 Appendix A, General Design Criteria for Nuclear Power Plants, establishes minimum design requirements to provide reasonable assurance of adequate safety. 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, provides guidance on how the safety significance of systems, structures, and components (SSCs) should be reflected in their regulatory treatment. The Nuclear Energy Institute (NEI) has provided 10 CFR 50.69 SSC Categorization Guideline (NEI-00-04) that factors in probabilistic risk assessment (PRA) model insights, as well as deterministic insights, through an integrated decision-making panel. Employing the PRA to inform deterministic requirements enables an appropriately balanced, technically sound categorization to be established. No FHR currently has an adequate PRA or set of design basis accidents to enable establishing the safety classification of its SSCs. While all SSCs used to comply with the general design criteria (GDCs) will be safety related, the intent is to limit the instrumentation risk significance through effective design and reliance on inherent passive safety characteristics. For example, FHRs have no safety-significant temperature threshold phenomena, thus, enabling the primary and reserve reactivity control systems required by GDC 26 to be passively, thermally triggered at temperatures well below those for which core or primary coolant boundary damage would occur. Moreover, the passive thermal triggering of the primary and reserve shutdown systems may relegate the control rod drive motors to the control system, substantially decreasing the amount of safety-significant wiring needed. Similarly, FHR decay heat removal systems are intended to be running continuously to minimize the amount of safety-significant instrumentation needed to initiate operation of systems and components important to safety as required in GDC 20. This paper provides an overview of the design process employed to develop a pre-conceptual FHR instrumentation architecture intended to lower plant capital and operational costs by minimizing reliance on expensive, safety related, safety-significant instrumentation through the use of inherent passive features of FHRs.

  15. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

  16. CRAD, Facility Safety- Technical Safety Requirements

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Technical Safety Requirments (TSA).

  17. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

    COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212-305-0303 F: 212 Psychiatric Institute Radiation Safety Office (Please complete this form within 24 hours and send a copy to your supervisor and The Radiation Safety Office) Your Name

  18. Normalization of Process Safety Metrics

    E-Print Network [OSTI]

    Wang, Mengtian

    2012-10-19T23:59:59.000Z

    and organizational risks, there is an emerging need to evaluate the process safety implementation across an organization through measurements. Thus, the process safety metric is applied as a powerful tool that measures safety activities, status, and performance...

  19. Specification of advanced safety modeling requirements (Rev. 0).

    SciTech Connect (OSTI)

    Fanning, T. H.; Tautges, T. J.

    2008-06-30T23:59:59.000Z

    The U.S. Department of Energy's Global Nuclear Energy Partnership has lead to renewed interest in liquid-metal-cooled fast reactors for the purpose of closing the nuclear fuel cycle and making more efficient use of future repository capacity. However, the U.S. has not designed or constructed a fast reactor in nearly 30 years. Accurate, high-fidelity, whole-plant dynamics safety simulations will play a crucial role by providing confidence that component and system designs will satisfy established design limits and safety margins under a wide variety of operational, design basis, and beyond design basis transient conditions. Current modeling capabilities for fast reactor safety analyses have resulted from several hundred person-years of code development effort supported by experimental validation. The broad spectrum of mechanistic and phenomenological models that have been developed represent an enormous amount of institutional knowledge that needs to be maintained. Complicating this, the existing code architectures for safety modeling evolved from programming practices of the 1970s. This has lead to monolithic applications with interdependent data models which require significant knowledge of the complexities of the entire code in order for each component to be maintained. In order to develop an advanced fast reactor safety modeling capability, the limitations of the existing code architecture must be overcome while preserving the capabilities that already exist. To accomplish this, a set of advanced safety modeling requirements is defined, based on modern programming practices, that focuses on modular development within a flexible coupling framework. An approach for integrating the existing capabilities of the SAS4A/SASSYS-1 fast reactor safety analysis code into the SHARP framework is provided in order to preserve existing capabilities while providing a smooth transition to advanced modeling capabilities. In doing this, the advanced fast reactor safety models will target leadership-class computing architectures for massively-parallel high-fidelity computations while providing continued support for rapid prototyping using modest fidelity computations on multiple-core desktop platforms.

  20. Adaptive control design with guaranteed margins for nonlinear plants

    E-Print Network [OSTI]

    Jang, Jinho, S.M. Massachusetts Institute of Technology

    2009-01-01T23:59:59.000Z

    Adaptive control is one of the technologies that improve both performance and safety as controller parameters can be redesigned autonomously in the presence of uncertainties. Considerable research has been accomplished in ...

  1. Quantification Of Margins And Uncertainties: A Bayesian Approach (full Paper)

    SciTech Connect (OSTI)

    Wallstrom, Timothy C [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    Quantification of Margins and Uncertainties (QMU) is 'a formalism for dealing with the reliability of complex technical systems, and the confidence which can be placed in estimates of that reliability.' (Eardleyet al, 2005). In this paper, we show how QMU may be interpreted in the framework of Bayesian statistical inference, using a probabilistic network. The Bayesian approach clarifies the probabilistic underpinnings of the formalism, and shows how the formalism can be used for deciSion-making.

  2. Another view of the Marginality Hypothesis: presidential influence in Congress

    E-Print Network [OSTI]

    Richard, Carl Mark

    1980-01-01T23:59:59.000Z

    to test the theory that electoral marginality affects the legislative behavior of House mem- bers. ilore scec'fically, it mey affect the degree to whir h represent- atives are responsive to their constituents. 4'he cuestion of why this happens leads us... studies done which deal with the numerous influences that can affect congressional behavior. Scholars tell us that among other things, a congressman's constituency, his House col- leagues, his party identification, and the executive branch, all in...

  3. Environmental Health and Safety Department

    E-Print Network [OSTI]

    . Fire Safety, Radiation Safety and Hazardous Materials Facility are at other locations on campus Training Requirements If you work with: · Biological Materials · Chemical Agents · Radiological Materials

  4. Safety Culture in Nuclear Installations

    Broader source: Energy.gov [DOE]

    IAEA-TECDOC-1329 Safety Culture in Nuclear Installations, Guidance for use in the Enhancement of Safety Culture, International Atomic Energy Agency IAEA, December 2002.

  5. Industrial Safety | The Ames Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    such as machine guarding, personal protective equipment (PPE), electrical safety, accident prevention and investigation, building design and code review, fire safety, and...

  6. Gordon wins NNSA Safety Professional

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    in electrical safety at the Laboratory and across the DOE complex," said Industrial Hygiene and Safety manager Theresa Cull. "I am very pleased that NNSA has recognized Lloyd's...

  7. Developed 2007 _____________________________ Environment, Health, & Safety _________ __________________

    E-Print Network [OSTI]

    Eisen, Michael

    _________ __________________ Training Program EHS 300~ Fiber optic Safety Course Syllabus Subject Category: Industrial Hygiene Course Alignment EH&S Website: Industrial Hygiene/Laser Safety Group - http

  8. Abstract--Although Locational Marginal Pricing (LMP) plays an important role in many restructured wholesale power

    E-Print Network [OSTI]

    Tesfatsion, Leigh

    1 Abstract-- Although Locational Marginal Pricing (LMP) plays an important role in many Terms-- Locational marginal pricing, wholesale power market, AC optimal power flow, DC optimal power congestion by means of Locational Marginal Pricing (LMP), i.e., the pricing of power by the location

  9. A STOCHASTIC PROGRAMMING APPROACH TO QUANTIFYING EFFECTS OF CONTINGENCIES ON LOCATIONAL MARGINAL PRICES

    E-Print Network [OSTI]

    Stankoviæ, Aleksandar

    on varia- tions of Locational Marginal Prices (LMPs) in restruc- tured power markets. The process: Locational marginal prices (LMPs), Un- certainty, Power system security, Optimization meth- ods, StochasticA STOCHASTIC PROGRAMMING APPROACH TO QUANTIFYING EFFECTS OF CONTINGENCIES ON LOCATIONAL MARGINAL

  10. Polished `Hoes', Dancehall Queens, and Sexual Freaks: Voices From the Margins of Caribbean Literature

    E-Print Network [OSTI]

    Zhou, Yaoqi

    Polished `Hoes', Dancehall Queens, and Sexual Freaks: Voices From the Margins of Caribbean is a book- length project that will examine multiply marginalized Caribbean women's narratives of resistance in the Caribbean, tends to reward normative behavior and marginalizes women who do not conform to set standards

  11. Fast Prediction of Loadability Margins by Constructing a Small-Signal Stability Boundary

    E-Print Network [OSTI]

    Cañizares, Claudio A.

    Fast Prediction of Loadability Margins by Constructing a Small-Signal Stability Boundary Based system. A novel approach is proposed in this paper for fast prediction of loadability margins to predict the loadability margins from any stable operating point along arbitrary loading directions through

  12. Radiation Safety Training Basic Radiation Safety Training for

    E-Print Network [OSTI]

    Dai, Pengcheng

    Radiation Safety Training Basic Radiation Safety Training for X-ray Users for Physics 461 & 462 Protocol Title: Basic Radiation Safety Training for X-ray Users Drafted By: Chris Millsaps, RSS Reviewers: ZB, TU, GS Purpose: To provide basic radiation safety training to the users of x-ray producing

  13. Safety Criteria and Safety Lifecycle for Artificial Neural Networks

    E-Print Network [OSTI]

    Kelly, Tim

    Safety Criteria and Safety Lifecycle for Artificial Neural Networks Zeshan Kurd, Tim Kelly and Jim. The paper also presents a safety lifecycle for artificial neural networks. This lifecycle focuses, knowledge. INTRODUCTION Artificial neural networks (ANNs) are used in many safety-related applications

  14. Laser Safety Management Policy Statement ............................................................................................................1

    E-Print Network [OSTI]

    Davidson, Fordyce A.

    Laser Safety Management Policy Statement...........................................................2 Laser Users.............................................................................................................2 Unit Laser Safety Officer (ULSO

  15. East Carolina University ENVIRONMENTAL SAFETY COMMITTEE

    E-Print Network [OSTI]

    as workers' compensation, accident prevention, industrial hygiene, occupational safety, fire and life safety

  16. Aviation Management and Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-15T23:59:59.000Z

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Cancels DOE O 440.2B. Admin Chg 1, dated 6-22-11, cancels DOE O 440.2C.

  17. Carbon Monoxide Safety Tips

    E-Print Network [OSTI]

    Shaw, Bryan W.; Garcia, Monica L.

    1999-07-26T23:59:59.000Z

    Protect yourself and your family from the deadly effects of carbon monoxide--a colorless, odorless poisonous gas. This publication describes the warning signs of carbon monoxide exposure and includes a home safety checklist....

  18. Dam Safety Regulation (Mississippi)

    Broader source: Energy.gov [DOE]

    The purpose of the Dam Safety Regulation is to ensure that all dams constructed in the state of Mississippi are permitted and thus do not potentially harm wildlife, water supplies and property. ...

  19. High Voltage Safety Act

    Broader source: Energy.gov [DOE]

    The purpose of the High Voltage Safety Act is to prevent injury to persons and property and interruptions of utility service resulting from accidental or inadvertent contact with high-voltage...

  20. Packaging and Transportation Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-09-27T23:59:59.000Z

    Establishes safety requirements for the proper packaging and transportation of offsite shipments and onsite transfers of hazardous materials andor modal transport. Cancels DOE 1540.2 and DOE 5480.3

  1. Packaging and Transportation Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-09-27T23:59:59.000Z

    Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Canceled by DOE 460.1A

  2. Packaging and Transportation Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-10-02T23:59:59.000Z

    Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1.

  3. Promulgating Nuclear Safety Requirements

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-05-15T23:59:59.000Z

    Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

  4. Reliability and Safety

    Broader source: Energy.gov [DOE]

    DOE solar reliability and safety research and development (R&D) focuses on testing photovoltaic (PV) modules, inverters, and systems for long-term performance, and helping investors, consumers,...

  5. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2015-01-26T23:59:59.000Z

    This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs).

  6. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2014-07-10T23:59:59.000Z

    The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

  7. Complete Experiment Safety Documentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, and Hazardous...

  8. Dam Safety (North Carolina)

    Broader source: Energy.gov [DOE]

    North Carolina Administrative Code Title 15A, Subchapter 2K lays out further regulations for the design, approval, construction, maintenance, and inspection of dams to ensure public safety and...

  9. Safety | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Argonne National Laboratory and the U.S. Department of Energy (DOE) are very concerned about the well-being of all employees. Students at the undergraduate and graduate...

  10. Safety in Buildings 

    E-Print Network [OSTI]

    Hutcheon, N. B.

    Building codes are essentially sets of safety regulations in respect of structure, fire, and health. They were originally developed in response to frequently demonstrated hazards of structural collapse, catastrophic fires, ...

  11. Nuclear Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

    The Nuclear Safety Division conducts a comprehensive nuclear power plant oversight review program of the nine reactors at the five nuclear power sites in Pennsylvania. It also monitors the...

  12. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-06-12T23:59:59.000Z

    The directive provides supplemental details to support the requirements of DOE O 452.2C, Nuclear Explosive Safety, dated 6-12-06. Canceled by DOE M 452.2-1A.

  13. Safety Basis Report

    SciTech Connect (OSTI)

    R.J. Garrett

    2002-01-14T23:59:59.000Z

    As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

  14. Radiation Safety Annual Refresher Training

    E-Print Network [OSTI]

    Thomas, David D.

    Radiation Safety Annual Refresher Training Radiation Protection Division Department of Environmental Health & Safety #12;Topics in Radiation Safety (applicable RPD Manual sections indicated) User;Topics in Radiation Safety (applicable RPD Manual sections indicated) User and Non-user topics Types

  15. Toolbox Safety Talk Lead Awareness

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Toolbox Safety Talk Lead Awareness Environmental Health & Safety Facilities Safety & Health Section Health & Safety for recordkeeping. Lead based paint is commonly found in homes built before 1978 and many industrial paints today still contain lead. Lead overexposure is one of the leading causes of workplace

  16. School of Forest Safety Training

    E-Print Network [OSTI]

    Thomas, Andrew

    ) · Laboratories: ­ Material Safety Data Sheets (MSDS) for chemicals ­ Chemical hygiene plan (CHP) manual

  17. Implementation of Stochastic Polynomials Approach in the RAVEN Code

    SciTech Connect (OSTI)

    Cristian Rabiti; Paul Talbot; Andrea Alfonsi; Diego Mandelli; Joshua Cogliati

    2013-10-01T23:59:59.000Z

    RAVEN, under the support of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, has been tasked to provide the necessary software and algorithms to enable the application of the conceptual framework developed by the Risk Informed Safety Margin Characterization (RISMC) [1] path. RISMC is one of the paths defined under the Light Water Reactor Sustainability (LWRS) DOE program.

  18. Mesozoic stratigraphy of northwestern Australian and northern Himalayan margins

    SciTech Connect (OSTI)

    Ogg, J.; Kopaskamerkel, D.C.

    1989-03-01T23:59:59.000Z

    The Mesozoic stratigraphies of the Himalayan margin, the Argo abyssal plain, and the Exmouth Plateau exhibit marked contrasts in their sedimentation histories. The sedimentary sequence on the northeastern Exmouth Plateau off Australia includes a Carnian to Rhaetian sequence of fluviodeltaic and marine clastics and carbonates, capped by a shallowing-upward sequence of platform carbonates overlain, with a major unconformity, by marine Aptian sediments deposited during rapid subsidence of the plateau. Argo abyssal plain basement is overlain by red-brown, bioturbated, inoceramid-rich quartzose claystones, bentonites, and quartz siltstones, dated by radiolarians and benthic foraminifera as lowest Cretaceous. This is overlain by red and green claystones and nannofossil chalks. The basal age indicates that sea-floor spreading began in the earliest Cretaceous, not Oxfordian as had been thought. In the Thakkola region of Nepal, uppermost Triassic through Lower Jurassic shelf and carbonate platform facies are capped by a ferruginous oolite deposit of latest Bathonian to earliest Callovian age. Sedimentation resumed in the middle Oxfordian with deposition of Berriasian( ) deep-water black organic-rich mud. Following a valanginian regression and progradation of terrigenous clastics, Aptian black shales were deposited. In geological studies of the northwestern Australian margin, the ubiquitous hiatus within the Callovian-Oxfordian has been termed the breakup unconformity. Existence of a similar-aged hiatus in the Himalayas on a margin which formed during the late Paleozoic, absence of any Jurassic on the Exmouth Plateau, and the apparent initiation of spreading in the Argo basin during the earliest Cretaceous suggest that this widespread unconformity is not associated with a continental breakup in these regions.

  19. Dangerous Liouville Wave -- exactly marginal but non-conformal deformation

    E-Print Network [OSTI]

    Chiu Man Ho; Yu Nakayama

    2008-07-26T23:59:59.000Z

    We give a non-trivially interacting field theory example of scale invariant but non-conformal field theory. The model is based on the exactly solvable Liouville field theory coupled with free scalars deformed by an exactly marginal operator. We show non-vanishing of the trace of the energy-momentum tensor by using the quantum Schwinger-Dyson equation for the Liouville field theory, which is a sophistication of the quantum higher equations of motion for the Liouville field theory introduced by Alyosha Zamolodchikov. Possibly dangerous implications for the super-critical string theory will be discussed.

  20. Margins in high temperature leak-before-break assessments

    SciTech Connect (OSTI)

    Budden, P.J.; Hooton, D.G.

    1997-04-01T23:59:59.000Z

    Developments in the defect assessment procedure R6 to include high-temperature mechanisms in Leak-before-Break arguments are described. In particular, the effect of creep on the time available to detect a leak and on the crack opening area, and hence leak rate, is discussed. The competing influence of these two effects is emphasized by an example. The application to Leak-before-Break of the time-dependent failure assessment diagram approach for high temperature defect assessment is then outlined. The approach is shown to be of use in assessing the erosion of margins by creep.

  1. Environment/Health/Safety (EHS): Laser Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8, 2000ConsumptionInnovationEnvironment, Safety andBerkeley LabERPEHS

  2. DOE explosives safety manual

    SciTech Connect (OSTI)

    Not Available

    1991-10-01T23:59:59.000Z

    The Department of Energy (DOE) policy requires that all DOE activities be conducted in a manner that protects the safety of the public and provides a safe and healthful workplace for employees. DOE has also prescribed that all personnel be protected in any explosives operation undertaken. The level of safety provided shall be at least equivalent to that of the best industrial practice. The risk of death or serious injury shall be limited to the lowest practicable minimum. DOE and contractors shall continually review their explosives operations with the aim of achieving further refinements and improvements in safety practices and protective features. This manual describes the Department's explosive safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives. It is intended to reflect the state-of-the-art in explosives safety. In addition, it is essential that applicable criteria and requirements for implementing this policy be readily available and known to those responsible for conducting DOE programs.

  3. Shock margin testing of a one-axis MEMS accelerometer.

    SciTech Connect (OSTI)

    Parson, Ted Blair; Tanner, Danelle Mary; Buchheit, Thomas Edward

    2008-07-01T23:59:59.000Z

    Shock testing was performed on a selected commercial-off-the-shelf - MicroElectroMechanical System (COTS-MEMS) accelerometer to determine the margin between the published absolute maximum rating for shock and the 'measured' level where failures are observed. The purpose of this testing is to provide baseline data for isolating failure mechanisms under shock and environmental loading in a representative device used or under consideration for use within systems and assemblies of the DOD/DOE weapons complex. The specific device chosen for this study was the AD22280 model of the ADXL78 MEMS Accelerometer manufactured by Analog Devices Inc. This study focuses only on the shock loading response of the device and provides the necessary data for adding influence of environmental exposure to the reliability of this class of devices. The published absolute maximum rating for acceleration in any axis was 4000 G for this device powered or unpowered. Results from this study showed first failures at 8000 G indicating a margin of error of two. Higher shock level testing indicated that an in-plane, but off-axis acceleration was more damaging than one in the sense direction.

  4. CASE STUDY FOR ENHANCED ACCIDENT TOLERANCE DESIGN CHANGES

    SciTech Connect (OSTI)

    Prescott, Steven [Idaho National Laboratory; Smith, Curtis [Idaho National Laboratory; Tony Koonce

    2014-09-01T23:59:59.000Z

    The ability to better characterize and quantify safety margin is important to improved decision making about Light Water Reactor (LWR) design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the Risk Informed Safety Margin Characterization (RISMC) Pathway provides methods and tools that enable mitigation options known as risk informed margins management (RIMM) strategies. The methods and tools provided by RISMC are essential to a comprehensive and integrated RIMM approach that supports effective preservation of margin for both active and passive SSCs. In this report, we discuss the methods and technologies behind RIMM for an application focused on enhanced accident tolerance design changes for a representative nuclear power plant. We look at a variety of potential plant modifications and evaluate, using the RISMC approach, the implications to safety margin for the various strategies.

  5. Seismic Safety Guide

    SciTech Connect (OSTI)

    Eagling, D.G. (ed.)

    1983-09-01T23:59:59.000Z

    This guide provides managers with practical guidelines for administering a comprehensive earthquake safety program. The Guide is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, evaluation and rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, special considerations related to shielding blocks, non-structural elements, lifelines, fire protection and emergency facilities. Management of risk and liabilities is also covered. Nuclear facilities per se are not dealt with specifically. The principles covered also apply generally to nuclear facilities but the design and construction of such structures are subject to special regulations and legal controls.

  6. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguardsUpdates >-SafetySafety

  7. Safety in Numbers

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR EMaterials (CRM)SafetySafety

  8. Safety aspects of EB melting

    SciTech Connect (OSTI)

    Hainz, L.C. [Hainz Engineering Services, Inc., Albany, OR (United States)

    1994-12-31T23:59:59.000Z

    Electron Beam melting technology, along with other vacuum metallurgical technologies, requires special attention to safety involving operation and maintenance of the EB furnace and systems. Although the EB industry has been relatively accident free, the importance of safety awareness and compliance becomes increasingly important. It is very important to provide a safe work environment for employees and economically important to protect the equipment from damage and potential downtime. Safety and accident prevention directly affects overhead costs by keeping accident insurance rates at a minimum. Routine safety requirements will be reviewed and safety aspects requiring extra attention will be addressed. Safety improvements and experiences of furnace users will be shared as examples.

  9. An Overview of the Safety Case for Small Modular Reactors

    SciTech Connect (OSTI)

    Ingersoll, Daniel T [ORNL] [ORNL

    2011-01-01T23:59:59.000Z

    Several small modular reactor (SMR) designs emerged in the late 1970s and early 1980s in response to lessons learned from the many technical and operational challenges of the large Generation II light-water reactors. After the accident at the Three Mile Island plant in 1979, an ensuing reactor redesign effort spawned the term inherently safe designs, which later evolved into passively safe terminology. Several new designs were engineered to be deliberately small in order to fully exploit the benefits of passive safety. Today, new SMR designs are emerging with a similar philosophy of offering highly robust and resilient designs with increased safety margins. Additionally, because these contemporary designs are being developed subsequent to the September 11, 2001, terrorist attack, they incorporate a number of intrinsic design features to further strengthen their safety and security. Several SMR designs are being developed in the United States spanning the full spectrum of reactor technologies, including water-, gas-, and liquid-metal-cooled ones. Despite a number of design differences, most of these designs share a common set of design principles to enhance plant safety and robustness, such as eliminating plant design vulnerabilities where possible, reducing accident probabilities, and mitigating accident consequences. An important consequence of the added resilience provided by these design approaches is that the individual reactor units and the entire plant should be able to survive a broader range of extreme conditions. This will enable them to not only ensure the safety of the general public but also help protect the investment of the owner and continued availability of the power-generating asset. Examples of typical SMR design features and their implications for improved plant safety are given for specific SMR designs being developed in the United States.

  10. Nuclear Safety Information Dashboard | Department of Energy

    Office of Environmental Management (EM)

    Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard The Nuclear Safety Information (NSI) Dashboard provides a new user interface to the Occurrence Reporting...

  11. Safety Interlocks Group - Advanced Photon Source

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Info APS Safety Page ESH Safety Manual Safety Interlocks Systems ACIS PSS FEEPS BLEPS UPS Division Links APS Organization Chart Beamlines Directory APS Engineering Support...

  12. Nuclear Explosive Safety Manual - DOE Directives, Delegations...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1A Admin Chg 1, Nuclear Explosive Safety Manual by Carl Sykes Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Nuclear Safety,...

  13. Radiation Safety Training Basic Radiation Safety Training for

    E-Print Network [OSTI]

    Dai, Pengcheng

    Radiation Safety Training Basic Radiation Safety Training for Sealed Source Users for Physics 461 Protocol Title: Training for Sealed Source Users Drafted By: Chris Millsaps, RSS Reviewers: ZB, TU, GS Purpose: To provide basic radiation safety training to the users of sealed sources located

  14. SAFETY PROCEDURE & GUIDELINES SUBJECT: Health and Safety Training

    E-Print Network [OSTI]

    Sinnamon, Gordon J.

    SAFETY PROCEDURE & GUIDELINES SUBJECT: Health and Safety Training APPLIES TO: All Departments that the health and safety training program is effective and is in compliance with the applicable federal for conducting training Establish who is responsible for determining the level and type of training required

  15. Radiation Safety Manual Dec 2012 Page 1 RADIATION SAFETY

    E-Print Network [OSTI]

    Grishok, Alla

    of External and Internal Doses E. Reports and Notices to Workers Chapter VII: Radiation ProtectionRadiation Safety Manual ­ Dec 2012 Page 1 RADIATION SAFETY MANUAL For Columbia University NewYork-Presbyterian Hospital New York State Psychiatric Institute Barnard College December 2012 #12;Radiation Safety Manual

  16. Safety and Security What do Safety/Security work with?

    E-Print Network [OSTI]

    Safety and Security on campus #12;Agenda · What do Safety/Security work with? · If something happens · Opening hours · Remember · Website · How to find us #12;The Section for Safety and Security work with; · Security revolving work environment · Handle locks, keys, alarms, surveillance · Responsible

  17. Software Safety Tutorial Status Update 1 Software Safety Tutorial

    E-Print Network [OSTI]

    Tian, Jeff

    Software Safety Tutorial Status Update 1 Software Safety Tutorial (Status Update) Jeff Tian, tian@engr.smu.edu CSE, SMU, Dallas, TX 75275 Topics · Project Overview · Software Safety Overview · Project Tasks competency for real-time software engineers. · Project team: Jeff Tian (SMU): Basics of SSE D.T. Huynh

  18. Safety Lifecycle for Developing Safety Critical Artificial Neural Networks

    E-Print Network [OSTI]

    Kelly, Tim

    Safety Lifecycle for Developing Safety Critical Artificial Neural Networks Zeshan Kurd, Tim Kelly.kelly}@cs.york.ac.uk Abstract. Artificial neural networks are employed in many areas of industry such as medicine and defence a safety lifecycle for artificial neural networks. The lifecycle fo- cuses on managing behaviour

  19. Local Safety Committee Engineering

    E-Print Network [OSTI]

    Saskatchewan, University of

    Minutes Local Safety Committee Name of Committee Engineering Worksite Mailing Address & Postal Code. Ventilation fume hoods V. Bendig and FMD report that an uninterrupted power supply will be attached to the ventilation control panel the week of Dec. 9. Action: T. Zintel and L. Harder will conduct a test the first

  20. Integrated Safety Management

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-04-25T23:59:59.000Z

    The order ensures that DOE/NNSA, systematically integrates safety into management and work practices at all levels, so that missions are accomplished efficiently while protecting the workers, the public, and the environment. Cancels DOE M 450.4-1 and DOE M 411.1-1C

  1. Nuclear Explosive Safety Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14T23:59:59.000Z

    This Department of Energy (DOE) Manual provides supplemental details on selected topics to support the requirements of DOE O 452.2D, Nuclear Explosive Safety, dated 4/14/09. Cancels DOE M 452.2-1. Admin Chg 1, dated 7-10-13, cancels DOE M 452.2-1A.

  2. Safety & Environmental Protection Services

    E-Print Network [OSTI]

    Glasgow, University of

    of care in waste storage and disposal is available on Safety and Environmental Protection Service's (SEPS sustainably and to protect the environment and, in line with this, recycles waste wherever practicable to biological properties). In addition some activities produce radioactive waste. Radioactive waste

  3. Packaging and Transportation Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2003-04-04T23:59:59.000Z

    To establish safety requirements for the proper packaging and transportation of Department of Energy (DOE)/National Nuclear Security Administration (NNSA) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1A. Canceled by DOE O 460.1C.

  4. DOE Explosives Safety Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-01-09T23:59:59.000Z

    The Manual describes the Departments explosive safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives. Cancels DOE M 440.1-1. Canceled by DOE O 440.1B Chg 1.

  5. Packaging and Transportation Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-05-14T23:59:59.000Z

    The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of radioactive and other hazardous materials and for modal transportation. Cancels DOE O 460.1B, 5-14-10

  6. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-06-12T23:59:59.000Z

    The directive establishes specific nuclear explosive safety (NES) program requirements to implement the DOE NES standards and other NES criteria for routine and planned nuclear explosive operations. Cancels DOE O 452.2B. Canceled by DOE O 452.2D.

  7. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14T23:59:59.000Z

    This Order establishes requirements to implement the nuclear explosive safety elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations. Cancels DOE O 452.2C. Admin Chg 1, 7-10-13

  8. Nuclear Explosive Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14T23:59:59.000Z

    This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs). Cancels DOE O 452.2C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.2D.

  9. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11T23:59:59.000Z

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature.

  10. Module Safety Issues (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2012-02-01T23:59:59.000Z

    Description of how to make PV modules so that they are less likely to turn into safety hazards. Making modules inherently safer with minimum additional cost is the preferred approach for PV. Safety starts with module design to ensure redundancy within the electrical circuitry to minimize open circuits and proper mounting instructions to prevent installation related ground faults. Module manufacturers must control the raw materials and processes to ensure that that every module is built like those qualified through the safety tests. This is the reason behind the QA task force effort to develop a 'Guideline for PV Module Manufacturing QA'. Periodic accelerated stress testing of production products is critical to validate the safety of the product. Combining safer PV modules with better systems designs is the ultimate goal. This should be especially true for PV arrays on buildings. Use of lower voltage dc circuits - AC modules, DC-DC converters. Use of arc detectors and interrupters to detect arcs and open the circuits to extinguish the arcs.

  11. Seismic margin review of the Maine Yankee Atomic Power Station: Fragility analysis

    SciTech Connect (OSTI)

    Ravindra, M. K.; Hardy, G. S.; Hashimoto, P. S.; Griffin, M. J.

    1987-03-01T23:59:59.000Z

    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants.

  12. Maximum Margin Clustering for State Decomposition of Metastable Systems

    E-Print Network [OSTI]

    Wu, Hao

    2015-01-01T23:59:59.000Z

    When studying a metastable dynamical system, a prime concern is how to decompose the phase space into a set of metastable states. Unfortunately, the metastable state decomposition based on simulation or experimental data is still a challenge. The most popular and simplest approach is geometric clustering which is developed based on the classical clustering technique. However, the prerequisites of this approach are: (1) data are obtained from simulations or experiments which are in global equilibrium and (2) the coordinate system is appropriately selected. Recently, the kinetic clustering approach based on phase space discretization and transition probability estimation has drawn much attention due to its applicability to more general cases, but the choice of discretization policy is a difficult task. In this paper, a new decomposition method designated as maximum margin metastable clustering is proposed, which converts the problem of metastable state decomposition to a semi-supervised learning problem so that...

  13. Nuclear Explosive Safety Evaluation Processes

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14T23:59:59.000Z

    This Manual provides supplemental details to support the nuclear explosive safety evaluation requirement of DOE O 452.2D, Nuclear Explosive Safety. Does not cancel other directives. Admin Chg 1, 7-10-13.

  14. Gas Pipeline Safety (West Virginia)

    Broader source: Energy.gov [DOE]

    The Gas Pipeline Safety Section of the Engineering Division is responsible for the application and enforcement of pipeline safety regulations under Chapter 24B of the West Virginia Code and 49 U.S...

  15. Nuclear Engineering Nuclear Criticality Safety

    E-Print Network [OSTI]

    Kemner, Ken

    development, Nuclear Operations Division (NOD) waste management and storage activities and other laboratoryNuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear

  16. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

    COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212-305-0303 F: 212: _______________ * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * Radiation Safety Office Approval: ______________________ Date: ________________________ Waste containers in place: Yes ___ No ___ Radiation signage on door: Yes ___ No ___ Room monitoring: Dates

  17. Radiation Safety (Revised March 2010)

    E-Print Network [OSTI]

    Kay, Mark A.

    to Workers; Inspections 27 10 CFR Part 20Standards for Protection Against Radiation 28 10 CFR Part 35Radiation Safety Manual (Revised March 2010) Updated December 2012 Stanford University, Stanford California #12; #12; Radiation Safety Manual (Revised March 2010) Updated

  18. ANNUAL SECURITY FIRE SAFETY REPORT

    E-Print Network [OSTI]

    ANNUAL SECURITY AND FIRE SAFETY REPORT OCTOBER 1, 2013 DARTMOUTH COLLEGE http://www.dartmouth.edu/~security/ #12;1 Table of Contents MESSAGE FROM THE DIRECTOR OF SAFETY AND SECURITY................................................................................................................................................................... 7 ANNUAL SECURITY REPORT

  19. TUFTS UNIVERSITY LASER SAFETY PROGRAM

    E-Print Network [OSTI]

    Dennett, Daniel

    with laser safety regulations promulgated by state, federal, and local agencies. The LSO administers and Maximum Permissible Exposures 12 X. Electrical Hazards 12 XI. General Safety Procedures 13 XII. Laser

  20. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    SciTech Connect (OSTI)

    GARVIN, L J; JENSEN, M A

    2004-04-13T23:59:59.000Z

    This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

  1. A margin based approach to determining sample sizes via tolerance bounds.

    SciTech Connect (OSTI)

    Newcomer, Justin T.; Freeland, Katherine Elizabeth

    2013-09-01T23:59:59.000Z

    This paper proposes a tolerance bound approach for determining sample sizes. With this new methodology we begin to think of sample size in the context of uncertainty exceeding margin. As the sample size decreases the uncertainty in the estimate of margin increases. This can be problematic when the margin is small and only a few units are available for testing. In this case there may be a true underlying positive margin to requirements but the uncertainty may be too large to conclude we have sufficient margin to those requirements with a high level of statistical confidence. Therefore, we provide a methodology for choosing a sample size large enough such that an estimated QMU uncertainty based on the tolerance bound approach will be smaller than the estimated margin (assuming there is positive margin). This ensures that the estimated tolerance bound will be within performance requirements and the tolerance ratio will be greater than one, supporting a conclusion that we have sufficient margin to the performance requirements. In addition, this paper explores the relationship between margin, uncertainty, and sample size and provides an approach and recommendations for quantifying risk when sample sizes are limited.

  2. Rapid assessment of redevelopment potential in marginal oil fields, application to the cut bank field 

    E-Print Network [OSTI]

    Chavez Ballesteros, Luis Eladio

    2005-02-17T23:59:59.000Z

    Quantifying infill potential in marginal oil fields often involves several challenges. These include highly heterogeneous reservoir quality both horizontally and vertically, incomplete reservoir databases, considerably ...

  3. Comment on Thompson's "Complexity, Diminishing Marginal Returns and Serial Mesopotamian Fragmentation."

    E-Print Network [OSTI]

    White, Douglas R.

    Comment on Thompson's "Complexity, Diminishing Marginal Returns and Serial Mesopotamian and correlations of Thompson's Figure 5 and redraws the figure to highlight the feedback loop versus the large

  4. CONSTRUCTION SAFETY MANUAL ADMINISTRATIVE POLICIES

    E-Print Network [OSTI]

    Knowles, David William

    Revised 06/10 10.1 Subcontractor Safety Policy 10.2 Scope 10.2.1 General 10.2.2 Department of Energy 10 the integration of safety management into all construction processes. Project managers, construction managers.7 Engineered Protective Systems 10.8 Procurement of Hazardous Material 10.9 Safety Training and Education 10

  5. Toolbox Safety Talk Heat Stress

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Toolbox Safety Talk Heat Stress Environmental Health & Safety Facilities Safety & Health Section for inducing heat stress. When the body is unable to cool itself by sweating, several heat-induced illnesses Stress · Know signs/symptoms of heat-related illnesses; monitor yourself and coworkers. · Block out

  6. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

    COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212-305-0303 F: 212-305-0318 rso-clinical@columbia by more than 50 percent. #12;COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212 ________________________________________________________ ________________________________________________________ #12;COLUMBIA UNIVERSITY Radiation Safety Program Medical Center - T: 212-305-0303 F: 212-305-0318 rso-clinical@columbia

  7. pamphlet04.doc SAFETY INFORMATION

    E-Print Network [OSTI]

    Oliver, Douglas L.

    to emergencies such as fire, chemical spill, electrical outage, communication system failure, etc. 2. RESEARCH Drugs 8 Communication Systems 9 Compliance Issues 10 Compressed Gas Cylinders 11 Electrical Safety 12 Electrical Power Failure 13 Emergency Procedures 14 Fire Safety 15 Hazard Reporting 16 Laser Safety 17

  8. Health and Safety Training Reciprocity

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2014-04-14T23:59:59.000Z

    Establishes a policy for reciprocity of employee health and safety training among DOE entities responsible for employee health and safety at DOE sites and facilities to increase efficiency and effectiveness of Departmental operations while meeting established health and safety requirements. Does not cancel other directives.

  9. Events Beyond Design Safety Basis Analysis

    Broader source: Energy.gov [DOE]

    This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. [Safety Bulletin 2011-01

  10. Accident tolerant fuel analysis

    SciTech Connect (OSTI)

    Smith, Curtis [Idaho National Laboratory; Chichester, Heather [Idaho National Laboratory; Johns, Jesse [Texas A& M University; Teague, Melissa [Idaho National Laboratory; Tonks, Michael Idaho National Laboratory; Youngblood, Robert [Idaho National Laboratory

    2014-09-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced ''RISMC toolkit'' that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional ''accident-tolerant'' (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  11. Accident Tolerant Fuel Analysis

    SciTech Connect (OSTI)

    Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

    2014-09-01T23:59:59.000Z

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

  12. Enhancing Railroad Hazardous Materials Transportation Safety...

    Office of Environmental Management (EM)

    Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Presentation made by Kevin...

  13. Independent Oversight Focused Safety Management Evaluation, Idaho...

    Office of Environmental Management (EM)

    Focused Safety Management Evaluation, Idaho National Engineering and Environmental Laboratory - January 2001 Independent Oversight Focused Safety Management Evaluation, Idaho...

  14. Unreviewed Safety Question Determination - Processing Waste in...

    Office of Environmental Management (EM)

    Unreviewed Safety Question Determination - Processing Waste in the Waste Characterization Glovebox Unreviewed Safety Question Determination - Processing Waste in the Waste...

  15. The Front Lines of Patient Safety

    E-Print Network [OSTI]

    Soloveichik, David

    patient safety · Incident Reporting · Root Cause Analysis · FMEA · Culture of Patient Safety Survey

  16. Safety First Safety Last Safety Always Summer in Minnesota means high humidity and sunny, hot

    E-Print Network [OSTI]

    Minnesota, University of

    Safety First Safety Last Safety Always Summer in Minnesota means high humidity and sunny, hot days. · Heat stroke is life threatening! Symptoms include high body temperature, red and dry skin, rapid before you get thirsty. Adequate fluid intake is the biggest key. Cool (not ice cold) water is the best

  17. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01T23:59:59.000Z

    A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

  18. Safety review advisor

    SciTech Connect (OSTI)

    Boshers, J.A.; Alguindigue, I.E.; Uhrig, R.E. (Tennessee Univ., Knoxville, TN (USA). Dept. of Nuclear Engineering); Burnett, C.G. (Tennessee Valley Authority, Knoxville, TN (USA))

    1989-01-01T23:59:59.000Z

    The University of Tennessee's Nuclear Engineering Department, in cooperation with the Tennessee Valley Authority (TVA), is evaluating the feasibility of utilizing an expert system to aid in 10CFR50.59 evaluations. This paper discusses the history of 10CFR50.59 reviews, and details the development approach used in the construction of a prototype Safety Review Advisor (SRA). The goals for this expert system prototype are to (1) aid the engineer in the evaluation process by directing his attention to the appropriate critical issues, (2) increase the efficiency, consistency, and thoroughness of the evaluation process, and (3) provide a foundation of appropriate Safety Analysis Report (SAR) references for the reviewer. 6 refs., 2 figs.

  19. Mars mission safety

    SciTech Connect (OSTI)

    Buden, D. (EG G Idaho, Idaho Falls (USA))

    1989-06-01T23:59:59.000Z

    Precautions that need to be taken to assure safety on a manned Mars mission with nuclear thermal propulsion are briefly considered. What has been learned from the 1955 SNAP-10A operation of a nuclear reactor in space and from the Rover/NERVA project is reviewed. The ways that radiation hazards can be dealt with at various stages of a Mars mission are examined.

  20. Health and safety

    SciTech Connect (OSTI)

    Snyder, K. (Mine Safety and Health Administration (US))

    1990-05-01T23:59:59.000Z

    This article discusses health and safety in coal mines and the primary issues in this area during 1989. Particular attention is given to the employment figures as well as the fatality statistics. According to this article, employment was up during 1989 to approximately 164,000 workers as compared to 136,000 in 1969. Attention is also given to dealing with coal mining regulations as well as a crackdown on illegal operators in the industry.

  1. Safety study application guide. Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly {open_quotes}low{close_quotes}) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, {open_quotes}Technical Safety Requirements,{close_quotes} and 5480.23, {open_quotes}Nuclear Safety Analysis Reports.{close_quotes} A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis.

  2. The Case for Increasing Enrollment and Leveraging Marginal Costs: CSUN Case Study

    E-Print Network [OSTI]

    Shubin, Carol

    The Case for Increasing Enrollment and Leveraging Marginal Costs: CSUN Case Study H. Hellenbrand1 will estimate the marginal cost for increasing enrollment from a theoretical point of view. This analysis will use data from the IPEDS data base and formulae for replacement costs suggested by the Legislative

  3. Faunal responses to oxygen gradients on the Pakistan margin: A comparison of foraminiferans, macrofauna and megafauna

    E-Print Network [OSTI]

    Levin, Lisa

    Faunal responses to oxygen gradients on the Pakistan margin: A comparison of foraminiferans Oxygen minimum zone Benthos Arabian Sea Biodiversity Deep sea a b s t r a c t The Pakistan Margin where oxygen levels were lowest. The rarity of larger animals between 300 and 700 m on the Pakistan

  4. ELSEVIER Geomorphology 14 (1995) 109-121 Hypsometric forcing of stagnant ice margins: Pleistocene valley

    E-Print Network [OSTI]

    Small, Eric

    1995-01-01T23:59:59.000Z

    ELSEVIER Geomorphology 14 (1995) 109-121 Hypsometric forcing of stagnant ice margins: Pleistocene December 1994 Abstract Topographic and sedimentological evidence indicates that stagnant ice conditions position for a stagnant ice margin to develop during valley glacier retreat. In the first model, valley

  5. The Continental Margin is a Key Source of Iron to the HNLC North Pacific Ocean

    E-Print Network [OSTI]

    The Continental Margin is a Key Source of Iron to the HNLC North Pacific Ocean Phoebe J. Lam1 concentrations in the upper 500m of the Western Subarctic Pacific, an iron-limited High Nutrient Low Chlorophyll a key source of bioavailable Fe to the HNLC North Pacific. Keywords: iron, continental margin, HNLC 1

  6. Improvement of LWR thermal margins by introducing thorium Cheuk Wah Lau a,*, Christophe Demazire a

    E-Print Network [OSTI]

    Demazière, Christophe

    Improvement of LWR thermal margins by introducing thorium Cheuk Wah Lau a,*, Christophe Demazière Keywords: Thorium PWR Thermal margins Transport calculations a b s t r a c t The use of thorium pins contain a mixture of uranium and thorium oxides, while a few fuel pins contain a mixture between

  7. Ranking Structured Documents: A Large Margin Based Approach for Patent Prior Art Search

    E-Print Network [OSTI]

    Gomes, Carla P.

    Ranking Structured Documents: A Large Margin Based Approach for Patent Prior Art Search Yunsong Guo propose an approach for automatically rank- ing structured documents applied to patent prior art search. Our model, SVM Patent Ranking (SVMP R) incorporates margin constraints that di- rectly capture

  8. Correlation of PDN Impedance with Jitter and Voltage Margin for High Speed Channels

    E-Print Network [OSTI]

    Swaminathan, Madhavan

    Correlation of PDN Impedance with Jitter and Voltage Margin for High Speed Channels Vishal Laddha vishal.laddha@gatech.edu, madhavan.swaminathan@ece.gatech.edu Abstract: Timing margin (jitter and plane cutouts is a major source of jitter and noise introduced by the package and the printed circuit

  9. Evaluation of Travis Peak gas reservoirs, west margin of the East Texas Basin

    E-Print Network [OSTI]

    Li, Yamin

    2009-05-15T23:59:59.000Z

    for basinward extension of Travis Peak gas production along the west margin of the East Texas Basin. Along the west margin of the East Texas Basin, southeast-trending Travis Peak sandstones belts were deposited by the Ancestral Red River fluvial-deltaic system...

  10. Structural development of the western margins of the Sirte basin

    SciTech Connect (OSTI)

    Anketell, J.M.; Kumati, S.M.

    1988-08-01T23:59:59.000Z

    The Sirte basin, situated in north-central Libya, is a broad, northwest-trending embayment comprising a complex of small horsts and grabens. The basin was initiated in the early Cretaceous by collapse of the Tibisti-Sirte arch and underwent further faulting, notably in Late Cretaceous to early paleocene time and during the latter part of the Eocene. Throughout the greater part of the region, faults are obscured by Neogene cover; however, west of the Dahra-Hofra horst they are exposed. The last major phase of faulting in this region is late Lutetian to early Priabonian in age with minor reactivation during Oligocene and Miocene time. A phase of intra-Lutetian movement is also recognized. Following deposition of open marine limestones and chalks in the early Lutetian, the region was tilted toward the east-northeast with emergence and development of a complex system of east-flowing drainage channels which sculpted the emerging surface. The channels are wide but shallow, ranging up to 2 km wide and 10 m deep. This phase of movement and intraformational erosion was terminated by slow subsidence and/or transgression with development of restricted marine shales. The late Eocene faults which delineate the western margin of the Dahra horst throw down to the west and display a complex en echelon pattern. They are interpreted in terms of Riedel shear mechanics related to oblique-slip reactivation of basement shears. Counterclockwise orientation of the shears indicates they formed in response to sinistral slip.

  11. Development of a hybrid margin angle controller for HVDC continuous operation

    SciTech Connect (OSTI)

    Sato, M. [Kansai Electric Power Co., Osaka (Japan)] [Kansai Electric Power Co., Osaka (Japan); Yamaji, K. [Shikoku Electric Power Co., Takamatsu (Japan)] [Shikoku Electric Power Co., Takamatsu (Japan); Sekita, M. [Electric Power Development Co., Tokyo (Japan)] [Electric Power Development Co., Tokyo (Japan); Amano, M.; Nishimura, M.; Konishi, H.; Oomori, T. [Hitachi, Ltd. (Japan)] [Hitachi, Ltd. (Japan)

    1996-11-01T23:59:59.000Z

    The objective of this paper is to present a new hybrid margin angle control method for HVDC continuous operation under AC system fault conditions. For stable continuous operation of HVDC systems, the margin angle controller must be designed to maintain the necessary margin angle to avoid commutation failures. The proposed method uses the open loop margin angle controller (MAC) as the basic controller, and adds output from the closed loop MAC to correct the control angle. A fast voltage detection algorithm is used for open loop control, and margin angle reference correction using harmonics detection for closed loop control are also developed. The combination of open and closed loop control provides quick responses when faults occur with stable and speedy recovery after fault clearance. The effectiveness of the developed controller is confirmed through EMTP digital simulations and also with the experiments using an analogue simulator.

  12. Manager, Digital Developer Risk & Information Management Group

    E-Print Network [OSTI]

    Plotkin, Joshua B.

    server · Deep understanding of the Web technology stack (TCP/IP, HTTP, HTML, XHTML, XML, JavaScript, CSS with at least one web programming languages such as Python, PHP, C/C++, C#, Ruby, or Java, especially on web, or other Web 2.0 solutions · Experience in machine learning, information retrieval, large-scale data mining

  13. Risk Informing the Commercial Nuclear Enterprise

    E-Print Network [OSTI]

    Bernstein, Joseph B.

    % Moderate 50% VeryLikely 95% Likely 80% Remote 20% CriticalInsignificant Minor Significant Major Impact Post-Fukushima Response New NRC Regulations EPA Cooling Water Intake regulation GSI 191 4 Cyber and MD sites Regulatory Critical Remote Low Industry proposing alternatives to federal and state EPA Key

  14. Policies,Safety&U Annual Security and Fire Safety Report

    E-Print Network [OSTI]

    Lee, Dongwon

    ................................................................................ 5 ABOUT THE PENN STATE HARRISBURG SAFETY AND POLICE SERVICES ..... 5 Role, Authority, and Training .................................................................... 7 SECURITY OF and ACCESS TO PENN STATE HARRISBURG FACILITIES ........ 8 Special Considerations

  15. Preliminary Safety Analysis Report (PSAR), The NSLS 200 MeV Linear Electron Accelerator

    SciTech Connect (OSTI)

    Blumberg, L.N.; Ackerman, A.I.; Dickinson, T.; Heese, R.N.; Larson, R.A.; Neuls, C.W.; Pjerov, S.; Sheehan, J.F.

    1993-06-15T23:59:59.000Z

    The radiological, fire and electrical hazards posed by a 200 MeV electron Linear Accelerator, which the NSLS Department will install and commission within a newly assembled structure, are addressed in this Preliminary Safety Analysis Report. Although it is clear that this accelerator is intended to be the injector for a future experimental facility, we address only the Linac in the present PSAR since neither the final design nor the operating characteristics of the experimental facility are known at the present time. The fire detection and control system to be installed in the building is judged to be completely adequate in terms of the marginal hazard presented - no combustible materials other than the usual cabling associated with such a facility have been identified. Likewise, electrical hazards associated with power supplies for the beam transport magnets and accelerator components such as the accelerator klystrons and electron gun are classified as marginal in terms of potential personnel injury, cost of equipment lost, program downtime and public impact perceptions as defined in the BNL Environmental Safety and Health Manual and the probability of occurrence is deemed to be remote. No unusual features have been identified for the power supplies or electrical distribution system, and normal and customary electrical safety standards as practiced throughout the NSLS complex and the Laboratory are specified in this report. The radiation safety hazards are similarly judged to be marginal in terms of probability of occurrence and potential injury consequences since, for the low intensity operation proposed - a factor of 25 less than the maximum Linac capability specified by the vendor - the average beam power is only 0.4 watts. The shielding specifications given in this report will give adequate protection to both the general public and nonradiation workers in areas adjacent to the building as well as radiation workers within the controlled access building.

  16. Lawn Maintenance Safety

    E-Print Network [OSTI]

    Smith, David

    2005-07-12T23:59:59.000Z

    debris and noise. ? Allow the engine to cool before returning it to a storage shed. ? Turn the power off and disconnect the spark plug wire before cleaning, inspecting, adjusting or repairing the cutting blade. Lawn Maintenance Safety ? Don?t run a... as possible to avoid being hit by passing vehicles. ? Never leave an electric- or gas-powered edger plugged in or running while unattended. ? Unplug or turn off an electric or gas-powered edger before inspecting, cleaning, adjusting or replacing the blade...

  17. Perspectives on reactor safety

    SciTech Connect (OSTI)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  18. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting theCommercialization and Innovation2010 2010AboutComplete Safety Training

  19. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting theCommercialization and Innovation2010 2010AboutComplete Safety

  20. Nuclear Safety Regulatory Framework

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin of Contamination in ManyDepartment of Energy NorthBDepartment of Energy Nuclear Safety

  1. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguardsUpdates >-Safety for

  2. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguardsUpdates >-Safety

  3. Safety | Department of Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguardsUpdatesis the FirstSafety

  4. Sandia Energy - Transportation Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del Sol Home DistributionTransportation Safety Home Stationary Power Nuclear Fuel Cycle

  5. Integrated Safety Management Policy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122Commercial602 1,39732on ArmedManufacturing | DepartmentINTEGRATED SAFETY MANAGEMENT

  6. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch > TheNuclear Press ReleasesIn theTreatmentSRSSafety The NuclearSafety for

  7. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch > TheNuclear Press ReleasesIn theTreatmentSRSSafety The NuclearSafety for

  8. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power Administration would like submit the followingthMeasurements |CompetitiveComplete Safety

  9. SSRL Safety Office Memo

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR E Q U E N C4Safety Office SSO

  10. Safety Staff Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR EMaterials (CRM) | U.S.Safety

  11. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR EMaterials (CRM)Safety for

  12. Safety for Users

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR EMaterials (CRM)Safety

  13. ARM - ARM Safety Policy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearchSOLICITATIONIMODI FICATION OF CONTRACTOperationsYearSafety Policy About

  14. Health & Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cn SunnybankD.jpgHanford LEED&soilASTI-SORTIHealth & Safety Health

  15. Material Safety Data Sheet

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHighand Retrievals from a New 183-GHzMAR Os2010Material Safety Data Sheet

  16. Nuclear explosive safety study process

    SciTech Connect (OSTI)

    NONE

    1997-01-01T23:59:59.000Z

    Nuclear explosives by their design and intended use require collocation of high explosives and fissile material. The design agencies are responsible for designing safety into the nuclear explosive and processes involving the nuclear explosive. The methodology for ensuring safety consists of independent review processes that include the national laboratories, Operations Offices, Headquarters, and responsible Area Offices and operating contractors with expertise in nuclear explosive safety. A NES Study is an evaluation of the adequacy of positive measures to minimize the possibility of an inadvertent or deliberate unauthorized nuclear detonation, high explosive detonation or deflagration, fire, or fissile material dispersal from the pit. The Nuclear Explosive Safety Study Group (NESSG) evaluates nuclear explosive operations against the Nuclear Explosive Safety Standards specified in DOE O 452.2 using systematic evaluation techniques. These Safety Standards must be satisfied for nuclear explosive operations.

  17. On the Criticality Safety of Transuranic Sodium Fast Reactor Fuel Transport Casks

    SciTech Connect (OSTI)

    Samuel Bays; Ayodeji Alajo

    2010-05-01T23:59:59.000Z

    This work addresses the neutronic performance and criticality safety issues of transport casks for fuel pertaining to low conversion ratio sodium cooled fast reactors, conventionally known as Advanced Burner Reactors. The criticality of a one, three, seven and 19-assembly cask capacity is presented. Both dry “helium” and flooded “water” filled casks are considered. No credit for fuel burnup or fission products was assumed. As many as possible of the conservatisms used in licensing light water reactor universal transport casks were incorporated into this SFR cask criticality design and analysis. It was found that at 7-assemblies or more, adding moderator to the SFR cask increases criticality margin. Also, removal of MAs from the fuel increases criticality margin of dry casks and takes a slight amount of margin away for wet casks. Assuming credit for borated fuel tube liners, this design analysis suggests that as many as 19 assemblies can be loaded in a cask if limited purely by criticality safety. If no credit for boron is assumed, the cask could possibly hold seven assemblies if low conversion ratio fast reactor grade fuel and not breeder reactor grade fuel is assumed. The analysis showed that there is a need for new cask designs for fast reactors spent fuel transportation. There is a potential of modifying existing transportation cask design as the starting point for fast reactor spent fuel transportation.

  18. Skid-Steer Loader Safety

    E-Print Network [OSTI]

    Smith, David

    2005-06-28T23:59:59.000Z

    -steer loaders have been used in the construc- tion and landscaping industry for years. They are also common on dairy, beef and swine operations. Unlike conventional tractors, these compact and maneuverable machines allow farmers to enter narrow alleyways... the automatic safety switches. Machine Safeguards Using and maintaining manufacturer-installed safety devices will eliminate many skid-loader injuries and fatalities. Occupational Safety and Health Administration (OSHA) regulations and industry standards...

  19. Response margins of the dynamic analysis of piping systems

    SciTech Connect (OSTI)

    Johnson, J.J.; Benda, B.J.; Chuang, T.Y.; Smith, P.D.

    1984-04-01T23:59:59.000Z

    This report is organized as follows: Section 2 describes the three piping systems of the Zion nuclear power plant which formed the basis of the present study. The auxiliary feedwater (AFW) piping from steam generator to containment, the residual heat removal (RHR) and safety injection piping in the auxiliary building, and the reactor coolant loops (RCL) including a portion of the branch lines were analyzed. Section 3 describes the analysis methods and the analyses performed. Section 4 presents the numerical results; the principal results presented as comparisons of response calculated by best estimate time history analysis methods vs. the SRP response spectrum technique. Section 5 draws conclusions from the results. Appendix A contains a brief description of the mathematical models that defined the structures containing the three piping systems. Response from these models provided input to the piping models. Appendix B provides a detailed derivation of the pseudostatic mode approach to the multisupport time history analysis method used in this study.

  20. Radiation Safety Work Control Form

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Radiation Safety Work Control Form (see instructions on pg-3) Rev. May 2014 Area: Form : Date: Preliminary Applicability Screen: (a) Will closing the beam line injection stoppers...

  1. Sandia National Laboratories: Hydrogen Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hydrogen Safety Solar Thermochemical Hydrogen Production On June 13, 2014, in SNL maintains the equipment, experts, and partnerships required to develop technology for solar...

  2. APS Safety Guidelines for Beamlines

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Guidelines for Beamlines Accident Investigations LOM Shop Usage User Shop Access - Policies and Procedures User Shop Orientation User Shop Authorization Certification Form...

  3. APS Experiment Safety Review Board

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    participates in project reviews as requested, recommends laser safety policy, reviews accident investigation conclusions, and evaluates plans to protect personnel where laser...

  4. Fermilab | Traffic Safety at Fermilab |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Submit a SuggestionQuestion Fermilab traffic rules (FESHM 9010) Fermilab traffic accident statistics Traffic safety awareness training Resources Texting While Driving...

  5. Natural Gas Pipeline Safety (Kansas)

    Broader source: Energy.gov [DOE]

    This article states minimum safety standards for the transportation of natural gas by pipeline and reporting requirements for operators of pipelines.

  6. Lessons Learned from Safety Events

    SciTech Connect (OSTI)

    Weiner, Steven C.; Fassbender, Linda L.

    2012-11-01T23:59:59.000Z

    The Hydrogen Incident Reporting and Lessons Learned website (www.h2incidents.org) was launched in 2006 as a database-driven resource for sharing lessons learned from hydrogen-related safety events to raise safety awareness and encourage knowledge-sharing. The development of this database, its first uses and subsequent enhancements have been described at the Second and Third International Conferences on Hydrogen Safety. [1,2] Since 2009, continuing work has not only highlighted the value of safety lessons learned, but enhanced how the database provides access to another safety knowledge tool, Hydrogen Safety Best Practices (http://h2bestpractices.org). Collaborations with the International Energy Agency (IEA) Hydrogen Implementing Agreement (HIA) Task 19 – Hydrogen Safety and others have enabled the database to capture safety event learnings from around the world. This paper updates recent progress, highlights the new “Lessons Learned Corner” as one means for knowledge-sharing and examines the broader potential for collecting, analyzing and using safety event information.

  7. Benthic biological and biogeochemical patterns and processes across an oxygen minimum zone (Pakistan margin, NE Arabian Sea)

    E-Print Network [OSTI]

    Levin, Lisa

    (Pakistan margin, NE Arabian Sea) Gregory L. Cowie a,Ã, Lisa A. Levin b a The Sir John Murray Laboratories), and organic matter (OM) availability on benthic communities and processes across the Pakistan Margin

  8. Thermal segmentation along the N. EcuadorS. Colombia margin (14N): Prominent influence of sedimentation rate in the trench

    E-Print Network [OSTI]

    Vallée, Martin

    Thermal segmentation along the N. Ecuador­S. Colombia margin (1­4°N): Prominent influence Ecuador Colombia Along the deformation front of the North Ecuador­South Colombia (NESC) margin, both

  9. Safety-Oriented Design of Component Assemblies using Safety Interfaces

    E-Print Network [OSTI]

    for upgrades at a later stage of the system life cycle. Thus, support for rigorous, compositional analysis from-based development. Keywords: Component-based system development, safety, component assemblies, safety interfaces as a promising approach for developing complex software systems by composing smaller indepen- dently developed

  10. General Safety Office of Environmental Health and Safety

    E-Print Network [OSTI]

    General Safety Web Manual Office of Environmental Health and Safety April 2010 #12;#12;Contents Emergency Telephone Numbers and Procedures............................(Click for web link) - How to Report............................................(Click for web link) - Chancellor - Vice Chancellors - Department Heads - Supervisors, Foreman and Managers

  11. Safety and Health Policy and Procedure Manual Biological Safety Manual

    E-Print Network [OSTI]

    Saidak, Filip

    Biological Safety Association (ABSA) best practices as well as all federal, state, and local regulations. IISafety and Health Policy and Procedure Manual Biological Safety Manual Section 280 INDEX I. Policy space suitable for work being conducted · Under the Office of Research Compliance, establish and manage

  12. National Transportation Safety Board Office of Aviation Safety

    E-Print Network [OSTI]

    Droegemeier, Kelvin K.

    NWS and Federal Aviation Administration (FAA) Advisory Circular "Aviation Weather Services", AC 00 Electronics Engineer Federal Aviation Administration 1 UTC ­ is an abbreviation for Coordinated Universal Time1 National Transportation Safety Board Office of Aviation Safety Washington, D.C. 20594

  13. Effect of post-implant edema on prostate brachytherapy treatment margins

    SciTech Connect (OSTI)

    Reed, Daniel R. [Radiation Oncology, Arizona Oncology Services, Phoenix, AZ (United States); Department of Radiation Oncology, Puget Sound Health Care System, Department of Veterans Affairs, Seattle, WA (United States); Department of Radiation Oncology, University of Washington, Seattle, WA (United States); Wallner, Kent [Department of Radiation Oncology, Puget Sound Health Care System, Department of Veterans Affairs, Seattle, WA (United States); Department of Radiation Oncology, University of Washington, Seattle, WA (United States); Radiation Oncology, Group Health Cooperative, Seattle, WA (United States); Ford, Eric [Department of Radiation Oncology, University of Washington, Seattle, WA (United States); Mueller, Amy [Department of Radiation Oncology, Puget Sound Health Care System, Department of Veterans Affairs, Seattle, WA (United States); Merrick, Gregory [Schiffler Cancer Center, Wheeling, WV (United States); Maki, Jeffrey [Department of Diagnostic Radiology, Puget Sound Health Care System, Department of Veterans Affairs, Seattle, WA (United States); Sutlief, Steven [Department of Radiation Oncology, Puget Sound Health Care System, Department of Veterans Affairs, Seattle, WA (United States); Department of Radiation Oncology, University of Washington, Seattle, WA (United States); Butler, Wayne [Schiffler Cancer Center, Wheeling, WV (United States)

    2005-12-01T23:59:59.000Z

    Purpose: To determine if postimplant prostate brachytherapy treatment margins calculated on Day 0 differ substantially from those calculated on Day 30. Methods: Thirty patients with 1997 American Joint Commission on Cancer clinical stage T1-T2 prostatic carcinoma underwent prostate brachytherapy with I-125 prescribed to 144 Gy. Treatment planning methods included using loose seeds in a modified peripheral loading pattern and treatment margins (TMs) of 5-8 mm. Postimplant plain radiographs, computed tomography scans, and magnetic resonance scans were obtained 1-4 hours after implantation (Day 0). A second set of imaging studies was obtained at 30 days after implantation (Day 30) and similarly analyzed. Treatment margins were measured as the radial distance in millimeters from the prostate edge to the 100% isodose line. The TMs were measured and tabulated at 90{sup o} intervals around the prostate periphery at 0.6-cm intervals. Each direction was averaged to obtain the mean anterior, posterior, left, and right margins. Results: The mean overall TM increased from 2.6 mm ({+-}2.3) on Day 0 to 3.5 mm ({+-}2.4) on Day 30. The mean anterior margin increased from 1.2 mm on Day 0 to 1.8 mm on Day 30. The posterior margin increased from 1.2 mm on Day 0 to 2.8 mm on Day 30. The lateral treatment margins increased most over time, with mean right treatment margin increasing from 3.9 mm on Day 0 to 4.7 mm on Day 30. Conclusion: Treatment margins appear to be durable in the postimplant period, with a clinically insignificant increase from Day 0 to Day 30.

  14. INTEGRATED SAFETY MANAGEMENT SYSTEM SAFETY CULTURE IMPROVEMENT INITIATIVE

    SciTech Connect (OSTI)

    MCDONALD JA JR

    2009-01-16T23:59:59.000Z

    In 2007, the Department of Energy (DOE) identified safety culture as one of their top Integrated Safety Management System (ISMS) related priorities. A team was formed to address this issue. The team identified a consensus set of safety culture principles, along with implementation practices that could be used by DOE, NNSA, and their contractors. Documented improvement tools were identified and communicated to contractors participating in a year long pilot project. After a year, lessons learned will be collected and a path forward determined. The goal of this effort was to achieve improved safety and mission performance through ISMS continuous improvement. The focus of ISMS improvement was safety culture improvement building on operating experience from similar industries such as the domestic and international commercial nuclear and chemical industry.

  15. LASER SAFETY MANUAL 2014 RICE UNIVERSITY 1

    E-Print Network [OSTI]

    Natelson, Douglas

    LASER SAFETY MANUAL 2014 RICE UNIVERSITY 1 Rice University Laser Safety Manual Environmental Health and Safety MS 123 P.O. Box 1892 Houston, TX 77251-1892 January 2014 #12;LASER SAFETY MANUAL 2014 RICE UNIVERSITY 2 Introduction The objective of the Rice University Laser Safety program is to assist all levels

  16. LASER SAFETY COMMITTEE CHARTER November, 2005

    E-Print Network [OSTI]

    Knowles, David William

    LASER SAFETY COMMITTEE CHARTER November, 2005 Function The Safety Review Committee (SRC) performs-committees to address specific health and safety matters. The Laser Safety Committee (LSC) is one of the SRC expert sub-committees. The Laser SafetyCommittee recommends policies and practices regarding the conduct and regulatory compliance

  17. LASER SAFETY MANUAL POLICIES AND PROCEDURES

    E-Print Network [OSTI]

    Zhang, Yuanlin

    LASER SAFETY MANUAL POLICIES AND PROCEDURES FOR LASER SAFETY AT TEXAS TECH UNIVERSITY LUBBOCK, TEXAS September 2002 #12;V-1 TEXAS TECH UNIVERSITY LASER SAFETY MANUAL TABLE OF CONTENTS SECTION I ­ MANAGEMENT OF LASER LICENSE Introduction A. Laser Safety Program I - 1 B. Radiation Laser Safety Committee I

  18. Health and Safety Handbook UPDATED: June 27, 2012

    E-Print Network [OSTI]

    Roy, Subrata

    .......................................................................................................5 Material Safety Data Sheets/ Chemical Inventories

  19. 880 IEEE TRANSACTIONS ON POWER SYSTEMS, VOL. 19, NO. 2, MAY 2004 Marginal Loss Modeling in LMP Calculation

    E-Print Network [OSTI]

    McCalley, James D.

    in the locational marginal pricing approach recently deployed in the ISO New England (ISO-NE) standard market design) [1] proposes location-based marginal pricing (LMP) together with firm transmission rights (FTR, Senior Member, IEEE Abstract--This paper discusses the pricing of marginal trans- mission network losses

  20. Abstract--The capability to deal effectively with the uncer-tainty associated with locational marginal prices (LMPs) in con-

    E-Print Network [OSTI]

    , standard market design, locational marginal prices, fixed/firm/financial transmission rights, transmission.S. electricity sector. The proposal uses locational marginal prices (LMPs) to identify congestion situations marginal prices (LMPs) in con- gestion management schemes requires the development of ap- propriate

  1. Abstract--This paper introduces the fundamental concept of locational marginal price (LMP) in the electricity markets, and

    E-Print Network [OSTI]

    Fu, Yong

    1 Abstract--This paper introduces the fundamental concept of locational marginal price (LMP Terms-- Congestion charge, locational marginal price, LMP difference, nodal price. NOMENCLATURE ba) are to implement the locational marginal pricing [1-3]. Under Standard Market Design (SMD) issued by FERC in July

  2. IMPORTANCE OF SAFETY CULTURE ASSESSMENT

    SciTech Connect (OSTI)

    Spitalnik, J.

    2004-10-06T23:59:59.000Z

    Safety Management has lately been considered by some Nuclear Regulatory agencies as the tool on which to concentrate their efforts to implement modern regulation structures, because Safety Culture was said to be difficult to monitor. However, Safety Culture can be assessed and monitored even if it is problematical to make Safety Culture the object of regulation. This paper stresses the feasibility and importance of Safety Culture Assessment based on self-assessment applications performed in several nuclear organizations in Latin America. Reasons and ownership for assessing Safety Culture are discussed, and relevant aspects considered for setting up and programming such an assessment are shown. Basic principles that were taken into account, as well as financial and human resources used in actual self-assessments are reviewed, including the importance of adequate statistical analyses and the necessity of proper feed-back of results. The setting up of action plans to enhance Safety Culture is the final step of the assessment program that once implemented will enable to establish a Safety Culture monitoring process within the organization.

  3. Nuclear Explosive Safety Evaluation Processes

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14T23:59:59.000Z

    This Manual provides supplemental details to support the nuclear explosive safety (NES) evaluation requirement of Department of Energy (DOE) Order (O) 452.2D, Nuclear Explosive Safety, dated 4/14/09. Admin Chg 1, dated 7-10-13, cancels DOE M 452.2-2.

  4. Physics Safety Induction OCTOBER 2012

    E-Print Network [OSTI]

    Tobar, Michael

    Physics Safety Induction OCTOBER 2012 FACULTY OF SCIENCES #12;The University of Western Australia · Be safe · Report anything unsafe #12;The University of Western Australia Physics Occupational Safety Sharma ­ ICRAR · Nikita Kostylev ­ Student Representative #12;The University of Western Australia School

  5. Environmental Health and Safety Assessment

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Environmental Health and Safety Assessment Program Manual 7/15/2013 #12;Environmental Health/26/2013. The most recent version of this document is available electronically at: http://sp.ehs.cornell.edu/env/general-environmental-management/environmental.........................................................................................................................4 #12;Environmental Health and Safety Assessment Program Manual Approved by: (Barb English) Last

  6. ANNUAL SECURITY & FIRE SAFETY REPORT

    E-Print Network [OSTI]

    Maxwell, Bruce D.

    ANNUAL SECURITY & FIRE SAFETY REPORT 2014 A guide to policies, procedures, practices, and programs implemented to keep students, faculty, and staff safe and facilities secure. www.montana.edu/reports/security.pdf #12;Inside this Report 2014 Annual Security and Fire Safety Report for Reporting Year 2013

  7. FAQS Qualification Card – Criticality Safety

    Broader source: Energy.gov [DOE]

    A key element for the Department’s Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA).

  8. University of Pittsburgh Safety Manual

    E-Print Network [OSTI]

    Sibille, Etienne

    and the reaction vessel is a glass vial, flask or bottle; H2 Rx conducted with a H-Cube Continuous is a glass flask or bottle contained within a Parr shaker or comparable equipment. 2.3 Level 3 ­ H2 Rx blast rooms, and removing reaction vessels. 4.2 Safety goggles or safety glasses with side impact

  9. _____________________________ Environment, Health, & Safety _________ __________________ Training Program

    E-Print Network [OSTI]

    for LBNL guests and employees. All employees of the lab, participating guests, students and subcontractors at LBNL. Course Objectives: · Acknowledge the policies and programs applicable to electrical safety at LBNL. · Define roles and responsibilities related to electrical safety at LBNL. · Recognize Stop Work

  10. LASER SAFETY POLICY Policy Statement

    E-Print Network [OSTI]

    Vertes, Akos

    LASER SAFETY POLICY Policy Statement Each department that acquires or operates lasers for use in the university's Laser Safety Manual. Reason for Policy/Purpose If improperly used or controlled, lasers can produce multiple injuries, including burns, blindness, and electrocution. This policy and the university

  11. Nuclear Reactor Safety Design Criteria

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1993-01-19T23:59:59.000Z

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Certified 11-18-10.

  12. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, E.

    1983-08-15T23:59:59.000Z

    A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.

  13. Electrical safety device

    DOE Patents [OSTI]

    White, David B. (Greenock, PA)

    1991-01-01T23:59:59.000Z

    An electrical safety device for use in power tools that is designed to automatically discontinue operation of the power tool upon physical contact of the tool with a concealed conductive material. A step down transformer is used to supply the operating power for a disconnect relay and a reset relay. When physical contact is made between the power tool and the conductive material, an electrical circuit through the disconnect relay is completed and the operation of the power tool is automatically interrupted. Once the contact between the tool and conductive material is broken, the power tool can be quickly and easily reactivated by a reset push button activating the reset relay. A remote reset is provided for convenience and efficiency of operation.

  14. Health, Safety, and Environment Division

    SciTech Connect (OSTI)

    Wade, C [comp.] [comp.

    1992-01-01T23:59:59.000Z

    The primary responsibility of the Health, Safety, and Environmental (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environmental protection. These activities are designed to protect the worker, the public, and the environment. Meeting these responsibilities requires expertise in many disciplines, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science and engineering, analytical chemistry, epidemiology, and waste management. New and challenging health, safety, and environmental problems occasionally arise from the diverse research and development work of the Laboratory, and research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed, to study specific problems for the Department of Energy. The results of these programs help develop better practices in occupational health and safety, radiation protection, and environmental science.

  15. Page 1Laser Safety Training Laser Institute of America Laser Safety Laser Institute of America

    E-Print Network [OSTI]

    Farritor, Shane

    Page 1Laser Safety Training © Laser Institute of America 1 Laser Safety © Laser Institute of America Laser Safety: Hazards, Bioeffects, and Control Measures Laser Institute of America Gus Anibarro Education Manager 2Laser Safety © Laser Institute of America Laser Safety Overview Laser Safety Accidents

  16. B PLANT DOCUMENTED SAFETY ANALYSIS

    SciTech Connect (OSTI)

    DODD, E.N.; KERR, N.R.

    2003-08-01T23:59:59.000Z

    This document provides the documented safety analysis (DSA) and Central Plateau Remediation Project (CP) requirements that apply to surveillance and maintenance (S&M) activities at the 221-B Canyon Building and ancillary support structures (B Plant). The document replaces BHI-010582, Documented Safety Analysis for the B-Plant Facility. The B Plant is non-operational, deactivated and undergoing long term S&M prior to decontamination and decommissioning (D&D). This DSA is compliant with 10 CFR 830, Nuclear Safety Management, Subpart B, ''Safety Basis Requirements.'' The DSA was developed in accordance with U.S. Department of Energy (DOE) standard DOE-STD-1120-98, Integration of Environment, Safety, and Health into Facility Disposition Activities (DOE 1998) per Table 2 of 10 CFR 830 Appendix A, DOE Richland Operation Office (RL) direction (02-ABD-0053, Fluor Hanford Nuclear Safety Basis Strategy and Criteria) for facilities in long term S&M, and RL Direction (02-ABD-0091, ''FHI Nuclear Safety Expectations for Nuclear Facilities in Surveillance and Maintenance''). A crosswalk was prepared to identify potential inconsistencies between the previous B Plant safety analysis and DOE-STD-1120-98 guidance. In general, the safety analysis met the criteria of DOE-STD-1120-98. Some format and content changes have been made, including incorporating recent facility modifications and updating the evaluation guidelines and control selection criteria in accordance with RL direction (02-ABD-0053). The facility fire hazard analysis (FHA) and Technical Safety Requirements (TSR) are appended to this DSA as an aid to the users, to minimize editorial redundancy, and to provide an efficient basis for update.

  17. Corporate Analysis of DOE Safety Performance

    Broader source: Energy.gov [DOE]

    The Office of Environment, Health, Safety and Security (EHSS), Office of Analysis develops analysis tools and performance dashboards, and conducts analysis of DOE safety performance corporately and on a variety of specific environment, safety and health topics.

  18. DEPARTMENT OF ENVIRONMENTAL HEALTH & SAFETY CHEMICAL HYGIENE

    E-Print Network [OSTI]

    Firestone, Jeremy

    DEPARTMENT OF ENVIRONMENTAL HEALTH & SAFETY CHEMICAL HYGIENE PLAN #12, 2014 #12;University of Delaware Department of Environmental Health & Safety Chemical Hygiene) #12;University of Delaware Department of Environmental Health & Safety Chemical Hygiene Plan

  19. Pipeline Safety Program Oak Ridge National Laboratory

    E-Print Network [OSTI]

    programs prepared by pipeline operators in accordance with Federal pipeline safety regulations, grounding, and interference, · environmentally sensitive areas, · federal pipeline safety regulationsPipeline Safety Program Oak Ridge National Laboratory managed by UT-Battelle, LLC for the U

  20. Table of Organization Environmental Health & Safety

    E-Print Network [OSTI]

    Jia, Songtao

    Safety Continues Page 3 Lauren Kelly Manager Hazardous Materials June, 2014 James Kaznosky, Senior Research Safety Lauren Kelly Manager Hazardous Materials Radioactive Waste (only) Hazardous Materials Assistant Physicist Vacant Assistant Physicist 2 #12;Environmental Safety/Hazardous Materials Management

  1. Experimental validation of the van Herk margin formula for lung radiation therapy

    SciTech Connect (OSTI)

    Ecclestone, Gillian; Heath, Emily [Department of Physics, Ryerson University, Toronto, Ontario M5B 2K3 (Canada)] [Department of Physics, Ryerson University, Toronto, Ontario M5B 2K3 (Canada); Bissonnette, Jean-Pierre [Department of Radiation Oncology, University of Toronto, Toronto, Ontario M5G 2M9, Canada and Department of Radiation Physics, Princess Margaret Cancer Centre, Toronto, Ontario M5G 2M9 (Canada)] [Department of Radiation Oncology, University of Toronto, Toronto, Ontario M5G 2M9, Canada and Department of Radiation Physics, Princess Margaret Cancer Centre, Toronto, Ontario M5G 2M9 (Canada)

    2013-11-15T23:59:59.000Z

    Purpose: To validate the van Herk margin formula for lung radiation therapy using realistic dose calculation algorithms and respiratory motion modeling. The robustness of the margin formula against variations in lesion size, peak-to-peak motion amplitude, tissue density, treatment technique, and plan conformity was assessed, along with the margin formula assumption of a homogeneous dose distribution with perfect plan conformity.Methods: 3DCRT and IMRT lung treatment plans were generated within the ORBIT treatment planning platform (RaySearch Laboratories, Sweden) on 4DCT datasets of virtual phantoms. Random and systematic respiratory motion induced errors were simulated using deformable registration and dose accumulation tools available within ORBIT for simulated cases of varying lesion sizes, peak-to-peak motion amplitudes, tissue densities, and plan conformities. A detailed comparison between the margin formula dose profile model, the planned dose profiles, and penumbra widths was also conducted to test the assumptions of the margin formula. Finally, a correction to account for imperfect plan conformity was tested as well as a novel application of the margin formula that accounts for the patient-specific motion trajectory.Results: The van Herk margin formula ensured full clinical target volume coverage for all 3DCRT and IMRT plans of all conformities with the exception of small lesions in soft tissue. No dosimetric trends with respect to plan technique or lesion size were observed for the systematic and random error simulations. However, accumulated plans showed that plan conformity decreased with increasing tumor motion amplitude. When comparing dose profiles assumed in the margin formula model to the treatment plans, discrepancies in the low dose regions were observed for the random and systematic error simulations. However, the margin formula respected, in all experiments, the 95% dose coverage required for planning target volume (PTV) margin derivation, as defined by the ICRU; thus, suitable PTV margins were estimated. The penumbra widths calculated in lung tissue for each plan were found to be very similar to the 6.4 mm value assumed by the margin formula model. The plan conformity correction yielded inconsistent results which were largely affected by image and dose grid resolution while the trajectory modified PTV plans yielded a dosimetric benefit over the standard internal target volumes approach with up to a 5% decrease in the V20 value.Conclusions: The margin formula showed to be robust against variations in tumor size and motion, treatment technique, plan conformity, as well as low tissue density. This was validated by maintaining coverage of all of the derived PTVs by 95% dose level, as required by the formal definition of the PTV. However, the assumption of perfect plan conformity in the margin formula derivation yields conservative margin estimation. Future modifications to the margin formula will require a correction for plan conformity. Plan conformity can also be improved by using the proposed trajectory modified PTV planning approach. This proves especially beneficial for tumors with a large anterior–posterior component of respiratory motion.

  2. Analysis of post-Kyoto CO? emissions trading using marginal abatement curves

    E-Print Network [OSTI]

    Ellerman, A. Denny.; Decaux, Annelène.

    Marginal abatement curves (MACs) are often used heuristically to demonstrate the advantages of emissions trading. In this paper, the authors derive MACs from EPPA, the MIT Joint Program's computable general equilibrium ...

  3. Storytelling on the margins : a theoretical framework for imagining a fashion innovation center in Tuscany

    E-Print Network [OSTI]

    Mills, Alexa (Alexa Timeaus)

    2008-01-01T23:59:59.000Z

    The importance of the margin has long been deemed important in creative processes. At both the level of the individual and the level of the city, research shows that creativity tends to flourish on the philosophical and ...

  4. 6Seismic stratigraphy and subsidence history of the United Arab Emirates (UAE) rifted margin

    E-Print Network [OSTI]

    Watts, A. B. "Tony"

    6Seismic stratigraphy and subsidence history of the United Arab Emirates (UAE) rifted margin). The United Arab Emirates (UAE) is underlain by a deep sedimentary basin which comprises a lower rifted

  5. Understanding the Zongo : processes of socio-spatial marginalization in Ghana

    E-Print Network [OSTI]

    Williamson, Emily Anne

    2014-01-01T23:59:59.000Z

    The spatial processes of marginalization and ghettoization have been described, labeled, and theorized extensively in the United States and Europe, yet there has been little research dedicated to these processes in the ...

  6. Mesozoic evolution of the northeast African shelf margin, Libya and Egypt

    SciTech Connect (OSTI)

    Aadland, R.K.; Schamel, S.

    1988-08-01T23:59:59.000Z

    The present tectonic features of the northeast African shelf margin between the Nile delta and the Gulf of Sirte are products of (1) precursory late Paleozoic basement arches, (2) early Mesozoic rifting and plate separation, and (3) Late Cretaceous structural inversion. Isopach and structural maps, cross sections, and sediment accumulation (geohistory) curves constructed from 89 wells in the Western Desert and 27 wells in northeastern Libya depict the structural and stratigraphic development of the northeast African shelf margin.

  7. Marginal Cost of Steam and Power from Cogeneration Systems Using a Rational Value-Allocation Procedure

    E-Print Network [OSTI]

    Kumana, J. D.; Al-Gwaiz, M. M.

    2004-01-01T23:59:59.000Z

    that their approach gives more realistic values for marginal steam and power costs, and yields superior results compared to conventional methods. It is recommended as the first step before energy optimization analysis for the process is undertaken. REFERENCES... companies operate in either modes 1a or 2a, as electric utility companies are loathe to purchase surplus power from a cogenerator unless it is priced substantially below the utility?s own cheapest marginal cost of production. Usually, the cogenerator...

  8. Helpful links for materials transport, safety, etc.

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Helpful links for materials transport, safety, etc. relating to experiment safety at the APS. Internal Reference Material: Transporting Hazardous Materials "Natural" radioactivity...

  9. Office of Worker Safety and Health Policy

    Broader source: Energy.gov [DOE]

    The Office of Worker Safety and Health Policy establishes Departmental expectations for worker safety and health through the development of rules, directives and guidance.

  10. RADIATION SAFETY MANUAL POLICIES AND PROCEDURES

    E-Print Network [OSTI]

    Zhang, Yuanlin

    RADIATION SAFETY MANUAL POLICIES AND PROCEDURES FOR RADIATION PROTECTION AT TEXAS TECH UNIVERSITY................................................................................................................I-1 B. Radiation Protection Program...............................................................................I-3 D. Radiation Safety Management

  11. BNL | CFN Operations Safety Awareness (COSA) Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    CFN Operations Safety Awareness (COSA) Training All users at the CFN must complete the CFN Operations Safety Awareness (COSA) Training before they can access the facilities. COSA...

  12. Hazardous Material Transportation Safety (South Dakota)

    Broader source: Energy.gov [DOE]

    This legislation authorizes the Division of Highway Safety, in the Department of Public Safety, to promulgate regulations pertaining to the safe transportation of hazardous materials by a motor...

  13. Safety and Security Enfrocment Process Overview

    Office of Environmental Management (EM)

    are to enhance and protect worker safety and health, nuclear safety, and classified information security by fostering a culture that seeks to attain and sustain compliance...

  14. Safety and Security Enforcement Process Overview

    Broader source: Energy.gov (indexed) [DOE]

    SAFETY AND SECURITY ENFORCEMENT PROCESS OVERVIEW August 2012 OFFICE OF ENFORCEMENT AND OVERSIGHT OFFICE OF HEALTH, SAFETY AND SECURITY U.S. DEPARTMENT OF ENERGY AUGUST 2012 DOE...

  15. CFN Ops Plan | Experimental Safety Committee

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experimental Safety Committee The CFN Experimental Safety Committee will consist of the members listed below. Additional SME's from the lab support divisions will be added as...

  16. Nuclear Explosive Safety Evaluation Processes - DOE Directives...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    2 Admin Chg 1, Nuclear Explosive Safety Evaluation Processes by Carl Sykes Functional areas: Administrative Change, Defense Nuclear Facility Safety and Health Requirement, Defense...

  17. Interdisciplinary: Industrial Hygienist/Safety Engineer

    Broader source: Energy.gov [DOE]

    This position is located in the Office of Worker Safety and Health Assessments that conducts assessments to provide critical feedback and objective information on occupational safety and health...

  18. CCB Laboratory Safety Orientation Checklist Laboratory Safety Training Review

    E-Print Network [OSTI]

    Heller, Eric

    ) Location and use of hazardous waste accumulation areas Location of Safety Data hazardous materials, equipment, or processes that pertain to the research program and meeting area Location of fire extinguishers and closest pull station Location

  19. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  20. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Dotson, CW

    1980-08-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, lspra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  1. Chemical Hazards and Safety Issues in Fusion Safety Design

    SciTech Connect (OSTI)

    Cadwallader, L.C. [Idaho National Engineering and Environmental Laboratory (United States)

    2003-09-15T23:59:59.000Z

    Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard.

  2. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21T23:59:59.000Z

    With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

  3. Integrated Safety Management System Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2006-11-01T23:59:59.000Z

    This manual provides requirements and guidance for DOE and contractors to ensure development and implementation of an effective Integrated Safety Management system that is periodically reviewed and continuously improved. Canceled by DOE O 450.2.

  4. Safety | Linac Coherent Light Source

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Overview Each person who works at LCLS is required to be familiar with and identify in advance the hazards associated with hisher work, the hazards associated with work...

  5. SEAS LABORATORY SAFETY OFFICER ORIENTATION

    E-Print Network [OSTI]

    delegated by the Deans and Senior University Administration, the ESCO for each school or administrative unit/EH&S and lab · Communicate with lab members and PI · Get support from EH&S, ESCO and safety committees "The

  6. Forrestal Security and Safety Procedures

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1983-02-02T23:59:59.000Z

    To establish uniform procedures for the security and safety of the Forrestal Building and to inform all personnel of precautionary measures. This directive does not cancel another directive. Canceled by DOE N 251.11.

  7. Safety and Occupational Health Manager

    Broader source: Energy.gov [DOE]

    This position is located in the Office of Environment, Security, Safety and Health, under the Deputy Assistant Secretary (DAS) for Business Operations/Chief Operating Officer (COO). The Office of...

  8. CAHNRS Safety Committee Meeting Minutes

    E-Print Network [OSTI]

    Collins, Gary S.

    was cancelled, so there is no report. EH&S sent out a reminder that they have a short Hazardous Waste of Internal Audits is apparently developing a university level protocol for lab safety and training. 2

  9. BIOLOGICAL SAFETY POLICY PROGRAM TOPICS

    E-Print Network [OSTI]

    Fang-Yen, Christopher

    research protocols involving hazardous materials, reviews construction design for safety features with or near biologically hazardous materials (infectious agents, biohazards or recombinant DNA). 1.3 "Infectious waste" or "biohazardous waste" is defined by the Pennsylvania Department of Environmental

  10. Biodiesel Safety and Best Management

    E-Print Network [OSTI]

    Lee, Dongwon

    Biodiesel Safety and Best Management Practices for Small-Scale Noncommercial Use and Production you produce biodiesel: · Chemical-resistantgloves(butylrubberisbestfor methanol and lye........................................................................... 1 FuelOptionsfromBiomassOilFeedstocks ......................... 1 UsingBiodiesel

  11. Tank Farms Technical Safety Requirements

    SciTech Connect (OSTI)

    DANNA, M.A.

    2003-10-24T23:59:59.000Z

    The TSRs define the acceptable conditions, safe boundaries, bases thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Farms Documented Safety Analysis (DSA), in parallel with the DSA.

  12. FAQS Reference Guide – Occupational Safety

    Broader source: Energy.gov [DOE]

    This reference guide has been developed to address the competency statements in the July 2011 version of DOE-STD-1160-2011, Occupational Safety Functional Area Qualification Standard.

  13. Gallium Safety in the Laboratory

    SciTech Connect (OSTI)

    Cadwallader, L.C.

    2003-05-07T23:59:59.000Z

    A university laboratory experiment for the US Department of Energy magnetic fusion research program required a simulant for liquid lithium. The simulant choices were narrowed to liquid gallium and galinstan (Ga-In-Sn) alloy. Safety information on liquid gallium and galinstan were compiled, and the choice was made to use galinstan. A laboratory safety walkthrough was performed in the fall of 2002 to support the galinstan experiment. The experiment has been operating successfully since early 2002.

  14. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  15. Hanford Generic Interim Safety Basis

    SciTech Connect (OSTI)

    Lavender, J.C.

    1994-09-09T23:59:59.000Z

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  16. Normalization of Process Safety Metrics 

    E-Print Network [OSTI]

    Wang, Mengtian

    2012-10-19T23:59:59.000Z

    , for this research, the number of process safety incidents is not available; since all the companies just started recording process safety incidents after API RP 745 was issued. Therefore, the most similar reported indicator-operational oil spills is used... for lagging metrics testing as a proper substitute. The major related data was obtained for this section as follows: • Process and environmental incidents (operational oil spills) • Total oil production volume • Total natural gas production volume • Total...

  17. Topaz II preliminary safety assessment

    SciTech Connect (OSTI)

    Marshall, A.C. (Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States)); Standley, V. (Air Force Phillips Laboratory, Albuquerque, New Mexico 87110 (United States)); Voss, S.S. (Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)); Haskin, E. (Department of Chemical and Nuclear Engineering Department, Institute for Nuclear Power Studies, University of New Mexico, Albuquerque, New Mexico 87110 (United States))

    1993-01-10T23:59:59.000Z

    The Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz II space nuclear power system. A preliminary safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safety assessment and future Topaz II activities. A review of the Russian flight safety program was conducted and documented. Our preliminary safety assessment included a top level event tree, neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, and analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment, it appears that it will be possible to safely launch the Topaz II system in the U.S. with some possible system modifications. The principal system modifications will probably include design changes to preclude water flooded criticality and to assure intact reentry.

  18. Advancing the Hydrogen Safety Knowledge Base

    SciTech Connect (OSTI)

    Weiner, Steven C.

    2014-12-01T23:59:59.000Z

    A White Paper of the International Energy Agency Hydrogen Implementing Agreement Task 31 - Hydrogen Safety

  19. Protecting Health and Safety in Education Abroad

    E-Print Network [OSTI]

    Protecting Health and Safety in Education Abroad Faculty and Staff Handbook #12;1 Office of people on campus and beyond CSU to ensure your health and safety. This CSU team serves you before, during . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 In-Country Health and Safety Health and Safety Issues

  20. LASER SAFETY MANUAL 2012 RICE UNIVERSITY 1

    E-Print Network [OSTI]

    Natelson, Douglas

    LASER SAFETY MANUAL 2012 RICE UNIVERSITY 1 Rice University Laser Safety Manual Environmental Health and Safety MS 123 P.O. Box 1892 Houston, TX 77251-1892 December 2012 #12;LASER SAFETY MANUAL 2012 RICE, and general procedures to aid those individuals working in the laser laboratory environment. It is intended

  1. HAZARD ALERT ENVIRONMENT HEALTH AND SAFETY

    E-Print Network [OSTI]

    Calgary, University of

    HAZARD ALERT ENVIRONMENT HEALTH AND SAFETY EH&S Hazard Alert - 2010.06.18 HAZARD ALERT ­ Reaction Manual. http://www.ucalgary.ca/safety/files/safety/LaboratoryFumeHoodUserStandard.pdf #12;HAZARD ALERT ENVIRONMENT HEALTH AND SAFETY EH&S Hazard Alert - 2010.06.18 In the recent incident the sash was closed while

  2. Texas Tech University Safety and Health Handbook

    E-Print Network [OSTI]

    Gelfond, Michael

    of the mission of this institution. Responsibility for the administration of the institution's safety, healthTexas Tech University Safety and Health Handbook for Supervisors/Safety Coordinators February 19, 1997 #12;i Table of Contents University Safety, Health, and Environmental Policy

  3. Safety Case Development: Current Practice, Future Prospects

    E-Print Network [OSTI]

    Kelly, Tim

    and maintenance, and the problems engineers face in these areas. 1.1 The Purpose and Content of a Safety Case and evidence aspects of the safety case are combined; · Safety Case Maintenance - examining the need the safety requirements, so long as the lanes fail independently. · SE - the results of hardware reliability

  4. Food Safety Participant Materials for Notebook

    E-Print Network [OSTI]

    foods. · Not eating foods that have been irradiated. · Eating whole foods instead of processed foodsUNIT 5: Food Safety Participant Materials for Notebook #12;Navigating for Success Food Safety p 1 Food Safety Good food safety practices are crucial to reducing foodborne illnesses. Nutrition educators

  5. Toolbox Safety Talk Aerial Work Platforms

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Toolbox Safety Talk Aerial Work Platforms Environmental Health & Safety Facilities Safety & Health to Environmental Health & Safety for recordkeeping. Aerial work platforms are important tools and if used correctly, and equipment damage. This guide addresses safe use of aerial work platforms and provides tips to prevent

  6. Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

  7. Wintertime pytoplankton bloom in the Subarctic Pacific supportedby continental margin iron

    SciTech Connect (OSTI)

    Lam, Phoebe J.; Bishop, James K.B.; Henning, Cara C.; Marcus,Matthew A.; Waychunas, Glenn A.; Fung, Inez

    2004-06-08T23:59:59.000Z

    Heightened biological activity was observed in February 1996in the high-nutrient low-chlorophyll (HNLC) subarctic North PacificOcean, a region that is thought to beiron-limited. Here we provideevidence supporting the hypothesis that Ocean Station Papa (OSP) in thesubarctic Pacific received a lateral supply of particulate iron from thecontinental margin off the Aleutian Islands in the winter, coincidentwith the observed biological bloom. Synchrotron X-ray analysis was usedto describe the physical form, chemistry, and depth distributions of ironin size fractionated particulate matter samples. The analysis revealsthat discrete micron-sized iron-rich hotspots are ubiquitous in the upper200m at OSP, more than 900km from the closest coast. The specifics of thechemistry and depth profiles of the Fe hot spots trace them to thecontinental margins. We thus hypothesize that iron hotspots are a markerfor the delivery of iron from the continental margin. We confirm thedelivery of continental margin iron to the open ocean using an oceangeneral circulation model with an iron-like tracer source at thecontinental margin. We suggest that iron from the continental marginstimulated a wintertime phytoplankton bloom, partially relieving the HNLCcondition.

  8. Safety Series No. 75-INSAG-4, Safety Culture: A report by the International Nuclear Safety Advisory Group, International Atomic Energy Agency

    Broader source: Energy.gov [DOE]

    Safety Series No. 75-INSAG-4, Safety Culture: A report by the International Nuclear Safety Advisory Group, International Atomic Energy Agency, IAEA, 1991

  9. MSU Safety & Risk Management Page 1 of 2 SAFETY & RISK MANAGEMENT

    E-Print Network [OSTI]

    Dyer, Bill

    MSU Safety & Risk Management Page 1 of 2 SAFETY & RISK MANAGEMENT OCCUPATIONAL HEALTH & SAFETY Safety & Risk Management (SRM) of new hires. Completion of a baseline occupational health evaluation Protection Program.) #12;MSU Safety & Risk Management Page 2 of 2 MSU provides additional medical evaluations

  10. RADIATION SAFETY OFFICE Campus Radiation Safety Manual UNIVERSITY OF NEW ORLEANS Previous Revision: May 1999

    E-Print Network [OSTI]

    Li, X. Rong

    SAFETY OFFICER AND RADIATION PROTECTION STAFF The Radiation Safety Officer has the responsibilityRADIATION SAFETY OFFICE Campus Radiation Safety Manual UNIVERSITY OF NEW ORLEANS Previous Revision radiation safety program will be conducted in such a manner that exposure to faculty, staff, students

  11. Health and Safety Policy Version 2012, Page 1 of 8 Health and Safety Policy

    E-Print Network [OSTI]

    Low, Robert

    Health and Safety Policy Version 2012, Page 1 of 8 Health and Safety Policy #12;Health and Safety Policy Version 2012, Page 2 of 8 Coventry University Health and Safety Policy 1. Introduction, Purpose and Scope The objective of our Health and Safety Policy is to enable the University to operate effectively

  12. Chapter 13 Employee Health and Safety 13.01 Safety Policy and Accident Reporting

    E-Print Network [OSTI]

    Sheridan, Jennifer

    Chapter 13 Employee Health and Safety 13.01 Safety Policy and Accident Reporting General Safety. If an accident occurs, this responsibility includes making an adequate investigation and taking necessary are responsible for following established safety procedures and using protective equipment. Safety and Accident

  13. Safety of magnetic fusion facilities: Requirements

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This Standard identifies safety requirements for magnetic fusion facilities. Safety functions are used to define outcomes that must be achieved to ensure that exposures to radiation, hazardous materials, or other hazards are maintained within acceptable limits. Requirements applicable to magnetic fusion facilities have been derived from Federal law, policy, and other documents. In addition to specific safety requirements, broad direction is given in the form of safety principles that are to be implemented and within which safety can be achieved.

  14. Hot roller embossing system equipped with a temperature margin-based controller

    SciTech Connect (OSTI)

    Kim, Seyoung, E-mail: seyoungkim@kimm.re.kr; Son, Youngsu; Lee, Sunghee; Ham, Sangyong; Kim, Byungin [Department of Robotics and Mechatronics, Korea Institute of Machinery and Materials (KIMM), Daejeon (Korea, Republic of)

    2014-08-15T23:59:59.000Z

    A temperature control system was proposed for hot roller embossing. The roll surface was heated using induction coils and cooled with a circulating chilled water system. The temperature of the roll surface was precisely controlled by a temperature margin-based control algorithm that we developed. Implementation of the control system reduced deviations in the roll surface temperature to less than ±2?°C. The tight temperature control and the ability to rapidly increase and decrease the roll temperature will allow optimum operating parameters to be developed quickly. The temperature margin-based controller could also be used to optimize the time course of electrical power and shorten the cooling time by choosing an appropriate temperature margin, possibly for limited power consumption. The chiller-equipped heating roll with the proposed control algorithm is expected to decrease the time needed to determine the optimal embossing process.

  15. Nuclear power plant cable materials : review of qualification and currently available aging data for margin assessments in cable performance.

    SciTech Connect (OSTI)

    Celina, Mathias Christopher; Gillen, Kenneth Todd; Lindgren, Eric Richard

    2013-05-01T23:59:59.000Z

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostlyinert' aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section - a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on original qualification testing data alone. The non-availability of conclusive predictions for the aging conditions of 40-year-old cables implies that the same levels of uncertainty will remain for any re-qualification or extended operation of these cables. The highly variable aging behavior of the range of materials employed also implies that simple, standardized aging tests are not sufficient to provide the required aging data and performance predictions for all materials. It is recommended that focused studies be conducted that would yield the material aging parameters needed to predict aging behaviors under low dose, low temperature plant equivalent conditions and that appropriately aged specimens be prepared that would mimic oxidatively-aged 40- to 60- year-old materials for confirmatory LOCA performance testing. This study concludes that it is not sufficient to expose materials to rapid, high radiation and high temperature levels with subsequent LOCA qualification testing in order to predictively quantify safety margins of existing infrastructure with regard to LOCA performance. We need to better understand how cable jacketing and insulation materials have degraded over decades of power plant operation and how this aging history relates to service life prediction and the performance of existing equipment to withstand a LOCA situation.

  16. A literature review of safety culture.

    SciTech Connect (OSTI)

    Cole, Kerstan Suzanne; Stevens-Adams, Susan Marie; Wenner, Caren A.

    2013-03-01T23:59:59.000Z

    Workplace safety has been historically neglected by organizations in order to enhance profitability. Over the past 30 years, safety concerns and attention to safety have increased due to a series of disastrous events occurring across many different industries (e.g., Chernobyl, Upper Big-Branch Mine, Davis-Besse etc.). Many organizations have focused on promoting a healthy safety culture as a way to understand past incidents, and to prevent future disasters. There is an extensive academic literature devoted to safety culture, and the Department of Energy has also published a significant number of documents related to safety culture. The purpose of the current endeavor was to conduct a review of the safety culture literature in order to understand definitions, methodologies, models, and successful interventions for improving safety culture. After reviewing the literature, we observed four emerging themes. First, it was apparent that although safety culture is a valuable construct, it has some inherent weaknesses. For example, there is no common definition of safety culture and no standard way for assessing the construct. Second, it is apparent that researchers know how to measure particular components of safety culture, with specific focus on individual and organizational factors. Such existing methodologies can be leveraged for future assessments. Third, based on the published literature, the relationship between safety culture and performance is tenuous at best. There are few empirical studies that examine the relationship between safety culture and safety performance metrics. Further, most of these studies do not include a description of the implementation of interventions to improve safety culture, or do not measure the effect of these interventions on safety culture or performance. Fourth, safety culture is best viewed as a dynamic, multi-faceted overall system composed of individual, engineered and organizational models. By addressing all three components of safety culture, organizations have a better chance of understanding, evaluating, and making positive changes towards safety within their own organization.

  17. JOURNAL OF GEOPHYSICAL RESEARCH, VOL. ???, XXXX, DOI:10.1029/, Deformation-induced melting in the margins of the1

    E-Print Network [OSTI]

    in the margins of the1 West-Antarctic ice streams2 Jenny Suckale 1 , John D. Platt 2 , Thibaut Perol 2 and James for publication. #12;X - 2 SUCKALE, PLATT, PEROL AND RICE: MELTING IN ICE-STREAM MARGINS Abstract. Flow of glacial 16, 2014, 10:19am D R A F T #12;SUCKALE, PLATT, PEROL AND RICE: MELTING IN ICE-STREAM MARGINS X - 3 1

  18. Topaz II preliminary safety assessment

    SciTech Connect (OSTI)

    Marshall, A.C. (Sandia National Labs., Albuquerque, NM (United States)); Standley, V. (Air Force Phillips Laboratory, Albuquerque, NM (United States)); Voss, S.S. (Los Alamos National Lab., NM (United States)); Haskin, E. (New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering)

    1992-01-01T23:59:59.000Z

    The Strategic Defense Initiative Organization (SDIO) decided to investigate the possibility of launching a Russian Topaz 11 space nuclear power system. A preliminary safety assessment was conducted to determine whether or not a space mission could be conducted safely and within budget constraints. As part of this assessment, a safety policy and safety functional requirements were developed to guide both the safely assessment and future Topaz II activities. A review of the Russian flight safety program was conducted and documented. Our preliminary safety assessment included a top level event tree, neutronic analysis of normal and accident configurations, an evaluation of temperature coefficients of reactivity, a reentry and disposal analysis, and analysis of postulated launch abort impact accidents, and an analysis of postulated propellant fire and explosion accidents. Based on the assessment, it appears that it will be possible to safely launch the Topaz II system in the US with some possible system modifications. The principal system modifications will probably include design changes to preclude water flooded criticality and to assure intact reentry.

  19. Recommended research on LNG safety

    SciTech Connect (OSTI)

    Carpenter, H.J.; Gilmore, F.R.

    1981-03-01T23:59:59.000Z

    The US Department of Energy (DOE) is conducting research on the safety and other environmental aspects of liquefied energy gases including liquefied natural gas (LNG). The effort reported here was conducted as part of the planning for further research into the safety aspects of transporting and storing LNG, with primary emphasis on public safety. Although the modern LNG industry has enjoyed excellent success in providing for safe operations, significant questions remain on the part of many, the expressions of which were intensified with the addition of marine-based LNG import terminals. Public safety with regard to large-scale importation of this fuel has received widespread attention in the US Congress, state legislatures, county and city governments, and from various individuals and public groups, with coverage in all the news media, including books published on the subject. The safety concerns have centered around the consequences to the public of a large spill of the cryogenic liquid from an ocean tanker or a larger storage tank, either of which might hold as much as 125,000 m/sup 3/ of LNG.

  20. Tank farms criticality safety manual

    SciTech Connect (OSTI)

    FORT, L.A.

    2003-03-27T23:59:59.000Z

    This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type.

  1. Environment/Health/Safety (EHS): Safety Concerns Form

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8, 2000ConsumptionInnovationEnvironment, SafetySafety CommitteeConcerns

  2. Quantification of the Variability of Diaphragm Motion and Implications for Treatment Margin Construction

    SciTech Connect (OSTI)

    Rit, Simon; Herk, Marcel van; Zijp, Lambert [Department of Radiation Oncology, The Netherlands Cancer Institute-Antoni van Leeuwenhoek Hospital, Amsterdam (Netherlands); Sonke, Jan-Jakob, E-mail: j.sonke@nki.nl [Department of Radiation Oncology, The Netherlands Cancer Institute-Antoni van Leeuwenhoek Hospital, Amsterdam (Netherlands)

    2012-03-01T23:59:59.000Z

    Purpose: To quantify the variability of diaphragm motion during free-breathing radiotherapy of lung patients and its effect on treatment margins to account for geometric uncertainties. Methods and Materials: Thirty-three lung cancer patients were analyzed. Each patient had 5-19 cone-beam scans acquired during different treatment fractions. The craniocaudal position of the diaphragm dome on the same side as the tumor was tracked over 2 min in the projection images, because it is both easily visible and a suitable surrogate to study the variability of the tumor motion and its impact on treatment margins. Intra-acquisition, inter-acquisition, and inter-patient variability of the respiratory cycles were quantified separately, as were the probability density functions (PDFs) of the diaphragm position over each cycle, each acquisition, and each patient. Asymmetric margins were simulated using each patient PDF and compared to symmetric margins computed from a margin recipe. Results: The peak-to-peak amplitude variability (1 SD) was 3.3 mm, 2.4 mm, and 6.1 mm for the intra-acquisition, inter-acquisition, and inter-patient variability, respectively. The average PDF of each cycle was similar to the sin{sup 4} function but the PDF of each acquisition was closer to a skew-normal distribution because of the motion variability. Despite large interfraction baseline variability, the PDF of each patient was generally asymmetric with a longer end-inhale tail because the end-exhale position was more stable than the end-inhale position. The asymmetry of the PDF required asymmetric margins around the time-averaged position to account for the position uncertainty but the average difference was 1.0 mm (range, 0.0-4.4 mm) for a sharp penumbra and an idealized online setup correction protocol. Conclusion: The respiratory motion is more irregular during the fractions than between the fractions. The PDF of the respiratory motion is asymmetrically distributed. Both the intra-acquisition variability and the PDF asymmetry have a limited impact on dose distributions and inferred margins. The use of a margin recipe to account for respiratory motion with an estimate of the average motion amplitude was adequate in almost all patients.

  3. Hanford’s Robust Safety Culture Gains One More Site-Wide Safety Standard

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. – The safety of the Hanford Site workforce has been bolstered with another program added to the list of Site-wide Safety Standards. The latest Site-wide Safety Standard covers Fall Protection.

  4. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011

    Broader source: Energy.gov [DOE]

    PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis.

  5. Mapping the Potential for Biofuel Production on Marginal Lands: Differences in Definitions, Data and Models across Scales

    E-Print Network [OSTI]

    Lewis, Sarah M

    2014-01-01T23:59:59.000Z

    D. Land availability for biofuel production. Environ. Sci.of land available for biofuel production. Environ. Sci.so marginal land for biofuel crops is limited. Energy Policy

  6. Why Have Bank Interest Margins Been so High in Indonesia since the 1997/1998 Financial Crisis?

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    this fact. Demirgüç- Kunt and Huizinga (1998) show that the average margins of Indonesian banks for the 1988

  7. Vehicle Battery Safety Roadmap Guidance

    SciTech Connect (OSTI)

    Doughty, D. H.

    2012-10-01T23:59:59.000Z

    The safety of electrified vehicles with high capacity energy storage devices creates challenges that must be met to assure commercial acceptance of EVs and HEVs. High performance vehicular traction energy storage systems must be intrinsically tolerant of abusive conditions: overcharge, short circuit, crush, fire exposure, overdischarge, and mechanical shock and vibration. Fail-safe responses to these conditions must be designed into the system, at the materials and the system level, through selection of materials and safety devices that will further reduce the probability of single cell failure and preclude propagation of failure to adjacent cells. One of the most important objectives of DOE's Office of Vehicle Technologies is to support the development of lithium ion batteries that are safe and abuse tolerant in electric drive vehicles. This Roadmap analyzes battery safety and failure modes of state-of-the-art cells and batteries and makes recommendations on future investments that would further DOE's mission.

  8. Autoclave nuclear criticality safety analysis

    SciTech Connect (OSTI)

    D`Aquila, D.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States); Tayloe, R.W. Jr. [Battelle, Columbus, OH (United States)

    1991-12-31T23:59:59.000Z

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  9. Environment, Safety and Health Reporting

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-01-01T23:59:59.000Z

    To ensure timely collection, reporting, analysis, and dissemination of information on environment, safety, and health issues as required by law or regulations or as needed to ensure that the Department of Energy (DOE) and National Nuclear Security Administration are kept fully informed on a timely basis about events that could adversely affect the health and safety of the public or the workers, the environment, the intended purpose of DOE facilities, or the credibility of the Department. Cancels DOE O 210.1, DOE O 231.1, DOE O 232.1A. Canceled by DOE O 231.1B. DOE O 231.1B cancels all portions pertaining to environment, safety, and health reporting. Occurrence reporting and processing of operations information provisions remain in effect until January 1, 2012.

  10. System safety management lessons learned

    SciTech Connect (OSTI)

    Piatt, J.A.

    1989-05-01T23:59:59.000Z

    The Assistant Secretary of the Army for Research, Development and Acquisition directed the Army Safety Center to provide an audit of the causes of accidents and safety of use restrictions on recently fielded systems by tracking residual hazards back through the acquisition process. The objective was to develop ''lessons learned'' that could be applied to the acquisition process to minimize mishaps in fielded systems. System safety management lessons learned are defined as Army practices or policies, derived from past successes and failures, that are expected to be effective in eliminating or reducing specific systemic causes of residual hazards. They are broadly applicable and supportive of the Army structure and acquisition objectives. 29 refs., 7 figs.

  11. Nuclear reactor safety heat transfer

    SciTech Connect (OSTI)

    Jones, O.C.

    1982-07-01T23:59:59.000Z

    Reviewed is a book which has 5 parts: Overview, Fundamental Concepts, Design Basis Accident-Light Water Reactors (LWRs), Design Basis Accident-Liquid-Metal Fast Breeder Reactors (LMFBRs), and Special Topics. It combines a historical overview, textbook material, handbook information, and the editor's personal philosophy on safety of nuclear power plants. Topics include thermal-hydraulic considerations; transient response of LWRs and LMFBRs following initiating events; various accident scenarios; single- and two-phase flow; single- and two-phase heat transfer; nuclear systems safety modeling; startup and shutdown; transient response during normal and upset conditions; vapor explosions, natural convection cooling; blockages in LMFBR subassemblies; sodium boiling; and Three Mile Island.

  12. A bootstrap towards asymptotic safety

    E-Print Network [OSTI]

    K. Falls; D. F. Litim; K. Nikolakopoulos; C. Rahmede

    2013-01-17T23:59:59.000Z

    A search strategy for asymptotic safety is put forward and tested for a simplified version of gravity in four dimensions using the renormalization group. Taking the action to be a high-order polynomial of the Ricci scalar, a self-consistent ultraviolet fixed point is found where curvature invariants become increasingly irrelevant with increasing mass dimension. Intriguingly, universal scaling exponents take near-Gaussian values despite the presence of residual interactions. Asymptotic safety of metric gravity would seem in reach if this pattern carries over to the full theory.

  13. Environment, Safety, and Health Reporting

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2003-08-19T23:59:59.000Z

    To ensure timely collection, reporting, analysis, and dissemination of information on environment, safety, and health issues as required by law or regulations or as needed to ensure that the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) are kept fully informed on a timely basis about events that could adversely affect the health and safety of the public or the workers, the environment, the intended purpose of DOE facilities, or the credibility of the Department. Cancels DOE O 210.1, DOE O 231.1, and DOE O 232.1A. Canceled by DOE O 232.2.

  14. Safety Around Sources of Radiation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguards andSafety Alerts Safety

  15. Safety Comes First | Jefferson Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton nSafeguards andSafety AlertsSafety

  16. Environment/Health/Safety Concerns

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville Power AdministrationField8, 2000ConsumptionInnovationEnvironment, SafetySafetyEHS Emergencies

  17. BioSafety On Campus Holiday Fire Safety

    E-Print Network [OSTI]

    Becker, Luann

    to biohazardous or potentially infectious agents. At UCSB, the Biological Safety Program is one of five units an average of 24 civilian deaths, 27 civilian injuries, and $13.3 million in direct property damage per year of the total number of natural Christmas trees sold, which is estimated at 30 million trees, in the United

  18. ENVIRONMENT, SAFETY, HEALTH, AND QUALITY DIVISION Chapter 42: Subcontractor Safety

    E-Print Network [OSTI]

    Wechsler, Risa H.

    URL: http://www-group.slac.stanford.edu/esh/eshmanual/references/subcontractorProcedNonGreen.pdf 1 Purpose The purpose of this procedure is to ensure that SLAC's environment, safety, and health (ESH) requirements, as documented in the hazard-specific chapters of this ESH Manual, are incorporated

  19. ENVIRONMENT, SAFETY, HEALTH, AND QUALITY DIVISION Chapter 42: Subcontractor Safety

    E-Print Network [OSTI]

    Wechsler, Risa H.

    to persons, damage to property, or harm to the environment could bring operations at SLAC to a halt. To avoid Manual (SLAC-I-720-0A29Z-001) Chapter 42, "Subcontractor Safety" Or contact the program manager. 26 line managers, points of contact (POCs), project managers (PMs), field construction and service

  20. Health and Safety Policy Statement4 Health and Safety Policy

    E-Print Network [OSTI]

    Haase, Markus

    To achieve this, the University will ensure effective management of risk by setting and reviewing a quality-based health and safety management system and workplace health framework, and by allocating the resources necessary to attain these. It will also define clear management systems and ensure the involvement of all

  1. 324 Building safety basis criteria document

    SciTech Connect (OSTI)

    STEFFEN, J.M.

    1999-06-02T23:59:59.000Z

    The Safety Basis Criteria document describes the proposed format, content, and schedule for the preparation of an updated Safety Analysis Report (SAR) and Operational Safety Requirements document (OSR) for the 324 Building. These updated safety authorization basis documents are intended to cover stabilization and deactivation activities that will prepare the facility for turnover to the Environmental Restoration Contractor for final decommissioning. The purpose of this document is to establish the specific set of criteria needed for technical upgrades to the 324 Facility Safety Authorization Basis, as required by Project Hanford Procedure HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval.

  2. Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-03-28T23:59:59.000Z

    This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

  3. CRAD, Engineering Design and Safety Basis - December 22, 2009...

    Broader source: Energy.gov (indexed) [DOE]

    Engineering Design and Safety Basis - December 22, 2009 CRAD, Engineering Design and Safety Basis - December 22, 2009 December 22, 2009 Engineering Design and Safety Basis...

  4. Office of Environment, Safety and Health Evaluations Appraisal...

    Broader source: Energy.gov (indexed) [DOE]

    of ES&H Evaluations HSS Office of Health, Safety and Security ISM Integrated Safety Management QRB Quality Review Board TSR Technical Safety Requirement VSF Vital Systems...

  5. Safety and Occupational Health Specialist (Fall Protection Specialist)

    Broader source: Energy.gov [DOE]

    The incumbent in this position serves as a Fall Protection Specialist in the Safety Office. Safety is responsible for administering BPA's safety program and providing advice, counsel, direction,...

  6. National Report Joint Convention on the Safety of Spent Fuel...

    Office of Environmental Management (EM)

    National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management National Report Joint Convention on the Safety of Spent...

  7. Marginal costs of freeway traffic congestion with on-road pollution exposure externality

    E-Print Network [OSTI]

    Bertini, Robert L.

    Marginal costs of freeway traffic congestion with on-road pollution exposure externality Alexander August 2012 Received in revised form 6 March 2013 Accepted 23 September 2013 Keywords: External costs Traffic congestion On-road In-vehicle Pollution exposure Vehicle emissions a b s t r a c t The health cost

  8. Leverage and Beliefs: Personal Experience and Risk Taking in Margin Lending*

    E-Print Network [OSTI]

    Straight, Aaron

    Leverage and Beliefs: Personal Experience and Risk Taking in Margin Lending* Peter Koudijs+ Hans of financial distress to address this question. An investor syndicate speculating in English stocks went times, and declining when asset prices fall (Adrian and Shin 2010). For example, when the stock market

  9. Separation and Volatility of Locational Marginal Prices in Restructured Wholesale Power Markets

    E-Print Network [OSTI]

    Tesfatsion, Leigh

    1 Separation and Volatility of Locational Marginal Prices in Restructured Wholesale Power Markets (LMPs) in an ISO-managed restructured wholesale power market operating over an AC transmission grid-determining) generation companies induce correlations among neighboring LMPs. Index Terms--Restructured wholesale power

  10. The marginal cost of carbon abatement from planting street trees in New York City

    E-Print Network [OSTI]

    Fried, Jeremy S.

    cooling and heating energy consumption of buildings through the process of transpiration, shadingAnalysis The marginal cost of carbon abatement from planting street trees in New York City Kent F Buford Avenue, St. Paul, MN 55108, United States d Yale University, 195 Prospect Street, New Haven, CT

  11. Proceedings of the Combustion Institute, Volume 28, 2000/pp. 757763 EXPERIMENTAL DETERMINATION OF THE STABILITY MARGIN

    E-Print Network [OSTI]

    Lieuwen, Timothy C.

    757 Proceedings of the Combustion Institute, Volume 28, 2000/pp. 757­763 EXPERIMENTAL DETERMINATION the response of the combustion process heat release to driven flow oscillations and the response determine the stability margin of combustors. Such an approach would enable combustion engi- neers

  12. Using Temporal Information in an Automated Classification of Summer, Marginal Ice Zone Imagery*

    E-Print Network [OSTI]

    Kansas, University of

    Using Temporal Information in an Automated Classification of Summer, Marginal Ice Zone Imagery, even with the human eye. BackScatter instability causu the intensities of the fiistyear ice, multiyear ice, and open water classes to intermix, thus making an intensity-based classification invalid

  13. Power Control by Kalman Filter With Error Margin for Wireless IP Networks

    E-Print Network [OSTI]

    Leung, Kin K.

    Power Control by Kalman Filter With Error Margin for Wireless IP Networks Kin K. Leung AT&T Labs, Room 4-120 100 Schulz Drive Red Bank, NJ 07701 Email: kkleung@research.att.com ABSTRACT A power-control enough due to little interference temporal correlation. In this paper, we enhance the power-control

  14. Eastern margin variability of the South Pacific Convergence Zone Benjamin R. Lintner1

    E-Print Network [OSTI]

    Lintner, Benjamin Richard

    intensity associated with increased moisture near the mean eastern SPCZ margin and an eastward displacement a spurious ``double ITCZ'' [Zhang, 2001]. Such behavior may stem from deficiencies in ocean: Scientific programme overview, 2006, available at http://www.eol. ucar.edu/projects/vocals]. [3] Regionally

  15. Eos, Vol. 89, No. 7, 12 February 2008 Understanding passive margins--thick

    E-Print Network [OSTI]

    Stern, Robert J.

    carbon dioxide. Natural hazards of hurricanes, tsunamis, sea level rise, and rapid subsidence imaging to better understand the 4-D evolution of the conti- nental United States. GeoSwath empha- sizes conti- nental evolution. Passive margins are built above broad transitional zones, several hun- dred

  16. Review article Assessment of tsunami hazard to the U.S. Atlantic margin

    E-Print Network [OSTI]

    ten Brink, Uri S.

    , and the presence of ten nuclear power plants along the coast, make this region highly vulnerable to flooding to the generation of landslides along the U.S. Atlantic margin. Analysis of landslide statistics along the fluvial initiated by seismic acceleration, and failed as aggregate slope failures. How tsunamis are generated from

  17. Marginally trapped surfaces in L4 an extended Weierstrass-Bryant representation

    E-Print Network [OSTI]

    Gálvez, José Antonio

    Marginally trapped surfaces in L4 and an extended Weierstrass-Bryant representation Juan A. Aledoa-30203 Cartagena, Murcia, Spain. e-mail: pablo.mira@upct.es Date: February 2, 2005 Keywords: Bryant surfaces in L3, and the Bryant repre- sentation for mean curvature one surfaces in the hyperbolic 3-space

  18. Author's personal copy Methane seepage along the Hikurangi Margin of New Zealand: Geochemical

    E-Print Network [OSTI]

    Wehrli, Bernhard

    : Methane seepage gas hydrate water column sea surface carbon isotopes Hikurangi Margin The concentration and carbon isotope values of dissolved methane were measured in the water column at Rock Garden, Omakere­Temperature­Depth (CTD) operations were at Faure Site of Rock Garden. Here, seafloor bubble release was observed by ROV

  19. Non-marginally bound inhomogeneous dust collapse in higher dimensional space-time

    E-Print Network [OSTI]

    S. G. Ghosh; A. Banerjee

    2002-12-16T23:59:59.000Z

    We investigate the occurrence and nature of a naked singularity in the gravitational collapse of an inhomogeneous dust cloud described by a self-similar higher dimensional Tolman-Bondi space-time. Bound, marginally bound and unbound space-times are analyzed. The degree of inhomogeneity of the collapsing matter necessary to form a naked singularity is given.

  20. Optimized planning target volume margin in helical tomotherapy for prostate cancer: is there a preferred method?

    E-Print Network [OSTI]

    Cao, Yuan Jie; Chang, Kyung Hwan; Shim, Jang Bo; Kim, Kwang Hyeon; Jang, Min Sun; Yoon, Won Sup; Yang, Dae Sik; Park, Young Je; Kim, Chul Yong

    2015-01-01T23:59:59.000Z

    To compare the dosimetrical differences between plans generated by helical tomotherapy using 2D or 3D margining technique in in prostate cancer. Ten prostate cancer patients were included in this study. For 2D plans, planning target volume (PTV) was created by adding 5 mm (lateral/anterior-posterior) to clinical target volume (CTV). For 3D plans, 5 mm margin was added not only in lateral/anterior-posterior, but also in superior-inferior to CTV. Various dosimetrical indices, including the prescription isodose to target volume (PITV) ratio, conformity index (CI), homogeneity index (HI), target coverage index (TCI), modified dose homogeneity index (MHI), conformation number (CN), critical organ scoring index (COSI), and quality factor (QF) were determined to compare the different treatment plans. Differences between 2D and 3D PTV indices were not significant except for CI (p = 0.023). 3D margin plans (11195 MUs) resulted in higher (13.0%) monitor units than 2D margin plans (9728 MUs). There were no significant d...