National Library of Energy BETA

Sample records for informed safety margin

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

    SciTech Connect (OSTI)

    Curtis Smith

    2014-06-01

    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.

  2. A risk-informed approach to safety margins analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-07-01

    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.

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

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-03-01

    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.

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

    SciTech Connect (OSTI)

    Robert W Youngblood

    2010-09-01

    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.

  5. 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

    2014-09-01

    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.

  6. 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

    2012-08-01

    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.

  7. 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

    2014-06-01

    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.

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

    SciTech Connect (OSTI)

    D. Blanchard; R. Youngblood

    2012-04-01

    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.

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

    SciTech Connect (OSTI)

    R. Youngblood; D. Blanchard

    2011-09-01

    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.

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

    SciTech Connect (OSTI)

    Curtis Smith; Cristian Rabiti; Richard Martineau

    2012-11-01

    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.”

  11. On the quantification of safety margins

    E-Print Network [OSTI]

    Pagani, Lorenzo P

    2004-01-01

    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 ...

  12. 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.

    2012-09-20

    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.

  13. 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

  14. Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings

    SciTech Connect (OSTI)

    Dey, M. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Arsenault, F.; Patterson, M.; Gaal, M. [SCIENTECH, Inc., Rockville, MD (United States)

    1993-09-01

    These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission`s Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements.

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

    SciTech Connect (OSTI)

    Beaulieu, R. A.

    2013-10-03

    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.

  16. 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION JEnvironmentalBowerbank, Maine:Kansas: Energy ResourcesParish,Caldera Rim Margins Jump to:

  17. pamphlet04.doc SAFETY INFORMATION

    E-Print Network [OSTI]

    pamphlet04.doc SAFETY INFORMATION EMPLOYEE HANDOUT EMERGENCY ASSISTANCE (Fire, Police, Accident of Hazardous Materials Into/Outside the UCHC #12;pamphlet04.doc 1. SAFETY POLICY: The Health Center continually

  18. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12University Safety NumerousSafety

  19. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 ofSafety Staff

  20. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 ofSafety

  1. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12University Safety

  2. 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)

    2008-07-15

    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)

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

    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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterestedReplacement-2-A WholesaleRetrofit

  4. Risk Informed Safety Margin Characterization Case Study: Selection 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergyInterestedReplacement-2-A WholesaleRetrofitElectrical Equipment To Be Subjected to

  5. 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

    2013-08-01

    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.

  6. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    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)

  7. Quantification of margins and uncertainty for risk-informed decision analysis.

    SciTech Connect (OSTI)

    Alvin, Kenneth Fredrick

    2010-09-01

    QMU stands for 'Quantification of Margins and Uncertainties'. QMU is a basic framework for consistency in integrating simulation, data, and/or subject matter expertise to provide input into a risk-informed decision-making process. QMU is being applied to a wide range of NNSA stockpile issues, from performance to safety. The implementation of QMU varies with lab and application focus. The Advanced Simulation and Computing (ASC) Program develops validated computational simulation tools to be applied in the context of QMU. QMU provides input into a risk-informed decision making process. The completeness aspect of QMU can benefit from the structured methodology and discipline of quantitative risk assessment (QRA)/probabilistic risk assessment (PRA). In characterizing uncertainties it is important to pay attention to the distinction between those arising from incomplete knowledge ('epistemic' or systematic), and those arising from device-to-device variation ('aleatory' or random). The national security labs should investigate the utility of a probability of frequency (PoF) approach in presenting uncertainties in the stockpile. A QMU methodology is connected if the interactions between failure modes are included. The design labs should continue to focus attention on quantifying uncertainties that arise from epistemic uncertainties such as poorly-modeled phenomena, numerical errors, coding errors, and systematic uncertainties in experiment. The NNSA and design labs should ensure that the certification plan for any RRW is supported by strong, timely peer review and by an ongoing, transparent QMU-based documentation and analysis in order to permit a confidence level necessary for eventual certification.

  8. Nuclear safety information sharing agreement between NRC and...

    Office of Environmental Management (EM)

    for DOE and NRC to exchange information related to safety issues associated with non-reactor nuclear facilities. The NRC-DOE Inter-Agency nuclear safety information sharing...

  9. Quantifying reactor safety margins: Part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

    SciTech Connect (OSTI)

    Boyack, B.E.; Duffey, R.B.; Griffith, P.; Katsma, K.R.; Lellouche, G.S.; Levy, S.; Rohatgi, U.S.; Wilson, G.E.; Wulff, W.; Zuber, N.

    1988-01-01

    In August 1988, the Nuclear Regulatory Commission (NRC) approved the final version of a revised rule on the acceptance of emergency core cooling systems (ECCS) entitled ''Emergency Core Cooling System; Revisions to Acceptance Criteria.'' The revised rule states an alternate ECCS performance analysis, based on best-estimate methods, may be used to provide more realistic estimates of plant safety margins, provided the licensee quantifies the uncertainty of the estimates and included that uncertainty when comparing the calculated results with prescribed acceptance limits. To support the revised ECCS rule, the NRC and its contractors and consultants have developed and demonstrated a method called the Code Scaling, Applicability, and Uncertainty (CSAU) evaluation methodology. It is an auditable, traceable, and practical method for combining quantitative analyses and expert opinions to arrive at computed values of uncertainty. This paper provides an overview of the CSAU evaluation methodology and its application to a postulated cold-leg, large-break loss-of-coolant accident in a Westinghouse four-loop pressurized water reactor with 17 /times/ 17 fuel. The code selected for this demonstration of the CSAU methodology was TRAC-PF1/MOD1, Version 14.3. 23 refs., 5 figs., 1 tab.

  10. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Office of Environmental Management (EM)

    for the two agencies to exchange information related to safety issues associated with non-reactor nuclear facilities that would be beneficial to both agencies in performance of...

  11. Safety and Operational Guidelines | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page onRAPID/Geothermal/Exploration/ColoradoRemsenburg-Speonk, NewMichigan:Roxbury,RushS.KSPARQLSacketsSafety and Operational

  12. Fire and Life Safety Information - Hanford Site

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFES OctoberEvanServices » IncentivesStocks 7,171Fire Department

  13. 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)

    2008-07-15

    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)

  14. SECTION 13-CHEMICAL SAFETY NOTE: Much of the information contained in this Chemical Safety section is duplicated from the

    E-Print Network [OSTI]

    Selmic, Sandra

    164 SECTION 13- CHEMICAL SAFETY NOTE: Much of the information contained in this Chemical Safety section is duplicated from the "Chemical Hygiene Plan for Laboratories" in the Louisiana Tech University ( Section 12) when working with chemicals. REQULATORY BASIS FOR RULES GOVERNING THE SAFE USE OF CHEMICALS

  15. Nuclear Safety Information Agreement Between the U.S. Nuclear...

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

    Environment, Health, Safety and Security (EHSS DOE), Cathy Haney (Director, Office of Nuclear Materials Safety and Safeguards (NRC)), Marissa Bailey (Director, Division of Fuel...

  16. Revised: February 2013 Information for Laboratory Safety and Important Contacts

    E-Print Network [OSTI]

    Haykin, Simon

    from safety shower immediately or 2. Roll on floor and scream for help or 3. Wrap with fire blanket to smother flame (a coat or other nonflammable fibe

  17. Laser safety information for the Atomic, Molecular and Optical (AMO) Physics Labs at Lehigh University modified from the laser safety program developed by the office of Environmental

    E-Print Network [OSTI]

    Huennekens, John

    1 Laser safety information for the Atomic, Molecular and Optical (AMO) Physics Labs at Lehigh University modified from the laser safety program developed by the office of Environmental Health and Safety using the following reference materials: I. American National Standards for Safe Use of Lasers - ANSI Z

  18. Stanford School of Medicine ILC LK005 Project Classroom Safety Training Information and Certification

    E-Print Network [OSTI]

    Kay, Mark A.

    : ______________ (must be Stanford faculty or management staff) Reserving space in the ILC Project Classroom LK005Stanford School of Medicine ILC LK005 Project Classroom Safety Training Information on the Stanford SU-17 form. LK005 Project Classroom Safety Rules and Procedures 1. Food and Beverages or Cosmetic

  19. UMTS on the Road: Broadcasting Intelligent Road Safety Information via MBMS

    E-Print Network [OSTI]

    Zemen, Thomas

    UMTS on the Road: Broadcasting Intelligent Road Safety Information via MBMS Danilo Valerio, Fabio, intersection safety, road congestion warning, accident warning, etc. All these services aim at increasing road resources imposing a severe limit to the sustainable number of users. In this work we quantify this limit

  20. Safety

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

    General Employee Radiological HS4240-W Chemical Safety HS4680-W PPE To access these training modules link here LTRAIN from inside LLNL, or here from anywhere. All JLF...

  1. Safety and Health Regulatory and Policy Response Line- General Information

    Broader source: Energy.gov [DOE]

    The DOE Worker Safety and Health Standards Response Line, established in 1992, is a service that responds to questions DOE, DOE contractor, and DOE subcontractor personnel regarding DOE-adopted and -prescribed standards and directives. These responses may not represent official OSHA policies.

  2. seismic margin

    Office of Scientific and Technical Information (OSTI)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnicalInformation4563 LLNL Small-scale Friction Sensitivityv b, iNOTICE OF OPEN CHANGE

  3. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    SciTech Connect (OSTI)

    Monteleone, S.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  4. Transactions of the twenty-fifth water reactor safety information meeting

    SciTech Connect (OSTI)

    Monteleone, S.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

  5. 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

    2013-11-01

    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.

  6. Lead Safety Awareness This Bulletin provides information on the safe handling of lead

    E-Print Network [OSTI]

    Lead Safety Awareness PURPOSE This Bulletin provides information on the safe handling of lead and lead compounds during use and storage. Improper handling of lead and lead compounds may impact operations at Department of Energy (DOE) facilities. BACKGROUND Lead is found in batteries, pipes, solder

  7. Technical background information for the environmental and safety report, Volume 4: White Oak Lake and Dam

    SciTech Connect (OSTI)

    Oakes, T.W.; Kelly, B.A.; Ohnesorge, W.F.; Eldridge, J.S.; Bird, J.C.; Shank, K.E.; Tsakeres, F.S.

    1982-03-01

    This report has been prepared to provide background information on White Oak Lake for the Oak Ridge National Laboratory Environmental and Safety Report. The paper presents the history of White Oak Dam and Lake and describes the hydrological conditions of the White Oak Creek watershed. Past and present sediment and water data are included; pathway analyses are described in detail.

  8. DAM SAFETY DECISION-MAKING: COMBINING ENGINEERING ASSESSMENTS WITH RISK INFORMATION

    E-Print Network [OSTI]

    Bowles, David S.

    DAM SAFETY DECISION-MAKING: COMBINING ENGINEERING ASSESSMENTS WITH RISK INFORMATION David S. Bowles breaching a dam; so drop the matter before a dispute breaks out. Proverbs 17:14 (NIV) ABSTRACT A decision assessments and risk assessments. The approach can be adapted to any dam owner's unique decision context

  9. Informational meeting on new environmental health and safety master's

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation CurrentHenry Bellamy,ImpactScientificInfluence ofMedia on

  10. Embrittlement Database from the Radiation Safety Information Computational Center

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    The Embrittlement Data Base (EDB) is a comprehensive collection of data from surveillance capsules of U.S. commercial nuclear power reactors and from experiments in material test reactors. The collected data are contained in either the Power Reactor Embrittlement Data Base (PR-EDB) or the Test Reactor Embrittlement Data Base (TR-EDB). The EDB work includes verification of the quality of the EDB, provision for user-friendly software to access and process the data, exploration and/or confirmation of embrittlement prediction models, provision for rapid investigation of regulatory issues, and provision for the technical bases for voluntary consensus standards or regulatory guides. The EDB is designed for use with a personal computer. The data are collected into "raw data files." Traceability of all data is maintained by including complete references along with the page numbers. External data verification of the PR-EDB is the responsibility of the vendors, who were responsible for the insertion and testing of the materials in the surveillance capsules. Internal verification is accomplished by checking against references and checking for inconsistencies. Examples of information contained in the EDBs are: Charpy data, tensile data, reactor type, irradiation environments, fracture toughness data, instrumented Charpy data, pressure-temperature (P-T) data, chemistry data, and material history. The TR-EDB additionally has annealing Charpy data. The current version of the PR-EDB contains the test results from 269 Charpy capsules irradiated in 101 reactors. These results include 320 plate data points, 123 forging data points, 113 standard reference materials (SRMS) or correlation monitor (CM) points, 244 weld material data points, and 220 heat-affected-zone (HAZ) material data points. Similarly, the TR-EDB contains information for 290 SRM or CM points, 342 plate data points, 165 forging data points, 378 welds, and 55 HAZ materials. [copied from http://rsicc.ornl.gov/RelatedLinks.aspx?t=edb

  11. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    SciTech Connect (OSTI)

    Daling, P.M.; Lavender, J.C.

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983).

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

    SciTech Connect (OSTI)

    Smith, Curtis L; Mandelli, Diego; Zhegang Ma

    2014-11-01

    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.

  13. Printed copies of the WSU Spokane Annual Security/Fire Safety Report can be obtained at the Office of Security and Public Safety. Information prepared by the Office of Security and Public

    E-Print Network [OSTI]

    Collins, Gary S.

    of Security and Public Safety. Information prepared by the Office of Security and Public Safety at WSU Spokane and Security Department Information 3 Reporting, Access and Programs 3-5 Policies and Procedures 6Printed copies of the WSU Spokane Annual Security/Fire Safety Report can be obtained at the Office

  14. Liquid-metal fast-breeder reactors: Preliminary safety and environmental information document. Volume VI

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning LMFBR design characteristics; uranium-plutonium/uranium recycle homogeneous core; uranium-plutonium/uranium spiked recycle heterogeneous core; uranium-plutonium/uranium spiked recycle homogeneous core; uranium-plutonium/thorium spiked recycle heterogeneous core; uranium-plutonium/thorium spiked recycle homogeneous core; thorium-plutonium/thorium spiked recycle homogeneous core; denatured uranium-233/thorium cycle homogeneous core; safety consideration for the LMFBR; and environmental considerations.

  15. Coastal ocean margins program

    SciTech Connect (OSTI)

    Not Available

    1988-12-01

    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.

  16. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    SciTech Connect (OSTI)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  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

    2011-10-20

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

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli; Cristian Rabiti

    2013-11-01

    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.

  19. Preliminary Safety Information Document for the Standard MHTGR. Volume 1, (includes latest Amendments)

    SciTech Connect (OSTI)

    1986-12-01

    With NRC concurrence, the Licensing Plan for the Standard HTGR describes an application program consistent with 10CFR50, Appendix O to support a US Nuclear Regulatory Commission (NRC) review and design certification of an advanced Standard modular High Temperature Gas-Cooled Reactor (MHTGR) design. Consistent with the NRC's Advanced Reactor Policy, the Plan also outlines a series of preapplication activities which have as an objective the early issuance of an NRC Licensability Statement on the Standard MHTGR conceptual design. This Preliminary Safety Information Document (PSID) has been prepared as one of the submittals to the NRC by the US Department of Energy in support of preapplication activities on the Standard MHTGR. Other submittals to be provided include a Probabilistic Risk Assessment, a Regulatory Technology Development Plan, and an Emergency Planning Bases Report.

  20. Hydrogen Safety Panel

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

    or otherwise restricted information. Project ID: scs07weiner PNNL-SA-65397 2 IEA HIA Task 19 Working Group Hydrogen Safety Training Props Hydrogen Safety Panel Incident...

  1. Consumers' Dependency on Media for Information about Food Safety Incidents Related to the Beef Industry 

    E-Print Network [OSTI]

    Charanza, Ashley

    2012-10-19

    Food safety has become an important topic in today's mainstream media. Food safety incidents, specifically related to the beef industry, have the potential to damage the beef industry severely, and negative coverage in the media can alter consumers...

  2. IN AN EMERGENCY, CALL PUBLIC SAFETY AT 843.953.5611 Stay informed. Be prepared. Visit emergency.cofc.edu

    E-Print Network [OSTI]

    Kunkle, Tom

    IN AN EMERGENCY, CALL PUBLIC SAFETY AT 843.953.5611 Stay informed. Be prepared. Visit emergency instructions from emergency personnel · Do not use elevators. · Take personal belongings (ID, keys, purses authorized to do so by emergency personnel. FIRES · Activate the nearest fire alarm pull station. · Call

  3. Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics

    SciTech Connect (OSTI)

    Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1993-03-01

    This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

  4. ENVIRONMENTAL, HEALTH AND SAFETY

    E-Print Network [OSTI]

    California at Davis, University of

    ENVIRONMENTAL, HEALTH AND SAFETY PROGRAMS SPRING 2012 Including: Free Information Session New Program in Health and Safety CONTINUING AND PROFESSIONAL EDUCATION #12;2 Our Health and Safety Programs Workplace Health and Safety Certificate Program For every dollar invested in workplace safety, organizations

  5. 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...

  6. Approved Module Information for EC214C, 2014/5 Module Title/Name: Health, Safety & Risk Module Code: EC214C

    E-Print Network [OSTI]

    Neirotti, Juan Pablo

    Outcomes: * Intellecutal skills Assess the risks associated with workplaces, machinery, processes, and work the principles and application of health safety and risk management practices within the construction workApproved Module Information for EC214C, 2014/5 Module Title/Name: Health, Safety & Risk Module Code

  7. ACCESSING ROAD TRAVEL REPORTS The safest traveler is the well-informed traveler. While road safety conditions in a country affect that country's

    E-Print Network [OSTI]

    Arnold, Jonathan

    ACCESSING ROAD TRAVEL REPORTS The safest traveler is the well-informed traveler. While road safety of countries will appear and you can view each road travel report by clicking "Download Now". #12;

  8. Guidelines for nuclear-power-plant safety-issue-prioritization information development

    SciTech Connect (OSTI)

    Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L.; Smith, R.I.; Weakley, S.A.

    1983-02-01

    Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions.

  9. November 2014 Laboratory Safety Manual Appendix C Templates for Lab-Specific Information

    E-Print Network [OSTI]

    Brown, Sally

    or laboratory. This CHP covers the following laboratory spaces: Building(s): Room #(s): If Parts of Room your lab's Chemical Hygiene Plan (CHP). These templates are also available as documents which can's CHP consists of the generic UW Laboratory Safety Manual plus your lab's laboratory- specific

  10. The New Mexico State University Police Department's Crime Prevention and Public Information Offices Presents Pedestrian Safety

    E-Print Network [OSTI]

    Johnson, Eric E.

    Presents Pedestrian Safety: It's Not Just For Kids We have been doing it since we could walk, but aside, pedestrians have great latitude in what they can do, with only the following restrictions: When available, pedestrians must generally cross at crosswalks. Cities are authorized to mandate crossing only at crosswalks

  11. Residence Hall Fire Safety

    E-Print Network [OSTI]

    Residence Hall Fire Safety Information Department of Public Safety Residential Life & Housing #12;Part 1 ! Building Information Pursuant to New York City Fire Code and Local Law 10, this Fire Safety, as well as what to do in a fire emergency. Building Construction Residential buildings built before 1968

  12. Central Coast consumers want more food-related information, from safety to ethics

    E-Print Network [OSTI]

    Howard, Phil

    2006-01-01

    of food packaging or food waste. Several participants notedwas grown and the fate of food waste. Preferred information

  13. Generic safety documentation model

    SciTech Connect (OSTI)

    Mahn, J.A.

    1994-04-01

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

  14. Transactions of the twenty-third water reactor safety information meeting to be held at Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995

    SciTech Connect (OSTI)

    Monteleone, S. [comp.

    1995-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 23rd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory, Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  15. 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

  16. SU-E-T-573: The Robustness of a Combined Margin Recipe for Uncertainties During Radiotherapy

    SciTech Connect (OSTI)

    Stroom, J; Vieira, S; Greco, C [Champalimaud Foundation, Lisbon, Lisbon (Portugal)

    2014-06-01

    Purpose: To investigate the variability of a safety margin recipe that combines CTV and PTV margins quadratically, with several tumor, treatment, and user related factors. Methods: Margin recipes were calculated by monte-carlo simulations in 5 steps. 1. A spherical tumor with or without isotropic microscopic was irradiated with a 5 field dose plan2. PTV: Geometric uncertainties were introduced using systematic (Sgeo) and random (sgeo) standard deviations. CTV: Microscopic disease distribution was modelled by semi-gaussian (Smicro) with varying number of islets (Ni)3. For a specific uncertainty set (Sgeo, sgeo, Smicro(Ni)), margins were varied until pre-defined decrease in TCP or dose coverage was fulfilled. 4. First, margin recipes were calculated for each of the three uncertainties separately. CTV and PTV recipes were then combined quadratically to yield a final recipe M(Sgeo, sgeo, Smicro(Ni)).5. The final M was verified by simultaneous simulations of the uncertainties.Now, M has been calculated for various changing parameters like margin criteria, penumbra steepness, islet radio-sensitivity, dose conformity, and number of fractions. We subsequently investigated A: whether the combined recipe still holds in all these situations, and B: what the margin variation was in all these cases. Results: We found that the accuracy of the combined margin recipes remains on average within 1mm for all situations, confirming the correctness of the quadratic addition. Depending on the specific parameter, margin factors could change such that margins change over 50%. Especially margin recipes based on TCP-criteria are more sensitive to more parameters than those based on purely geometric Dmin-criteria. Interestingly, measures taken to minimize treatment field sizes (by e.g. optimizing dose conformity) are counteracted by the requirement of larger margins to get the same tumor coverage. Conclusion: Margin recipes combining geometric and microscopic uncertainties quadratically are accurate under varying circumstances. However margins can change up to 50% for different situations.

  17. Facility Safety

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

    1996-10-24

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

  18. Facility Safety

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

    1995-11-16

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

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

    SciTech Connect (OSTI)

    Szilard, Ronaldo H; Smith, Curtis L

    2014-09-01

    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.

  20. 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 ...

  1. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

  2. IMPROVING EFFICIENT MARGINAL ESTIMATORS IN BIVARIATE MODELS WITH PARAMETRIC MARGINALS

    E-Print Network [OSTI]

    Schick, Anton

    AND ANTON SCHICK Abstract. Suppose we have data from a bivariate model with parametric marginals. Efficient nonparametric estimators in the presence of a constraint, see e.g. Schick and Wefelmeyer (2008) for a recent = The research of Hanxiang Peng was supported in parts by NSF Grant DMS 0940365. The research of Anton Schick

  3. Annual Fire Safety Report

    E-Print Network [OSTI]

    2014 Annual Fire Safety Report University of California, Santa Barbara Fire Marshals) requires that certain information pertaining to the Fire Safety in Student Housing Buildings of current. #12; 2 9/19/14 HIGHER EDUCATION OPPORTUNITY ACT INTRODUCTION Fire Safety is an essential tool

  4. Ferrocyanide Safety Program: Safety criteria for ferrocyanide watch list tanks

    SciTech Connect (OSTI)

    Postma, A.K.; Meacham, J.E.; Barney, G.S. [and others] [and others

    1994-01-01

    This report provides a technical basis for closing the ferrocyanide Unreviewed Safety Question (USQ) at the Hanford Site. Three work efforts were performed in developing this technical basis. The efforts described herein are: 1. The formulation of criteria for ranking the relative safety of waste in each ferrocyanide tank. 2. The current classification of tanks into safety categories by comparing available information on tank contents with the safety criteria; 3. The identification of additional information required to resolve the ferrocyanide safety issue.

  5. High-temperature gas-cooled reactors: preliminary safety and environmental information document. Volume IV

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning medium-enriched uranium/thorium once-through fuel cycle; medium-enrichment uranium-233/thorium recycle fuel; high-enrichment uranium-235/thorium recycle (spiked) fuel cycle; high-enrichment uranium-233/thorium recycle (spiked) fuel cycle; and gas-turbine high-temperature gas-cooled reactor.

  6. Post this advisory as necessary to keep our community informed. Campus Safety

    E-Print Network [OSTI]

    Miami, University of

    materials from a conex storage box on the MTLSS construction site. An additional vehicle of interest was also observed in the area during the incident. VEHICLE INFORMATION Suspect Vehicle #1 ­ Possible FL Tag OCT### Suspect Vehicle #2 ­ FL Tag 660HMP SUSPECT DESCRIPTION Vehicle #1 ­ Driver ­ Black Male, 5

  7. DOE handbook electrical safety

    SciTech Connect (OSTI)

    1998-01-01

    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.

  8. PAT-1 safety analysis report addendum author responses to request for additional information.

    SciTech Connect (OSTI)

    Weiner, Ruth F.; Schmale, David T.; Kalan, Robert J.; Akin, Lili A.; Miller, David Russell; Knorovsky, Gerald Albert; Yoshimura, Richard Hiroyuki; Lopez, Carlos; Harding, David Cameron; Jones, Perry L.; Morrow, Charles W.

    2010-09-01

    The Plutonium Air Transportable Package, Model PAT-1, is certified under Title 10, Code of Federal Regulations Part 71 by the U.S. Nuclear Regulatory Commission (NRC) per Certificate of Compliance (CoC) USA/0361B(U)F-96 (currently Revision 9). The National Nuclear Security Administration (NNSA) submitted SAND Report SAND2009-5822 to NRC that documented the incorporation of plutonium (Pu) metal as a new payload for the PAT-1 package. NRC responded with a Request for Additional Information (RAI), identifying information needed in connection with its review of the application. The purpose of this SAND report is to provide the authors responses to each RAI. SAND Report SAND2010-6106 containing the proposed changes to the Addendum is provided separately.

  9. Important Propane Safety Information Propane is a fuel that is stored as a liquid and used as a gas. Propane is often used to fuel

    E-Print Network [OSTI]

    Kienzle, Stefan W.

    Important Propane Safety Information Propane is a fuel that is stored as a liquid and used as a gas. Propane is often used to fuel barbeques, appliances in recreational vehicles (RVs), and other portable equipment. Used properly, propane is a safe and convenient fuel. Follow these tips to stay safe. Basics

  10. Information on DOE O 420.1C, Facility Safety | Department of Energy

    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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergy HeadquartersFuelBConservation StandardsEnergyDepartmentOwner (ISO)OfficerInformation

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

    E-Print Network [OSTI]

    2007-01-01

    , USA b Nuclear Power Engineering, Quality and Safety Management Department, Tokyo Electric Power 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

  12. Hydrogen Technologies Safety Guide

    SciTech Connect (OSTI)

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

    2015-01-01

    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.

  13. Investing in International Information Exchange Activities to Improve the Safety, Cost Effectiveness and Schedule of Cleanup - 13281

    SciTech Connect (OSTI)

    Seed, Ian; James, Paula; Mathieson, John; Judd, Laurie; Elmetti-Ramirez, Rosa; Han, Ana

    2013-07-01

    With decreasing budgets and increasing pressure on completing cleanup missions as quickly, safely and cost-effectively as possible, there is significant benefit to be gained from collaboration and joint efforts between organizations facing similar issues. With this in mind, the US Department of Energy (DOE) and the UK Nuclear Decommissioning Authority (NDA) have formally agreed to share information on lessons learned on the development and application of new technologies and approaches to improve the safety, cost effectiveness and schedule of the cleanup legacy wastes. To facilitate information exchange a range of tools and methodologies were established. These included tacit knowledge exchange through facilitated meetings, conference calls and Site visits as well as explicit knowledge exchange through document sharing and newsletters. A DOE web-based portal has been established to capture these exchanges and add to them via discussion boards. The information exchange is operating at the Government-to-Government strategic level as well as at the Site Contractor level to address both technical and managerial topic areas. This effort has resulted in opening a dialogue and building working relationships. In some areas joint programs of work have been initiated thus saving resource and enabling the parties to leverage off one another activities. The potential benefits of high quality information exchange are significant, ranging from cost avoidance through identification of an approach to a problem that has been proven elsewhere to cost sharing and joint development of a new technology to address a common problem. The benefits in outcomes significantly outweigh the costs of the process. The applicability of the tools and methods along with the lessons learned regarding some key issues is of use to any organization that wants to improve value for money. In the waste management marketplace, there are a multitude of challenges being addressed by multiple organizations and the effective pooling and exchange of knowledge and experience can only be of benefit to all participants to help complete the cleanup mission more quickly and more cost effectively. This paper examines in detail the tools and processes used to promote information exchange and the progress made to date. It also discusses the challenges and issues involved and proposes recommendations to others who are involved in similar activities. (authors)

  14. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    SciTech Connect (OSTI)

    Monteleone, S. [comp.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Finland, France, Italy, Japan, Russia, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting.

  15. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    SciTech Connect (OSTI)

    Weiss, A. J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately.

  16. Job Safety

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

    Job Safety and Health It's the law EMPLOYEES: Must have access to: DOE safety and health publications; The worker safety and health program for their location; This...

  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. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03

    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).

  19. Request for Investigation or Inspection of Safety or Classified...

    Energy Savers [EERE]

    Request for Investigation or Inspection of Safety or Classified Information Security Violations Request for Investigation or Inspection of Safety or Classified Information Security...

  20. What Can We Learn from Hydrogen Safety Event Databases?

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

    transportation 4 | Fuel Cell Technologies Office eere.energy.gov Safety Information Portal Information Portal will serve as a central point for access to the hydrogen safety...

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

    E-Print Network [OSTI]

    _____________________________ Environment, Health, & Safety _________ __________________ Training-based Training Frequency: One Time Course Purpose: This training contains general requirements and information. This training will familiarize you with the hazards of electricity and the requirements for electrical safety

  2. Dynamics of the continental margins

    SciTech Connect (OSTI)

    Not Available

    1990-11-01

    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.

  3. Path to development of quantitative safety goals

    SciTech Connect (OSTI)

    Joksimovic, V.; Houghton, W.J.

    1980-04-01

    There is a growing interest in defining numerical safety goals for nuclear power plants as exemplified by an ACRS recommendation. This paper proposes a lower frequency limit of approximately 10/sup -4//reactor-year for design basis events. Below this frequency, down, to a small frequency such as 10/sup -5//reactor-year, safety margin can be provided by, say, site emergency plans. Accident sequences below 10/sup -5/ should not impact public safety, but it is prudent that safety research programs examine sequences with significant consequences. Once tentatively agreed upon, quantitative safety goals together with associated implementation tools would be factored into regulatory and design processes.

  4. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

    The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

  5. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    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.

  6. TWRS safety management plan

    SciTech Connect (OSTI)

    Popielarczyk, R.S., Westinghouse Hanford

    1996-08-01

    The Tank Waste Remediation System (TWRS) Safety Management Program Plan for development, implementation and maintenance of the tank farm authorization basis is described. The plan includes activities and procedures for: (a) Updating the current Interim Safety Basis, (b) Development,implementation and maintenance of a Basis for Interim Operations, (c) Development, implementation and maintenance of the Final Safety Analyses Report, (d) Development and implementation of a TWRS information Management System for monitoring the authorization basis.

  7. Ladder Safety Information Sheet

    Broader source: Energy.gov [DOE]

    Falls are the number one cause of workplace fatalities in the construction industry. Ladder fall injury facts state that 43 percent of all fatal falls in the last decade have involved ladders. Ladder fall prevention measures is necessary in order to prevent further falls.

  8. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 of

  9. Assessment of seismic margin calculation methods

    SciTech Connect (OSTI)

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

    1989-03-01

    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.

  10. Health & Safety

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

    Health & Safety Health & Safety1354608000000Health & SafetySome of these resources are LANL-only and will require Remote Access.NoQuestions? 667-5809library@lanl.gov Health &...

  11. Twenty-First Water Reactor Safety Information Meeting. Volume 3, Primary system integrity; Aging research, products and applications; Structural and seismic engineering; Seismology and geology: Proceedings

    SciTech Connect (OSTI)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

  12. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  13. Multivariate Distributions with Proportional Reversed Hazard Marginals

    E-Print Network [OSTI]

    Kundu, Debasis

    Multivariate Distributions with Proportional Reversed Hazard Marginals Debasis Kundu1 & Manuel Franco2 & Juana-Maria Vivo3 Abstract Several univariate proportional reversed hazard models have been a class of bivariate models with proportional reversed hazard marginals. It is observed that the proposed

  14. Facility Safety

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

    2000-11-20

    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.

  15. Electromagnetic exploration of the Exmouth and Vøring rifted margins

    E-Print Network [OSTI]

    Myer, David Gerard

    2012-01-01

    Haq, B.U. , 1992. Seismic stratigraphy and passive marginHaq, B.U. , 1992. Seismic stratigraphy and passive marginHaq, B.U. , 1992. Seismic stratigraphy and passive margin

  16. Margins, Liquidity and the Cost of Hedging

    E-Print Network [OSTI]

    Mello, Antonio S.

    2012-05-21

    Recent financial reforms, such as the Dodd-Frank Act in the U.S. and the European Market Infrastructure Regulation, encourage greater use of clearing and therefore increased margining of derivative trades. They also impose ...

  17. The law of demand versus diminishing marginal utility

    E-Print Network [OSTI]

    Bettie, Bruce R.; Lafrance, Jeffrey T.

    2006-01-01

    Diminishing marginal utility will provide a negative sloperegularity for u. Thus, this utility function (or a simpleDiminishing Marginal Utility Endnotes References Burt,

  18. Marginal Energy Price Report - July 1999 | Department of Energy

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

    Report - July 1999 Marginal Energy Price Report - July 1999 Estimated Consumer Marginal Energy Prices for the Commercial and Residental Sectors for use in the Life-Cycle Cost...

  19. Sandia Energy - Transportation Safety

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

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

  20. In CHI 2005: ACM Conference on Human Factors in Computing Systems Improving Aviation Safety with Information Visualization

    E-Print Network [OSTI]

    Hearst, Marti

    system that significantly reduced the crash rate among experienced helicopter pilots flying a high-critical information, helicopters. ACM Classification Keywords H.5.1. [Multimedia Information Systems]: Artificial visualization of airflow hazards, when presented to helicopter pilots in a highly realistic simulator

  1. Facility Safety

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

    2005-12-22

    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.

  2. 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.

  3. Facility Safety

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

    1995-10-13

    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.

  4. Facility Safety

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

    2005-12-22

    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.

  5. Facility Safety

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

    2012-12-04

    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.

  6. Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1

    SciTech Connect (OSTI)

    Lee, B.L. Jr. [Battelle, Columbus, OH (United States); D`Aquila, D.M. [Lockheed Martin Utility Services, Inc., Oak Ridge, TN (United States)

    1996-01-01

    The original validation report, POEF-T-3636, was documented in August 1994. The document was based on calculations that were executed during June through August 1992. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This revision is written to clarify the margin of safety being used at Portsmouth for nuclear criticality safety calculations. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Lockheed Martin Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. For calculations of Portsmouth systems using the specified codes and systems covered by this validation, a maximum k{sub eff} including 2{sigma} of 0.9605 or lower shall be considered as subcritical to ensure a calculational margin of safety of 0.02. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25.

  7. Electromagnetic exploration of the Exmouth and Vøring rifted margins

    E-Print Network [OSTI]

    Myer, David Gerard

    2012-01-01

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

  8. Slideshow, National Safety Month- June 2013

    Broader source: Energy.gov [DOE]

    National Safety Month is recognized by employers, employees, and safety and health professionals throughout the country. During the month of June, HSS provided information, activities, and events pertaining to weekly themes.

  9. Environment Safety and Health Reporting Manual

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

    1995-09-30

    This Manual provides detailed requirements to supplement DOE O 231.1, Environment, Safety and Health Reporting, which establishes management objectives and requirements for reporting environment, safety and health information. Does not cancel other directives.

  10. Environment, Safety, and Health Reporting Manual

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

    1996-11-07

    This Manual provides detailed requirements to supplement DOE O 231.1, ENVIRONMENT, SAFETY AND HEALTH REPORTING, which establishes management objectives and requirements for reporting environment, safety and health information. Chg 1, 11-7-96.

  11. Laboratory Safety Manual Table of Contents

    E-Print Network [OSTI]

    Natelson, Douglas

    Laboratory Safety Manual Table of Contents I. Emergency Procedures a. Laboratory Contact Information b. Location of Laboratory Emergency Equipment c. Laboratory Hazard and Evacuation Maps d. University Emergency Procedures II. University Policies and Procedures a. Rice University Laboratory Safety

  12. Environmental Health & Safety (EH&S) Laboratory Safety Training

    E-Print Network [OSTI]

    Environmental Health & Safety (EH&S) Laboratory Safety Training Fiscal Year 2015 1 #12;Important to ehsibc@wusm.wustl.edu For more information, see http://ehs.wustl.edu/resources/EHS%20Docum ents/MyIBC%20 fiscal year A lab fails the initial inspection during two consecutive fiscal years The Dean

  13. Environmental Health & Safety (EH&S) Laboratory Safety Training

    E-Print Network [OSTI]

    7/8/2014 1 Environmental Health & Safety (EH&S) Laboratory Safety Training Fiscal Year 2015 1 to ehsibc@wusm.wustl.edu For more information, see http://ehs.wustl.edu/resources/EHS%20Docum ents/MyIBC%20 will be notified if: A lab fails both the initial inspection and re- inspection in a single fiscal year A lab

  14. Safety Engineer

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will ensure DOE Federal personnel and contractors develop effective safety programs and continuously evaluates those activities to ensure compliance with DOE...

  15. The Safety Data Sheet, or SDS, is written or printed material used to convey the hazards of a hazardous chemical product. It contains 16 sections of important chemical information, including

    E-Print Network [OSTI]

    The Safety Data Sheet, or SDS, is written or printed material used to convey the hazards of a hazardous chemical product. It contains 16 sections of important chemical information, including: Chemical characteristics; Physical and health hazards, including relevant exposure limits; Precautions for safe handling

  16. Earthquake Safety Guide for Homeowners

    E-Print Network [OSTI]

    Oklahoma, University of

    Earthquake Safety Guide for Homeowners FEMA 530 / September 2005 FEMA #12; PublishingInformation The Homeowner's Guide to Earthquake Safety was originally developed and published by the California Seismic that slid 2 feet off its foundation as a result of the 6.5 San Simeon Earthquake. #12;CONTENTS Page

  17. EMERGENCY PREPAREDNESS & SAFETY GUIDE EMERGENCIES

    E-Print Network [OSTI]

    Schrag, Daniel

    EMERGENCY PREPAREDNESS & SAFETY GUIDE EMERGENCY CONTACTS REPORTING EMERGENCIES MEDICAL EMERGENCIES Health & Safety (EH&S) EMERGENCY CONTACT INFORMATION 911 617-495-1212 617-495-5560 617-432-1901 617-495-5711 617-495-2060 EMERGENCY CONTACTS continued #12;Harvard News Updates Harvard Public Affairs

  18. Implementation of Information Management System for Radiation Safety of Personnel at the Russian Northwest Center for Radioactive Waste Management 'SevRAO' - 13131

    SciTech Connect (OSTI)

    Chizhov, K.; Simakov, A.; Seregin, V.; Kudrin, I.; Shandala, N.; Tsovyanov, A.; Kryuchkov, V. [Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency, RF Ministry of Health and Social Development. 46, Zhivopisnaya St., Moscow, 123182 (Russian Federation)] [Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency, RF Ministry of Health and Social Development. 46, Zhivopisnaya St., Moscow, 123182 (Russian Federation); Krasnoschekov, A.; Kosnikov, A. [Northwest Center for Radioactive Waste Management 'SevRAO' - a branch of the Federal State Unitary Enterprise 'Enterprise for Radioactive Waste Management' 'RosRAO' 183017, Murmansk, Lobova st., 100 (Russian Federation)] [Northwest Center for Radioactive Waste Management 'SevRAO' - a branch of the Federal State Unitary Enterprise 'Enterprise for Radioactive Waste Management' 'RosRAO' 183017, Murmansk, Lobova st., 100 (Russian Federation); Kemsky, I. [Regional management - 120 of the Federal Medical-Biological Agency, 184682, Snezhnogorsk, Valentina Biryukova St., 5/1 (Russian Federation)] [Regional management - 120 of the Federal Medical-Biological Agency, 184682, Snezhnogorsk, Valentina Biryukova St., 5/1 (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority, Postboks 55, 1332 Oesteraas (Norway)] [Norwegian Radiation Protection Authority, Postboks 55, 1332 Oesteraas (Norway)

    2013-07-01

    The report is an overview of the information-analytical system designed to assure radiation safety of workers. The system was implemented in the Northwest Radioactive Waste Management Center 'SevRAO' (which is a branch of the Federal State Unitary Enterprise 'Radioactive Waste Management Enterprise RosRAO'). The center is located in the Northwest Russia. In respect to 'SevRAO', the Federal Medical-Biological Agency is the regulatory body, which deals with issues of radiation control. The main document to regulate radiation control is 'Reference levels of radiation factors in radioactive wastes management center'. This document contains about 250 parameters. We have developed a software tool to simplify control of these parameters. The software includes: input interface, the database, dose calculating module and analytical block. Input interface is used to enter radiation environment data. Dose calculating module calculates the dose on the route. Analytical block optimizes and analyzes radiation situation maps. Much attention is paid to the GUI and graphical representation of results. The operator can enter the route at the industrial site or watch the fluctuations of the dose rate field on the map. Most of the results are presented in a visual form. Here we present some analytical tasks, such as comparison of the dose rate in some point with control levels at this point, to be solved for the purpose of radiation safety control. The program helps to identify points making the largest contribution to the collective dose of the personnel. The tool can automatically calculate the route with the lowest dose, compare and choose the best route. The program uses several options to visualize the radiation environment at the industrial site. This system will be useful for radiation monitoring services during the operation, planning of works and development of scenarios. The paper presents some applications of this system on real data over three years - from March 2009 to February 2012. (authors)

  19. Forrestal Security and Safety Procedures

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

    1983-02-02

    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.

  20. Job Safety Health Poster Spanish 09042014.docx

    Office of Environmental Management (EM)

    (OSHA), empleados de contratistas de la Oficina de Cumplimiento (http:energy.goviearequest-investigation-or-inspection- safety-or-classified-information-security-violatio...

  1. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12University SafetyHealthSafetySafety,

  2. Safety Requirements and Fault Trees using Retrenchment

    E-Print Network [OSTI]

    Banach, Richard

    this initial model has been created, the elicitation of safety requirements yields a fresh set of criteria are applied, the information linking the design and the safety assessment phases is often carried outSafety Requirements and Fault Trees using Retrenchment R. Banach and R. Cross Computer Science

  3. Facility Safety

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

    2002-05-20

    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.

  4. Marginal Abatement Cost Tool (MACTool) | Open Energy Information

    Open Energy Info (EERE)

    also determines which economic sectors would be likely to respond to a given carbon price, thus assessing the effectiveness of a cap-and-trade system. When to Use This Tool...

  5. Intrusion Margins and Associated Fractures | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource History View NewTexas: Energy ResourcesOrder at 8, 13Renewable PowerMismatch | OpenTechnology andIntrusion

  6. ECN GHG Marginal Abatement Cost curves (NAMAC) | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QA J-E-1 SECTION J APPENDIX E LISTStar2-0057-EA Jump to:of the NationalDynetek Europe GmbH JumpE+CoTheECN GHG

  7. Unitary-process discrimination with error margin

    E-Print Network [OSTI]

    T. Hashimoto; A. Hayashi; M. Hayashi; M. Horibe

    2010-06-10

    We investigate a discrimination scheme between unitary processes. By introducing a margin for the probability of erroneous guess, this scheme interpolates the two standard discrimination schemes: minimum-error and unambiguous discrimination. We present solutions for two cases. One is the case of two unitary processes with general prior probabilities. The other is the case with a group symmetry: the processes comprise a projective representation of a finite group. In the latter case, we found that unambiguous discrimination is a kind of "all or nothing": the maximum success probability is either 0 or 1. We also closely analyze how entanglement with an auxiliary system improves discrimination performance.

  8. Marginal Energy Prices - RECS97 Update

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

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nAand DOE Safetyof Energy ThisSites |and theDepartment ofMarchMarginal

  9. Chemical and Hazardous Materials Department of Environmental Health and Safety

    E-Print Network [OSTI]

    O'Toole, Alice J.

    Chemical and Hazardous Materials Safety Department of Environmental Health and Safety 800 West information useful in the recognition, evaluation, and control of workplace hazards and environmental factors safety, fire safety, and hazardous waste disposal. Many chemicals have properties that make them

  10. Winter Safety Information & Tips

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

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyThe U.S.Lacledeutilities.Energy Thefull swing, andWindEnergyDrew Bittner7 1

  11. Geologic hazards on the Atlantic continental margin of the United States

    SciTech Connect (OSTI)

    Folger, D.W.

    1985-01-01

    Although 46 exploratory holes have failed to reveal commercial hydrocarbon accumulations on the US Atlantic margin, about twice that number were drilled on the contiguous Canadian margin before large reserves were discovered. Thus, despite the initial results, exploration on the US margin will probably continue and additional information will be needed to augment the extensive environmental data base acquired over the past 10 years. The extent, timing, causes, and importance of sediment instability of the Continental Slopes of Georges Bank, Baltimore Canyon Trough and Carolina Trough--where future exploration will take place--remain controversial. Many question remain to be answered regarding such phenomena as creep on the upper slope, mass wasting in canyons and gullies, and slumping associated with faults and salt diapirs. Along the southeastern margin, the distribution of cavernous porosity below the shelf is only broadly known. Caverns pose a potential threat to drilling operations ranging from collapse of rigs to circulation loss and sheared drill strings. In deeper waters of the Continental Slope (700-2000 m), clathrates or frozen gas hydrates are common. The potential hazard of blow-outs from gas trapped beneath this layer are unknown. Additional information is needed to assess the bottom stresses imposed by tidal, storm, and geostrophically-driven currents on offshore rigs and structures, particularly in such areas as Georges Bank, the Carolina Trough, and the Blake Plateau.

  12. Development of a pilot safety information document (PSID) for the replacement of radioactive liquid waste treatment facility at Los Alamos National Laboratory 

    E-Print Network [OSTI]

    Selvage, Ronald Derek

    1995-01-01

    Radioactive Liquid Waste Treatment Facility. The PSID documents risk analysis for the proposed facility and some of the alternatives, accident analysis, radioactive and hazardous material doses to off-site individuals, and the cumulative safety risk from...

  13. MARGINAL EXPENSE OIL WELL WIRELESS SURVEILLANCE MEOWS

    SciTech Connect (OSTI)

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

    2004-11-01

    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.

  14. Regnar -- Development of a marginal field

    SciTech Connect (OSTI)

    Thalund, K.M.; Brodersen, F.P.; Roigaard-Petersen, B.

    1994-12-31

    Regnar is a small marginal field located some 13 km from the main Dan F complex and is the first subsea completion in Danish waters, operated by Maersk Olie og Gas AS. A short lifetime has been predicted for the field which therefore has been developed as a low cost project, using a combination of subsea technology and minimum topside facilities. Regnar consists of a subsea x-mas tree producing through a 6 inch pipeline with a 2 1/2 inch chemical piggyback line to Dan F. The x-mas tree and the subsea choke valve are controlled from a buoy moored nearby the well. The buoy is radio linked to Dan F. The Regnar field was brought on stream on September 26, 1993.

  15. OCCUPATIONAL HEALTH AND SAFETY

    E-Print Network [OSTI]

    OCCUPATIONAL HEALTH AND SAFETY MANAGEMENT SYSTEM Department of Occupational Health and Safety Revised December 2009 #12;Occupational Health and Safety (OHS) Management System 1. Introduction.............................................................................................................. 3 2.2 Management of Health and Safety

  16. Sandia Energy - NASA Award for Marginal Ice Zone Observations...

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

    NASA Award for Marginal Ice Zone Observations and Process Experiment (MIZOPEX) Home Climate Office of Science News News & Events Research & Capabilities Monitoring Analysis...

  17. The Law of Demand versus Diminishing Marginal Utility

    E-Print Network [OSTI]

    Beattie, Bruce R.; LaFrance, Jeffrey T

    2006-01-01

    not guarantee DSD. This form of utility function generates aHausman). This type of utility model is commonplace amongversus Diminishing Marginal Utility References Burt, O.R.

  18. The Law of Demand Versus Diminishing Marginal Utility

    E-Print Network [OSTI]

    Beattie, Bruce R.; LaFrance, Jeffrey T.

    2006-01-01

    not guarantee DSD. This form of utility function generates aHausman). This type of utility model is commonplace amongversus Diminishing Marginal Utility References Burt, O.R.

  19. Department of Energy Cites Bechtel Jacobs for Classified Information...

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

    Jacobs for Classified Information Security and Worker Safety and Health Violations Department of Energy Cites Bechtel Jacobs for Classified Information Security and Worker Safety...

  20. Safety harness

    DOE Patents [OSTI]

    Gunter, Larry W. (615 Sand Pit Rd., Leesville, SC 29070)

    1993-01-01

    A safety harness to be worn by a worker, especially a worker wearing a plastic suit thereunder for protection in a radioactive or chemically hostile environment, which safety harness comprises a torso surrounding portion with at least one horizontal strap for adjustably securing the harness about the torso, two vertical shoulder straps with rings just forward of the of the peak of the shoulders for attaching a life-line and a pair of adjustable leg supporting straps releasibly attachable to the torso surrounding portion. In the event of a fall, the weight of the worker, when his fall is broken and he is suspended from the rings with his body angled slightly back and chest up, will be borne by the portion of the leg straps behind his buttocks rather than between his legs. Furthermore, the supporting straps do not restrict the air supplied through hoses into his suit when so suspended.

  1. Environment, Safety and Health Reporting

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

    2012-01-01

    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.

  2. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C. (Malmoe, SE)

    1984-01-01

    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.

  3. Facility Safety

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

    2013-06-21

    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.

  4. Incorporating safety risk in early system architecture trade studies

    E-Print Network [OSTI]

    Dulac, Nicholas

    Ideally, safety should be a part of the early decision making used in conceptual system design. However, effectively evaluating safety risk3 early enough to inform the early trade studies is not possible with current ...

  5. Environment, Safety, and Health Reporting

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

    2003-08-19

    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.

  6. Criticality Safety Evaluation of Hanford Tank Farms Facility

    SciTech Connect (OSTI)

    WEISS, E.V.

    2000-12-15

    Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

  7. 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.

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

    SciTech Connect (OSTI)

    Milbrandt, A.; Overend, R. P.

    2009-08-01

    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.

  9. INTRODUCTION Margin evolution and plate-reconstruction models require a

    E-Print Network [OSTI]

    Müller, Dietmar

    ­243 Formation and evolution of Australian passive margins: implications for locating the boundary between. STAGG2 AND P. A. SYMONDS2 1 Division of Geology and Geophysics, Building F05, School of Geosciences. Australian passive margins display a large variety of styles, including narrow, wide, volcanic and non

  10. Delivering safety

    SciTech Connect (OSTI)

    Baldwin, N.D.; Spooner, K.G.; Walkden, P.

    2007-07-01

    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)

  11. Safety Issues

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 of 6Site Safety

  12. Radiation 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMassR&D100 Winners * Impacts on GlobalRachel Ruggirello RachelRadiation DrySafety Home

  13. Job Safety

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

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nA Guidephysics_today_article.pdf MoreEnergy JulyTemansonupdatedJob Safety

  14. General Radiation Safety Information About USF Research Small amounts of radioactive materials are used in research work at the University of South Florida

    E-Print Network [OSTI]

    Arslan, Hüseyin

    Radiation Safety office strives to keep radiation doses to workers, the public, and the environment As Low in a person, he or she receives a radiation dose. Radiation doses are measured in millirems (mrem) or rems, the average background radiation dose is 300 mrem/yr. Manufactured sources contribute an additional background

  15. Introduction to LNG vehicle safety. Topical report

    SciTech Connect (OSTI)

    Bratvold, D.; Friedman, D.; Chernoff, H.; Farkhondehpay, D.; Comay, C.

    1994-03-01

    Basic information on the characteristics of liquefied natural gas (LNG) is assembled in this report to provide an overview of safety issues and practices for the use of LNG vehicles. This document is intended for those planning or considering the use of LNG vehicles, including vehicle fleet owners and operators, public transit officials and boards, local fire and safety officials, manufacturers and distributors, and gas industry officials. Safety issues and mitigation measures that should be considered for candidate LNG vehicle projects are addressed.

  16. Criticality safety basics, a study guide

    SciTech Connect (OSTI)

    V. L. Putman

    1999-09-01

    This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

  17. Your Safety and at Syracuse University

    E-Print Network [OSTI]

    Raina, Ramesh

    programs to disclose campus crime statistics and security information. A 1998 amendment renamed the lawYour Safety and Security at Syracuse University A comprehensive report on campus security and fire and security measures on and around our campus. The need for security encompasses more than personal safety

  18. Your Safety and Security at Syracuse University

    E-Print Network [OSTI]

    Raina, Ramesh

    programs to disclose campus crime statistics and security information. A 1998 amendment renamed the lawYour Safety and Security at Syracuse University A comprehensive report on campus security and fire and security measures on and around our campus. The need for security encompasses more than personal safety

  19. AUGUST AND SEPTEMBER SYSTEM SAFETY PROGRESS REPORT

    E-Print Network [OSTI]

    Rathbun, Julie A.

    failure at NOL during safety testing. 2. 2 Status The change has been incorporated into the Qual information to as sure controlled conditions during the hazardous field test sequences for the protection life cycle of the LSP Experiment. 5. 3 ATM 1056 Ground Ope rations and Safety Plan was released on 28

  20. RADIATION SAFETY MANUAL 2014 RICE UNIVERSITY 1

    E-Print Network [OSTI]

    Natelson, Douglas

    microscopes. Notify the RSO of any new radiation sources. Notify the RSO if any radiation sources with radioactive materials must attend formal radiation safety training provided by EHS. #12;RADIATION SAFETY with information concerning risk. 4. Provide suggestions for reducing exposure. 5. Monitor your radiation dose wit

  1. Emergency Information Desk Reference

    E-Print Network [OSTI]

    Gopalakrishnan, K.

    Emergency Information Desk Reference ECU Police Department ECU Environmental Health & Safety Revised Feb 2012 #12;Emergency Information Desk Reference 2 INTRODUCTION Emergencies, accidents, and injuries can occur at any time and without warning. ECU has designed this emergency information desk

  2. Radiotherapy margin design with particular consideration of high curvature CTVs

    SciTech Connect (OSTI)

    Herschtal, Alan; Kron, Tomas; Fox, Chris [Peter MacCallum Cancer Centre, St. Andrews Place, E. Melbourne, Victoria 3002 (Australia)

    2009-03-15

    In applying 3D conformal radiation therapy to a tumor clinical target volume (CTV), a margin is added around the CTV to account for any sources of error in the application of treatment which may result in misalignment between the CTV and the dose distribution actually delivered. The volume enclosed within the CTV plus the margin is known as the PTV, or planning target volume. The larger the errors are anticipated to be, the wider the margin will need to be to accommodate those errors. Based on the approach of van Herk et al. [''The probability of correct target dosage: Dose-population histograms for deriving treatment margins in radiotherapy,'' Int. J. Radiat. Oncol. Biol., Phys. 47(4), 1121-1135 (2000)] this paper develops the mathematical theory behind the calculation of the margin width required to ensure that the entire CTV receives sufficiently high dose with sufficiently high probability. The margin recipe developed not only considers the magnitude of the errors but also includes a term to adjust for curved CTV surfaces. In doing so, the accuracy of the margin recipe is enhanced yet remains mathematically concise enough to be readily implemented in the clinical setting. The results are particularly relevant for clinical situations in which the uncertainties in treatment are large relative to the size of the CTV.

  3. Marginal erg facies: A trial approach toward a descriptive classification

    SciTech Connect (OSTI)

    Caputo, M.V. ); Langford, R.P. )

    1991-03-01

    During the late 1970s and early 1980s, sedimentologists began recognizing the margins of eolian sand seas as separate, components which differed from interior sand seas in geometry, extent, and facies. Stratigraphers have now observed these differences in eolian rocks. Erg margins may be grouped in five ways: (1) by associations with extradunal environments-coastal plain, lacustrine, periglacial, marine (tidal flat, coastal sabkha, beach, and lagoon), and arid alluvial (alluvial fan, fluvial, playa, inland sabkha); (2) by allocyclic controls-eustasy, plate tectonism, and climate; (3) by autocyclic controls-local tectonism, topography, vegetation, hydrology, structure, sediment source and supply, and wind regime; (4) by geographic position-upwind, downwind, and along-wind margins; and (5) by sedimentary facies-texture and architecture. In contrast with erg interiors, erg margins are characterized by smaller, less complex dune-forms related to thinner sand accumulation; elementary dune architecture; more vegetation and bioturbation; high occurrence of sand sheet, zibar, and serir facies; expansive, low-relief interdunes with widely distributed dunes; and a greater proportion of interbedded extradunal deposits. Some of the published studies on ancient eolian systems have identified erg margin facies that have been influences by marine and arid alluvial processes. Few reports have described lacustrine-eolian and periglacial-eolian interactions. This study is an attempt to organize known features of modern and ancient erg margins into a scheme based on erg margin controls.

  4. Environment, Safety and Health Reporting

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

    2011-06-27

    The order addresses DOE/NNSA receiving timely, accurate information about events that have affected or could adversely affect the health, safety and security of the public or workers, the environment, the operations of DOE facilities, or the credibility of the Department. Admin Chg 1, dated 11-28-12, Supersedes DOE O 231.1B.

  5. 2011 WSU SPOKANE ANNUAL Security/Fire Safety

    E-Print Network [OSTI]

    Collins, Gary S.

    Security/Fire Safety Report can be obtained at the Office of Security and Public Safety. Information Information and Preparation of Statistics 1 Director's Letter 2 Mission Statement and Security Department INFORMATION The Jeanne Clery Disclosure of Campus Security Policy and Campus Crime Statistics Act (also

  6. 2012 WSU SPOKANE ANNUAL Security/Fire Safety

    E-Print Network [OSTI]

    Collins, Gary S.

    Security/Fire Safety Report can be obtained at the Office of Security and Public Safety. Information Information and Preparation of Statistics 1 Director's Letter 2 Mission Statement and Security Department INFORMATION The Jeanne Clery Disclosure of Campus Security Policy and Campus Crime Statistics Act (also

  7. Nuclear Safety | Department of Energy

    Office of Environmental Management (EM)

    Nuclear Safety Nuclear Safety The Office of Nuclear Safety establishes and maintains nuclear safety policy, requirements, and guidance including policy and requirements relating to...

  8. Recursive Pathways to Marginal Likelihood Estimation with Prior-Sensitivity Analysis

    E-Print Network [OSTI]

    Cameron, Ewan

    2013-01-01

    We investigate the utility to contemporary Bayesian studies of recursive, Gauss-Seidel-type pathways to marginal likelihood estimation characterized by reverse logistic regression and the density of states. Through a pair of illustrative, numerical examples (including mixture modeling of the well-known 'galaxy dataset') we highlight both the remarkable diversity of bridging schemes amenable to recursive normalization and the notable efficiency of the resulting pseudo-mixture densities for gauging prior-sensitivity in the model selection context. Our key theoretical contributions show the connection between the nested sampling identity and the density of states. Further, we introduce a novel heuristic ('thermodynamic integration via importance sampling') for qualifying the role of the bridging sequence in marginal likelihood estimation. An efficient pseudo-mixture density scheme for harnessing the information content of otherwise discarded draws in ellipse-based nested sampling is also introduced.

  9. Criticality Safety Analysis Of As-loaded Spent Nuclear Fuel Casks

    SciTech Connect (OSTI)

    Banerjee, Kaushik; Scaglione, John M

    2015-01-01

    The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, and normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory, and taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be potentially used to offset (1) uncertainties in the safety basis that needs to account for the effects of system aging during extended dry storage prior to transportation, and (2) increases in SNF system reactivity over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific, as-loaded criticality margins for SNF stored at eight reactor sites (215 loaded casks were analyzed) under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated keff margin varies from 0.05 to almost 0.3 keff for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF casks.

  10. SHIPBOARD LABORATORY SAFETY PROGRAM

    E-Print Network [OSTI]

    SHIPBOARD LABORATORY SAFETY PROGRAM INTEGRATED OCEAN DRILLING PROGRAM U.S. IMPLEMENTING ORGANIZATION AUGUST 2013 #12;IODP Shipboard Laboratory Safety: Introduction 2 CONTENTS Introduction ................................................................................................................................6 TAMU EHSD: Laboratory Safety Manual

  11. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    Fuel Cell Technologies Publication and Product Library (EERE)

    This guidance document provides information on safety requirements for hydrogen and fuel cell projects funded by the U.S. Department of Energy Fuel Cell Technologies Program.

  12. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    SciTech Connect (OSTI)

    U.S. Department of Energy Fuel Cell Technologies Program

    2010-04-01

    This guidance document provides information on safety requirements for hydrogen and fuel cell projects funded by the U.S. Department of Energy Fuel Cell Technologies Program.

  13. Commercial Vehicle Safety Alliance Commercial Vehicle Safety...

    Office of Environmental Management (EM)

    Program Update: Ensuring Safe Transportation of Radioactive Material Carlisle Smith Director, Hazardous Materials Programs Commercial Vehicle Safety Alliance Email:...

  14. 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

  15. Design of miniature floating platform for marginal fields

    E-Print Network [OSTI]

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

    2013-01-01

    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, ...

  16. Making In-Class Competitions Desirable For Marginalized Groups

    E-Print Network [OSTI]

    McGovern, Amy

    with and hinder other opponents (e.g. a stock car race or boxing match). Students using Spacewar were com- peting may also appeal other groups of students who can be marginalized in engineering. Our results indicate

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

    E-Print Network [OSTI]

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

    2004-01-01

    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 ...

  18. August 2012 Safety Forecast

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

    During the month of August, the focus safety areas be ramp safety and seat belt awareness. Heat continues to be a factor during the month of August. Continue...

  19. FIRE SAFETY REPORT ENVIRONMENTAL HEALTH & SAFETY SERVICES

    E-Print Network [OSTI]

    Hong, Don

    FIRE SAFETY REPORT 2014 ENVIRONMENTAL HEALTH & SAFETY SERVICES #12;1 | M T S U F I R E S A F E T Y R E P O R T FIRE SAFETY REPORT TABLE OF CONTENTS INTRODUCTION 2 RESPONSIBILITIES AND DUTIES OF THE MTSU FIRE MARSHAL 2 GENERAL 3 SMOKING POLICY 3 CLASS A COMBUSTIBLES 4 CLASS B COMBUSTIBLES 4 FIRE

  20. The value of marginal analysis in electric power system operations

    SciTech Connect (OSTI)

    Katzman, M.T.; Shelton, R.B.

    1989-01-01

    Electric utilities have traditionally based their calculation of costs and derived prices on the basis of averages. Marginal analysis provides an alternative method of costing and price setting. Not only does marginal analysis yield different computations, it can lead to different and more efficient decisions. This point is illustrated by the evaluation of biomass cogeneration to a utility and the costing of rural extensions. 7 refs., 3 figs., 3 tabs.

  1. Electricity Prices in a Competitive Environment: Marginal Cost Pricing

    Reports and Publications (EIA)

    1997-01-01

    Presents the results of an analysis that focuses on two questions: (1) How are prices for competitive generation services likely to differ from regulated prices if competitive prices are based on marginal costs rather than regulated cost-of-service pricing? (2) What impacts will the competitive pricing of generation services (based on marginal costs) have on electricity consumption patterns, production costs, and the financial integrity of electricity suppliers?

  2. Hot Cell Facility (HCF) Safety Analysis Report

    SciTech Connect (OSTI)

    MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

    2000-11-01

    This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

  3. Transverse extension of Guatemala active margin: implications for accretion

    SciTech Connect (OSTI)

    McMillen, K.J.

    1987-05-01

    The inner trench wall of the Middle America Trench off Guatemala does not show evidence of accretion, based on DSDP Legs 67 and 84. The presence of normal faults on the lower inner trench slope has resulted in various subsidence models for the margin. Fault traces would be expected to trend parallel to the margin (northwest-southeast) if margin subsidence had occurred. Instead, the faults trend north-south and occur in groups of faults downdropped to the east and to the west. The faults do not seem to be related to margin subsidence but rather to previously proposed Cenozoic Central American rifting. The rifting resulted from crustal bending as the Central American block rounded southern Mexico during differential North American/Caribbean plate motion. The rifts, which extend nearly to the trench axis, underlie the San Jose submarine canyon and align with the Guatemala City graben. Possible east-west accommodation zones, between fault zones that dip in opposite directions, exist near the shelf edge. These accommodation zones may have formed along lines of weakness where oceanic crust was previously emplaced into the margin during or prior to the Eocene. These rifts show that compressional and extension features can occur simultaneously with underthrusting on active margins.

  4. Environmental Health & Safety Department New Employee Exposure Assessment

    E-Print Network [OSTI]

    Nicholson, Bruce J.

    Environmental Health & Safety Department New Employee Exposure Assessment PURPOSE: The purpose of the assessment questions, Environmental Health & Safety will inform you and your supervisor of any additional of this assessment is to determine your required health & safety training by evaluating your use of and exposure

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

    SciTech Connect (OSTI)

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

    2006-09-01

    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.

  6. Bed radar reflectivity across the north margin of Whillans Ice Stream, West Antarctica, and implications for margin processes

    E-Print Network [OSTI]

    Raymond, C. F.; Catania, Ginny A.; Nereson, Nadine; van der Veen, Cornelis J.

    2006-01-01

    the margin is mediated by processes other than deformation of thick dilated till that is the source of lubrication allowing fast motion in the interior of the ice stream....

  7. 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 ...

  8. Safety Alerts

    Broader source: Energy.gov [DOE]

    Documents downloaded from the password-protected areas of this web site may be made available to the DOE Federal and contractor community and to the military. These documents are not permitted to be made available to the general public via an Internet web site. All parties with access to the password-protected areas of the EHSS web site are to exercise due diligence to maintain control of information.

  9. [Cover page, Margins: Left 1 in

    Office of Scientific and Technical Information (OSTI)

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield MunicipalTechnicalInformation4563 LLNL Small-scale Friction Sensitivityv b W r88 LunarOrganic

  10. 2011 Annual Criticality Safety Program Performance Summary

    SciTech Connect (OSTI)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The TSR limits fuel plate bundles to 1085 grams U-235, which is the maximum loading of an ATR fuel element. The overloaded fuel plate bundle contained 1097 grams U-235 and was assembled under an 1100 gram U-235 limit in 1982. In 2003, the limit was reduced to 1085 grams citing a new criticality safety evaluation for ATR fuel elements. The fuel plate bundle inventories were not checked for compliance prior to implementing the reduced limit. A subsequent review of the NMIS inventory did not identify further violations. Requirements Management - The INL Criticality Safety program is organized and well documented. The source requirements for the INL Criticality Safety Program are from 10 CFR 830.204, DOE Order 420.1B, Chapter III, 'Nuclear Criticality Safety,' ANSI/ANS 8-series Industry Standards, and DOE Standards. These source requirements are documented in LRD-18001, 'INL Criticality Safety Program Requirements Manual.' The majority of the criticality safety source requirements are contained in DOE Order 420.1B because it invokes all of the ANSI/ANS 8-Series Standards. DOE Order 420.1B also invokes several DOE Standards, including DOE-STD-3007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities.' DOE Order 420.1B contains requirements for DOE 'Heads of Field Elements' to approve the criticality safety program and specific elements of the program, namely, the qualification of criticality staff and the method for preparing criticality safety evaluations. This was accomplished by the approval of SAR-400, 'INL Standardized Nuclear Safety Basis Manual,' Chapter 6, 'Prevention of Inadvertent Criticality.' Chapter 6 of SAR-400 contains sufficient detail and/or reference to the specific DOE and contractor documents that adequately describe the INL Criticality Safety Program per the elements specified in DOE Order 420.1B. The Safety Evaluation Report for SAR-400 specifically recognizes that the approval of SAR-400 approves the INL Criticality Safety Program. No new source requirements were released in 2011. A revision to LRD-18001 is

  11. Office of Environmental Health and Safety Chemical and Biological Safety Section

    E-Print Network [OSTI]

    Hammack, Richard

    including industrial hygienists, biosafety professionals, laboratory safety professionals, hazardous waste each section manages an extensive and comprehensive array of programs, this information paper addresses management professionals, and lead and asbestos management professionals. As our name and professional

  12. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01

    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.

  13. 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

  14. State discrimination with error margin and its locality

    E-Print Network [OSTI]

    A. Hayashi; T. Hashimoto; M. Horibe

    2008-07-10

    There are two common settings in a quantum-state discrimination problem. One is minimum-error discrimination where a wrong guess (error) is allowed and the discrimination success probability is maximized. The other is unambiguous discrimination where errors are not allowed but the inconclusive result "I don't know" is possible. We investigate discrimination problem with a finite margin imposed on the error probability. The two common settings correspond to the error margins 1 and 0. For arbitrary error margin, we determine the optimal discrimination probability for two pure states with equal occurrence probabilities. We also consider the case where the states to be discriminated are multipartite, and show that the optimal discrimination probability can be achieved by local operations and classical communication.

  15. Ferrocyanide safety study

    SciTech Connect (OSTI)

    Wegeng, R.S.

    1989-05-01

    The overall objective of this study is to investigate the potentially rapid reactions between the ferrocyanide-containing salts, present in the SST's, and oxidants, such as nitrate, also present in the SST's. The objective of the energetics subtask is to investigate, on a screening basis, SST operational and compositional parameters which could affect the reaction between nickel cesium ferrocyanide, the expected form of cyanide in the SST, and nitrates and/or the nitrate radiolysis product nitrite. The objective of the large-scale explosion study is to independently confirm the results of the PNL laboratory-scale experiments and to determine the explosive behavior of a large sample of ferrocyanide and oxidant. The objective of the PNL-5441 revision subtask is to revise the complexant stability report, PNL-5441, to provide a current overview of the ferrocyanide safety issue and provide information to permit establishment of guidelines for SST management. 1 fig.

  16. Environmental Health and Safety -Safety Manual Table of Contents

    E-Print Network [OSTI]

    Li, X. Rong

    1 Environmental Health and Safety - Safety Manual Table of Contents I. Assignment of Responsibility Management Program..................................81 XIX. Water Vessel Safety Program

  17. Setting Up a New Lab: Environmental Health and Safety Information All laboratories are subject to the rules and regulations of the State of Washington and

    E-Print Network [OSTI]

    Borenstein, Elhanan

    to the rules and regulations of the State of Washington and the University of Washington. The department at the following url: http://www.ehs.washington.edu/ New principal investigators can find information helpful to opening their laboratory with good practices at the following url: http://www.ehs.washington

  18. Environmental Health and Safety Department

    E-Print Network [OSTI]

    . Fire Safety, Radiation Safety and Hazardous Materials Facility are at other locations on campus://www.ehs.gatech.edu/EHS_Policy_Statement.pdf #12;EHS The main Georgia Tech Environmental Health and Safety Office is located at 490 Tenth Street: Radiation Safety Fire SafetyHazardous Materials #12;SAFETY RESPONSIBILITY Safety is a shared responsibility

  19. Environment, Safety and Health Reporting

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

    2011-06-27

    The order addresses DOE/NNSA receiving timely, accurate information about events that have affected or could adversely affect the health, safety and security of the public or workers, the environment, the operations of DOE facilities, or the credibility of the Department. Cancels DOE N 234.1. Supersedes DOE O 231.1A Chg 1, DOE M 231.1-1A Chg 2.

  20. Office of Information Management

    Broader source: Energy.gov [DOE]

    The Office of Information Management provides a broad range of information technology services in support of the Associate Under Secretary for the Office of Environment, Health, Safety and Security (AU).

  1. The marginal leakage of some dental cements in humans: a PIXE-microbeam approach

    SciTech Connect (OSTI)

    Zadro, A.; Passi, P. [Dental School, Department of Dental Materials, University of Padua (Italy); Cavalleri, G. [Dental School, Department of Restorative Dentistry, University of Verona (Italy); Galassini, S.; Moschini, G.; Rossi, P. [INFN, Laboratori Nazionali di Legnaro (Italy)

    1999-06-10

    The marginal leakage and water absorption of dental cements and restorative materials has been investigated by many authors with several techniques, some of which led to valid results. However, no technique could give, by itself, information both on leakage and water absorption, as these measurements usually need different investigations. PIXE micro beam offers the possibility of investigating these two aspects at the same time, since it is possible to map a proper marker element. In the present study, cavities were made on 50 extracted human molars, then filled with five different temporary cements (IRM, Cavit W, Kalsogen, Fermit N, SuperEBA). The filled teeth were placed into a 5% silver nitrate solution, and after three days, one, two, three and four weeks were examined. The samples for microPIXE were prepared after embedding the teeth in epoxy resin, and sectioning and grinding them down to a thickness of about 1 mm. The sections were placed on metal holders, and examined with a scanning proton {mu}beam, in Legnaro (Italy) at the AN2000 LAB of INFN National Laboratories. The beam consisted of 2.4 MeV protons, it had a cross section of 1.5 micron in diameter and typical currents of the order of some {mu}A were used. The maps were obtained by an 'ad hoc' software with a McIntosh personal computer. Mapping of silver allowed to evaluate both the marginal leakage and the water absorption for each cement. The samples filled with Cavit W showed a great infiltration, as the tracing element was found in the cement bulk, along the margins and inside the cavity, while those filled with IRM and Kalsogen presented only a deposition of the tracing solution on the cement surface. SuperEBA showed a poor resistance against microleakage, because the marker element was only detected along the cavity margins. Fermit N showed the best marginal integrity, and on its surface no traces of siver were found. In this case the better resistance may be due to the resin present in the composition of the material.

  2. Georgia Institute of Laboratory Safety

    E-Print Network [OSTI]

    ENVIRONMENTAL HEALTH AND SAFETY POLICY.......................................10 Purpose Institute Council for Environmental Health and Safety (IC.........................................................................................12 Chemical and Environmental Safety Committee (CESC

  3. Criticality Safety | Department of Energy

    Office of Environmental Management (EM)

    Nuclear Safety Management American Nuclear Society, Nuclear Criticality Safety Division ANSIANS-8 Standards U.S. Department of Energy Nuclear Criticality Safety Program Orders,...

  4. Occupational Health and Safety Manual

    E-Print Network [OSTI]

    Occupational Health and Safety Manual #12;1 Introduction. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 York University Occupational Health and Safety Policy and Programs. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Occupational Health and Safety Legislation

  5. Modular HTGR Safety Basis and Approach

    SciTech Connect (OSTI)

    Thomas Hicks

    2011-08-01

    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.

  6. Environment, Safety, and Health Reporting Manual

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

    2000-01-28

    This Manual provides detailed requirements to supplement DOE O 231.1, Environment, Safety and Health Reporting, which establishes management objectives and requirements for reporting environment, safety and health information. (Paragraphs 2a, 2a(1), 2a(2), 2b, 2b(1), 2b(2), and 2i(3)(a) through 2i(3)(d) of Chapter II, and Appendix A canceled by DOE N 231.1; Chapter IV canceled by DOE O 470.2A.)

  7. 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

  8. Optical Safety of LEDs

    SciTech Connect (OSTI)

    none,

    2013-06-01

    Solid-state lighting program technology fact sheet that clarifies the issue of LED lighting safety for the human eye and takes a look at current standards for photobiological safety.

  9. Aviation safety analysis

    E-Print Network [OSTI]

    Ausrotas, Raymond A.

    1984-01-01

    Introduction: Just as the aviation system is complex and interrelated, so is aviation safety. Aviation safety involves design of aircraft and airports, training of ground personnel and flight crew members' maintenance of ...

  10. Complete Safety Training

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

    Complete Safety Training Print All users are required to take online safety training before they may begin work at the ALS. It is the responsibility of the Principal Investigator...

  11. Hydrogen Safety Knowledge Tools

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

    Data Partners Best Practices - LANL, SNL, NREL, NASA, Hydrogen Safety Panel, and IEA HIA Tasks 19 and 22 Incident Reporting - NASA and Hydrogen Safety Panel 3 Objectives H2...

  12. Preliminary Safety Design RM

    Office of Environmental Management (EM)

    Preliminary Safety Design Review Module March 2010 CD-0 O 0 OFFICE OF Pr C CD-1 F ENVIRO Standard R reliminar Rev Critical Decis CD-2 M ONMENTAL Review Plan ry Safety view Module...

  13. 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.

  14. 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

  15. 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

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

    E-Print Network [OSTI]

    Tesfatsion, Leigh

    the performance of these markets. In this paper, different AC and DC optimal power flow (OPF) models are presented Operator (MISO). Keywords: Locational marginal pricing, wholesale power market, AC optimal power flow, DC optimal power flow, U.S. Midwest Independent System Operator (MISO). #12;3 1 INTRODUCTION In an April 2003

  17. 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

  18. 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

  19. 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.

    2013-01-24

    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.

  20. Tectonic evolution of the southwestern Black Sea margin, offshore Turkey 

    E-Print Network [OSTI]

    Can, Emrah

    1996-01-01

    to the Srednogorie intra-arc zone in Bulgaria. Following back-arc extension, the whole margin was affected by a compressional tectonic regime during Paleocene-early Eocene time. Under this regime, a series of thrust faults formed, which were connected to the Stara...

  1. DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety...

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

    DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules June 14, 2005 - 4:53pm Addthis...

  2. HANFORD SAFETY ANALYSIS & RISK ASSESSMENT HANDBOOK (SARAH)

    SciTech Connect (OSTI)

    EVANS, C B

    2004-12-21

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

  3. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    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.

  4. Nuclear Explosive Safety Manual

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

    2009-04-14

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

  5. Methods to Improve Process Safety Performance through Flange Connection Leak Prediction and Control 

    E-Print Network [OSTI]

    Nelson, Jeremy

    2014-08-08

    by predicting the asset’s expected corrosion rate and its service life. However, this fixed safety margin does not consider the inherent uncertainty in an individual asset’s degradation rate due to variability in the material’s corrosion resistance...

  6. Annual Fire Safety Report

    E-Print Network [OSTI]

    Al Faruque, Mohammad Abdullah

    1 2014 Annual Fire Safety Report University of California Campus Fire Marshals HIGHER EDUCATION to the Fire Safety in Student Housing Buildings of current or perspective students and employees be reported INTRODUCTION Fire Safety is an essential tool in protecting a campus community from injuries, deaths, business

  7. Fire Safety January 2011

    E-Print Network [OSTI]

    Lennard, William N.

    1 Fire Safety PROCEDURES January 2011 firesafety@uwo.ca Campus Phones ­ EMERGENCY ­ Dial 911 Fire Safety Service is the focal point for the coordinated administration of the University Fire Safety program and plans, and is the University's representative in contacts dealing with all aspects of Fire

  8. SYSTEM SAFETY PROGRESS REPORT,

    E-Print Network [OSTI]

    Rathbun, Julie A.

    . The Lead Assembly contains between 150 and 200 mg of HNS and, therefore, will require manufacturing explosive potential. The additional safety effort required has been defined to the LSP Experiment Manager will be tested for manufacturing safety. System Safety will participate in the test which will consist 26 July

  9. Health, Safety & Wellbeing Policy

    E-Print Network [OSTI]

    Mottram, Nigel

    Health, Safety & Wellbeing Policy Statement The University of Glasgow is one of the four oldest our very best to minimise the risk to the health, safety and wellbeing of staff, students, researchers resource and our students as our valued customers and partners. We acknowledge health and safety as a core

  10. OCCUPATIONAL SAFETY and HEALTH

    E-Print Network [OSTI]

    MARYLAND OCCUPATIONAL SAFETY and HEALTH ACT safety and health protection on the job STATE OCCUPATIONAL SAFETY AND HEALTH STANDARDS, AND OTHER APPLICABLE REGULATIONS MAY BE OBTAINED FROM and Health Administration, The Curtis Center, Suite 740 West, 170 S. Independence Mall West, Philadelphia, PA

  11. Seismic Safety Study

    SciTech Connect (OSTI)

    Tokarz, F J; Coats, D W

    2006-05-16

    During the past three decades, the Laboratory has been proactive in providing a seismically safe working environment for its employees and the general public. Completed seismic upgrades during this period have exceeded $30M with over 24 buildings structurally upgraded. Nevertheless, seismic questions still frequently arise regarding the safety of existing buildings. To address these issues, a comprehensive study was undertaken to develop an improved understanding of the seismic integrity of the Laboratory's entire building inventory at the Livermore Main Site and Site 300. The completed study of February 2005 extended the results from the 1998 seismic safety study per Presidential Executive Order 12941, which required each federal agency to develop an inventory of its buildings and to estimate the cost of mitigating unacceptable seismic risks. Degenkolb Engineers, who performed the first study, was recontracted to perform structural evaluations, rank order the buildings based on their level of seismic deficiencies, and to develop conceptual rehabilitation schemes for the most seriously deficient buildings. Their evaluation is based on screening procedures and guidelines as established by the Interagency Committee on Seismic Safety in Construction (ICSSC). Currently, there is an inventory of 635 buildings in the Laboratory's Facility Information Management System's (FIMS's) database, out of which 58 buildings were identified by Degenkolb Engineers that require seismic rehabilitation. The remaining 577 buildings were judged to be adequate from a seismic safety viewpoint. The basis for these evaluations followed the seismic safety performance objectives of DOE standard (DOE STD 1020) Performance Category 1 (PC1). The 58 buildings were ranked according to three risk-based priority classifications (A, B, and C) as shown in Figure 1-1 (all 58 buildings have structural deficiencies). Table 1-1 provides a brief description of their expected performance and damage state following a major earthquake, rating the seismic vulnerability (1-10) where the number 10 represents the highest and worst. Buildings in classifications A and B were judged to require the Laboratory's highest attention towards rehabilitation, classification C buildings could defer rehabilitation until a major remodel is undertaken. Strengthening schemes were developed by Degenkolb Engineers for the most seriously deficient A and B classifications (15 total), which the Laboratory's Plant Engineering Department used as its basis for rehabilitation construction cost estimates. A detailed evaluation of Building 2580, a strengthening scheme, and a construction cost estimate are pending. Specific details of the total estimated rehabilitation costs, a proposed 10-year seismic rehabilitation plan, exemption categories by building, DOE performance guidelines, cost comparisons for rehabilitation, and LLNL reports by Degenkolb Engineers are provided in Appendix A. Based on the results of Degenkolb Engineers evaluations, along with the prevailing practice for the disposition of seismically deficient buildings and risk-based evaluations, it is concluded that there is no need to evacuate occupants from these 58 buildings prior to their rehabilitation.

  12. 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 performance based techniques that aim to improve the safety of neural networks for safety critical for safety assurance. As a result, neural networks are typically restricted to advisory roles in safety

  13. 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

  14. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    SciTech Connect (OSTI)

    Not Available

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

  15. Chemical Hygiene and Safety Plan

    SciTech Connect (OSTI)

    Berkner, K.

    1992-08-01

    The objective of this Chemical Hygiene and Safety Plan (CHSP) is to provide specific guidance to all LBL employees and contractors who use hazardous chemicals. This Plan, when implemented, fulfills the requirements of both the Federal OSHA Laboratory Standard (29 CFR 1910.1450) for laboratory workers, and the Federal OSHA Hazard Communication Standard (29 CFR 1910.1200) for non-laboratory operations (e.g., shops). It sets forth safety procedures and describes how LBL employees are informed about the potential chemical hazards in their work areas so they can avoid harmful exposures and safeguard their health. Generally, communication of this Plan will occur through training and the Plan will serve as a the framework and reference guide for that training.

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

    E-Print Network [OSTI]

    Choi, Jung Sun

    2013-05-01

    , in that their voices are taken to be insignificant, and they are constantly queered even by the marginal group. In his book Enforcing Normalcy: Disability, Deafness and the Body, Lennard J. Davis focuses on the word ?normal? to understand the historical process... and problems that society and culture have faced. He defines a group of chosen words, called ?Keywords,? as ?significant indicative words in certain forms of thought? and ?certain uses [of these words] bound together certain ways of seeing culture and society...

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

    SciTech Connect (OSTI)

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

    2006-09-15

    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.

  18. R E V I E W Functionality and the evolution of marginal stability in proteins

    E-Print Network [OSTI]

    Pollock, David

    R E V I E W Functionality and the evolution of marginal stability in proteins: Inferences from proteins are marginally stable. This has inspired several explanations. Having noted that the functionality that marginally stable proteins should have an evolutionary advantage over proteins of differing stability. Others

  19. Passive margins getting squeezed in the mantle convection vice Philippe Yamato,1

    E-Print Network [OSTI]

    Becker, Thorsten W.

    Passive margins getting squeezed in the mantle convection vice Philippe Yamato,1 Laurent Husson,1 2013. [1] Passive margins often exhibit uplift, exhumation, and tectonic inversion. We speculate passive margins. In order to address this issue, we design a 2-D viscous numerical model wherein

  20. DOE Explosives Safety Manual

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

    1996-03-29

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

  1. Coiled Tubing Safety Manual

    SciTech Connect (OSTI)

    Crow, W.

    1999-04-06

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

  2. Aviation Management and Safety

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

    2011-06-15

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

  3. Aviation Management and Safety

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

    2011-06-15

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

  4. 1 Food Safety Policy July 2010 Food Safety Policy

    E-Print Network [OSTI]

    Sussex, University of

    1 Food Safety Policy July 2010 Food Safety Policy Food Safety Policy 19.7.2010 19.7.2014 #12;2 Food 5. Organisational Responsibilities 6. The Legal References 7. Glossary of Terms #12;3 Food Safety Policy July 2010 Food Safety Policy 1. Introduction 1.1 The University has a duty to assess the risks

  5. Environment, Health, and Safety | NREL

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFES October 27th, 2010Environment, Health, Safety &

  6. Environment/Health/Safety (EHS)

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFES October 27th, 2010Environment, Health, SafetyThis is an example

  7. ORISE: Integrated Safety Management (ISM)

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformationJesseworkSURVEY UNIVERSE TheForensic ScienceHow to WorkIntegrated Safety

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

    SciTech Connect (OSTI)

    None

    2009-04-01

    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.

  9. Evaluation of the Planning Target Volume in the Treatment of Head and Neck Cancer With Intensity-Modulated Radiotherapy: What Is the Appropriate Expansion Margin in the Setting of Daily Image Guidance?

    SciTech Connect (OSTI)

    Chen, Allen M.; Farwell, D. Gregory; Luu, Quang; Donald, Paul J.; Perks, Julian; Purdy, James A.

    2011-11-15

    Purpose: To compare patterns of disease failure among patients treated with intensity-modulated radiotherapy (IMRT) in conjunction with daily image-guided radiotherapy (IGRT) for head and neck cancer, according to the margins used to expand the clinical target volume (CTV) to create a planning target volume (PTV). Methods and Materials: Two-hundred and twenty-five patients were treated with IMRT for squamous cell carcinoma of the head and neck. Daily IGRT scans were acquired using either kilovoltage or megavoltage volumetric imaging prior to each delivered fraction. The first 95 patients were treated with IMRT with 5-mm CTV-to-PTV margins. The subsequent 130 patients were treated using 3-mm PTV expansion margins. Results: Two-year estimates of overall survival, local-regional control, and distant metastasis-free survival were 76%, 78%, and 81%, respectively. There were no differences with respect to any of these endpoints among patients treated with 5-mm and 3-mm PTV expansion margins (p > 0.05, all). The 2-year local-regional control rate for patients treated with IMRT with 5-mm and 3-mm PTV margins was 78% and 78%, respectively (p = 0.96). Spatial evaluation revealed no differences in the incidences of marginal failures among those treated with 5-mm and 3-mm PTV margins. Conclusions: The use of 3-mm PTV expansion margins appears adequate and did not increase local-regional failures among patients treated with IMRT for head and neck cancer. These data demonstrate the safety of PTV reduction of less than 5 mm and support current protocols recommending this approach in the setting of daily IGRT.

  10. Octob~r System Safety Progress ALSEP ARRAY E

    E-Print Network [OSTI]

    Rathbun, Julie A.

    defined to MSC System Safety. The effect of a boyd bolt shearing failure at a time when an astronaut. The plan provides detailed information to assure controlled conditions during the hazardous field test Ground Operations and Safety Plan is being updated to incorporate NASA MSC comments and the latest

  11. SPRINGFIELD ARMORY 1911-A1 PISTOLS OPERATION AND SAFETY MANUAL

    E-Print Network [OSTI]

    Westall, James M.

    SPRINGFIELD ARMORY® 1911-A1 PISTOLS OPERATION AND SAFETY MANUAL Important Safety Information Inside Read this manual before handling this firearm. Keep this manual with your pistol and review it before or fire your pistol until they have read this manual. Transfer this manual with the firearm upon ownership

  12. Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements

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

    2006-07-24

    This Guide provides information to assist in implementation of Title 10 Code of Federal Regulations Part 830.203, "Unreviewed Safety Question Process," of the Nuclear Safety Management Rules for Category 1, 2, and 3 nuclear facilities owned or operated by the Department of Energy, including the National Nuclear Security Administration. Cancels DOE G 424.1-1.

  13. Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements

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

    2001-10-24

    This Guide provides information to assist in the implementation and interpretation of Title 10 Code of Federal Regulations (CFR) Part 830.203, Unreviewed Safety Question Process, of the Nuclear Safety Management Rules for applicable nuclear facilities owned or operated by the Department of Energy (DOE), including the National Nuclear Security Administration (NNSA). Canceled by DOE N 251.93.

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

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    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.

  15. HMSC Safety Committee September 10, 2009

    E-Print Network [OSTI]

    Lounge for coffee, donuts and more information from the Red Cross. Exterior Lighting: The HMSC parking lot will be a pilot sight for the PUD in using LED streetlights. These will meet the criteria for parking lots safety lighting yet limit up cast. Randy will coordinate with the PUD and Hollis. The wattage

  16. Tritium radioluminescent devices, Health and Safety Manual

    SciTech Connect (OSTI)

    Traub, R.J.; Jensen, G.A.

    1995-06-01

    This document consolidates available information on the properties of tritium, including its environmental chemistry, its health physics, and safe practices in using tritium-activated RL lighting. It also summarizes relevant government regulations on RL lighting. Chapters are divided into a single-column part, which provides an overview of the topic for readers simply requiring guidance on the safety of tritium RL lighting, and a dual-column part for readers requiring more technical and detailed information.

  17. Safety of Accelerator Facilities

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

    2004-07-23

    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.

  18. Integrated Safety Management Policy

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

    2011-04-25

    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. Supersedes DOE P 450.4, DOE P 411.1, DOE P 441.1, DOE P 450.2A, and DOE P 450.7

  19. Safety of Accelerator Facilities

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

    2011-07-21

    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. Supersedes DOE O 420.2B.

  20. Safety of Accelerator Facilities

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

    2001-01-08

    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.

  1. Electronic DOE Information Security System (eDISS) PIA, Office...

    Energy Savers [EERE]

    Electronic DOE Information Security System (eDISS) PIA, Office of Health Safety and Security Electronic DOE Information Security System (eDISS) PIA, Office of Health Safety and...

  2. 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...

  3. 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.

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

    E-Print Network [OSTI]

    Chiu Man Ho; Yu Nakayama

    2008-07-26

    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.

  5. 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).

  6. CRAD, Facility Safety- Unreviewed Safety Question 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 Unreviewed Safety Question (USQ) process.

  7. 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.

  8. Mechanical integrity implementation and related process safety management elements

    SciTech Connect (OSTI)

    Hudson, K.M. [General Physics Corp., San Diego, CA (United States)

    1995-12-31

    The OSHA Process Safety Management (PSM) rule requires covered facilities to establish a mechanical integrity (MI) program. The MI program must address an ongoing effort to maintain the integrity of process equipment and safety systems by providing written procedures, training, inspection and testing, and quality assurance. Development of an MI program requires information from other PSM elements such as equipment process safety information and employee participation as building blocks for the program. Information obtained from other elements of PSM can be used as the basis for inspection and testing, frequency of testing, written maintenance procedures, training of maintenance personnel, and quality assurance of spare parts and newly installed equipment. This paper presents highlights in the implementation of a mechanical integrity program. A description of the use of process safety information and baseline inspections is detailed with appropriate examples. The MI program stems from an initial documentation review, and culminates in a completely functional MI program in compliance with the regulation.

  9. WPN 11-6: Health and Safety Guidance

    Broader source: Energy.gov [DOE]

    To update and provide clarification and additional information related to the implementation and installation of health and safety measures as part of the U.S. Department of Energy (DOE) Weatherization Assistance Program (WAP).

  10. Lawrence Berkeley National Laboratory Integrated Safety Management (ISM) Plan

    E-Print Network [OSTI]

    Organization Chart). · Added more language in on-the-job-training for Users to make current status more clear · Updated organization charts. · Updated JHA information. · Added Section 7 Accountability. · Added Section.....................................................................2 3.0 SAFETY ORGANIZATION

  11. Institutional glovebox safety committee (IGSC) annual report FY2010

    SciTech Connect (OSTI)

    Cournoyer, Michael E; Roybal, Richard F; Lee, Roy J

    2011-01-04

    The Institutional Glovebox Safety Committee (IGSC) was chartered to minimize and/or prevent glovebox operational events. Highlights of the IGSC's third year are discussed. The focus of this working committee is to address glovebox operational and safety issues and to share Lessons Learned, best practices, training improvements, and glovebox glove breach and failure data. Highlights of the IGSC's third year are discussed. The results presented in this annual report are pivotal to the ultimate focus of the glovebox safety program, which is to minimize work-related injuries and illnesses. This effort contributes to the LANL Continuous Improvement Program by providing information that can be used to improve glovebox operational safety.

  12. Normalization of Process Safety Metrics 

    E-Print Network [OSTI]

    Wang, Mengtian

    2012-10-19

    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...

  13. Information Safety in University Chemistry Courses

    E-Print Network [OSTI]

    Nejdl, Wolfgang

    chemicals 14 3.1 Legal basis: Chemicals Act and Ordinance on Hazardous Substances 14 3.2 Storage and disposal 39 5.1 Cleaning glassware 39 5.2 Disposal of laboratory wastes 39 5.3 Disposal of minimal amounts.2 Physiological effects of electric currents 51 #12;4 8 Working with radiation 52 8.1 Working with radioactivity

  14. Facility Safety (For Informational Purposes Only)

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

    2014-12-04

    This draft has been scheduled for final review before the Directives Review Board on 12/18/14. All major comments and concerns should be provided to your DRB representative, following your organization process. If you do not know who your representative is, please see the list of DRB members. If your office is represented by Ingrid Kolb, Director, Office of Management, please submit your major concerns and comments to the DRB Liaison, Camille Beben (Camille.Beben@hq.doe.gov; 202-586-1014). All major comments and concerns should be submitted by COB 12/16/2014.

  15. Public Health and Safety | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource HistoryPotentialRuralUtilityScalePVGeneration Jump to:SpatialResolutionWidthPrue, Oklahoma:Open

  16. Public Order and Safety | 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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on QA:QAsource HistoryPotentialRuralUtilityScalePVGeneration Jump to:SpatialResolutionWidthPrue, Oklahoma:OpenOrder and

  17. Safety Basis Information System | Department of Energy

    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 Data Center Home Page on Delicious Rank EERE:Financing Tool FitsProjectData Dashboard RutlandSTEAB's Priorities throughANDSafety Basis

  18. Ladder Safety Information Sheet | Department of Energy

    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 Data Center Home Page on Delicious RankADVANCED MANUFACTURING OFFICE INDUSTRIALU.S. DepartmentJeanKeyLANLLG:KAHUKULaboratory2 AugustLadder

  19. Nuclear Safety Information | Department of Energy

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

    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 Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirley Ann JacksonDepartment ofOffice|in the subsurface isProject |NewsATVA Watts Bar Nuclear

  20. Uncertainties in the effects of burnup and their impact on criticality safety licensing criteria

    SciTech Connect (OSTI)

    Carlson, R.W.; Fisher, L.E.

    1990-07-13

    Current criteria for criticality safety for spent fuel shipping and storage casks are conservative because no credit is permitted for the effects of burnup of the fuel inside the cask. Cask designs that will transport and store large numbers of fuel assemblies (20 or more) must devote a substantial part of their payload to criticality control measures if they are to meet this criteria. The Department of Energy is developing the data necessary to support safety analyses that incorporate the effects of burnup for the next generation of spent fuel shipping casks. The efforts described here are devoted to the development of acceptance criteria that will be the basis for accepting safety analyses. Preliminary estimates of the uncertainties of the effects of burnup have been developed to provide a basis for the consideration of critically safety criteria. The criticality safety margins in a spent fuel shipping or storage cask are dominated by the portions of a fuel assembly that are in low power regions of a reactor core, and the reactor operating conditions are very different from spent fuel storage or transport cask conditions. Consequently, the experience that has been gathered during years of reactor operation does not apply directly to the prediction of criticality safety margins for spent fuel shipping or storage casks. The preliminary estimates of the uncertainties presented in this paper must be refined by both analytical and empirical studies that address both the magnitude of the uncertainties and their interdependence. 9 refs., 5 figs.

  1. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect (OSTI)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  2. Environmental, safety, and health engineering

    SciTech Connect (OSTI)

    Woodside, G.; Kocurek, D.

    1997-12-31

    A complete guide to environmental, safety, and health engineering, including an overview of EPA and OSHA regulations; principles of environmental engineering, including pollution prevention, waste and wastewater treatment and disposal, environmental statistics, air emissions and abatement engineering, and hazardous waste storage and containment; principles of safety engineering, including safety management, equipment safety, fire and life safety, process and system safety, confined space safety, and construction safety; and principles of industrial hygiene/occupational health engineering including chemical hazard assessment, personal protective equipment, industrial ventilation, ionizing and nonionizing radiation, noise, and ergonomics.

  3. Chemical Hygiene and Safety Plan

    E-Print Network [OSTI]

    Ricks Editor, R.

    2009-01-01

    V. , Ed. , Safety in the Chemical Laboratory. J. Chem.£d. Amer/can Chemical Society. Easlon. PA. 18042. Vol. Lof Laboratory Safety. the Chemical Rubber Company Cleveland.

  4. Department of Systems & Information

    E-Print Network [OSTI]

    Zhigilei, Leonid V.

    , communication systems, control systems, economic systems, energy and environmental systems, human factors systems, safety-critical systems, wireless communications, game theory and artificial intelligenceDeveloping Leaders of Innovation Department of Systems & Information Engineering #12;In the U

  5. Improving the safety of LWR power plants. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-04-01

    This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs (improving or maintaining level of safety with simpler systems or in a more cost-effective manner).

  6. Safety shutdown separators

    DOE Patents [OSTI]

    Carlson, Steven Allen; Anakor, Ifenna Kingsley; Farrell, Greg Robert

    2015-06-30

    The present invention pertains to electrochemical cells which comprise (a) an anode; (b) a cathode; (c) a solid porous separator, such as a polyolefin, xerogel, or inorganic oxide separator; and (d) a nonaqueous electrolyte, wherein the separator comprises a porous membrane having a microporous coating comprising polymer particles which have not coalesced to form a continuous film. This microporous coating on the separator acts as a safety shutdown layer that rapidly increases the internal resistivity and shuts the cell down upon heating to an elevated temperature, such as 110.degree. C. Also provided are methods for increasing the safety of an electrochemical cell by utilizing such separators with a safety shutdown layer.

  7. Colorado School of Mines Police Department, Campus Security and Fire Safety Report -2013 2013 ANNUAL SECURITY

    E-Print Network [OSTI]

    information about safety and security at the Colorado School of Mines. In addition to outlining the policiesColorado School of Mines Police Department, Campus Security and Fire Safety Report -2013 1 2013 ANNUAL SECURITY & FIRE SAFETY REPORT PREPARED BY: THE COLORADO SCHOOL OF MINES DEPARTMENT OF PUBLIC

  8. Designing Homes for Function and Safety 

    E-Print Network [OSTI]

    Harris, Janie

    2002-01-31

    and Safety Janie Harris Extension Specialist, Housing and Environment The Texas A&M University System The traditional home is designed for an able-bodied, nonelderly adult. Since that description fits less than 15 percent of our population, many people... communicate information about how to use them, regardless of a person?s sensory abilities. a71 Tolerance for error: The design minimizes both safety hazards and the consequences of accidents or unintended actions. a71 Low physical effort: Activities can be car...

  9. Pattern of Failure After Limited Margin Radiotherapy and Temozolomide for Glioblastoma

    SciTech Connect (OSTI)

    McDonald, Mark W.; Shu, Hui-Kuo G.; Curran, Walter J.; Crocker, Ian R.

    2011-01-01

    Purpose: To evaluate the pattern of failure after limited margin radiotherapy for glioblastoma. Methods and Materials: We analyzed 62 consecutive patients with newly diagnosed glioblastoma treated between 2006 and 2008 with standard fractionation to a total dose of 60Gy with concurrent temozolomide (97%) or arsenic trioxide (3%). The initial clinical target volume included postoperative T2 abnormality with a median margin of 0.7cm. The boost clinical target volume included residual T1-enhancing tumor and resection cavity with a median margin of 0.5cm. Planning target volumes added a 0.3- or 0.5-cm margin to clinical target volumes. The total boost planning target volume (PTV{sub boost}) margin was 1cm or less in 92% of patients. The volume of recurrent tumor (new T1 enhancement) was categorized by the percent within the 60-Gy isodose line as central (>95%), infield (81-95%), marginal (20-80%), or distant (<20%). For comparison, an initial planning target volume with a 2-cm margin and PTV{sub boost} with a 2.5-cm margin were created for each patient. Results: With a median follow-up of 12 months, radiographic tumor progression developed in 43 of 62 patients. Imaging was available for analysis in 41: 38 (93%) had central or infield failure, 2 (5%) had marginal failure, and 1 (2%) had distant failure relative to the 60-Gy isodose line. The treated PTV{sub boost} (median, 140cm{sup 3}) was, on average, 70% less than the PTV{sub boost} with a 2.5-cm margin (median, 477cm{sup 3}) (p < 0.001). Conclusions: A PTV{sub boost} margin of 1cm or less did not appear to increase the risk of marginal and/or distant tumor failures compared with other published series. With careful radiation planning and delivery, it appears that treatment margins for glioblastoma can be reduced.

  10. Social Media: Flood #FloodSafety #SummerSafety

    E-Print Network [OSTI]

    Social Media: Flood #FloodSafety #SummerSafety Please help the NWS spread these important.weather.gov/floodsafety #FloodSafety Twitter: A trickling creek could turn into a roaring waterway within minutes. www.weather.gov/floodsafety #FloodSafety #12; Facebook: It's important to know what kind of flooding you can expect in your

  11. Laboratory Health and Safety Procedure -1 -Bishop's University Safety Policy

    E-Print Network [OSTI]

    Laboratory Health and Safety Procedure - 1 - Bishop's University Safety Policy 1.03 Laboratory community. This manual is intended to provide basic rules for safe practices in a laboratory. Individual and training specific to the needs of their laboratory safety programs when the safety subject

  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. Health and Safety Policy Statement4 Health and Safety Policy

    E-Print Network [OSTI]

    Haase, Markus

    Health and Safety Policy Statement4 Health and Safety Policy Statement UnIVERSITY OF LEEDS-based health and safety management system and workplace health framework, and by allocating the resources as a minimum l the development of a health and safety management framework based upon the University protocols

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

    E-Print Network [OSTI]

    FACS 2006 Safety-Oriented Design of Component Assemblies using Safety Interfaces Jonas Elmqvist compositional rules and derived safety interfaces for each component. The derivation of safety interfaces and the automatically generated interfaces. The component model uses reactive modules as the formal notation

  15. Packaging and Transportation Safety

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

    1995-09-27

    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

  16. Packaging and Transportation Safety

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

    2010-05-14

    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. Supersedes DOE O 460.1B.

  17. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

    - 14 Lasers 25 Lifts 15 Manual Handling 23 No Smoking Policy 2 Office Safety and Use of Computer and Good Conduct 49 Visitors and Contractors 13 Water Supplies and Drainage 25 Workshop 23 Workstation Risk

  18. 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,...

  19. Nuclear Explosive Safety

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

    2014-07-10

    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).

  20. Packaging and Transportation Safety

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

    1995-09-27

    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)]

    1996-10-02

    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.

  2. Nuclear Explosive Safety

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

    2006-06-12

    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.

  3. 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, ...

  4. Promulgating Nuclear Safety Requirements

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

    1996-05-15

    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.

  5. LABORATORY SAFETY October 2012

    E-Print Network [OSTI]

    Chan, Hue Sun

    of the program are: 1) the adherence to appropriate design criteria when designing and constructing a laboratoryLABORATORY SAFETY PROGRAM October 2012 #12;OUTLINE 1.0 INTRODUCTION AND SCOPE ...................................................................................................................................6 4.0 LABORATORY DESIGN, CONSTRUCTION, DECOMMISSIONING

  6. East Carolina University ENVIRONMENTAL SAFETY COMMITTEE

    E-Print Network [OSTI]

    Gopalakrishnan, K.

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

  7. Let The People Know the Facts: Can Government Information Removed From the Internet Be Reclaimed?

    E-Print Network [OSTI]

    2006-01-01

    Acting Director of the Information Security Oversight OfficeActing Director, Information Security Oversight Office,Chemical Safety Information, Site Security and Fuels

  8. Radiological Emergency Response Health and Safety Manual

    SciTech Connect (OSTI)

    D. R. Bowman

    2001-05-01

    This manual was created to provide health and safety (H&S) guidance for emergency response operations. The manual is organized in sections that define each aspect of H and S Management for emergency responses. The sections are as follows: Responsibilities; Health Physics; Industrial Hygiene; Safety; Environmental Compliance; Medical; and Record Maintenance. Each section gives guidance on the types of training expected for managers and responders, safety processes and procedures to be followed when performing work, and what is expected of managers and participants. Also included are generic forms that will be used to facilitate or document activities during an emergency response. These ensure consistency in creating useful real-time and archival records and help to prevent the loss or omission of information.

  9. 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

  10. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

    this form to Radiation Safety's Dosimetry Program.) ___ Yes ___ No 1. Was the Dosimeter placed or stored

  11. 2015 Construction Safety Workshop Presentations

    Broader source: Energy.gov [DOE]

    2015 Construction Safety Workshop Presentations, June 16, 2015 - Forrestal Building - Washington, DC

  12. HEALTH AND SAFETY INDUCTION Introduction

    E-Print Network [OSTI]

    Mucina, Ladislav

    HEALTH AND SAFETY INDUCTION Introduction Welcome to Curtin's online health and safety induction University is committed to providing and maintaining high standards of health and safety so we can prevent with staff, and by continually improving our health and safety management system. This course is designed

  13. Phytologia (December 2009) 91(3) 571 VARIATION AMONG THE SMOOTH-LEAF MARGINED

    E-Print Network [OSTI]

    Adams, Robert P.

    -coumarate: CoA Ligase, Abscisic acid-insensitive 3, petN, psbM, SNPs, taxonomy. The smooth-leaf margined

  14. "Do It Again": Comic Repetition, Participatory Reception and Gendered Identity on Musical Comedy's Margins

    E-Print Network [OSTI]

    Baltimore, Samuel Dworkin

    2013-01-01

    Oz Before the Rainbow. Baltimore: Johns Hopkins Universityby Samuel Dworkin Baltimore ABSTRACT OF THE DISSERTATION “DoMargins by Samuel Dworkin Baltimore Doctor of Philosophy in

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

    SciTech Connect (OSTI)

    Newcomer, Justin T.; Freeland, Katherine Elizabeth

    2013-09-01

    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.

  16. Characterization report for the ferrocyanide safety issue

    SciTech Connect (OSTI)

    Pulsipher, B.A.; Burger, L.L.; Liebetrau, A.M.; Scheele, R.D.

    1997-06-01

    Recently PNNL was tasked by DOE to develop and demonstrate a risk-based strategic approach to characterizing Hanford`s Nuclear Waste Tanks. This strategic approach was documented in a report entitled ``A Risk-Based Focused Decision-Management Approach for Justifying Characterization of Hanford Tank Waste``. In support of the general approach, a specific strategy for addressing each of the several safety issues associated with the tanks was developed. This report documents the approach for the Ferrocyanide Safety Issue. The purpose of this report is to describe a structured logic diagram (SLD) for determining the risk associated with the ferrocyanide tank safety issue and provide the supporting information for the SLD. The SLD addresses the resolution of risks resulting from the presence of ferrocyanide layers within the Hanford tanks. The informational requirements for determining risk from any reaction stemming from ferrocyanide are outlined in the SLD. This report will describe the potential paths to a successful resolution of the ferrocyanide safety issue. Complete development of the intervention pathway is outside the scope of this current activity. General descriptions of the approach, key components of the SLD, and conclusions are provided in the body of this report. The complete SLD, descriptions of each box shown in the SLD, a discussion on how to fill data needs, and a list of contributors is provided in the appendices.

  17. Health and Safety Manual Civil and Environmental Engineering Dept.

    E-Print Network [OSTI]

    Eberhard, Marc O.

    ..........................................................................................................................14 MILLING MACHINE SAFETY RULES

  18. Criticality Safety Basics for INL Emergency Responders

    SciTech Connect (OSTI)

    Valerie L. Putman

    2012-08-01

    This document is a modular self-study guide about criticality safety principles for Idaho National Laboratory emergency responders. This guide provides basic criticality safety information for people who, in response to an emergency, might enter an area that contains much fissionable (or fissile) material. The information should help responders understand unique factors that might be important in responding to a criticality accident or in preventing a criticality accident while responding to a different emergency.

    This study guide specifically supplements web-based training for firefighters (0INL1226) and includes information for other Idaho National Laboratory first responders. However, the guide audience also includes other first responders such as radiological control personnel.

    For interested readers, this guide includes clearly marked additional information that will not be included on tests. The additional information includes historical examples (Been there. Done that.), as well as facts and more in-depth information (Did you know …).

    INL criticality safety personnel revise this guide as needed to reflect program changes, user requests, and better information. Revision 0, issued May 2007, established the basic text. Revision 1 incorporates operation, program, and training changes implemented since 2007. Revision 1 increases focus on first responders because later responders are more likely to have more assistance and guidance from facility personnel and subject matter experts. Revision 1 also completely reorganized the training to better emphasize physical concepts behind the criticality controls that help keep emergency responders safe. The changes are based on and consistent with changes made to course 0INL1226.

  19. Use of a Web Site to Enhance Criticality Safety Training

    SciTech Connect (OSTI)

    Huang, S T; Morman, J

    2003-08-04

    Currently, a website dedicated to enhancing communication and dissemination of criticality safety information is sponsored by the U.S. Department of Energy (DOE) Nuclear Criticality Safety Program (NCSP). This website was developed as part of the DOE response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2, which reflected the need to make criticality safety information available to a wide audience. The website is the focal point for DOE nuclear criticality safety (NCS) activities, resources and references, including hyperlinks to other sites actively involved in the collection and dissemination of criticality safety information. The website is maintained by the Lawrence Livermore National Laboratory (LLNL) under auspices of the NCSP management. One area of the website contains a series of Nuclear Criticality Safety Engineer Training (NCSET) modules. During the past few years, many users worldwide have accessed the NCSET section of the NCSP website and have downloaded the training modules as an aid for their training programs. This trend was remarkable in that it points out a continuing need of the criticality safety community across the globe. It has long been recognized that training of criticality safety professionals is a continuing process involving both knowledge-based training and experience-based operations floor training. As more of the experienced criticality safety professionals reach retirement age, the opportunities for mentoring programs are reduced. It is essential that some method be provided to assist the training of young criticality safety professionals to replenish this limited human expert resource to support on-going and future nuclear operations. The main objective of this paper is to present the features of the NCSP website, including its mission, contents, and most importantly its use for the dissemination of training modules to the criticality safety community. We will discuss lessons learned and several ideas for future development in the area of web-based training for criticality safety professionals. Our effort is intended to stimulate a discussion of ideas and solicit participation in the development of the next generation of a web-based criticality training site that can be used to assist the training of newcomers to this important safety discipline.

  20. Seismic Safety Guide

    SciTech Connect (OSTI)

    Eagling, D.G.

    1983-09-01

    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.

  1. Measuring Process Safety Management

    SciTech Connect (OSTI)

    Sweeney, J.C. (ARCO Chemical Co., Newtown Square, PA (United States))

    1992-04-01

    Many companies are developing and implementing Process Safety Management (PSM) systems. Various PSM models, including those by the Center for Chemical Process Safety (CCPS), the American Petroleum Institute (API), the Chemical Manufacturers Association (CMA) and OSHA have emerged to guide the design, development and installation of these systems. These models represent distillations of the practices, methods and procedures successfully used by those who believed that a strong correlation exists between sound PSM practices and achieving reductions in the frequency and severity of process incidents. This paper describes the progress of CCPS research toward developing a PSM performance measurement model. It also provides a vision for future CCPS research to define effectiveness indices.

  2. SSC Safety Review Document

    SciTech Connect (OSTI)

    Toohig, T.E. [ed.

    1988-11-01

    The safety strategy of the Superconducting Super Collider (SSC) Central Design Group (CDG) is to mitigate potential hazards to personnel, as far as possible, through appropriate measures in the design and engineering of the facility. The Safety Review Document identifies, on the basis of the Conceptual Design Report (CDR) and related studies, potential hazards inherent in the SSC project independent of its site. Mitigative measures in the design of facilities and in the structuring of laboratory operations are described for each of the hazards identified.

  3. Integration of Environment, Safety, and Health into Facility Disposition Activities

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

    1998-05-01

    Volume One of this Standard has been revised to provide a Department of Energy (DOE) approved methodology for preparing a Documented Safety Analysis (DSA) for decommissioning of nuclear facilities, as well as environmental restoration activities that involve work not done within a permanent structure. Methodologies provided in this Standard are intended to be compliant with Title 10 of the Code of Federal Regulations (CFR) Part 830, Nuclear Safety Management, Subpart B, Safety Basis Requirements. Volume Two contains the appendices that provide additional environment, safety and health (ES&H) information to complement Volume 1 of this Standard. Volume 2 of the Standard is much broader in scope than Volume 1 and satisfies several purposes. Integrated safety management expectations are provided in accordance with facility disposition requirements contained in DOE O 430.1B, Real Property Asset Management.

  4. Binary Join Trees for Computing Marginals in the Shenoy-Shafer Architecture

    E-Print Network [OSTI]

    Shenoy, Prakash P.

    1997-08-01

    -2003, USA pshenoy@ku.edu http://lark.cc.ku.edu/~pshenoy ? Appeared in International Journal of Approximate Reasoning, 17(2-3), 1997, 239?263. ii Binary Join Trees for Computing Marginals in the Shenoy... NETWORK FRAMEWORK .................................................2 3 AXIOMS FOR LOCAL COMPUTATION..........................................................5 4 COMPUTING A MARGINAL USING THE FUSION ALGORITHM ........................6 5 FUSION...

  5. 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

  6. Wind speed influence on phytoplankton bloom dynamics in the Southern Ocean Marginal Ice Zone

    E-Print Network [OSTI]

    Moore, Keith

    Wind speed influence on phytoplankton bloom dynamics in the Southern Ocean Marginal Ice Zone Dillon; published 7 August 2007. [1] Analysis of satellite ocean color and wind speed data within the seasonal ice. Moore (2007), Wind speed influence on phytoplankton bloom dynamics in the Southern Ocean Marginal Ice

  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. From Camp Dwellers to Urban Refugees?: Urbanization and Marginalization of Refugee Camps in Lebanon.

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    - 1 - From Camp Dwellers to Urban Refugees?: Urbanization and Marginalization of Refugee Camps villes invisibles 1. Introduction Palestinian refugees in Lebanon are marginalized in their host society with the relationship between the refugees' own socio-political dynamic, political actors, and space. The migrations

  9. 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

  10. 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

  11. Produce through coiled tubing to keep marginal wells unloaded

    SciTech Connect (OSTI)

    Not Available

    1986-12-01

    The use of coiled tubing as an alternate production tubing string has been attempted or considered by numerous operators in the past. However, its use has been tempered due to several problems known to be inherent with coiled tubing recompletions. Some of the problems encountered are: Killing the well to allow for tubing installation always carries the risk of formation damage; Candidate wells normally are marginal producers and may not produce sufficient revenue to justify the cost of a major workover; Procedures followed to install surface equipment may be hazardous; Previous installation designs required running the coiled tubing to the top of the tree, affecting the functional loss of all existing wellhead equipment; Often substandard modifications were required to reconnect into existing production facilities. However, a prototype spool and tubing hanger that incorporated modifications designed to solve these problems has been developed jointly by Reeled Tubing, Inc., and Well-head Control Systems. The solution is a new concept in the coiled tubing hanger. The design incorporates a floating element, which is a combination slip bowl, seal element and retaining sub. The entire assembly is installed and activated in the bore of a specially designed spool installed between the primary and secondary master valves of the existing wellhead.

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

    SciTech Connect (OSTI)

    Ingersoll, Daniel T [ORNL] [ORNL

    2011-01-01

    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.

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

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

    January 8, 2015 Nuclear Safety Delegations for Documented Safety Analysis Approval (EA CRAD 31-09, Rev. 0) This Criteria Review and Approach Document (EA CRAD 31-09, Rev. 0)...

  14. Integrating Safety into Design and Construction | Department...

    Office of Environmental Management (EM)

    Integrating Safety into Design and Construction Integrating Safety into Design and Construction DepSecMemoIntegratingSafetyInDesignAndConstruction05Dec2005.pdf More Documents &...

  15. Commercial Vehicle Safety Alliance | Department of Energy

    Office of Environmental Management (EM)

    Commercial Vehicle Safety Alliance Commercial Vehicle Safety Alliance Commercial Vehicle Safety Alliance More Documents & Publications North American Standard Level VI Inspection...

  16. Community Pedestrian Safety Engagement Workshops in California

    E-Print Network [OSTI]

    Babka, Rhianna JoIris; Cooper, Jill F; Alfsen, Wendy; Sabin, Marilyn

    2011-01-01

    Highway Administration. Pedestrian & Bicycle Safety. http://How to Develop a Pedestrian Safety Action Plan. 2006.Developing and Implementing a Pedestrian Safety Action Plan.

  17. Laser Pointer Safety INTRODUCTION

    E-Print Network [OSTI]

    Laser Pointer Safety INTRODUCTION The use of laser diode pointers that operate in the visible to the retractable, metal pointer, the laser pointer beam will produce a small dot of light on whatever object at which it is aimed. It can draw an audience¹s attention to a particular key point in a slide show. Laser

  18. DOE Explosives Safety Manual

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

    2006-01-09

    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.

  19. Nuclear Explosive Safety Manual

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

    2009-04-14

    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.

  20. Nuclear Explosive Safety

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

    2006-06-12

    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.

  1. Nuclear Explosive Safety

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

    2009-04-14

    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.

  2. Nuclear Explosive Safety

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

    2015-01-26

    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). Supersedes DOE O 452.2D and DOE M 452.2-1A.

  3. Nuclear Explosive Safety

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

    2009-04-14

    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

  4. 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

  5. Integrated Safety Management

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

    2011-04-25

    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. Supersedes DOE M 450.4-1 and DOE M 411.1-1C

  6. Module Safety Issues (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2012-02-01

    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.

  7. Packaging and Transportation Safety

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

    2003-04-04

    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.

  8. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11

    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.

  9. 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. There are many techniques that aim to improve the performance of neural networks for safety-critical systems

  10. 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

  11. 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

  12. Safety Logics I: Absolute Safety Zhisheng Huang and John Bell #

    E-Print Network [OSTI]

    Huang, Zhisheng

    Support Systems, Safety and Liability, and is supported by the United Kingdom Engineering and Physical extensions of it. We then give an example of reasoning about safety in nuclear power stations, and conclude which agents can reason about safety. This # This research forms part of the RED project, Decision

  13. 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

    2014-06-01

    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.

  14. HANFORD NUCLEAR CRITICALITY SAFETY PROGRAM DATABASE

    SciTech Connect (OSTI)

    TOFFER, H.

    2005-05-02

    The Hanford Database is a useful information retrieval tool for a criticality safety practitioner. The database contains nuclear criticality literature screened for parameter studies. The entries, characterized with a value index, are segregated into 16 major and six minor categories. A majority of the screened entries have abstracts and a limited number are connected to the Office of Scientific and Technology Information (OSTI) database of full-size documents. Simple and complex searches of the data can be accomplished very rapidly and the end-product of the searches could be a full-size document. The paper contains a description of the database, user instructions, and a number of examples.

  15. Proceedings: Decommissioning, Decontamination, ALARA, and Worker Safety Workshop

    SciTech Connect (OSTI)

    None

    2000-09-01

    This workshop on decontamination, ALARA, and worker safety was the sixth in a series initiated by EPRI to aid utility personnel in assessing the technologies for decommissioning nuclear power plants. The workshop focused on specific aspects of decommissioning related to the management of worker radiation exposure and safety. The information presented will help individual utilities assess benefits of programs in these areas for their projects, including their potential to reduce decommissioning costs.

  16. Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements

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

    2010-04-08

    This Guide, including its attachments, provides information to assist in the implementation of Title 10 Code of Federal Regulations (CFR) Section 830.203, “Unreviewed Safety Question Process,” of the Nuclear Safety Management Rules for Category 1, 2, and 3 nuclear facilities owned or operated by the Department of Energy (DOE), including the National Nuclear Security Administration (NNSA). Cancels DOE G 424.1-1A. Admin Chg 1 dated 4-12-13.

  17. Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements

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

    2010-04-08

    This Guide, including its attachments, provides information to assist in the implementation of Title 10 Code of Federal Regulations (CFR) Section 830.203, “Unreviewed Safety Question Process,” of the Nuclear Safety Management Rules for Category 1, 2, and 3 nuclear facilities owned or operated by the Department of Energy (DOE), including the National Nuclear Security Administration (NNSA). Admin Chg 2, dated 6-12-13, supersedes DOE G 424.1-1B Admin Chg 1.

  18. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    SciTech Connect (OSTI)

    GARVIN, L J; JENSEN, M A

    2004-04-13

    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.

  19. Safety Training for Shop Personnel

    E-Print Network [OSTI]

    Sniadecki, Nathan J.

    3 Electrical Safety, Basic Online Initial 4 Lockout Tag-Out Initial 5 Globally Harmonized System Extinguisher - Hands-On Yes No 3 Electrical Safety, Basic-Online Yes No 4 Lockout Tag-Out Yes No 5 Globally

  20. Nuclear Explosive Safety Evaluation Processes

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

    2009-04-14

    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.

  1. CRAD, NNSA- Safety Basis (SB)

    Broader source: Energy.gov [DOE]

    CRAD for Safety Basis (SB). Criteria Review and Approach Documents (CRADs) that can be used to conduct a well-organized and thorough assessment of elements of safety and health programs.

  2. LASER Safety Manual August 2007

    E-Print Network [OSTI]

    UW LASER Safety Manual August 2007 Radiation Safety Office Environmental Health and Safety;Contents 1. Laser Basics 1.1 Laser Theory 1.2 Types of Lasers 2. Hazards and Safety Standards 2 2.6.4 Other Hazards 2.7 Hazard Classes 2.7.1 Introduction 2.7.2 Class 3B Lasers 2.7.3 Class 4 Lasers

  3. ORBITAL MIGRATION OF PROTOPLANETS IN A MARGINALLY GRAVITATIONALLY UNSTABLE DISK

    SciTech Connect (OSTI)

    Boss, Alan P.

    2013-02-20

    Core accretion and disk instability require giant protoplanets to form in the presence of disk gas. Protoplanet migration models generally assume disk masses low enough that the disk's self-gravity can be neglected. However, disk instability requires a disk massive enough to be marginally gravitationally unstable (MGU). Even for core accretion, an FU Orionis outburst may require a brief MGU disk phase. We present a new set of three-dimensional, gravitational radiation hydrodynamics models of MGU disks with multiple protoplanets, which interact gravitationally with the disk and with each other, including disk gas mass accretion. Initial protoplanet masses are 0.01 to 10 M {sub Circled-Plus} for core accretion models, and 0.1 to 3 M {sub Jup} for Nice scenario models, starting on circular orbits with radii of 6, 8, 10, or 12 AU, inside a 0.091 M {sub Sun} disk extending from 4 to 20 AU around a 1 M {sub Sun} protostar. Evolutions are followed for up to {approx}4000 yr and involve phases of relative stability (e {approx} 0.1) interspersed with chaotic phases (e {approx} 0.4) of orbital interchanges. The 0.01 to 10 M {sub Circled-Plus} cores can orbit stably for {approx}1000 yr: monotonic inward or outward orbital migration of the type seen in low mass disks does not occur. A system with giant planet masses similar to our solar system (1.0, 0.33, 0.1, 0.1 M {sub Jup}) was stable for over 1000 yr, and a Jupiter-Saturn-like system was stable for over 3800 yr, implying that our giant planets might well survive an MGU disk phase.

  4. Residential Fire Safety Policies Introduction

    E-Print Network [OSTI]

    Johnson Jr.,, Ray

    Residential Fire Safety Policies Introduction University Housing and Campus Code Compliance and Fire Safety at the City University of New York at Queens College in compliance with the Higher Education Opportunity Act (HEOA) have developed an annual fire safety report. This document summarizes

  5. ANNUAL FIRE SAFETY RESIDENCE HALLS

    E-Print Network [OSTI]

    Fernandez, Eduardo

    1 2013 ANNUAL FIRE SAFETY REPORT FOR RESIDENCE HALLS As Required by the Higher Education Opportunity Act (HEOA) #12;2 INTRODUCTION Contents of this annual fire safety report reflect the requirements outlined in the HEOA, which are included in Florida Atlantic University's (FAU) campus fire safety program

  6. CHEMICAL LABORATORY SAFETY AND METHODOLOGY

    E-Print Network [OSTI]

    Northern British Columbia, University of

    CHEMICAL LABORATORY SAFETY AND METHODOLOGY MANUAL August 2013 #12;ii Emergency Numbers UNBC Prince-Emergency Numbers UNBC Prince George Campus Chemstores 6472 Chemical Safety 6472 Radiation Safety 6472 Biological the safe use, storage, handling, waste and emergency management of chemicals on the University of Northern

  7. 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

  8. Health and Safety Training Reciprocity

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

    2014-04-14

    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. Safety-Critical Universit at

    E-Print Network [OSTI]

    Peleska, Jan - Fachbereich 3

    . Hazard Analysis and Risk Assessment 5. Design Criteria for Safety-Critical Systems 6. Validation, Veri#12. Hazard Analysis and Risk Assessment 5. Design Criteria for Safety-Critical Systems 6. Validation, Veri#12Safety-Critical Systems Prof. Dr. Jan Peleska Universit at Bremen | TZI Dr. Ing. Cornelia Zahlten

  10. Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1

    SciTech Connect (OSTI)

    Dukelow, G.T.; Hanson, G.A. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States)

    1995-05-01

    The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies.

  11. Managing chemicals safety: Putting it all together

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    Businesses that use hazardous chemicals can prevent accidents--if they have the right information. It's up to industry, large and small, to manage chemicals safely. But an effective, integrated approach to prevention involves a whole network of other players, too: fire and emergency services, trade associations, labor organizations, professional societies, government at all levels, insurance companies and financial lenders, the environmental community and other public interest groups, and the media. Sharing information across this network is what makes prevention work. The publication is one piece of that information mosaic. It shows owners and managers of smaller enterprises how to get started in chemical safety management. It gives basic definitions and describes the benefits. It suggests initial steps and recommends sources and resources for additional information.

  12. Using Temporal Information in an Automated Classification of Summer, Marginal Ice Zone Imagery*

    E-Print Network [OSTI]

    Kansas, University of

    * Donna Haverkamp and Costas Tsatsoulis Department of Electrical Engineering and Computer Science- analyzed temperature records and regional statistics in order to achieve an automated ice's ice/water concentrations and melt state with temperature and wind data, a current interpretation

  13. The Terre Haute Door Company (THDC) designs three types of steel doors: Standard, High Security, and Maximum Security. Each door requires different amounts of machine and labor time and has different profit margins; this

    E-Print Network [OSTI]

    Phillips, David

    margins; this information is given in the following table. Machine 1 Machine 2 Hours Manpower Hours to it only 120 hours per week on machine 1 and 100 hours on machine 2 before required maintenance, and 280 hours of manpower available per week. Write a linear program that determines how many of each door

  14. Nuclear safety research collaborations between the U.S. and Russian Federation International Nuclear Safety Centers

    SciTech Connect (OSTI)

    Hill, D. J.; Braun, J. C.; Klickman, A. E.; Bougaenko, S. E.; Kabonov, L. P.; Kraev, A. G.

    2000-05-05

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) have formed International Nuclear Safety Centers to collaborate on nuclear safety research. USDOE established the US Center (ISINSC) at Argonne National Laboratory (ANL) in October 1995. MINATOM established the Russian Center (RINSC) at the Research and Development Institute of Power Engineering (RDIPE) in Moscow in July 1996. In April 1998 the Russian center became a semi-independent, autonomous organization under MINATOM. The goals of the center are to: Cooperate in the development of technologies associated with nuclear safety in nuclear power engineering; Be international centers for the collection of information important for safety and technical improvements in nuclear power engineering; and Maintain a base for fundamental knowledge needed to design nuclear reactors. The strategic approach is being used to accomplish these goals is for the two centers to work together to use the resources and the talents of the scientists associated with the US Center and the Russian Center to do collaborative research to improve the safety of Russian-designed nuclear reactors. The two centers started conducting joint research and development projects in January 1997. Since that time the following ten joint projects have been initiated: INSC databases--web server and computing center; Coupled codes--Neutronic and thermal-hydraulic; Severe accident management for Soviet-designed reactors; Transient management and advanced control; Survey of relevant nuclear safety research facilities in the Russian Federation; Computer code validation for transient analysis of VVER and RBMK reactors; Advanced structural analysis; Development of a nuclear safety research and development plan for MINATOM; Properties and applications of heavy liquid metal coolants; and Material properties measurement and assessment. Currently, there is activity in eight of these projects. Details on each of these joint projects are given.

  15. Anisotropic Margin Expansions in 6 Anatomic Directions for Oropharyngeal Image Guided Radiation Therapy

    SciTech Connect (OSTI)

    Yock, Adam D. [Department of Radiation Physics, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Graduate School of Biomedical Sciences, The University of Texas Health Science Center at Houston, Houston, Texas (United States); Garden, Adam S. [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Court, Laurence E. [Department of Radiation Physics, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Graduate School of Biomedical Sciences, The University of Texas Health Science Center at Houston, Houston, Texas (United States); Beadle, Beth M. [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Zhang, Lifei [Department of Radiation Physics, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Dong, Lei, E-mail: dong.lei@scrippshealth.org [Department of Radiation Physics, The University of Texas MD Anderson Cancer Center, Houston, Texas (United States); Graduate School of Biomedical Sciences, The University of Texas Health Science Center at Houston, Houston, Texas (United States)

    2013-11-01

    Purpose: The purpose of this work was to determine the expansions in 6 anatomic directions that produced optimal margins considering nonrigid setup errors and tissue deformation for patients receiving image-guided radiation therapy (IGRT) of the oropharynx. Methods and Materials: For 20 patients who had received IGRT to the head and neck, we deformably registered each patient's daily images acquired with a computed tomography (CT)-on-rails system to his or her planning CT. By use of the resulting vector fields, the positions of volume elements within the clinical target volume (CTV) (target voxels) or within a 1-cm shell surrounding the CTV (normal tissue voxels) on the planning CT were identified on each daily CT. We generated a total of 15,625 margins by dilating the CTV by 1, 2, 3, 4, or 5 mm in the posterior, anterior, lateral, medial, inferior, and superior directions. The optimal margins were those that minimized the relative volume of normal tissue voxels positioned within the margin while satisfying 1 of 4 geometric target coverage criteria and 1 of 3 population criteria. Results: Each pair of geometric target coverage and population criteria resulted in a unique, anisotropic, optimal margin. The optimal margin expansions ranged in magnitude from 1 to 5 mm depending on the anatomic direction of the expansion and on the geometric target coverage and population criteria. Typically, the expansions were largest in the medial direction, were smallest in the lateral direction, and increased with the demand of the criteria. The anisotropic margin resulting from the optimal set of expansions always included less normal tissue than did any isotropic margin that satisfied the same pair of criteria. Conclusions: We demonstrated the potential of anisotropic margins to reduce normal tissue exposure without compromising target coverage in IGRT to the head and neck.

  16. 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

  17. Supplementary Materials Table 1: Simulated log-normal survival data marginal posterior probability of inclusion of relevant

    E-Print Network [OSTI]

    Vannucci, Marina

    .1835 Table 1: Simulated log-normal survival data: Marginal posterior probabilities of inclusion of rele- vant: Marginal posterior probabilities of inclusion of rele- vant variables under different maximum correlation

  18. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01

    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.

  19. 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))

    1989-01-01

    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.

  20. Enhancing Railroad Hazardous Materials Transportation Safety...

    Office of Environmental Management (EM)

    Safety Enhancing Railroad Hazardous Materials Transportation Safety Presented by Kevin R. Blackwell, Radioactive Materials Program Manager. Enhancing Railroad Hazardous Materials...

  1. Mars mission safety

    SciTech Connect (OSTI)

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

    1989-06-01

    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.

  2. Integrated Safety Management Policy

    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 on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergy HeadquartersFuelBConservationEnergy5975-01 REPORTDepartment ofINTEGRATED SAFETY

  3. Safety | Department of Energy

    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 Data Center Home Page on Delicious Rank EERE: Alternative FuelsofProgram: Report AppendicesA TokenCommercialSTEM VolunteerSafety Alerts

  4. Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

    SciTech Connect (OSTI)

    Kisner, Roger A; Mullens, James Allen; Wilson, Thomas L; Wood, Richard Thomas; Korsah, Kofi; Qualls, A L; Muhlheim, Michael David; Holcomb, David Eugene; Loebl, Andy

    2007-08-01

    Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

  5. Oxygen and organic matter thresholds for benthic faunal activity on the Pakistan margin oxygen minimum zone (7001100 m)

    E-Print Network [OSTI]

    Levin, Lisa

    Oxygen and organic matter thresholds for benthic faunal activity on the Pakistan margin oxygen) on the bathyal Pakistan margin, where sediments grade from fully laminated sediment at 700 m (0.12 mL LÀ1 O2 [5 m matter to generate abrupt faunal transitions on the Pakistan margin. & 2008 Elsevier Ltd. All rights

  6. Safety, codes and standards for hydrogen installations :

    SciTech Connect (OSTI)

    Harris, Aaron P.; Dedrick, Daniel E.; LaFleur, Angela Christine; San Marchi, Christopher W.

    2014-04-01

    Automakers and fuel providers have made public commitments to commercialize light duty fuel cell electric vehicles and fueling infrastructure in select US regions beginning in 2014. The development, implementation, and advancement of meaningful codes and standards is critical to enable the effective deployment of clean and efficient fuel cell and hydrogen solutions in the energy technology marketplace. Metrics pertaining to the development and implementation of safety knowledge, codes, and standards are important to communicate progress and inform future R&D investments. This document describes the development and benchmarking of metrics specific to the development of hydrogen specific codes relevant for hydrogen refueling stations. These metrics will be most useful as the hydrogen fuel market transitions from pre-commercial to early-commercial phases. The target regions in California will serve as benchmarking case studies to quantify the success of past investments in research and development supporting safety codes and standards R&D.

  7. Thermohydraulic and Safety Analysis for CARR Under Station Blackout Accident

    SciTech Connect (OSTI)

    Wenxi Tian; Suizheng Qiu; Guanghui Su; Dounan Jia [Xi'an Jiaotong University, 28 Xianning Road, Xi'an 710049 (China); Xingmin Liu - China Institute of Atomic Energy

    2006-07-01

    A thermohydraulic and safety analysis code (TSACC) has been developed using Fortran 90 language to evaluate the transient thermohydraulic behaviors and safety characteristics of the China Advanced Research Reactor(CARR) under Station Blackout Accident(SBA). For the development of TSACC, a series of corresponding mathematical and physical models were considered. Point reactor neutron kinetics model was adopted for solving reactor power. All possible flow and heat transfer conditions under station blackout accident were considered and the optional models were supplied. The usual Finite Difference Method (FDM) was abandoned and a new model was adopted to evaluate the temperature field of core plate type fuel element. A new simple and convenient equation was proposed for the resolution of the transient behaviors of the main pump instead of the complicated four-quadrant model. Gear method and Adams method were adopted alternately for a better solution to the stiff differential equations describing the dynamic behaviors of the CARR. The computational result of TSACC showed the enough safety margin of CARR under SBA. For the purpose of Verification and Validation (V and V), the simulated results of TSACC were compared with those of Relap5/Mdo3. The V and V result indicated a good agreement between the results by the two codes. Because of the adoption of modular programming techniques, this analysis code is expected to be applied to other reactors by easily modifying the corresponding function modules. (authors)

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

    E-Print Network [OSTI]

    Williamson, Emily Anne

    2014-01-01

    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 ...

  9. 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 ...

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

    E-Print Network [OSTI]

    Mills, Alexa (Alexa Timeaus)

    2008-01-01

    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 ...

  11. Some Improvements to the Shenoy-Shafer and Hugin Architectures for Computing Marginals

    E-Print Network [OSTI]

    Schmidt, Tuija; Shenoy, Prakash P.

    1998-01-01

    The main aim of this paper is to describe two modifications to the Shenoy–Shafer architecture with the goal of making it computationally more efficient in computing marginals of the joint valuation. We also describe a ...

  12. The evolution of lithospheric deformation and crustal structure from continental margins to oceanic spreading centers

    E-Print Network [OSTI]

    Behn, Mark Dietrich, 1974-

    2002-01-01

    This thesis investigates the evolution of lithospheric deformation and crustal structure from continental margins to mid-ocean ridges. The first part (Ch. 2) examines the style of segmentation along the U.S. East Coast ...

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

    SciTech Connect (OSTI)

    Ecclestone, Gillian; Heath, Emily; Bissonnette, Jean-Pierre

    2013-11-15

    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.

  14. Subsidence history, crustal structure, and evolution of the Somaliland-Yemen conjugate margin

    E-Print Network [OSTI]

    Ali, Mohammed

    seismic refraction data and process-oriented gravity and flexure modeling. The margin is asymmetric et al., 2001; Dauteuil et al., 2001; Hebert et al., 2001; Manighetti et al., 1997]. Seismic and well

  15. A reference time scale for Site U1385 (Shackleton Site) on the SW Iberian Margin

    E-Print Network [OSTI]

    Hodell, D.; Lourens, L.; Crowhurst, S.; Konijnendijk, T.; Tjallingii, R.; Jimenez-Espejo, F.; Skinner, L.; Tzedakis, P. C.

    2015-07-16

    ACCEPTED MANUSCRIPT 5 fidelity of the sediments on the SW Iberian Margin make this region a prime target for ocean drilling. In 2011, an Ancillary Program Letter (APL 763) was submitted to the Integrated Ocean Drilling Program (IODP) requesting four...

  16. Estimating Marginal Returns to Medical Care: Evidence from At-Risk Newborns

    E-Print Network [OSTI]

    Almond, Douglas

    A key policy question is whether the benefits of additional medical expenditures exceed their costs. We propose a new approach for estimating marginal returns to medical spending based on variation in medical inputs generated ...

  17. Ferrocyanide Safety Project: FY 1991 annual report

    SciTech Connect (OSTI)

    Hallen, R.T.; Burger, L.L.; Hockey, R.L.; Lilga, M.A.; Scheele, R.D.; Tingey, J.M.

    1992-06-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in the single-shell waste storage tanks (SSTs), in particular the risk of explosion. This Task Team, which is composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), an outside consultants, was formed in response to the need for an updated analysis of safety questions on the Hanford SSTSs. The Ferrocyanide Safety Project, discussed in this report, is being conducted by PNL as part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, which is sponsored by the US Department of Energy's Tank Safety Project Office, is to provide technical information on ferrocyanide chemistry and its interaction and reactive behavior with other tank constituents. Ultimately, this information will be used to maintain the tanks in a safe condition, implement interim stabilization strategies, and identify optimal disposal options. While by itself ferrocyanide is a stable complex of ferrous ion and cyanide, it can be made to explode in the laboratory in the presence of oxidizing materials such as nitrates and/or nitrites temperatures above 280{degree}C or by sufficient electrical spark. The specific goal of the PNL project is so determine the conditions necessary for the ferrocyanide-bearing wastes in Hanford SSTs to represent a hazard, to determine the conditions where these same wastes am not a hazard, or to determine the conditions which are necessary to assure the wastes are safe prior to treatment for permanent disposal. This annual report gives the results of the work conducted by PNL in FY 1991. The activities mainly focused on preparing and characterizing synthetic wastes and alkali nickel ferrocyanides produced using the In-Farm cesium scavenging flowsheet and pure potential nickel ferrocyanides that could be produced by all of the cesium scavenging flowsheets.

  18. Ferrocyanide Safety Project: FY 1991 annual report

    SciTech Connect (OSTI)

    Hallen, R.T.; Burger, L.L.; Hockey, R.L.; Lilga, M.A.; Scheele, R.D.; Tingey, J.M.

    1992-06-01

    The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in the single-shell waste storage tanks (SSTs), in particular the risk of explosion. This Task Team, which is composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), an outside consultants, was formed in response to the need for an updated analysis of safety questions on the Hanford SSTSs. The Ferrocyanide Safety Project, discussed in this report, is being conducted by PNL as part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, which is sponsored by the US Department of Energy`s Tank Safety Project Office, is to provide technical information on ferrocyanide chemistry and its interaction and reactive behavior with other tank constituents. Ultimately, this information will be used to maintain the tanks in a safe condition, implement interim stabilization strategies, and identify optimal disposal options. While by itself ferrocyanide is a stable complex of ferrous ion and cyanide, it can be made to explode in the laboratory in the presence of oxidizing materials such as nitrates and/or nitrites temperatures above 280{degree}C or by sufficient electrical spark. The specific goal of the PNL project is so determine the conditions necessary for the ferrocyanide-bearing wastes in Hanford SSTs to represent a hazard, to determine the conditions where these same wastes am not a hazard, or to determine the conditions which are necessary to assure the wastes are safe prior to treatment for permanent disposal. This annual report gives the results of the work conducted by PNL in FY 1991. The activities mainly focused on preparing and characterizing synthetic wastes and alkali nickel ferrocyanides produced using the In-Farm cesium scavenging flowsheet and pure potential nickel ferrocyanides that could be produced by all of the cesium scavenging flowsheets.

  19. Information Security

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

    2007-06-29

    Establishes security requirements for the protection and control of information and matter required to be classified or controlled by statutes, regulations, or Department of Energy directives. Section E, Technical Surveillance Countermeasures Program, is Official Use Only. Please contact the DOE Office of Health, Safety and Security at 301-903-0292 if your official duties require you to have access to this part of the directive. Cancels: DOE M 471.2-1B, DOE M 471.2-1C, DOE M 471.2-4, and DOE O 471.2A

  20. Information Security

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

    2005-08-26

    This Manual establishes security requirements for the protection and control of information and matter required to be classified or controlled by statutes, regulations, or Department of Energy directives. Attachment E, Technical Surveillance Countermeasures Program, is for Official Use Only. Contact the Office of Security and Safety Performance Assurance at 301-903-3653 if your official duties require you to have access to this part of the directive. Cancels: DOE M 471.2-1B, DOE M 471.2-1C, DOE M 471.2-4, and DOE O 471.2A.

  1. 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.

    1993-06-15

    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.

  2. Nuclear safety for the space exploration initiative. Final report

    SciTech Connect (OSTI)

    Dix, T.E.

    1991-11-01

    The results of a study to identify potential hazards arising from nuclear reactor power systems for use on the lunar and Martian surfaces, related safety issues, and resolutions of such issues by system design changes, operating procedures, and other means are presented. All safety aspects of nuclear reactor power systems from prelaunch ground handling to eventual disposal were examined consistent with the level of detail for SP-100 reactor design at the 1988 System Design Review and for launch vehicle and space transport vehicle designs and mission descriptions as defined in the 90-day Space Exploration Initiative (SEI) study. Information from previous aerospace nuclear safety studies was used where appropriate. Safety requirements for the SP-100 space nuclear reactor system were compiled. Mission profiles were defined with emphasis on activities after low earth orbit insertion. Accident scenarios were then qualitatively defined for each mission phase. Safety issues were identified for all mission phases with the aid of simplified event trees. Safety issue resolution approaches of the SP-100 program were compiled. Resolution approaches for those safety issues not covered by the SP-100 program were identified. Additionally, the resolution approaches of the SP-100 program were examined in light of the moon and Mars missions.

  3. SUESS ET AL.: SEA FLOOR METHANE HYDRATES AT HYDRATE RIDGE, CASCADIA MARGIN Sea Floor Methane Hydrates at Hydrate Ridge, Cascadia Margin

    E-Print Network [OSTI]

    Goldfinger, Chris

    SUESS ET AL.: SEA FLOOR METHANE HYDRATES AT HYDRATE RIDGE, CASCADIA MARGIN 1 Sea Floor Methane are exposed at the sea floor. A methane-oxidizing bacterial consortium populates the exposures of hydrate; colonies of vent macro-fauna are abundant as well. Discharge of methane from destabilized hydrate

  4. 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)

    1994-03-01

    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.

  5. Radiation Safety System

    SciTech Connect (OSTI)

    Vylet, Vaclav; Liu, James C.; Walker, Lawrence S.; /Los Alamos

    2012-04-04

    The goal of this work is to provide an overview of a Radiation safety system (RSS) designed for protection from prompt radiation hazard at accelerator facilities. RSS design parameters, functional requirements and constraints are derived from hazard analysis and risk assessment undertaken in the design phase of the facility. The two main subsystems of a RSS are access control system (ACS) and radiation control system (RCS). In this text, a common approach to risk assessment, typical components of ACS and RCS, desirable features and general design principles applied to RSS are described.

  6. Lawn Maintenance Safety (Spanish) 

    E-Print Network [OSTI]

    Smith, David

    2005-07-12

    . David W. Smith, Extension Safety Program Programa de Seguridad de Extensi?n Cortac?spedes empujados Los cortac?spedes empujados por detr?s incluyen dos tipos, los que se impulsan por s? mismos y los que se deben empujar. Estos cortac?spedes son com... maleza ? Antes de podar, remueva los vidrios, ramas, rocas y basura que podr?an convertirse en proyectiles. ? Mire si hay cables el?ctricos expuestos, l?neas de sistemas de comunicaci?n y cables de extensi?n para evitar da?arlos con el hilo de la...

  7. Conceptual Safety Design RM

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustments (BillionProvedTravel TravelChallenges |1-01Concentrating Solar Power ConcentratingConceptual Safety

  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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit the following commentsMethods for Estimating:I Overview ofComplete Safety

  9. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room News PublicationsAuditsCluster Compatibilitydefault Changes from Tukey toComplete Safety

  10. Safety - 88-Inch Cyclotron

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid youOxygen GenerationTechnologies |Education STEM Education LosSafety The

  11. Safety | Argonne National Laboratory

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid youOxygen GenerationTechnologies |Education STEM Education LosSafetyNews

  12. Safety and the APM

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 ofSafety

  13. Experiment Safety Requirements

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunitiesof Energy8) WignerEnergyAboutExperiment Safety

  14. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12 Page 1NEWS MEDIA16,30879543332Safety

  15. Sandia Energy - 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II)Geothermal EnergyRenewable EnergyWAves Nearshore)OperationsSafety Home

  16. Nuclear explosive safety study process

    SciTech Connect (OSTI)

    NONE

    1997-01-01

    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. NRC - regulator of nuclear safety

    SciTech Connect (OSTI)

    1997-05-01

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

  18. 242-A evaporator safety analysis report

    SciTech Connect (OSTI)

    CAMPBELL, T.A.

    1999-05-17

    This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.

  19. Facility Safety | Department of Energy

    Office of Environmental Management (EM)

    improved DOE program and field implementation of nuclear safety management programs and fire protection and natural phenomena hazard control requirements. Nuclear facility program...

  20. Design Considerations for Fire Safety 

    E-Print Network [OSTI]

    Wilson, A. Grant; Schmidt, William A.; Degenkolb, John G.; Reilly, Edward J.; Robinson, A. Pitts; Sandvik, Robert G.; Semple, J. Brooks

    1971-01-28

    Papers presented at the Symposium on Design Considerations for Fire Safety at the Semiannual Meeting of The American Society of Heating, Refrigerating and Air-conditioning Engineers

  1. Aviation Safety Council Taipei, Taiwan

    E-Print Network [OSTI]

    Ladkin, Peter B.

    Aviation Safety Council Taipei, Taiwan GE 536 Occurrence Investigation Report Runway Overrun During ............................................................. 12 1.6.1 Maintenance Records......................................................... 12 1

  2. Gordon wins NNSA Safety Professional

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

    Year award March 12, 2009 LOS ALAMOS, New Mexico, March 12, 2009-Laboratory Chief Electrical Safety Officer Lloyd Gordon received the 2008 National Nuclear Security...

  3. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

    that address key functional areas of project management, engineering and design, safety, environment, security, and quality assurance, grouped by each specific CD phase. This...

  4. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

    SciTech Connect (OSTI)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

  5. Software Safety Tutorial Status Update 1 Software Safety Tutorial

    E-Print Network [OSTI]

    Tian, Jeff

    ? · Software safety: The property of being accident- free for (embedded) software systems. Accident: failures with severe consequences Hazard: condition for accident Specialized techniques · Software safety engineering./property/environment damage excess energy/dangerous substance computers relatively safe but computer control accidents

  6. Radiation Safety Manual March 21, 2015 RADIATION SAFETY

    E-Print Network [OSTI]

    Lance, Veronica P.

    . Radioactive Drug Research Committee D. Radiation Safety Officers E. Authorized Users Chapter II: Radiation. Clinical Applications C. Loans and Transfers of Radioactive Materials Chapter VI: Occupational Exposure of Packages Containing Radioactive Materials A. Packages Delivered to the Radiation Safety Office B. Packages

  7. Idaho National Engineering Laboratory (INEL) Environmental Restoration (ER) Program Baseline Safety Analysis File (BSAF)

    SciTech Connect (OSTI)

    1995-09-01

    The Baseline Safety Analysis File (BSAF) is a facility safety reference document for the Idaho National Engineering Laboratory (INEL) environmental restoration activities. The BSAF contains information and guidance for safety analysis documentation required by the U.S. Department of Energy (DOE) for environmental restoration (ER) activities, including: Characterization of potentially contaminated sites. Remedial investigations to identify and remedial actions to clean up existing and potential releases from inactive waste sites Decontamination and dismantlement of surplus facilities. The information is INEL-specific and is in the format required by DOE-EM-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports. An author of safety analysis documentation need only write information concerning that activity and refer to BSAF for further information or copy applicable chapters and sections. The information and guidance provided are suitable for: {sm_bullet} Nuclear facilities (DOE Order 5480-23, Nuclear Safety Analysis Reports) with hazards that meet the Category 3 threshold (DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports) {sm_bullet} Radiological facilities (DOE-EM-STD-5502-94, Hazard Baseline Documentation) Nonnuclear facilities (DOE-EM-STD-5502-94) that are classified as {open_quotes}low{close_quotes} hazard facilities (DOE Order 5481.1B, Safety Analysis and Review System). Additionally, the BSAF could be used as an information source for Health and Safety Plans and for Safety Analysis Reports (SARs) for nuclear facilities with hazards equal to or greater than the Category 2 thresholds, or for nonnuclear facilities with {open_quotes}moderate{close_quotes} or {open_quotes}high{close_quotes} hazard classifications.

  8. Environment/Health/Safety (EHS): JHA

    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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFES October 27th, 2010Environment, Health, SafetyThis is an

  9. Implementation Guide for Use with 10 CFR Part 851, Worker Safety and Health Programs

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

    2006-12-27

    This Guide provides supplemental information and describes implementation practices to assist contractors in effectively developing, managing and implementing worker safety and health programs required by 10 Code of Federal Regulations, Part 851, Worker Safety and Health Program. Canceled by DOE G 440.1-1B.

  10. R&D for Safety Codes and Standards: Materials and Components Compatibility

    SciTech Connect (OSTI)

    Somerday, Brian P.; LaFleur, Chris; Marchi, Chris San

    2015-08-01

    This project addresses the following technical barriers from the Safety, Codes and Standards section of the 2012 Fuel Cell Technologies Office Multi-Year Research, Development and Demonstration Plan (section 3.8): (A) Safety data and information: limited access and availability (F) Enabling national and international markets requires consistent RCS (G) Insufficient technical data to revise standards.

  11. 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

  12. HEALTH AND SAFETY POLICY UNIVERSITY OF ABERDEEN

    E-Print Network [OSTI]

    Neri, Peter

    HEALTH AND SAFETY POLICY June 2012 #12;UNIVERSITY OF ABERDEEN HEALTH AND SAFETY POLICY 2012 Contents Page Foreword by the Principal 2 A) Health and Safety Policy Statement 3 B) Organisation and Responsibilities for Health and Safety 4 C) Health and Safety Management in Schools/Support Services 6 D) Training

  13. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety...

    Office of Environmental Management (EM)

    DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011...

  14. HEALTH, SAFETY AND ENVIRONMENTAL MANAGEMENT SYSTEM Safety Regulations and Policies for Offices

    E-Print Network [OSTI]

    Saskatchewan, University of

    HEALTH, SAFETY AND ENVIRONMENTAL MANAGEMENT SYSTEM Safety Regulations and Policies for Offices #12 Table of Contents University of Saskatchewan Policies Relating to Health, Safety and Environment) ............................................................ 15 The Saskatchewan Occupational Health and Safety Act and Regulations............................ 17

  15. Health and safety.

    SciTech Connect (OSTI)

    Avery, Rosemary Penelope; Johns, William

    2010-08-01

    This document provides information on the possible human exposure to environmental media potentially contaminated with radiological materials and chemical constituents from operations at Sandia National Laboratories/New Mexico (SNL/NM). This report is based on the best available information for Calendar Year (CY) 2008, and was prepared in support of future analyses, including those that may be performed as part of the SNL/NM Site-Wide Environmental Impact Statement.

  16. Laboratory Personnel Safety Check List Employee/Student Name_________________________________ Date_______________

    E-Print Network [OSTI]

    Rubloff, Gary W.

    Laboratory Personnel Safety Check List Employee/Student Name_________________________________ Date in the laboratory? 2. _______ Has the PI/Lab Supervisor discussed all hazardous components of the research? a in the laboratory? 4. _______ Has the PI/Lab Supervisor discussed the need for the employee/student to inform health

  17. Taiwan High Speed Rail Keeping passenger safety at the forefront

    E-Print Network [OSTI]

    Taiwan High Speed Rail Keeping passenger safety at the forefront Overview The Need Taiwan High, high-speed travel in Taiwan." -- Ming-Der Lee, manager of Maintenance Management Information Systems, Taiwan High Speed Rail Corporation Like a few countries, life on the island nation of Taiwan is shaped

  18. Evaluating and Predicting Patient Safety for Medical Devices with

    E-Print Network [OSTI]

    Zhang, Jiajie

    devices with integral information technology, then applied and tested them on several infusion pumps to evaluate and compare the safety of two 1- channel volumetric infusion pumps. The results show user errors at the human device level. Its use is demonstrated in the analysis of two infusion pumps

  19. Author's personal copy Gasoline prices and traffic safety in Mississippi

    E-Print Network [OSTI]

    Levinson, David M.

    more than 16% from 1973 to 1974 when the oil crisis occurred. International oil prices historically-grade unleaded gasoline price data from the Energy Information Administration of the U.S. Department of EnergyAuthor's personal copy Gasoline prices and traffic safety in Mississippi Guangqing Chi a, , Arthur

  20. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, E.

    1983-08-15

    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.

  1. 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).

  2. Nuclear Explosive Safety Evaluation Processes

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

    2009-04-14

    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.

  3. NOVEMBER SYSTEM SAFETY PROGRESS REPORT

    E-Print Network [OSTI]

    Rathbun, Julie A.

    Support Engineering· #12;I L NOVEMBER SYSTEM SAFETY PROGRESS REPORT' ALSEP ARRAY E l. 0 IDENTIFIED HA to Subpack No. 1 is through the use of four (4) boyd bolts. These boyd bolts deflect the sunshield to create defined to the MSC Safety Office. The effect of a boyd bolt shearing at a time when an astro- naut is over

  4. Environment/Health/Safety (EHS): Personal Protective Equipment...

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

    EHS Occupational Safety Safety Group Home Electrical Safety Ergonomics ISM Occupational Safety Group Organization Personal Protective Equipment (PPE) Injury Review & Analysis...

  5. Office of Health and Safety | Department of Energy

    Office of Environmental Management (EM)

    Health and Safety Office of Health and Safety Mission The Office of Health and Safety establishes worker safety and health requirements and expectations for the Department to...

  6. DOE HQ Occupational Safety and Health Program | Department of...

    Energy Savers [EERE]

    DOE HQ Occupational Safety and Health Program DOE HQ Occupational Safety and Health Program HQ Occupational Safety and Health Program Procedures PDF icon DOE HQ Occupational Safety...

  7. Development of a public health information infrastructure for postmarket evidence

    E-Print Network [OSTI]

    Maro, Judith C

    2009-01-01

    Postmarket data on prescription medical product performance has historically been incomplete, underutilized, and mismanaged to inform safety and comparative clinical effectiveness. Congress has tasked the Food and Drug ...

  8. Liquefied Gaseous Fuels Safety and Environmental Control Assessment Program: second status report

    SciTech Connect (OSTI)

    1980-10-01

    This document is arranged in three volumes and reports on progress in the Liquefied Gaseous Fuels (LGF) Safety and Environmental Control Assessment Program made in fiscal Year (FY)-1979 and early FY-1980. Volume 3 contains reports from 6 government contractors on LPG, anhydrous ammonia, and hydrogen energy systems. Report subjects include: simultaneous boiling and spreading of liquefied petroleum gas (LPG) on water; LPG safety research; state-of-the-art of release prevention and control technology in the LPG industry; ammonia: an introductory assessment of safety and environmental control information; ammonia as a fuel, and hydrogen safety and environmental control assessment.

  9. 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.

  10. Worker Health and Safety | Department of Energy

    Office of Environmental Management (EM)

    Worker Health and Safety Worker Health and Safety The U.S. Department of Energy's (DOE) worker health and safety requirements and expectations ensure protection of workers from the...

  11. Electronic Safety Resource Tools -- Supporting Hydrogen and Fuel Cell Commercialization

    SciTech Connect (OSTI)

    Barilo, Nick F.

    2014-09-29

    The Pacific Northwest National Laboratory (PNNL) Hydrogen Safety Program conducted a planning session in Los Angeles, CA on April 1, 2014 to consider what electronic safety tools would benefit the next phase of hydrogen and fuel cell commercialization. A diverse, 20-person team led by an experienced facilitator considered the question as it applied to the eight most relevant user groups. The results and subsequent evaluation activities revealed several possible resource tools that could greatly benefit users. The tool identified as having the greatest potential for impact is a hydrogen safety portal, which can be the central location for integrating and disseminating safety information (including most of the tools identified in this report). Such a tool can provide credible and reliable information from a trustworthy source. Other impactful tools identified include a codes and standards wizard to guide users through a series of questions relating to application and specific features of the requirements; a scenario-based virtual reality training for first responders; peer networking tools to bring users from focused groups together to discuss and collaborate on hydrogen safety issues; and a focused tool for training inspectors. Table ES.1 provides results of the planning session, including proposed new tools and changes to existing tools.

  12. Study of Cost Effective Large Advanced Pressurized Water Reactors that Employ Passive Safety Features

    SciTech Connect (OSTI)

    Winters, J. W.; Corletti, M. M.; Hayashi, Y.

    2003-11-12

    A report of DOE sponsored portions of AP1000 Design Certification effort. On December 16, 1999, The United States Nuclear Regulatory Commission issued Design Certification of the AP600 standard nuclear reactor design. This culminated an 8-year review of the AP600 design, safety analysis and probabilistic risk assessment. The AP600 is a 600 MWe reactor that utilizes passive safety features that, once actuated, depend only on natural forces such as gravity and natural circulation to perform all required safety functions. These passive safety systems result in increased plant safety and have also significantly simplified plant systems and equipment, resulting in simplified plant operation and maintenance. The AP600 meets NRC deterministic safety criteria and probabilistic risk criteria with large margins. A summary comparison of key passive safety system design features is provided in Table 1. These key features are discussed due to their importance in affecting the key thermal-hydraulic phenomenon exhibited by the passive safety systems in critical areas. The scope of some of the design changes to the AP600 is described. These changes are the ones that are important in evaluating the passive plant design features embodied in the certified AP600 standard plant design. These design changes are incorporated into the AP1000 standard plant design that Westinghouse is certifying under 10 CFR Part 52. In conclusion, this report describes the results of the representative design certification activities that were partially supported by the Nuclear Energy Research Initiative. These activities are unique to AP1000, but are representative of research activities that must be driven to conclusion to realize successful licensing of the next generation of nuclear power plants in the United States.

  13. Criticality Safety Basics for INL FMHs and CSOs

    SciTech Connect (OSTI)

    V. L. Putman

    2012-04-01

    Nuclear power is a valuable and efficient energy alternative in our energy-intensive society. However, material that can generate nuclear power has properties that require this material be handled with caution. If improperly handled, a criticality accident could result, which could severely harm workers. This document is a modular self-study guide about Criticality Safety Principles. This guide's purpose it to help you work safely in areas where fissionable nuclear materials may be present, avoiding the severe radiological and programmatic impacts of a criticality accident. It is designed to stress the fundamental physical concepts behind criticality controls and the importance of criticality safety when handling fissionable materials outside nuclear reactors. This study guide was developed for fissionable-material-handler and criticality-safety-officer candidates to use with related web-based course 00INL189, BEA Criticality Safety Principles, and to help prepare for the course exams. These individuals must understand basic information presented here. This guide may also be useful to other Idaho National Laboratory personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. This guide also includes additional information that will not be included in 00INL189 tests. The additional information is in appendices and paragraphs with headings that begin with 'Did you know,' or with, 'Been there Done that'. Fissionable-material-handler and criticality-safety-officer candidates may review additional information at their own discretion. This guide is revised as needed to reflect program changes, user requests, and better information. Issued in 2006, Revision 0 established the basic text and integrated various programs from former contractors. Revision 1 incorporates operation and program changes implemented since 2006. It also incorporates suggestions, clarifications, and additional information from readers and from personnel who took course 00INL189. Revision 1 also completely reorganized the training to better emphasize physical concepts behind the criticality controls that fissionable material handlers and criticality safety officers must understand. The reorganization is based on and consistent with changes made to course 00INL189 due to a review of course exam results and to discussions with personnel who conduct area-specific training.

  14. Approach for tank safety characterization of Hanford site waste

    SciTech Connect (OSTI)

    Meacham, J.E.; Babad, H.; Cash, R.J.; Dukelow, G.T.; Eberlein, S.J.; Hamilton, D.W.; Johnson, G.D.; Osborne, J.W.; Payne, M.A.; Sherwood, D.J. [and others

    1995-03-01

    The overall approach and associated technical basis for characterizing Hanford Site waste to help identify and resolve Waste Tank Safety Program safety issues has been summarized. The safety issues include flammable gas, noxious vapors, organic solvents, condensed-phase exothermic reactions (ferrocyanide and organic complexants), criticality, high heat, and safety screening. For the safety issues involving chemical reactions (i.e., flammable gas, organic solvents, ferrocyanide, and organic complexants), the approach to safety characterization is based on the fact that rapid exothermic reactions cannot occur if either fuel, oxidizer, or temperature (initiators) is not sufficient or controlled. The approach to characterization has been influenced by the progress made since mid-1993: (1) completion of safety analyses on ferrocyanide, criticality, organic solvent in tank 241-C-103, and sludge dryout. (2) successful mitigation of tank 241-SY-101; (3) demonstration of waste aging in laboratory experiments and from waste sampling, and (4) increased understanding of the information that can be obtained from headspace sampling. Headspace vapor sampling is being used to confirm that flammable gas does not accumulate in the single-shell tanks, and to determine whether organic solvents are present. The headspaces of tanks that may contain significant quantities of flammable gas will be monitored continuously using standard hydrogen monitors. For the noxious vapors safety issue, characterization will consist of headspace vapor sampling of most of the Hanford Site waste tanks. Sampling specifically for criticality is not required to confirm interim safe storage; however, analyses for fissile material will be conducted as waste samples are obtained for other reasons. High-heat tanks will be identified through temperature monitoring coupled with thermal analyses.

  15. Enhancing Railroad Hazardous Materials Transportation Safety...

    Office of Environmental Management (EM)

    Safety Rail Routing Enhancing Railroad Hazardous Materials Transportation Safety Rail Routing Presentation made by Kevin Blackwell for the NTSF annual meeting held from May 14-16,...

  16. 2015 Nuclear & Facility Safety Programs Workshop | Department...

    Office of Environmental Management (EM)

    featuring tracks for the Facility Representative (FR), Safety System Oversight (SSO), Fire Safety (FS) and Readiness communities. Distinguished speakers from inside and outside...

  17. Sandia Energy - Test Site Operations & Maintenance Safety

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

    Test Site Operations & Maintenance Safety Home Stationary Power Energy Conversion Efficiency Wind Energy SWiFT Facility & Testing Test Site Operations & Maintenance Safety Test...

  18. Technical Standards, Safety Analysis Toolbox Codes - November...

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

    report, Selection of Computer Codes for DOE Safety Analysis Applications, (August, 2002). Technical Standards, Safety Analysis Toolbox Codes More Documents & Publications DOE G...

  19. DOE/EFCOG Electrical Safety Workshops

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

    NREL 2014 EFCOGDOE Electrical Safety Workshop July 14 - 18, 2014 Hosted by the National Renewable Energy Laboratory (NREL), the 2014 EFCOGDOE Electrical Safety Workshop will be...

  20. Independent Activity Report, Defense Nuclear Facilities Safety...

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

    Defense Nuclear Facilities Safety Board Public Meeting - October 2012 Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting - October 2012 October...

  1. Office of Worker Safety and Health Policy

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  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)

    2012-03-01

    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. Thermal Reactor Safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  4. SAFETY MANUAL ENVIRONMENTAL

    E-Print Network [OSTI]

    Firestone, Jeremy

    of the Delaware Hazardous Chemical Information Act ................. 1 2.0 Purpose of the OSHA Laboratory Standard in this manual can be found on the Web under http://www.udel.edu/ExecVP/polprod #12;i Contents 1.0 Purpose ........................................................................ 5 6.0 Hazardous Chemicals (Definition

  5. APS Safety and Training | Beamline Safety Coordinators Meetings

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

    Safety Coordinators Meeting - Presentation.pptx Beamline General Task Worker Package 19290-0.pdf lms-proc-200 r3.pdf APS Procedure - Work Planning and Control at the APS.pdf...

  6. 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

  7. 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

    2013-05-01

    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.

  8. Worker Safety and Health and Nuclear Safety Quarterly Performance Analysis (January - March 2008)

    SciTech Connect (OSTI)

    Kerr, C E

    2009-10-07

    The DOE Office of Enforcement expects LLNL to 'implement comprehensive management and independent assessments that are effective in identifying deficiencies and broader problems in safety and security programs, as well as opportunities for continuous improvement within the organization' and to 'regularly perform assessments to evaluate implementation of the contractor's processes for screening and internal reporting.' LLNL has a self-assessment program, described in ES&H Manual Document 4.1, that includes line, management and independent assessments. LLNL also has in place a process to identify and report deficiencies of nuclear, worker safety and health and security requirements. In addition, the DOE Office of Enforcement expects LLNL to evaluate 'issues management databases to identify adverse trends, dominant problem areas, and potential repetitive events or conditions' (page 14, DOE Enforcement Process Overview, December 2007). LLNL requires that all worker safety and health and nuclear safety noncompliances be tracked as 'deficiencies' in the LLNL Issues Tracking System (ITS). Data from the ITS are analyzed for worker safety and health (WSH) and nuclear safety noncompliances that may meet the threshold for reporting to the DOE Noncompliance Tracking System (NTS). This report meets the expectations defined by the DOE Office of Enforcement to review the assessments conducted by LLNL, analyze the issues and noncompliances found in these assessments, and evaluate the data in the ITS database to identify adverse trends, dominant problem areas, and potential repetitive events or conditions. The report attempts to answer three questions: (1) Is LLNL evaluating its programs and state of compliance? (2) What is LLNL finding? (3) Is LLNL appropriately managing what it finds? The analysis in this report focuses on data from the first quarter of 2008 (January through March). This quarter is analyzed within the context of information identified in previous quarters to include April 2007 through March 2008. The results from analyzing the deficiencies are presented in accordance with the two primary NTS reporting thresholds for WSH and nuclear safety noncompliances: (1) those related to certain events or conditions and (2) those that are management issues. In addition, WSH noncompliances were also analyzed to determine if any fell under the 'other significant condition' threshold. This report also identifies noncompliance topical areas that may have issues that do not meet the NTS reporting threshold but should remain under observation. These are placed on the 'watch list' for continued analysis.

  9. Mapping the Potential for Biofuel Production on Marginal Lands: Differences in Definitions, Data and Models across Scales

    E-Print Network [OSTI]

    Lewis, Sarah M

    2014-01-01

    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

  10. Mapping the Potential for Biofuel Production on Marginal Lands: Differences in Definitions, Data and Models across Scales

    E-Print Network [OSTI]

    Lewis, Sarah M

    2014-01-01

    availability for biofuel production. Environ. Sci. Technol.of land available for biofuel production. Environ. Sci.the Potential for Biofuel Production on Marginal Lands:

  11. Criticality Safety Code Validation with LWBR’s SB Cores

    SciTech Connect (OSTI)

    Putman, Valerie Lee

    2003-01-01

    The first set of critical experiments from the Shippingport Light Water Breeder Reactor Program included eight, simple geometry critical cores built with 233UO2-ZrO2, 235UO2-ZrO2, ThO2, and ThO2-233UO2 nuclear materials. These cores are evaluated, described, and modeled to provide benchmarks and validation information for INEEL criticality safety calculation methodology. In addition to consistency with INEEL methodology, benchmark development and nuclear data are consistent with International Criticality Safety Benchmark Evaluation Project methodology.Section 1 of this report introduces the experiments and the reason they are useful for validating some INEEL criticality safety calculations. Section 2 provides detailed experiment descriptions based on currently available experiment reports. Section 3 identifies criticality safety validation requirement sources and summarizes requirements that most affect this report. Section 4 identifies relevant hand calculation and computer code calculation methodologies used in the experiment evaluation, benchmark development, and validation calculations. Section 5 provides a detailed experiment evaluation. This section identifies resolutions for currently unavailable and discrepant information. Section 5 also reports calculated experiment uncertainty effects. Section 6 describes the developed benchmarks. Section 6 includes calculated sensitivities to various benchmark features and parameters. Section 7 summarizes validation results. Appendices describe various assumptions and their bases, list experimenter calculations results for items that were independently calculated for this validation work, report other information gathered and developed by SCIENTEC personnel while evaluating these same experiments, and list benchmark sample input and miscellaneous supplementary data.

  12. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21

    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

  13. Drain Tank Information for Developing Design Basis of the Preliminary Design - R00

    SciTech Connect (OSTI)

    Ferrada, Juan J [ORNL

    2011-01-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of cooling accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)], Neutral Beam Injector (NBI) components, and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004 design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by U.S. ITER. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design-basis accident:1 a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassettes lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout anddimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  14. Drain Tank Information for Developing Design Basis of the Preliminary Design

    SciTech Connect (OSTI)

    Ferrada, Juan J

    2012-02-01

    Tokamak Cooling Water System (TCWS) drain tanks (DTs) serve two functions: normal operation and safety operation. Normal DTs are used for regular maintenance operations when draining is necessary. Safety DTs are used to receive the water leaked into the Vacuum Vessel (VV) after an in-vessel loss of coolant accident (LOCA) event. The preliminary design of the DTs shall be based on the information provided by this document. The capacity of the normal DTs is estimated based on the internal volume of in-vessel components [e.g., First Wall/Blanket (FW/BLK) and Divertor (DIV)]; Neutral Beam Injector (NBI) components; and TCWS piping, heat exchangers, electric heaters, pump casing, pressurizers, and valves. Water volumes have been updated based on 2004-design information, changes adopted because of approved Project Change Requests (PCRs), and data verification by US ITER and AREVA Federal Services, the US ITER A and E Company. Two tanks will store water from normal draining operations of the FW/BLK and DIV Primary Heat Transfer Systems (PHTSs). One tank will store water from normal draining operations of the NBI PHTS. The capacity of the safety DTs is based on analysis of a design basis accident: a large leak from in-vessel components. There are two safety DTs that will receive water from a VV LOCA event and drainage from the VV, as needed. In addition, there is one sump tank for the DIV that will be used for collecting drain water from the draining and drying processes and specifically for draining the DIV system as the DIV cassette lines are at a lower elevation than the DT connection point. Information documented in this report must be refined and verified during the preliminary design of the DTs, and there are several aspects to be considered to complete the preliminary design. Input to these design considerations is discussed in this report and includes, but is not limited to, water inventory; operating procedures/maintenance; Failure Modes and Effects Analysis (FMEA); tank layout and dimensions, including design margin; classification under French Nuclear Pressure Directives, Equipements Sous Pression Nucleaires (ESPN); and adaptations for construction.

  15. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    SciTech Connect (OSTI)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

  16. Skid-Steer Loader Safety 

    E-Print Network [OSTI]

    Smith, David

    2005-06-28

    Skid-steer loaders are very useful tools, but can be lethal if not used according to the manufacturer's instructions. You can reduce your risk of injury or death by following the proper safety precautions outlined in this publication....

  17. Alberta's Occupational Health and Safety

    E-Print Network [OSTI]

    Machel, Hans

    Alberta's Occupational Health and Safety Regulations An Explanation of the New First Aid Regulation of the First Aid Regulation Alberta's newest edition of the First Aid Regulation (AR 48/2000) came into effect

  18. Integrated Safety Management System Manual

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

    2006-11-01

    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.

  19. 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.

  20. Program desk manual for occupational safety and health -- U.S. Department of Energy Richland Operations, Office of Environment Safety and Health

    SciTech Connect (OSTI)

    Musen, L.G.

    1998-08-27

    The format of this manual is designed to make this valuable information easily accessible to the user as well as enjoyable to read. Each chapter contains common information such as Purpose, Scope, Policy and References, as well as information unique to the topic at hand. This manual can also be provided on a CD or Hanford Internet. Major topics include: Organization and program for operational safety; Occupational medicine; Construction and demolition; Material handling and storage; Hoisting and rigging; Explosives; Chemical hazards; Gas cylinders; Electrical; Boiler and pressure vessels; Industrial fire protection; Industrial hygiene; and Safety inspection checklist.