Sample records for life safety code

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

    E-Print Network [OSTI]

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

  2. Certification plan for safety and PRA codes

    SciTech Connect (OSTI)

    Toffer, H.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States)); Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States))

    1990-05-01T23:59:59.000Z

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan's objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations.

  3. Certification plan for safety and PRA codes

    SciTech Connect (OSTI)

    Toffer, H.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States); Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1990-05-01T23:59:59.000Z

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA&PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan`s objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations.

  4. Light-water reactor safety analysis codes

    SciTech Connect (OSTI)

    Jackson, J.F.; Ransom, V.H.; Ybarrondo, L.J.; Liles, D.R.

    1980-01-01T23:59:59.000Z

    A brief review of the evolution of light-water reactor safety analysis codes is presented. Included is a summary comparison of the technical capabilities of major system codes. Three recent codes are described in more detail to serve as examples of currently used techniques. Example comparisons between calculated results using these codes and experimental data are given. Finally, a brief evaluation of current code capability and future development trends is presented.

  5. Page 1 of 24 Environment Health & Safety, Building Code Enforcement Program

    E-Print Network [OSTI]

    Wu, Dapeng Oliver

    of the International Code Council, Incorporated. #12;Page 2 of 24 CHAPTER 1 ADMINISTRATION SECTION 101 GENERAL 101, stability, sanitation, adequate light and ventilation, energy conservation, and safety to life and propertyPage 1 of 24 Environment Health & Safety, Building Code Enforcement Program ADMINISTRATIVE CODE

  6. Code Gaps and Future Research Needs of Combustion Safety: Building...

    Energy Savers [EERE]

    Code Gaps and Future Research Needs of Combustion Safety: Building America Expert Meeting Update Code Gaps and Future Research Needs of Combustion Safety: Building America Expert...

  7. Safety, codes and standards for hydrogen installations :

    SciTech Connect (OSTI)

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

    2014-04-01T23:59:59.000Z

    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.

  8. FUEL CELL TECHNOLOGIES PROGRAM Safety, Codes, and

    E-Print Network [OSTI]

    . Many odorants can also contaminate fuel cells. Hydrogen burns very quickly. Under optimal combustionFUEL CELL TECHNOLOGIES PROGRAM Safety, Codes, and Standards Hydrogen and fuel cell technologies, nuclear, natural gas, and coal with carbon sequestration. Fuel cells provide a highly efficient means

  9. Safety, Codes, and Standards | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM615_CostNSARDevelopmental AssignmentAprilANDSafetySafety, Codes, and

  10. NHA HYDROGEN SAFETY CODES AND STANDARDS ACTIVITIES

    E-Print Network [OSTI]

    laboratories, code officials and model building code organizations to bring experts together in a focused and other information needed by the Code Officials to complete the development of these new codes needs to be disseminated to building code officials such as National Fire Protection Association (NFPA

  11. Interface design of VSOP'94 computer code for safety analysis

    SciTech Connect (OSTI)

    Natsir, Khairina, E-mail: yenny@batan.go.id; Andiwijayakusuma, D.; Wahanani, Nursinta Adi [Center for Development of Nuclear Informatics - National Nuclear Energy Agency, PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia); Yazid, Putranto Ilham [Center for Nuclear Technology, Material and Radiometry- National Nuclear Energy Agency, Jl. Tamansari No.71, Bandung 40132 (Indonesia)

    2014-09-30T23:59:59.000Z

    Today, most software applications, also in the nuclear field, come with a graphical user interface. VSOP'94 (Very Superior Old Program), was designed to simplify the process of performing reactor simulation. VSOP is a integrated code system to simulate the life history of a nuclear reactor that is devoted in education and research. One advantage of VSOP program is its ability to calculate the neutron spectrum estimation, fuel cycle, 2-D diffusion, resonance integral, estimation of reactors fuel costs, and integrated thermal hydraulics. VSOP also can be used to comparative studies and simulation of reactor safety. However, existing VSOP is a conventional program, which was developed using Fortran 65 and have several problems in using it, for example, it is only operated on Dec Alpha mainframe platforms and provide text-based output, difficult to use, especially in data preparation and interpretation of results. We develop a GUI-VSOP, which is an interface program to facilitate the preparation of data, run the VSOP code and read the results in a more user friendly way and useable on the Personal 'Computer (PC). Modifications include the development of interfaces on preprocessing, processing and postprocessing. GUI-based interface for preprocessing aims to provide a convenience way in preparing data. Processing interface is intended to provide convenience in configuring input files and libraries and do compiling VSOP code. Postprocessing interface designed to visualized the VSOP output in table and graphic forms. GUI-VSOP expected to be useful to simplify and speed up the process and analysis of safety aspects.

  12. Referred by UCSD Environment, Health & Safety Office Industrial Hygiene, Mail Code 0958

    E-Print Network [OSTI]

    Russell, Lynn

    Referred by UCSD Environment, Health & Safety Office Industrial Hygiene, Mail Code 0958 I:\\Industrial_Hygiene

  13. FPS 12.1 Life Safety, 5/24/2000

    Broader source: Energy.gov [DOE]

    The objective of this surveillance is for the Facility Representative to verify that conditions in the plant provide an appropriate level of life safety for workers conducting operations in the...

  14. Foundational development of an advanced nuclear reactor integrated safety code.

    SciTech Connect (OSTI)

    Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01T23:59:59.000Z

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

  15. AGR-1 Safety Test Predictions using the PARFUME code

    SciTech Connect (OSTI)

    Blaise Collin

    2012-05-01T23:59:59.000Z

    The PARFUME modeling code was used to predict failure probability of TRISO-coated fuel particles and diffusion of fission products through these particles during safety tests following the first irradiation test of the Advanced Gas Reactor program (AGR-1). These calculations support the AGR-1 Safety Testing Experiment, which is part of the PIE effort on AGR-1. Modeling of the AGR-1 Safety Test Predictions includes a 620-day irradiation followed by a 300-hour heat-up phase of selected AGR-1 compacts. Results include fuel failure probability, palladium penetration, and fractional release of fission products. Results show that no particle failure is predicted during irradiation or heat-up, and that fractional release of fission products is limited during irradiation but that it significantly increases during heat-up.

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

    SciTech Connect (OSTI)

    Putman, Valerie Lee

    2003-01-01T23:59:59.000Z

    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.

  17. AGR-2 Safety Test Predictions Using the PARFUME Code

    SciTech Connect (OSTI)

    Blaise Collin

    2014-09-01T23:59:59.000Z

    This report documents calculations performed to predict failure probability of TRISO-coated fuel particles and diffusion of fission products through these particles during safety tests following the second irradiation test of the Advanced Gas Reactor program (AGR-2). The calculations include the modeling of the AGR-2 irradiation that occurred from June 2010 to October 2013 in the Advanced Test Reactor (ATR) and the modeling of a safety testing phase to support safety tests planned at Oak Ridge National Laboratory and at Idaho National Laboratory (INL) for a selection of AGR-2 compacts. The heat-up of AGR-2 compacts is a critical component of the AGR-2 fuel performance evaluation, and its objectives are to identify the effect of accident test temperature, burnup, and irradiation temperature on the performance of the fuel at elevated temperature. Safety testing of compacts will be followed by detailed examinations of the fuel particles to further evaluate fission product retention and behavior of the kernel and coatings. The modeling was performed using the particle fuel model computer code PARFUME developed at INL. PARFUME is an advanced gas-cooled reactor fuel performance modeling and analysis code (Miller 2009). It has been developed as an integrated mechanistic code that evaluates the thermal, mechanical, and physico-chemical behavior of fuel particles during irradiation to determine the failure probability of a population of fuel particles given the particle-to-particle statistical variations in physical dimensions and material properties that arise from the fuel fabrication process, accounting for all viable mechanisms that can lead to particle failure. The code also determines the diffusion of fission products from the fuel through the particle coating layers, and through the fuel matrix to the coolant boundary. The subsequent release of fission products is calculated at the compact level (release of fission products from the compact). PARFUME calculates the release fraction as the ratio of the number of atoms released from the compact to the amount produced in the compact fuel kernels and through uranium contamination. These safety test predictions aim at giving guidance for the upcoming safety tests to be conducted at ORNL and INL. The AGR-2 compacts modeled in this study belong to the four U.S. capsules of the AGR-2 irradiation test train. For each capsule, the compacts with the lowest and highest burnups were selected to provide a prediction envelope. The objective of this document is to present results of calculations and analyses made by PARFUME on these selected AGR-2 compacts. These results include: • Fuel failure probability • Palladium penetration • Fractional release of fission products Details associated with completion of these calculations are provided in the remainder of this document: the AGR-2 Safety Testing plan is briefly introduced in Section 2, PARFUME modeling is outlined in Section 3, results are described in Section 4, conclusions are given in Section 5, and references are listed in Section 6.

  18. Proving the Absence of RunTime Errors in SafetyCritical Avionics Code

    E-Print Network [OSTI]

    Cousot, Patrick

    , time­triggered, real­time, safety critical, embedded software as found in earth transportation, nuclearProving the Absence of Run­Time Errors in Safety­Critical Avionics Code Patrick Cousot École is not acceptable in safety and mission crit­ ical applications. An avenue is therefore opened for formal methods

  19. FY 2009 Merit Review and Peer Evaluation Report EDUCATION; SAFETY, CODES AND STANDARDS; AND TECHNOLOGY VALIDATION

    E-Print Network [OSTI]

    supported ongoing efforts to educate first responders and code officials, local communities, and teachers focus on near- term fuel cell applications such as forklifts. Code Officials: Reviewers felt601 FY 2009 Merit Review and Peer Evaluation Report EDUCATION; SAFETY, CODES AND STANDARDS

  20. TRAC Code Modifications Made for APT Blanket Safety Analyses

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07T23:59:59.000Z

    This report provides documentation of the necessary source code modifications made to the TRAC-PF1/MOD2 code version 5.4.28a developed at Los Alamos National Laboratory.

  1. Comparison between VNIIEF computer programs used to study NPP safety and similar western codes

    SciTech Connect (OSTI)

    Pevnitsky, A.V.; Tarasov, V.A.; Solovyev, V.P. [and others

    1995-12-31T23:59:59.000Z

    This report gives schematic comparison between VNIIEF computer programs used to study NPP safety and similar western codes. This comparison is schematic and in no way pretends to be complete.

  2. Certification process of safety analysis and risk management computer codes at the Savannah River Site

    SciTech Connect (OSTI)

    Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Toffer, H.; Lewis, C.J.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

    1992-05-01T23:59:59.000Z

    The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

  3. Certification process of safety analysis and risk management computer codes at the Savannah River Site

    SciTech Connect (OSTI)

    Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Toffer, H.; Lewis, C.J.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States))

    1992-01-01T23:59:59.000Z

    The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

  4. RBMK thermohydraulic safety assessments using RELAP5/MOD3 codes

    SciTech Connect (OSTI)

    Tsiklauri, G.V.; Schmitt, B.E.

    1995-06-01T23:59:59.000Z

    The capability of the RELAP5/MOD3 code to validate various transients encountered in RBMK reactor postulated accidents has been assessed. The assessment results include a loss of coolant accident at the inlet of the core pressure tube, the blockage of a pressure tube, and the pressure response of the core cavity to in core pressure tube ruptures. These assessments show that the RELAP5/MOD3 code can predict major phenomena during postulated accidents in the RBMK reactors.

  5. SCALE 6: Comprehensive Nuclear Safety Analysis Code System

    SciTech Connect (OSTI)

    Bowman, Stephen M [ORNL

    2011-01-01T23:59:59.000Z

    Version 6 of the Standardized Computer Analyses for Licensing Evaluation (SCALE) computer software system developed at Oak Ridge National Laboratory, released in February 2009, contains significant new capabilities and data for nuclear safety analysis and marks an important update for this software package, which is used worldwide. This paper highlights the capabilities of the SCALE system, including continuous-energy flux calculations for processing multigroup problem-dependent cross sections, ENDF/B-VII continuous-energy and multigroup nuclear cross-section data, continuous-energy Monte Carlo criticality safety calculations, Monte Carlo radiation shielding analyses with automated three-dimensional variance reduction techniques, one- and three-dimensional sensitivity and uncertainty analyses for criticality safety evaluations, two- and three-dimensional lattice physics depletion analyses, fast and accurate source terms and decay heat calculations, automated burnup credit analyses with loading curve search, and integrated three-dimensional criticality accident alarm system analyses using coupled Monte Carlo criticality and shielding calculations.

  6. DOE Safety, Codes, and Standards Activities | 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 onYouTube YouTube Note: Since the YouTube| Department of Energy81stEnforcementEnergyEACDepartment ofDOE Safety,

  7. Safety, Codes and Standards - Basics | 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 onYouTube YouTube Note: Since the.pdfBreakingMay 2015 <Department of iiBiodieselWATER,Program ManagementProcessSafety,

  8. DOE Safety, Codes, and Standards Activities | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T,Office of Policy, OAPM |TRUJuly 29, 2013 Agency/ Sub- agency RIN/SESSafety, Codes

  9. Hydrogen Pipeline Safety Our goal is to establish the codes and standards necessary

    E-Print Network [OSTI]

    Perkins, Richard A.

    Hydrogen Pipeline Safety METALS Our goal is to establish the codes and standards necessary miles of hydrogen pipelines are currently in operation in the U.S. (compared to > 1M miles of natural, materials, mechanical properties, and standards for hydrogen pipelines. Construction is complete on the 750

  10. Title: Environmental Health and Safety --Chemical Hygiene Plan Code: 1-310-100

    E-Print Network [OSTI]

    Huang, Jianyu

    Title: Environmental Health and Safety -- Chemical Hygiene Plan Code: 1-310-100 Date: 7: · Occupational exposure monitoring · Preparation of a Chemical Hygiene Plan · Employee information and training keeping The new laboratory standard requires each employer to appoint a Chemical Hygiene Officer

  11. Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.

    SciTech Connect (OSTI)

    Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d'%C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

    2011-06-01T23:59:59.000Z

    This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the experienced user-base and the experimental validation base was decaying away quickly.

  12. SECTION GS1020 CONSTRUCTION CODE REQUIREMENTS

    E-Print Network [OSTI]

    Zhang, Yuanlin

    101, Life Safety Code; 5. National Fire Protection Association Codes and Standards; 6. ANSI/ASME A17SECTION GS1020 ­ CONSTRUCTION CODE REQUIREMENTS PART 1 - GENERAL 1.1 RELATED DOCUMENTS A. Drawings includes the following: 1. Construction code requirements for all construction at Texas Tech University. 1

  13. Uncertainty quantification in safety codes using a Bayesian approach with data from separate and integral effect tests

    E-Print Network [OSTI]

    Yurko, Joseph Paul

    2014-01-01T23:59:59.000Z

    Uncertainty quantification in thermal-hydraulic safety codes is a very challenging and computationally expensive endeavor. Methods are therefore needed to reduce that computational burden, while still providing a reasonable ...

  14. Computer code for space-time diagnostics of nuclear safety parameters

    SciTech Connect (OSTI)

    Solovyev, D. A.; Semenov, A. A.; Gruzdov, F. V.; Druzhaev, A. A.; Shchukin, N. V.; Dolgenko, S. G.; Solovyeva, I. V.; Ovchinnikova, E. A. [National Research Nuclear Univ. MEPhI, Kashirskoe, 31, 115409, Moscow (Russian Federation)

    2012-07-01T23:59:59.000Z

    The computer code ECRAN 3D (Experimental and Calculation Reactor Analysis) is designed for continuous monitoring and diagnostics of reactor cores and databases for RBMK-1000 on the basis of analytical methods for the interrelation parameters of nuclear safety. The code algorithms are based on the analysis of deviations between the physically obtained figures and the results of neutron-physical and thermal-hydraulic calculations. Discrepancies between the measured and calculated signals are equivalent to obtaining inadequacy between performance of the physical device and its simulator. The diagnostics system can solve the following problems: identification of facts and time for inconsistent results, localization of failures, identification and quantification of the causes for inconsistencies. These problems can be effectively solved only when the computer code is working in a real-time mode. This leads to increasing requirements for a higher code performance. As false operations can lead to significant economic losses, the diagnostics system must be based on the certified software tools. POLARIS, version 4.2.1 is used for the neutron-physical calculation in the computer code ECRAN 3D. (authors)

  15. Sensitivity of risk parameters to component unavailability in reactor safety study (PSAP/PSAB computer codes). [PWR; BWR

    SciTech Connect (OSTI)

    Azarm, M.; Farahzad, P.; Tingle, A.

    1982-06-01T23:59:59.000Z

    The Probabilistic Sensitivity Analysis for Pressurized and Boiling Water Reactors (PSAP/PSAB) codes have been developed to update the WASH-1400 conclusions. The initial effort, reported in NUREG/CR-1879 Sensitivity of Risk Parameters to Human Errors in Reactor Safety Study for a PWR, concentrated on developing a code for system sensitivity to human errors based on an expanded version of the PWR fault trees from the Reactor Safety Study (RSS). The success of that effort and the insights gained from the code's use initiated the development of the PSAP/PSAB codes. The two codes allow the user to evaluate the impact of new data and system models on the conclusions drawn in WASH-1400. They are designed to be fast running and modular so that detailed sensitivity studies can be run efficiently.

  16. Hot water decontamination of beef carcasses to increase microbiological safety and shelf-life

    E-Print Network [OSTI]

    Barakate, Michelle Lee

    1991-01-01T23:59:59.000Z

    : -:r . ~ &:: ? ri:~ 4 c:r l, &, ?a??. . ' ' !"-' &! ~i i 4?'&. " ~ li r, '?Pil ril i '. ' rl iit'~'. ~a', '. ''+, I";= t I t h( ii il HOT WATER DECONTAMINATION OF BEEF CARCASSES TO INCREASE MICROBIOLOGICAL SAFETY AND SHELF-LIFE A Thesis... by MICHELLE LEE BARKATE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1991 Major Subject: Food Science and Technology HOT WATER DECONTAMINATION...

  17. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).

    SciTech Connect (OSTI)

    Schultz, Peter Andrew

    2011-12-01T23:59:59.000Z

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

  18. Overview of Development and Deployment of Codes, Standards and Regulations Affecting Energy Storage System Safety in the United States

    SciTech Connect (OSTI)

    Conover, David R.

    2014-08-22T23:59:59.000Z

    This report acquaints stakeholders and interested parties involved in the development and/or deployment of energy storage systems (ESS) with the subject of safety-related codes, standards and regulations (CSRs). It is hoped that users of this document gain a more in depth and uniform understanding of safety-related CSR development and deployment that can foster improved communications among all ESS stakeholders and the collaboration needed to realize more timely acceptance and approval of safe ESS technology through appropriate CSR.

  19. Inventory of Safety-related Codes and Standards for Energy Storage Systems with some Experiences related to Approval and Acceptance

    SciTech Connect (OSTI)

    Conover, David R.

    2014-09-11T23:59:59.000Z

    The purpose of this document is to identify laws, rules, model codes, codes, standards, regulations, specifications (CSR) related to safety that could apply to stationary energy storage systems (ESS) and experiences to date securing approval of ESS in relation to CSR. This information is intended to assist in securing approval of ESS under current CSR and to identification of new CRS or revisions to existing CRS and necessary supporting research and documentation that can foster the deployment of safe ESS.

  20. A generalized fitting technique for the LIFE2 fatigue analysis code

    SciTech Connect (OSTI)

    Sutherland, H.J. [Sandia National Labs., Albuquerque, NM (United States). Wind Energy Research Dept.; Wilson, T. [Univ. of New Mexico, Albuquerque, NM (United States). New Mexico Engineering Research Inst.

    1996-08-01T23:59:59.000Z

    The analysis of component fatigue lifetime for a wind energy conversion system (WECS) requires that the component load spectrum be formulated in terms of stress cycles. Typically, these stress cycles are obtained from time series data using a cycle identification scheme. As discussed by many authors, the matrix or matrices of cycle counts that describe the stresses on a turbine are constructed from relatively short, representative samples of time series data. The ability to correctly represent the long-term behavior of the distribution of stress cycles from these representative samples is critical to the analysis of service lifetimes. Several techniques are currently used to convert representative samples to the lifetime cyclic loads on the turbine. There has been recently developed a set of fitting algorithms that is particularly useful for matching the body of the distribution of fatigue stress cycles on a turbine component. Fitting techniques are now incorporated into the LIFE2 fatigue/fracture analysis code for wind turbines. In this paper, the authors provide an overview of the fitting algorithms and describe the pre- and post-count algorithms developed to permit their use in the LIFE2 code. Typical case studies are used to illustrate the use of the technique.

  1. Department of Environmental Health & Safety Emergency Management

    E-Print Network [OSTI]

    O'Toole, Alice J.

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

  2. Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC) : gap analysis for high fidelity and performance assessment code development.

    SciTech Connect (OSTI)

    Lee, Joon H.; Siegel, Malcolm Dean; Arguello, Jose Guadalupe, Jr.; Webb, Stephen Walter; Dewers, Thomas A.; Mariner, Paul E.; Edwards, Harold Carter; Fuller, Timothy J.; Freeze, Geoffrey A.; Jove-Colon, Carlos F.; Wang, Yifeng

    2011-03-01T23:59:59.000Z

    This report describes a gap analysis performed in the process of developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with rigorous verification, validation, and software quality requirements. The gap analyses documented in this report were are performed during an initial gap analysis to identify candidate codes and tools to support the development and integration of the Waste IPSC, and during follow-on activities that delved into more detailed assessments of the various codes that were acquired, studied, and tested. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. The gap analysis indicates that significant capabilities may already exist in the existing THC codes although there is no single code able to fully account for all physical and chemical processes involved in a waste disposal system. Large gaps exist in modeling chemical processes and their couplings with other processes. The coupling of chemical processes with flow transport and mechanical deformation remains challenging. The data for extreme environments (e.g., for elevated temperature and high ionic strength media) that are needed for repository modeling are severely lacking. In addition, most of existing reactive transport codes were developed for non-radioactive contaminants, and they need to be adapted to account for radionuclide decay and in-growth. The accessibility to the source codes is generally limited. Because the problems of interest for the Waste IPSC are likely to result in relatively large computational models, a compact memory-usage footprint and a fast/robust solution procedure will be needed. A robust massively parallel processing (MPP) capability will also be required to provide reasonable turnaround times on the analyses that will be performed with the code. A performance assessment (PA) calculation for a waste disposal system generally requires a large number (hundreds to thousands) of model simulations to quantify the effect of model parameter uncertainties on the predicted repository performance. A set of codes for a PA calculation must be sufficiently robust and fast in terms of code execution. A PA system as a whole must be able to provide multiple alternative models for a specific set of physical/chemical processes, so that the users can choose various levels of modeling complexity based on their modeling needs. This requires PA codes, preferably, to be highly modularized. Most of the existing codes have difficulties meeting these requirements. Based on the gap analysis results, we have made the following recommendations for the code selection and code development for the NEAMS waste IPSC: (1) build fully coupled high-fidelity THCMBR codes using the existing SIERRA codes (e.g., ARIA and ADAGIO) and platform, (2) use DAKOTA to build an enhanced performance assessment system (EPAS), and build a modular code architecture and key code modules for performance assessments. The key chemical calculation modules will be built by expanding the existing CANTERA capabilities as well as by extracting useful components from other existing codes.

  3. Theory and Implementation of Nuclear Safety System Codes - Part II: System Code Closure Relations, Validation, and Limitations

    SciTech Connect (OSTI)

    Glenn A Roth; Fatih Aydogan

    2014-09-01T23:59:59.000Z

    This is Part II of two articles describing the details of thermal-hydraulic sys- tem codes. In this second part of the article series, the system code closure relationships (used to model thermal and mechanical non-equilibrium and the coupling of the phases) for the governing equations are discussed and evaluated. These include several thermal and hydraulic models, such as heat transfer coefficients for various flow regimes, two phase pressure correlations, two phase friction correlations, drag coefficients and interfacial models be- tween the fields. These models are often developed from experimental data. The experiment conditions should be understood to evaluate the efficacy of the closure models. Code verification and validation, including Separate Effects Tests (SETs) and Integral effects tests (IETs) is also assessed. It can be shown from the assessments that the test cases cover a significant section of the system code capabilities, but some of the more advanced reactor designs will push the limits of validation for the codes. Lastly, the limitations of the codes are discussed by considering next generation power plants, such as Small Modular Reactors (SMRs), analyz- ing not only existing nuclear power plants, but also next generation nuclear power plants. The nuclear industry is developing new, innovative reactor designs, such as Small Modular Reactors (SMRs), High-Temperature Gas-cooled Reactors (HTGRs) and others. Sub-types of these reactor designs utilize pebbles, prismatic graphite moderators, helical steam generators, in- novative fuel types, and many other design features that may not be fully analyzed by current system codes. This second part completes the series on the comparison and evaluation of the selected reactor system codes by discussing the closure relations, val- idation and limitations. These two articles indicate areas where the models can be improved to adequately address issues with new reactor design and development.

  4. Radiation Safety Training Guide for Use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection

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

    1999-03-17T23:59:59.000Z

    This Guide provides an acceptable methodology for establishing and operating a radiation safety training program that will comply with U.S. Department of Energy (DOE) requirements specified in Title 10 of the Code of Federal Regulations (CFR), Part 835, Occupational Radiation Protection (DOE 1998a), hereinafter referred to as 10 CFR 835. In particular, this Guide provides guidance for achieving compliance with subpart J of 10 CFR 835. Canceled by DOE G 441.1-1B.

  5. Inventory of Safety-Related Codes and Standards for Energy Storage...

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

    which those approvals were conducted, the CSR criteria applied, the scientific and engineering basis supporting the validation of the system's safety and the documentation...

  6. Coupled neutronic and thermal-hydraulic code benchmark activities at the International Nuclear Safety Center.

    SciTech Connect (OSTI)

    Podlazov, L. N.

    1998-07-29T23:59:59.000Z

    Two realistic benchmark problems are defined and used to assess the performance of coupled thermal-hydraulic and neutronic codes used in simulating dynamic processes in VVER-1000 and RBMK reactor systems. One of the problems simulates a design basis accident involving the ejection of three control and protection system rods from a VVER-1000 reactor. The other is based on a postulated rod withdrawal from an operating RBMK reactor. Preliminary results calculated by various codes are compared. While these results show significant differences, the intercomparisons performed so far provide a basis for further evaluation of code limitations and modeling assumptions.

  7. Objective 1: Extend Life, Improve Performance, and Maintain Safety of the Current Fleet Implementation Plan

    SciTech Connect (OSTI)

    Robert Youngblood

    2011-01-01T23:59:59.000Z

    Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60 year operating licenses. Figure E 1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development (R&D) Roadmap has organized its activities in accordance with four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document describes how Objective 1 and the LWRS Program will be implemented. The existing U.S. nuclear fleet has a remarkable safety and performance record and today accounts for 70% of the low greenhouse gas emitting domestic electricity production. Extending the operating lifetimes of current plants beyond 60 years and, where possible, making further improvements in their productivity will generate early benefits from research, development, and demonstration investments in nuclear power. DOE’s role in Objective 1 is to partner with industry and the Nuclear Regulatory Commission in appropriate ways to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, plant license extensions, and age-related regulatory oversight decisions. The DOE research, development, and demonstration role will focus on aging phenomena and issues that require long-term research and are generic to reactor type. Cost-shared demonstration activities will be conducted when appropriate.

  8. Objective 1: Extend Life, Improve Performance, and Maintain Safety of the Current Fleet Implementation Plan

    SciTech Connect (OSTI)

    Robert Youngblood

    2011-02-01T23:59:59.000Z

    Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60 year operating licenses. Figure E 1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development (R&D) Roadmap has organized its activities in accordance with four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document describes how Objective 1 and the LWRS Program will be implemented. The existing U.S. nuclear fleet has a remarkable safety and performance record and today accounts for 70% of the low greenhouse gas emitting domestic electricity production. Extending the operating lifetimes of current plants beyond 60 years and, where possible, making further improvements in their productivity will generate early benefits from research, development, and demonstration investments in nuclear power. DOE’s role in Objective 1 is to partner with industry and the Nuclear Regulatory Commission in appropriate ways to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, plant license extensions, and age-related regulatory oversight decisions. The DOE research, development, and demonstration role will focus on aging phenomena and issues that require long-term research and are generic to reactor type. Cost-shared demonstration activities will be conducted when appropriate.

  9. Roadmap to an Engineering-Scale Nuclear Fuel Performance & Safety Code

    SciTech Connect (OSTI)

    Turner, John A [ORNL; Clarno, Kevin T [ORNL; Hansen, Glen A [ORNL

    2009-09-01T23:59:59.000Z

    Developing new fuels and qualifying them for large-scale deployment in power reactors is a lengthy and expensive process, typically spanning a period of two decades from concept to licensing. Nuclear fuel designers serve an indispensable role in the process, at the initial exploratory phase as well as in analysis of the testing results. In recent years fuel performance capabilities based on first principles have been playing more of a role in what has traditionally been an empirically dominated process. Nonetheless, nuclear fuel behavior is based on the interaction of multiple complex phenomena, and recent evolutionary approaches are being applied more on a phenomenon-by-phenomenon basis, targeting localized problems, as opposed to a systematic approach based on a fundamental understanding of all interacting parameters. Advanced nuclear fuels are generally more complex, and less understood, than the traditional fuels used in existing reactors (ceramic UO{sub 2} with burnable poisons and other minor additives). The added challenges are primarily caused by a less complete empirical database and, in the case of recycled fuel, the inherent variability in fuel compositions. It is clear that using the traditional approach to develop and qualify fuels over the entire range of variables pertinent to the U.S. Department of Energy (DOE) Office of Nuclear Energy on a timely basis with available funds would be very challenging, if not impossible. As a result the DOE Office of Nuclear Energy has launched the Nuclear Energy Advanced Modeling and Simulation (NEAMS) approach to revolutionize fuel development. This new approach is predicated upon transferring the recent advances in computational sciences and computer technologies into the fuel development program. The effort will couple computational science with recent advances in the fundamental understanding of physical phenomena through ab initio modeling and targeted phenomenological testing to leapfrog many fuel-development activities. Realizing the full benefits of this approach will likely take some time. However, it is important that the developmental activities for modeling and simulation be tightly coupled with the experimental activities to maximize feedback effects and accelerate both the experimental and analytical elements of the program toward a common objective. The close integration of modeling and simulation and experimental activities is key to developing a useful fuel performance simulation capability, providing a validated design and analysis tool, and understanding the uncertainties within the models and design process. The efforts of this project are integrally connected to the Transmutation Fuels Campaign (TFC), which maintains as a primary objective to formulate, fabricate, and qualify a transuranic-based fuel with added minor actinides for use in future fast reactors. Additional details of the TFC scope can be found in the Transmutation Fuels Campaign Execution Plan. This project is an integral component of the TFC modeling and simulation effort, and this multiyear plan borrowed liberally from the Transmutation Fuels Campaign Modeling and Simulation Roadmap. This document provides the multiyear staged development plan to develop a continuum-level Integrated Performance and Safety Code (IPSC) to predict the behavior of the fuel and cladding during normal reactor operations and anticipated transients up to the point of clad breach.

  10. Nuclear Energy Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (IPSC) : FY10 development and integration.

    SciTech Connect (OSTI)

    Criscenti, Louise Jacqueline; Sassani, David Carl; Arguello, Jose Guadalupe, Jr.; Dewers, Thomas A.; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Wang, Yifeng; Schultz, Peter Andrew

    2011-02-01T23:59:59.000Z

    This report describes the progress in fiscal year 2010 in developing the Waste Integrated Performance and Safety Codes (IPSC) in support of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The goal of the Waste IPSC is to develop an integrated suite of computational modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. Waste IPSC activities in fiscal year 2010 focused on specifying a challenge problem to demonstrate proof of concept, developing a verification and validation plan, and performing an initial gap analyses to identify candidate codes and tools to support the development and integration of the Waste IPSC. The current Waste IPSC strategy is to acquire and integrate the necessary Waste IPSC capabilities wherever feasible, and develop only those capabilities that cannot be acquired or suitably integrated, verified, or validated. This year-end progress report documents the FY10 status of acquisition, development, and integration of thermal-hydrologic-chemical-mechanical (THCM) code capabilities, frameworks, and enabling tools and infrastructure.

  11. East Carolina University ENVIRONMENTAL SAFETY COMMITTEE

    E-Print Network [OSTI]

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

  12. RDS - A systematic approach towards system thermal hydraulics input code development for a comprehensive deterministic safety analysis

    SciTech Connect (OSTI)

    Salim, Mohd Faiz, E-mail: mohdfaizs@tnb.com.my [Nuclear Energy Department, Tenaga Nasional Berhad, Level 32, Dua Sentral, 50470 Kuala Lumpur (Malaysia); Roslan, Ridha [Nuclear Installation Division, Atomic Energy Licensing Board, Batu 24, Jalan Dengkil, 43800 Dengkil, Selangor (Malaysia); Ibrahim, Mohd Rizal Mamat [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)

    2014-02-12T23:59:59.000Z

    Deterministic Safety Analysis (DSA) is one of the mandatory requirements conducted for Nuclear Power Plant licensing process, with the aim of ensuring safety compliance with relevant regulatory acceptance criteria. DSA is a technique whereby a set of conservative deterministic rules and requirements are applied for the design and operation of facilities or activities. Computer codes are normally used to assist in performing all required analysis under DSA. To ensure a comprehensive analysis, the conduct of DSA should follow a systematic approach. One of the methodologies proposed is the Standardized and Consolidated Reference Experimental (and Calculated) Database (SCRED) developed by University of Pisa. Based on this methodology, the use of Reference Data Set (RDS) as a pre-requisite reference document for developing input nodalization was proposed. This paper shall describe the application of RDS with the purpose of assessing its effectiveness. Two RDS documents were developed for an Integral Test Facility of LOBI-MOD2 and associated Test A1-83. Data and information from various reports and drawings were referred in preparing the RDS. The results showed that by developing RDS, it has made possible to consolidate all relevant information in one single document. This is beneficial as it enables preservation of information, promotes quality assurance, allows traceability, facilitates continuous improvement, promotes solving of contradictions and finally assisting in developing thermal hydraulic input regardless of whichever code selected. However, some disadvantages were also recognized such as the need for experience in making engineering judgments, language barrier in accessing foreign information and limitation of resources. Some possible improvements are suggested to overcome these challenges.

  13. Approved Module Information for CE1007, 2014/5 Module Title/Name: Health, Safety & the Environment Module Code: CE1007

    E-Print Network [OSTI]

    Neirotti, Juan Pablo

    Module Code: CE1007 School: Engineering and Applied Science Module Type: Standard Module New ModuleApproved Module Information for CE1007, 2014/5 Module Title/Name: Health, Safety & the Environment? No Module Credits: 10 Module Management Information Module Leader Name George Drahun Email Address j

  14. National electrical code changes for 1996 and USA participation in International Energy Agency activities related to photovoltaics safety and grid interconnection

    SciTech Connect (OSTI)

    Bower, W.

    1995-01-01T23:59:59.000Z

    As photovoltaic (PV) systems gain more acceptance in utility-interactive applications throughout the world, many organizations are placing increasingly higher priorities on writing guidelines, codes and standards. These guidelines and codes are being written to improve safety, installation, acceptance, listing or certification of the PV components or systems. Sandia National Laboratories` PV System Applications Department is working closely with the PV industry to address issues that are associated with fire and personnel safety and with National Electrical Code (NEC) requirements. Additionally, the United States has agreed to participate in two of the International Energy Agency (IEA) Annexes (topical tasks) of the Implementing Agreement for a Cooperative Programme on Photovoltaic Power Systems. This paper describes events and activities associated with the NEC and the IEA that are being led by Sandia National Laboratories with broad participation by the US PV industry.

  15. Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).

    SciTech Connect (OSTI)

    Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

    2010-09-01T23:59:59.000Z

    This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

  16. Industrial Safety | The Ames Laboratory

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

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

  17. Fact Sheet: Codes and Standards for Energy Storage System Performance...

    Energy Savers [EERE]

    Codes and Standards for Energy Storage System Performance and Safety (June 2014) Fact Sheet: Codes and Standards for Energy Storage System Performance and Safety (June 2014) The...

  18. Brain surgery breathes new life into aging plants

    SciTech Connect (OSTI)

    Makansi, J. [Pearl Street Inc. (United States)

    2006-04-15T23:59:59.000Z

    Unlike managing the human aging process, extending the life of a power plant often includes brain surgery, modernizing its control and automation system. Lately, such retrofits range from wholesale replacing of existing controls to the addition of specific control elements that help optimize performance. Pending revisions to safety codes and cybersecurity issues also need to be considered. 4 figs.

  19. DOE Vehicle Technologies Program 2009 Merit Review Report - Safety...

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

    Safety Codes and Standards DOE Vehicle Technologies Program 2009 Merit Review Report - Safety Codes and Standards Merit review of DOE Vehicle Technologies Program research efforts...

  20. aeroelastic code hawc: Topics by E-print Network

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

    placing the stability boundary. Safety and sustainability Gao, Grace Xingxin 50 Spinal codes MIT - DSpace Summary: Spinal codes are a new class of rateless codes that enable...

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

    SciTech Connect (OSTI)

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

    2008-07-15T23:59:59.000Z

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

  2. Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.

    SciTech Connect (OSTI)

    Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

    2011-01-01T23:59:59.000Z

    The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

  3. Safety Training for the Hydrogen Economy

    SciTech Connect (OSTI)

    Fassbender, Linda L.; Kinzey, Bruce R.; Akers, Bret M.

    2006-04-11T23:59:59.000Z

    PNNL and the Volpentest Hazardous Materials Management and Emergency Response (HAMMER) Training and Education Center are helping to prepare emergency responders and permitting/code enforcement officials for their respective roles in the future Hydrogen Economy. Safety will be a critical component of the anticipated hydrogen transition. Public confidence goes hand in hand with perceived safety to such an extent that, without it, the envisioned transition is unlikely to occur. Stakeholders and the public must be reassured that hydrogen, although very different from gasoline and other conventional fuels, is no more dangerous. Ensuring safety in the hydrogen infrastructure will require a suitably trained emergency response force for containing the inevitable incidents as they occur, coupled with knowledgeable code officials to ensure that such incidents are kept to a minimum. PNNL and HAMMER are, therefore, designing a hydrogen safety training program, funded by DOE's Hydrogen, Fuel Cells, and Infrastructure Technologies Program, and modeled after the Occupational Safety and Health Administration’s multi-tiered approach to hazardous materials training. Capabilities under development at HAMMER include classroom and long-distance (i.e., satellite and internet broadcast) learning, as well as life-size, hands-on hydrogen burn props for “training as real as it gets.” This paper presents insights gained from the early emergency response hydrogen safety training courses held in 2005 and current plans for design and construction of a number of hydrogen burn props.

  4. Hydrogen Technologies Safety Guide

    SciTech Connect (OSTI)

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

    2015-01-01T23:59:59.000Z

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

  5. Gas Pipeline Safety (West Virginia)

    Broader source: Energy.gov [DOE]

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

  6. Community Development Department Building & Safety Division

    E-Print Network [OSTI]

    BUILDING, RESIDENTIAL AND GREEN BUILDING CODES, AMENDING FREMONT MUNICIPAL CODE TITLE vn (BUILDING TO ENERGY REGULATIONS THE 2010 CALIFORNIA,GREEN BUILDING CODE The City of Fremont proposed to adopt local................ Community Development Department Building & Safety Division 39550 Liberty Street

  7. Dam Safety (North Carolina)

    Broader source: Energy.gov [DOE]

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

  8. 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, ...

  9. Technical Standards, ALOHA-Code Guidance- June 22, 2004

    Broader source: Energy.gov [DOE]

    DOE-EH-4.2.1.4-ALOHA-Code Guidance, ALOHA Computer Code Application Guidance for Documented Safety Analysis

  10. Course Code: Course Title

    E-Print Network [OSTI]

    Painter, Kevin

    - Frameworks; Decision Making Development life-cycle of a software system Bi-directional influence between-Critical Systems; Technology & Society. Brave New Worlds - Co-operative Computing; eLife. Learning OutcomesCourse Code: F29PD Course Title: Professional Development Course Co-ordinator: Sandy Jean

  11. ACTION: Technical Position on the Use of National Consensus and Building Codes to Meet DOE Order 420.18, Facility Safety, Albright, 9/13/07

    Broader source: Energy.gov [DOE]

    The attached technical position was developed in response to line organization requests for clarification and it will be posted on the Office ofNuclear Safety and Environmental Policy web page for...

  12. Facility Safety

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

    1996-10-24T23:59:59.000Z

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

  13. Facility Safety

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

    1995-11-16T23:59:59.000Z

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

  14. Code Description Code Description

    E-Print Network [OSTI]

    Leave* 5127 Officials 5217 Faculty Sick Leave Payment 5124 Personal Service Contracts 5211 Research Services Contracts Scholarships & Fellowships Faculty Fringe Contract Services #12;Banner Account Code

  15. Mechanical code comparator

    DOE Patents [OSTI]

    Peter, Frank J. (Albuquerque, NM); Dalton, Larry J. (Bernalillo, NM); Plummer, David W. (Albuquerque, NM)

    2002-01-01T23:59:59.000Z

    A new class of mechanical code comparators is described which have broad potential for application in safety, surety, and security applications. These devices can be implemented as micro-scale electromechanical systems that isolate a secure or otherwise controlled device until an access code is entered. This access code is converted into a series of mechanical inputs to the mechanical code comparator, which compares the access code to a pre-input combination, entered previously into the mechanical code comparator by an operator at the system security control point. These devices provide extremely high levels of robust security. Being totally mechanical in operation, an access control system properly based on such devices cannot be circumvented by software attack alone.

  16. Montana Coal Mining Code (Montana)

    Broader source: Energy.gov [DOE]

    The Department of Labor and Industry is authorized to adopt rules pertaining to safety standards for all coal mines in the state. The Code requires coal mine operators to make an accurate map or...

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

    E-Print Network [OSTI]

    Minnesota, University of

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

  18. RESEARCH SAFETY RADIATION SAFETY

    E-Print Network [OSTI]

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

  19. Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

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

    2014-12-19T23:59:59.000Z

    This Standard describes a framework and the criteria to be used for approval of (1) safety basis documents, as required by 10 Code of Federal Regulation (C.F.R.) 830, Nuclear Safety Management, and (2) safety design basis documents, as required by Department of Energy (DOE) Standard (STD)-1189-2008, Integration of Safety into the Design Process.

  20. Spinal codes

    E-Print Network [OSTI]

    Perry, Jonathan, S.M. Massachusetts Institute of Technology

    2012-01-01T23:59:59.000Z

    Spinal codes are a new class of rateless codes that enable wireless networks to cope with time-varying channel conditions in a natural way, without requiring any explicit bit rate selection. The key idea in the code is the ...

  1. Advanced Reactor Safety Research Division. Quarterly progress report, January 1-March 31, 1980

    SciTech Connect (OSTI)

    Agrawal, A.K.; Cerbone, R.J.; Sastre, C.

    1980-06-01T23:59:59.000Z

    The Advanced Reactor Safety Research Programs quarterly progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.

  2. Advanced Reactor Safety Research Division quarterly progress report, January 1-March 31, 1981

    SciTech Connect (OSTI)

    Cerbone, R.J.; Ginsberg, T.; Guppy, J.G.; Sastre, C.

    1981-05-01T23:59:59.000Z

    The Advanced Reactor Safety Research Programs Quarterly Progress Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.

  3. Advanced Reactor Safety Research Division. Quarterly progress report, July 1-September 30, 1980

    SciTech Connect (OSTI)

    Ramano, A.J. (comp.)

    1980-11-01T23:59:59.000Z

    The Advanced Reactor Safety Research Programs Quarterly Progress Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.

  4. Advanced Reactor Safety Research Division quarterly progress report, 1 October-31 December 1980

    SciTech Connect (OSTI)

    Cerbone, R.J.; Ginsberg, T.; Guppy, J.G.; Sastre, C.

    1981-02-01T23:59:59.000Z

    The Advanced Reactor Safety Research Programs quarterly progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, LMFBR Safety Experiments, SSC Code Development, and Fast Reactor Safety Code Validation.

  5. Advanced Reactor Safety Research Division. Quarterly progress report, July 1-September 30, 1979

    SciTech Connect (OSTI)

    Romano, A.J.

    1980-01-01T23:59:59.000Z

    The Advanced Reactor Safety Research Programs Quarterly Progress Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR Safety Evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.

  6. Advanced Reactor Safety Research Division. Quarterly progress report, April 1-June 30, 1980

    SciTech Connect (OSTI)

    Romano, A.J.

    1980-01-01T23:59:59.000Z

    The Advanced Reactor Safety Research Programs Quarterly Progress Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: HTGR safety evaluation, SSC Code Development, LMFBR Safety Experiments, and Fast Reactor Safety Code Validation.

  7. National Construction Safety Team Act Annual Report

    E-Print Network [OSTI]

    Magee, Joseph W.

    National Construction Safety Team Act Annual Report Fiscal Year 2008 Summary This annual report to Congress for FY 2008 is required by the National Construction Safety Team Act. NIST completed its federal report. The ICC Codes are widely adopted and used as the basis for state and local construction codes

  8. Local Safety Committee Engineering

    E-Print Network [OSTI]

    Saskatchewan, University of

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

  9. 4-H Club Health/Safety Officer Handbook 1 Health/Safety Officer

    E-Print Network [OSTI]

    4-H Club Health/Safety Officer Handbook 1 4-H Club Health/Safety Officer Handbook Family & Consumer Sciences website: http://fcs.tamu.edu (click on Health and Safety) Texas 4-H website: http://texas4-h Health/Safety Officer Handbook2 This handbook was created by the following Texas A&M AgriLife Extension

  10. CC: Security, Residential Life Evacuation Assistance Form

    E-Print Network [OSTI]

    Mahon, Bradford Z.

    CC: Security, Residential Life Evacuation Assistance Form Voluntary Self-Identification If you have will be kept confidential and used only by Environmental Health and Safety, Residential Life (if applicable

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

    E-Print Network [OSTI]

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

  12. Implementation Guide for Use in Developing Technical Safety Requirements

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

    2014-09-08T23:59:59.000Z

    The guide was developed in support of Title 10 Code of Federal Regulations (CFR) Part 830, Nuclear Safety Management. It provides guidance for the requirements defined in 10 CFR §830.205, Technical Safety Requirements.

  13. Facility Safety

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

    2000-11-20T23:59:59.000Z

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

  14. Code constructions and code families for nonbinary quantum stabilizer code

    E-Print Network [OSTI]

    Ketkar, Avanti Ulhas

    2005-11-01T23:59:59.000Z

    Stabilizer codes form a special class of quantum error correcting codes. Nonbinary quantum stabilizer codes are studied in this thesis. A lot of work on binary quantum stabilizer codes has been done. Nonbinary stabilizer codes have received much...

  15. Department of Energy Office of Nuclear Safety and Environmental...

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

    Safety, must comply with national consensus industry standards and the model building codes applicable for the state or region in which the facility is located. Certain...

  16. Campus Life www.bath.ac.uk/accommodation

    E-Print Network [OSTI]

    Burton, Geoffrey R.

    & Safety Regulations and Damage to Fire & Safety Equipment 40 - Disciplinary Code Flow Chart of Procedures - Energy, Environment and Sustainability 28 - What Are We Doing to Reduce Utility Usage? 28 - How Can You

  17. Holographic codes

    E-Print Network [OSTI]

    Latorre, Jose I

    2015-01-01T23:59:59.000Z

    There exists a remarkable four-qutrit state that carries absolute maximal entanglement in all its partitions. Employing this state, we construct a tensor network that delivers a holographic many body state, the H-code, where the physical properties of the boundary determine those of the bulk. This H-code is made of an even superposition of states whose relative Hamming distances are exponentially large with the size of the boundary. This property makes H-codes natural states for a quantum memory. H-codes exist on tori of definite sizes and get classified in three different sectors characterized by the sum of their qutrits on cycles wrapped through the boundaries of the system. We construct a parent Hamiltonian for the H-code which is highly non local and finally we compute the topological entanglement entropy of the H-code.

  18. Holographic codes

    E-Print Network [OSTI]

    Jose I. Latorre; German Sierra

    2015-02-23T23:59:59.000Z

    There exists a remarkable four-qutrit state that carries absolute maximal entanglement in all its partitions. Employing this state, we construct a tensor network that delivers a holographic many body state, the H-code, where the physical properties of the boundary determine those of the bulk. This H-code is made of an even superposition of states whose relative Hamming distances are exponentially large with the size of the boundary. This property makes H-codes natural states for a quantum memory. H-codes exist on tori of definite sizes and get classified in three different sectors characterized by the sum of their qutrits on cycles wrapped through the boundaries of the system. We construct a parent Hamiltonian for the H-code which is highly non local and finally we compute the topological entanglement entropy of the H-code.

  19. Model-based Safety Risk Assessment

    E-Print Network [OSTI]

    Lindsay, Peter

    development life-cycle, in order to identify critical system requirements, such as safety requirements their effectiveness, early in the system development life-cycle, on models derived directly from natural language of functional requirements of arbitrary detail ­ whether it is very early in the life-cycle when functions

  20. Safety, Codes, and Standards Fact Sheet

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy atLLC - FE DKT. 10-160-LNG - ORDERSTATE0-1of EnergyIndia Fuel cells

  1. Safety, Codes, and Standards Fact Sheet

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn'tOrigin ofEnergy atLLC - FE DKT. 10-160-LNG - ORDERSTATE0-1of EnergyIndia Fuel cellsFuel

  2. Safety, Codes, and Standards | 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 DataDepartment of Energy Your Density Isn'tOrigin ofEnergy atLLC - FE DKT. 10-160-LNG - ORDERSTATE0-1of EnergyIndia Fuel

  3. Facility Safety

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

    2005-12-22T23:59:59.000Z

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

  4. 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.

  5. Facility Safety

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

    1995-10-13T23:59:59.000Z

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

  6. Facility Safety

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

    2005-12-22T23:59:59.000Z

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

  7. Facility Safety

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

    2012-12-04T23:59:59.000Z

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

  8. CC: Security, Residential Life Evacuation Assistance Form

    E-Print Network [OSTI]

    Cantlon, Jessica F.

    CC: Security, Residential Life Evacuation Assistance Form Voluntary Self-Identification If you have will be kept confidential and used only by Environmental Health and Safety, Residential Life (if applicable:_______________________________________________________ ______________________________________________________________________________ ______________________________________________________________________________ #12;CC: Security, Residential Life If this is a temporary request, please provide a date when

  9. Building America Expert Meeting: Combustion Safety

    SciTech Connect (OSTI)

    Brand, L.

    2013-03-01T23:59:59.000Z

    This is a meeting overview of 'The Best Approach to Combustion Safety in a Direct Vent World', held June 28, 2012, in San Antonio, Texas. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

  10. Pressure Safety Program Implementation at ORNL

    SciTech Connect (OSTI)

    Lower, Mark [ORNL; Etheridge, Tom [ORNL; Oland, C. Barry [XCEL Engineering, Inc.

    2013-01-01T23:59:59.000Z

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply with pressure safety requirements in 10 CFR 851. It also describes actions taken to develop and implement ORNL’s Pressure Safety Program.

  11. Office of Nuclear Safety and Environmental Assessments | Department...

    Office of Environmental Management (EM)

    examine implementation of safety management programs during phases of the life cycle of a nuclear facility including operation, deactivation, decontamination, decommissioning and...

  12. Development of a three-dimensional two-fluid code with transient neutronic feedback for LWR applications

    E-Print Network [OSTI]

    Griggs, D. P.

    1981-01-01T23:59:59.000Z

    The development of a three-dimensional coupled neutronics/thermalhydraulics code for LWR safety analysis has been initiated. The transient neutronics code QUANDRY has been joined to the two-fluid thermal-hydraulics code ...

  13. High Performance “Reach” Codes

    E-Print Network [OSTI]

    Edelson, J.

    2011-01-01T23:59:59.000Z

    Jim Edelson New Buildings Institute A Growing Role for Codes and Stretch Codes in Utility Programs Clean Air Through Energy Efficiency November 9, 2011 ESL-KT-11-11-39 CATEE 2011, Dallas, Texas, Nov. 7 ? 9, 2011 New Buildings Institute ESL..., Nov. 7 ? 9, 2011 ?31? Flavors of Codes ? Building Codes Construction Codes Energy Codes Stretch or Reach Energy Codes Above-code programs Green or Sustainability Codes Model Codes ?Existing Building? Codes Outcome-Based Codes ESL-KT-11...

  14. CURRICULUM CODE: 611 & 613 MINOR CODE 061 DEGREE CODE: 31

    E-Print Network [OSTI]

    Qiu, Weigang

    CURRICULUM CODE: 611 & 613 MINOR CODE 061 DEGREE CODE: 31 DAAF 12/09 Hunter College of the City Stamp THIS AUDIT IS NOT OFFICIAL UNTIL APPROVED BY THE OFFICE OF THE REGISTRAR DEGREE AUDIT UNIT Student Specialization Section #12;CURRICULUM CODE: 611 & 613 MINOR CODE 061 DEGREE CODE: 31 DAAF 12/09 *****A SEPARATE

  15. CURRICULUM CODE_611 & 613 MINOR CODE 062 DEGREE CODE _31_

    E-Print Network [OSTI]

    Qiu, Weigang

    CURRICULUM CODE_611 & 613 MINOR CODE 062 DEGREE CODE _31_ 1/24/2006 Hunter College of the City-mail address Department Stamp THIS AUDIT IS NOT OFFICIAL UNTIL APPROVED BY THE OFFICE OF THE REGISTRAR, DEGREE Section Only For January 2010 Graduate #12;CURRICULUM CODE_611 & 613 MINOR CODE 062 DEGREE CODE _31_ 1

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

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

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

  17. REACTOR SAFETY KEYWORDS: best estimate plus

    E-Print Network [OSTI]

    Hoppe, Fred M.

    REACTOR SAFETY KEYWORDS: best estimate plus uncertainty analysis, epistemic error and aleatory phe- nomena that underlie the safety analyses. The use of BE codes within the reactor technology in advance and that result from a variety of operating conditions or states. These arise because the reactor

  18. Solar PV Permitting and Safety Training Webinar

    Broader source: Energy.gov [DOE]

    This webinar provides training on two permitting resources for municipal inspectors; a prescriptive process for building inspectors and a guidance document for permitting for PV for electrical inspectors. The webinar also runs through a number of key code articles in Massachusetts 2014 electrical code and examines a variety of safety hazards commonly found during or after solar PV installations.

  19. ENVIRONMENT, SAFETY & HEALTH DIVISION Chapter 12: Fire and Life Safety

    E-Print Network [OSTI]

    Wechsler, Risa H.

    of equipment located in the area The National Fire Protection Association (NFPA) categorizes fires into four National Fire Protection Association (NFPA) 10, "Standard for Portable Fire Extinguishers" (NFPA 10 buildings, located so that a person does not have to travel more than 75 feet to reach one Fire

  20. ENVIRONMENT, SAFETY & HEALTH DIVISION Chapter 12: Fire and Life Safety

    E-Print Network [OSTI]

    Wechsler, Risa H.

    -fired heaters 2. Heaters that lack a nationally recognized testing laboratory (NRTL) listing sticker 3. Radiant

  1. SAFETY PROCEDURE SP-24 NATIONAL HIGH MAGNETIC

    E-Print Network [OSTI]

    Weston, Ken

    affecting facility operations or equipment, including electrical, life safety, mechanical, or plumbing outages to any area in the NHMFL. Advance notice to affected areas shall be provided by the Facilities

  2. Speech coding

    SciTech Connect (OSTI)

    Ravishankar, C., Hughes Network Systems, Germantown, MD

    1998-05-08T23:59:59.000Z

    Speech is the predominant means of communication between human beings and since the invention of the telephone by Alexander Graham Bell in 1876, speech services have remained to be the core service in almost all telecommunication systems. Original analog methods of telephony had the disadvantage of speech signal getting corrupted by noise, cross-talk and distortion Long haul transmissions which use repeaters to compensate for the loss in signal strength on transmission links also increase the associated noise and distortion. On the other hand digital transmission is relatively immune to noise, cross-talk and distortion primarily because of the capability to faithfully regenerate digital signal at each repeater purely based on a binary decision. Hence end-to-end performance of the digital link essentially becomes independent of the length and operating frequency bands of the link Hence from a transmission point of view digital transmission has been the preferred approach due to its higher immunity to noise. The need to carry digital speech became extremely important from a service provision point of view as well. Modem requirements have introduced the need for robust, flexible and secure services that can carry a multitude of signal types (such as voice, data and video) without a fundamental change in infrastructure. Such a requirement could not have been easily met without the advent of digital transmission systems, thereby requiring speech to be coded digitally. The term Speech Coding is often referred to techniques that represent or code speech signals either directly as a waveform or as a set of parameters by analyzing the speech signal. In either case, the codes are transmitted to the distant end where speech is reconstructed or synthesized using the received set of codes. A more generic term that is applicable to these techniques that is often interchangeably used with speech coding is the term voice coding. This term is more generic in the sense that the coding techniques are equally applicable to any voice signal whether or not it carries any intelligible information, as the term speech implies. Other terms that are commonly used are speech compression and voice compression since the fundamental idea behind speech coding is to reduce (compress) the transmission rate (or equivalently the bandwidth) And/or reduce storage requirements In this document the terms speech and voice shall be used interchangeably.

  3. Department of Energy Construction Safety Reference Guide

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    DOE has adopted the Occupational Safety and Health Administration (OSHA) regulations Title 29 Code of Federal Regulations (CFR) 1926 ``Safety and Health Regulations for Construction,`` and related parts of 29 CFR 1910, ``Occupational Safety and Health Standards.`` This nonmandatory reference guide is based on these OSHA regulations and, where appropriate, incorporates additional standards, codes, directives, and work practices that are recognized and accepted by DOE and the construction industry. It covers excavation, scaffolding, electricity, fire, signs/barricades, cranes/hoists/conveyors, hand and power tools, concrete/masonry, stairways/ladders, welding/cutting, motor vehicles/mechanical equipment, demolition, materials, blasting, steel erection, etc.

  4. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem NotEnergy,ARMFormsGasReleaseSpeechesHall ATours, Programs and EventsFiberFire

  5. MELCOR computer code manuals

    SciTech Connect (OSTI)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A.; Hyman, C.R.; Sanders, R.L. [Oak Ridge National Lab., TN (United States)

    1995-03-01T23:59:59.000Z

    MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.

  6. LASER SAFETY POLICY MANUAL ENVIRONMENTAL HEALTH & SAFETY

    E-Print Network [OSTI]

    Houston, Paul L.

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

  7. ENVIRONMENTAL HEALTH AND SAFETY GENERAL SAFETY MANUAL

    E-Print Network [OSTI]

    Maroncelli, Mark

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

  8. Safety Bulletin

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

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

  9. Facility Safety

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

    2002-05-20T23:59:59.000Z

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

  10. Elements of a nuclear criticality safety program

    SciTech Connect (OSTI)

    Hopper, C.M.

    1995-07-01T23:59:59.000Z

    Nuclear criticality safety programs throughout the United States are quite successful, as compared with other safety disciplines, at protecting life and property, especially when regarded as a developing safety function with no historical perspective for the cause and effect of process nuclear criticality accidents before 1943. The programs evolved through self-imposed and regulatory-imposed incentives. They are the products of conscientious individuals, supportive corporations, obliged regulators, and intervenors (political, public, and private). The maturing of nuclear criticality safety programs throughout the United States has been spasmodic, with stability provided by the volunteer standards efforts within the American Nuclear Society. This presentation provides the status, relative to current needs, for nuclear criticality safety program elements that address organization of and assignments for nuclear criticality safety program responsibilities; personnel qualifications; and analytical capabilities for the technical definition of critical, subcritical, safety and operating limits, and program quality assurance.

  11. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Bureau of Construction Codes is responsible for the administration of the State Construction Code Act (1972 PA 230), also known as the Uniform Construction Code.

  12. Certification plan for reactor analysis computer codes

    SciTech Connect (OSTI)

    Toffer, H.; Crowe, R.D.; Schwinkendorf, K.N. [Westinghouse Hanford Co., Richland, WA (United States); Pevey, R.E. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1990-01-01T23:59:59.000Z

    A certification plan for reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations has been prepared. An action matrix, checklists, a time schedule, and a resource commitment table have been included in the plan. These items identify what is required to achieve certification of the codes, the time table that this will be accomplished on, and the resources needed to support such an effort.

  13. Toolbox Safety Talk Ladder Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

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

  14. Generalized concatenated quantum codes

    E-Print Network [OSTI]

    Grassl, Markus

    We discuss the concept of generalized concatenated quantum codes. This generalized concatenation method provides a systematical way for constructing good quantum codes, both stabilizer codes and nonadditive codes. Using ...

  15. Concatenated Conjugate Codes

    E-Print Network [OSTI]

    Mitsuru Hamada

    2006-10-31T23:59:59.000Z

    A conjugate code pair is defined as a pair of linear codes either of which contains the dual of the other. A conjugate code pair represents the essential structure of the corresponding Calderbank-Shor-Steane (CSS) quantum code. It is known that conjugate code pairs are applicable to (quantum) cryptography. We give a construction method for efficiently decodable conjugate code pairs.

  16. Toolbox Safety Talk Welding & Metal Work Safety

    E-Print Network [OSTI]

    Pawlowski, Wojtek

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

  17. CURRICULUM CODE 308 DEGREE CODE _40

    E-Print Network [OSTI]

    Qiu, Weigang

    CURRICULUM CODE 308 DEGREE CODE _40 Hunter College of the City University of New York - Office Print) E-mail address OES Stamp THIS AUDIT IS NOT OFFICIAL UNTIL APPROVED BY THE OFFICE OF THE REGISTRAR Specialization Section #12;CURRICULUM CODE_308_ DEGREE CODE _40__ Course Prefix & Number Course Title Credits

  18. Nuclear Safety Regulatory Framework

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

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

  19. Gas Pipeline Safety (Indiana)

    Broader source: Energy.gov [DOE]

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

  20. Life sciences

    SciTech Connect (OSTI)

    Day, L. (ed.)

    1991-04-01T23:59:59.000Z

    This document is the 1989--1990 Annual Report for the Life Sciences Divisions of the University of California/Lawrence Berkeley Laboratory. Specific progress reports are included for the Cell and Molecular Biology Division, the Research Medicine and Radiation Biophysics Division (including the Advanced Light Source Life Sciences Center), and the Chemical Biodynamics Division. 450 refs., 46 figs. (MHB)

  1. achieve product safety: Topics by E-print Network

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

    that are adaptively secure under a standard assumption 29 1Page ofProduct Code: 051000 Revision: 5 07 MAR 2002Issued: 7 Material Safety Data Sheet Materials Science Websites...

  2. Laser Safety Introduction

    E-Print Network [OSTI]

    McQuade, D. Tyler

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

  3. Homological stabilizer codes

    SciTech Connect (OSTI)

    Anderson, Jonas T., E-mail: jonastyleranderson@gmail.com

    2013-03-15T23:59:59.000Z

    In this paper we define homological stabilizer codes on qubits which encompass codes such as Kitaev's toric code and the topological color codes. These codes are defined solely by the graphs they reside on. This feature allows us to use properties of topological graph theory to determine the graphs which are suitable as homological stabilizer codes. We then show that all toric codes are equivalent to homological stabilizer codes on 4-valent graphs. We show that the topological color codes and toric codes correspond to two distinct classes of graphs. We define the notion of label set equivalencies and show that under a small set of constraints the only homological stabilizer codes without local logical operators are equivalent to Kitaev's toric code or to the topological color codes. - Highlights: Black-Right-Pointing-Pointer We show that Kitaev's toric codes are equivalent to homological stabilizer codes on 4-valent graphs. Black-Right-Pointing-Pointer We show that toric codes and color codes correspond to homological stabilizer codes on distinct graphs. Black-Right-Pointing-Pointer We find and classify all 2D homological stabilizer codes. Black-Right-Pointing-Pointer We find optimal codes among the homological stabilizer codes.

  4. Facility Safety

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

    2013-06-21T23:59:59.000Z

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

  5. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C. (Malmoe, SE)

    1984-01-01T23:59:59.000Z

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

  6. Half-Product Codes

    E-Print Network [OSTI]

    Emmadi, Santosh Kumar

    2014-12-11T23:59:59.000Z

    A class of codes, half-product codes, derived from product codes, is characterized. These codes have the implementation advantages of product codes and possess a special structural property which leads them to have larger (at least 3/2 times more...

  7. Tank farms criticality safety manual

    SciTech Connect (OSTI)

    FORT, L.A.

    2003-03-27T23:59:59.000Z

    This document defines the Tank Farms Contractor (TFC) criticality safety program, as required by Title 10 Code of Federal Regulations (CFR), Subpart 830.204(b)(6), ''Documented Safety Analysis'' (10 CFR 830.204 (b)(6)), and US Department of Energy (DOE) 0 420.1A, Facility Safety, Section 4.3, ''Criticality Safety.'' In addition, this document contains certain best management practices, adopted by TFC management based on successful Hanford Site facility practices. Requirements in this manual are based on the contractor requirements document (CRD) found in Attachment 2 of DOE 0 420.1A, Section 4.3, ''Nuclear Criticality Safety,'' and the cited revisions of applicable standards published jointly by the American National Standards Institute (ANSI) and the American Nuclear Society (ANS) as listed in Appendix A. As an informational device, requirements directly imposed by the CRD or ANSI/ANS Standards are shown in boldface. Requirements developed as best management practices through experience and maintained consistent with Hanford Site practice are shown in italics. Recommendations and explanatory material are provided in plain type.

  8. List of codes Language abbreviation codes

    E-Print Network [OSTI]

    Portugal MT Malta GR Greece SE Sweden TR Turkey Country codes for the ERASMUS Institutional Identification codes A Austria IR L Ireland BG Bulgaria LV Latvia B Belgium IS Iceland CY Cyprus MT Malta D Germany L

  9. Generalized Concatenation for Quantum Codes

    E-Print Network [OSTI]

    Grassl, Markus

    We show how good quantum error-correcting codes can be constructed using generalized concatenation. The inner codes are quantum codes, the outer codes can be linear or nonlinear classical codes. Many new good codes are ...

  10. Results and code predictions for ABCOVE (aerosol behavior code validation and evaluation) aerosol code validation: Test AB6 with two aerosol species. [LMFBR

    SciTech Connect (OSTI)

    Hilliard, R K; McCormack, J C; Muhlestein, L D

    1984-12-01T23:59:59.000Z

    A program for aerosol behavior code validation and evaluation (ABCOVE) has been developed in accordance with the LMFBR Safety Program Plan. The ABCOVE program is a cooperative effort between the USDOE, the USNRC, and their contractor organizations currently involved in aerosol code development, testing or application. The second large-scale test in the ABCOVE program, AB6, was performed in the 850-m/sup 3/ CSTF vessel with a two-species test aerosol. The test conditions simulated the release of a fission product aerosol, NaI, in the presence of a sodium spray fire. Five organizations made pretest predictions of aerosol behavior using seven computer codes. Three of the codes (QUICKM, MAEROS and CONTAIN) were discrete, multiple species codes, while four (HAA-3, HAA-4, HAARM-3 and SOFIA) were log-normal codes which assume uniform coagglomeration of different aerosol species. Detailed test results are presented and compared with the code predictions for seven key aerosol behavior parameters.

  11. 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.

  12. Pressure safety program Lawrence Livermore National Laboratory

    SciTech Connect (OSTI)

    Borzileri, C.; Traini, M.

    1992-10-01T23:59:59.000Z

    The Lawrence Livermore National Laboratory (LLNL) is a Research and Development facility. Programs include research in: nuclear weapons, energy, environmental, biomedical, and other DOE funded programs. LLNL is managed by the University of California for the Department of Energy. Many research and development programs require the use of pressurized fluid systems. In the early 1960`s, courses were developed to train personnel to safely work with pressurized systems. These courses served as a foundation for the Pressure Safety Program. The Pressure Safety Program is administered by the Pressure Safety Manager through the Hazards Control Department, and responsibilities include: (1) Pressure Safety course development and training, (2) Equipment documentation, tracking and inspections/retests, (3) Formal and informal review of pressure systems. The program uses accepted codes and standards and closely follows the DOE Pressure Safety Guidelines Manual. This manual was developed for DOE by Lawrence Livermore National Laboratory. The DOE Pressure Safety Guidelines Manual defines five (5) basic elements which constitute this Pressure Safety Program. These elements are: (1) A Pressure Safety Manual, (2) A Safety Committee, (3) Personnel who are trained and qualified, (4) Documentation and accountability for each pressure vessel or system, (5) Control of the selection and the use of high pressure hardware.

  13. Quantum convolutional stabilizer codes

    E-Print Network [OSTI]

    Chinthamani, Neelima

    2004-09-30T23:59:59.000Z

    Quantum error correction codes were introduced as a means to protect quantum information from decoherance and operational errors. Based on their approach to error control, error correcting codes can be divided into two different classes: block codes...

  14. Guam- Building Energy Code

    Broader source: Energy.gov [DOE]

    NOTE: In September 2012, The Guam Building Code Council adopted the draft [http://www.guamenergy.com/outreach-education/guam-tropical-energy-code/ Guam Tropical Energy Code]. It must be adopted by...

  15. Building Energy Code

    Broader source: Energy.gov [DOE]

    In 2009 S.B. 1182 created the Oklahoma Uniform Building Code Commission. The 11-member Commission was given the power to conduct rulemaking processes to adopt new building codes. The codes adopted...

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

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

    2001-10-24T23:59:59.000Z

    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.

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

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

    2006-07-24T23:59:59.000Z

    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.

  18. COG - Special Features of Interest to Criticality Safety Practitioners

    SciTech Connect (OSTI)

    Buck, R M; Heinrichs, D P; Krass, A W; Lent, E M

    2010-01-14T23:59:59.000Z

    COG is a modern, general-purpose, high fidelity, multi-particle transport code developed at the Lawrence Livermore National Laboratory specifically for use in deep penetration (shielding) and criticality safety calculations. This paper describes some features in COG of special interest to criticality safety practitioners.

  19. Water Reactor Safety Research Division quarterly progress report, January 1-March 31, 1980

    SciTech Connect (OSTI)

    Romano, A.J. (comp.)

    1980-06-01T23:59:59.000Z

    The Water Reactor Safety Research Programs Quarterly Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evaluation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.

  20. Water Reactor Safety Research Division. Quarterly progress report, April 1-June 30, 1980

    SciTech Connect (OSTI)

    Abuaf, N.; Levine, M.M.; Saha, P.; van Rooyen, D.

    1980-08-01T23:59:59.000Z

    The Water Reactor Safety Research Programs quarterly report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evlauation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.

  1. Codeword Stabilized Quantum Codes

    E-Print Network [OSTI]

    Andrew Cross; Graeme Smith; John A. Smolin; Bei Zeng

    2007-09-27T23:59:59.000Z

    We present a unifying approach to quantum error correcting code design that encompasses additive (stabilizer) codes, as well as all known examples of nonadditive codes with good parameters. We use this framework to generate new codes with superior parameters to any previously known. In particular, we find ((10,18,3)) and ((10,20,3)) codes. We also show how to construct encoding circuits for all codes within our framework.

  2. Generalized Concatenated Quantum Codes

    E-Print Network [OSTI]

    Markus Grassl; Peter Shor; Graeme Smith; John Smolin; Bei Zeng

    2009-01-09T23:59:59.000Z

    We introduce the concept of generalized concatenated quantum codes. This generalized concatenation method provides a systematical way for constructing good quantum codes, both stabilizer codes and nonadditive codes. Using this method, we construct families of new single-error-correcting nonadditive quantum codes, in both binary and nonbinary cases, which not only outperform any stabilizer codes for finite block length, but also asymptotically achieve the quantum Hamming bound for large block length.

  3. Encoding Subsystem Codes

    E-Print Network [OSTI]

    Pradeep Kiran Sarvepalli; Andreas Klappenecker

    2008-06-30T23:59:59.000Z

    In this paper we investigate the encoding of operator quantum error correcting codes i.e. subsystem codes. We show that encoding of subsystem codes can be reduced to encoding of a related stabilizer code making it possible to use all the known results on encoding of stabilizer codes. Along the way we also show how Clifford codes can be encoded. We also show that gauge qubits can be exploited to reduce the encoding complexity.

  4. On optimal constacyclic codes

    E-Print Network [OSTI]

    Giuliano G. La Guardia

    2013-11-11T23:59:59.000Z

    In this paper we investigate the class of constacyclic codes, which is a natural generalization of the class of cyclic and negacyclic codes. This class of codes is interesting in the sense that it contains codes with good or even optimal parameters. In this light, we propose constructions of families of classical block and convolutional maximum-distance-separable (MDS) constacyclic codes, as well as families of asymmetric quantum MDS codes derived from (classical-block) constacyclic codes. These results are mainly derived from the investigation of suitable properties on cyclotomic cosets of these corresponding codes.

  5. Building Energy Code

    Broader source: Energy.gov [DOE]

    The West Virginia State Fire Commission is responsible for adopting and promulgating statewide construction codes. These codes may be voluntarily adopted at the local level. Local jurisdictions...

  6. Delivering safety

    SciTech Connect (OSTI)

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

    2007-07-01T23:59:59.000Z

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

  7. Safety, Security

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

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

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

    SciTech Connect (OSTI)

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

    2009-03-01T23:59:59.000Z

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

  9. Tufts University Athletics Department Camp & Clinic Programs Staff and Volunteer Code of Conduct

    E-Print Network [OSTI]

    Dennett, Daniel

    , coaches, officials, and volunteers. This Code of Conduct has been designed to help ensure the safety with children. · All staff members, coaches, officials and volunteers will receive a copy of this CodeTufts University Athletics Department Camp & Clinic Programs Staff and Volunteer Code of Conduct

  10. Life Sciences

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn12electron 9 5Let us count theLienert namedLife Sciences Life

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

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

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

  12. Safety Software Guide Perspectives for the Design of New Nuclear Facilities (U)

    SciTech Connect (OSTI)

    VINCENT, Andrew

    2005-07-14T23:59:59.000Z

    In June of this year, the Department of Energy (DOE) issued directives DOE O 414.1C and DOE G 414.1-4 to improve quality assurance programs, processes, and procedures among its safety contractors. Specifically, guidance entitled, ''Safety Software Guide for use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance, DOE G 414.1-4'', provides information and acceptable methods to comply with safety software quality assurance (SQA) requirements. The guidance provides a roadmap for meeting DOE O 414.1C, ''Quality Assurance'', and the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and software application activities. [1, 2] The order and guide are part of a comprehensive implementation plan that addresses issues and concerns documented in Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1. [3] Safety SQA requirements for DOE as well as National Nuclear Security Administration contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE G 414.1-4 was developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. The Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities. While the safety software guidance is considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at all DOE nuclear facilities, new nuclear facilities are well suited to take advantage of the guide to ensure compliant programs and processes are implemented. Attributes such as the facility life-cycle stage and the hazardous nature of each facility operations are considered, along with the category and level of importance of the software. The discussion provided herein illustrates benefits of applying the Safety Software Guide to work activities dependent on software applications and directed toward the design of new nuclear facilities. In particular, the Guide-based systematic approach with software enables design processes to effectively proceed and reduce the likelihood of rework activities. Several application examples are provided for the new facility.

  13. EHS DSP Authorization Request Form 2012-001 Safety & Risk Management

    E-Print Network [OSTI]

    , regulations and Driver safety Program requirements. I authorize Safety & Risk Management to enroll me or more persons in one accident; $5,000 property damage). Vehicle Code Section 16020 (effective July 1EHS DSP Authorization Request Form 2012-001 Safety & Risk Management Request for Authorization

  14. Generalized Concatenation for Quantum Codes

    E-Print Network [OSTI]

    Markus Grassl; Peter W. Shor; Bei Zeng

    2009-05-04T23:59:59.000Z

    We show how good quantum error-correcting codes can be constructed using generalized concatenation. The inner codes are quantum codes, the outer codes can be linear or nonlinear classical codes. Many new good codes are found, including both stabilizer codes as well as so-called nonadditive codes.

  15. Acceptable NSLS Safety Documentation

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

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

  16. RADIATION SAFETY TRAINING MANUAL Radiation Safety Office

    E-Print Network [OSTI]

    Sibille, Etienne

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

  17. Graph concatenation for quantum codes

    E-Print Network [OSTI]

    Beigi, Salman

    Graphs are closely related to quantum error-correcting codes: every stabilizer code is locally equivalent to a graph code and every codeword stabilized code can be described by a graph and a classical code. For the ...

  18. Introduction to Safety Culture Advice

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes | NationalCurriculum Introduction to Radioecology (3 hrs)Safety

  19. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated CodesTransparencyDOE ProjectCrisisIndependent verificationIntegrated Safety

  20. Dam Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

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

  1. Pipeline Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

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

  2. CONCATENATED CODES BASED ON MULTIDIMENSIONAL PARITY-CHECK CODES AND TURBO CODES

    E-Print Network [OSTI]

    Wong, Tan F.

    CONCATENATED CODES BASED ON MULTIDIMENSIONAL PARITY-CHECK CODES AND TURBO CODES John M. Shea, Florida Abstract--Turbo-codes provide communications near capac- ity when very large interleavers (and parity-check code can be used as an outer code with a turbo code as an inner code in a serial

  3. SHSD Manager Safety Engineering Group Manager

    E-Print Network [OSTI]

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

  4. Code of a Tokamak Fusion Energy Facility ITER

    SciTech Connect (OSTI)

    Yasuhide Asada [Central Research Institute of Electric Power Industry - CRIEPI (Japan); Kenzo Miya [Keio University (Japan); Kazuhiko Hada; Eisuke Tada [Japan Atomic Energy Research Institute (Japan)

    2002-07-01T23:59:59.000Z

    The technical structural code for ITER (International Thermonuclear Experimental Fusion Reactor) and, as more generic applications, for D-T burning fusion power facilities (hereafter, Fusion Code) should be innovative because of their quite different features of safety and mechanical components from nuclear fission reactors, and the necessity of introducing several new fabrication and examination technologies. Introduction of such newly developed technologies as inspection-free automatic welding into the Fusion Code is rationalized by a pilot application of a new code concept of {sup s}ystem-based code for integrity{sup .} The code concept means an integration of element technical items necessary for construction, operation and maintenance of mechanical components of fusion power facilities into a single system to attain an optimization of the total margin of these components. Unique and innovative items of the Fusion Code are typically as follows: - Use of non-metals; - Cryogenic application; - New design margins on allowable stresses, and other new design rules; - Use of inspection-free automatic welding, and other newly developed fabrication technologies; - Graded approach of quality assurance standard to cover radiological safety-system components as well as non-safety-system components; - Consideration on replacement components. (authors)

  5. Life Insurance

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |Is Your HomeLatest Newsbiomass to

  6. Construction safety program for the National Ignition Facility, Appendix A

    SciTech Connect (OSTI)

    Cerruti, S.J.

    1997-06-26T23:59:59.000Z

    Topics covered in this appendix include: General Rules-Code of Safe Practices; 2. Personal Protective Equipment; Hazardous Material Control; Traffic Control; Fire Prevention; Sanitation and First Aid; Confined Space Safety Requirements; Ladders and Stairways; Scaffolding and Lift Safety; Machinery, Vehicles, and Heavy Equipment; Welding and Cutting-General; Arc Welding; Oxygen/Acetylene Welding and Cutting; Excavation, Trenching, and Shoring; Fall Protection; Steel Erection; Working With Asbestos; Radiation Safety; Hand Tools; Electrical Safety; Nonelectrical Work Performed Near Exposed High-Voltage Power-Distribution Equipment; Lockout/Tagout Requirements; Rigging; A-Cranes; Housekeeping; Material Handling and Storage; Lead; Concrete and Masonry Construction.

  7. Joint Source-Channel Coding via Turbo Codes

    E-Print Network [OSTI]

    Alajaji, Fady

    Joint Source-Channel Coding via Turbo Codes by Guang-Chong Zhu A dissertation submitted coding. One of the most exciting break- throughs in channel coding is the invention of Turbo codes, whose- tigate three joint source-channel coding issues in the context of Turbo codes. In the #12;rst part

  8. Unfolding the color code

    E-Print Network [OSTI]

    Aleksander Kubica; Beni Yoshida; Fernando Pastawski

    2015-03-06T23:59:59.000Z

    The topological color code and the toric code are two leading candidates for realizing fault-tolerant quantum computation. Here we show that the color code on a $d$-dimensional closed manifold is equivalent to multiple decoupled copies of the $d$-dimensional toric code up to local unitary transformations and adding or removing ancilla qubits. Our result not only generalizes the proven equivalence for $d=2$, but also provides an explicit recipe of how to decouple independent components of the color code, highlighting the importance of colorability in the construction of the code. Moreover, for the $d$-dimensional color code with $d+1$ boundaries of $d+1$ distinct colors, we find that the code is equivalent to multiple copies of the $d$-dimensional toric code which are attached along a $(d-1)$-dimensional boundary. In particular, for $d=2$, we show that the (triangular) color code with boundaries is equivalent to the (folded) toric code with boundaries. We also find that the $d$-dimensional toric code admits logical non-Pauli gates from the $d$-th level of the Clifford hierarchy, and thus saturates the bound by Bravyi and K\\"{o}nig. In particular, we show that the $d$-qubit control-$Z$ logical gate can be fault-tolerantly implemented on the stack of $d$ copies of the toric code by a local unitary transformation.

  9. List decoding of subspace codes and rank-metric codes

    E-Print Network [OSTI]

    Mahdavifar, Hessam

    2012-01-01T23:59:59.000Z

    2.2.2 Koetter-Kschischang Codes . . . . . . . . . . . .of Subspace Codes . . . . . . . . . . . . . . 2.3.1 OverviewList-decodable Codes of Arbitrary Dimension . . . . . . .

  10. Building Energy Code

    Broader source: Energy.gov [DOE]

    ''Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  11. Model Building Energy Code

    Broader source: Energy.gov [DOE]

    ''Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  12. Compiling Codes on Euclid

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

    Compiling Codes Compiling Codes Overview Open Mpi is the the only MPI library available on Euclid. This implementation of MPI-2 is described at Open MPI: Open Source High...

  13. Coding AuthentiCity

    E-Print Network [OSTI]

    Mercier, Rachel Havens

    2008-01-01T23:59:59.000Z

    This thesis analyzes the impact of form-based codes, focusing on two research questions: (1) What is the underlying motivation for adopting a form-based code? (2) What motivations have the most significant impact on ...

  14. Introduction to Algebraic Codes

    E-Print Network [OSTI]

    for health care. These self-correcting codes that occur in nature might be better than all of. our coding theory based on algebra or algebraic geometry. It is a myth

  15. Building Energy Code

    Broader source: Energy.gov [DOE]

    Note: Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  16. Building Energy Code

    Broader source: Energy.gov [DOE]

    ''Note: Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For...

  17. Cellulases and coding sequences

    DOE Patents [OSTI]

    Li, Xin-Liang (Athens, GA); Ljungdahl, Lars G. (Athens, GA); Chen, Huizhong (Lawrenceville, GA)

    2001-02-20T23:59:59.000Z

    The present invention provides three fungal cellulases, their coding sequences, recombinant DNA molecules comprising the cellulase coding sequences, recombinant host cells and methods for producing same. The present cellulases are from Orpinomyces PC-2.

  18. Building Energy Code

    Broader source: Energy.gov [DOE]

    The New Jersey Uniform Construction Code Act provides that model codes and standards publications shall not be adopted more frequently than once every three years. However, a revision or amendment...

  19. Building Energy Code

    Broader source: Energy.gov [DOE]

    All residential and commercial structures are required to comply with the state’s energy code. The 2009 New Mexico Energy Conservation Code (NMECC), effective June 2013, is based on 2009...

  20. Building Energy Code

    Broader source: Energy.gov [DOE]

    Prior to 1997, South Carolina's local governments adopted and enforced the building codes. In 1997, the law required statewide use of the most up-to-date building codes, which then required the...

  1. Remote-Handled Transuranic Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2001-08-01T23:59:59.000Z

    The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document representsthe development of a uniform content code system for RH-TRU waste to be transported in the 72-Bcask. It will be used to convert existing waste form numbers, content codes, and site-specificidentification codes into a system that is uniform across the U.S. Department of Energy (DOE) sites.The existing waste codes at the sites can be grouped under uniform content codes without any lossof waste characterization information. The RH-TRUCON document provides an all-encompassing|description for each content code and compiles this information for all DOE sites. Compliance withwaste generation, processing, and certification procedures at the sites (outlined in this document foreach content code) ensures that prohibited waste forms are not present in the waste. The contentcode gives an overall description of the RH-TRU waste material in terms of processes and|packaging, as well as the generation location. This helps to provide cradle-to-grave traceability ofthe waste material so that the various actions required to assess its qualification as payload for the72-B cask can be performed. The content codes also impose restrictions and requirements on themanner in which a payload can be assembled.The RH-TRU Waste Authorized Methods for Payload Control (RH-TRAMPAC), Appendix 1.3.7of the 72-B Cask Safety Analysis Report (SAR), describes the current governing procedures|applicable for the qualification of waste as payload for the 72-B cask. The logic for this|classification is presented in the 72-B Cask SAR. Together, these documents (RH-TRUCON,|RH-TRAMPAC, and relevant sections of the 72-B Cask SAR) present the foundation and|justification for classifying RH-TRU waste into content codes. Only content codes described in thisdocument can be considered for transport in the 72-B cask. Revisions to this document will be madeas additional waste qualifies for transport. |Each content code uniquely identifies the generated waste and provides a system for tracking theprocess and packaging history. Each content code begins with a two-letter site abbreviation thatindicates the shipper of the RH-TRU waste. The site-specific letter designations for each of the|DOE sites are provided in Table 1. Not all of the sites listed in Table 1 have generated/stored RH-|TRU waste.

  2. Coding for Cooperative Communications

    E-Print Network [OSTI]

    Uppal, Momin Ayub

    2011-10-21T23:59:59.000Z

    of SWCNSQ based CF relaying as a performance benchmark, we will present a practical code design using low-density parity-check (LDPC) codes for error protection at the source, and nested scalar quantization plus irregular repeat-accumulate (IRA) codes... develop and design practical coding strategies which perform very close to the infor- mation theoretic limits. The cooperative communication channels we consider are: (a) The Gaussian re- lay channel, (b) the quasi-static fading relay channel, (c...

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

    SciTech Connect (OSTI)

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

    2008-06-30T23:59:59.000Z

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

  4. Homological Product Codes

    E-Print Network [OSTI]

    Sergey Bravyi; Matthew B. Hastings

    2013-11-04T23:59:59.000Z

    Quantum codes with low-weight stabilizers known as LDPC codes have been actively studied recently due to their simple syndrome readout circuits and potential applications in fault-tolerant quantum computing. However, all families of quantum LDPC codes known to this date suffer from a poor distance scaling limited by the square-root of the code length. This is in a sharp contrast with the classical case where good families of LDPC codes are known that combine constant encoding rate and linear distance. Here we propose the first family of good quantum codes with low-weight stabilizers. The new codes have a constant encoding rate, linear distance, and stabilizers acting on at most $\\sqrt{n}$ qubits, where $n$ is the code length. For comparison, all previously known families of good quantum codes have stabilizers of linear weight. Our proof combines two techniques: randomized constructions of good quantum codes and the homological product operation from algebraic topology. We conjecture that similar methods can produce good stabilizer codes with stabilizer weight $n^a$ for any $a>0$. Finally, we apply the homological product to construct new small codes with low-weight stabilizers.

  5. Understanding Perception Through Neural 'Codes'

    E-Print Network [OSTI]

    Freeman, Walter J III

    2011-01-01T23:59:59.000Z

    Perception Through Neural ‘Codes’. In: Special Issue on “Perception Through Neural ‘Codes’. In: Special Issue on “Perception Through Neural ‘Codes’. In: Special Issue on “

  6. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01T23:59:59.000Z

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

  7. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01T23:59:59.000Z

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

  8. Shortened Turbo Codes

    E-Print Network [OSTI]

    David J.C. MacKay

    Simple arguments suggest that shortened codes must have distance properties equal to or better than those of their parent codes, and that they should be equally practical to decode. This relationship holds true in the case of low density generator codes and low density parity check codes. We investigate the properties of shortened turbo codes. I. Motivation for Shortening In our previous work on codes based on very sparse matrices we have observed that while codes with a low density generator matrix [1] are asymptotically bad, codes with a low density parity check matrix [2] are asymptotically good [3, 4, 5]. One way of viewing the relationship between low density generator matrix codes and low density parity check matrix codes is that one obtains a low density parity check matrix by taking the M \\Theta N parity check matrix [P IM ] of a (N; K) low density generator matrix code and chopping off its right-most M columns (where M = N \\Gamma K), to yield an M \\Theta K matrix [P], which...

  9. Safety Issues with Hydrogen as a Vehicle Fuel

    SciTech Connect (OSTI)

    Cadwallader, Lee Charles; Herring, James Stephen

    1999-10-01T23:59:59.000Z

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  10. Safety Issues with Hydrogen as a Vehicle Fuel

    SciTech Connect (OSTI)

    L. C. Cadwallader; J. S. Herring

    1999-09-01T23:59:59.000Z

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  11. Smoothing spline analysis of variance approach for global sensitivity analysis of computer codes

    E-Print Network [OSTI]

    Boyer, Edmond

    - ing sensitivity indices. Numerical tests performed on several analytical examples and scientific applications, such as nuclear safety assessment, meteorology or oil reservoir forecasting. Simulations are performed with complex computer codes that model diverse complex real world phenomena. Inputs

  12. ENVIRONMENT, SAFETY & HEALTH DIVISION 4 August 2011 SLAC-I-730-0A21L-006-R001 1 of 1

    E-Print Network [OSTI]

    Wechsler, Risa H.

    Code (BPVC) and ASME Pressure Piping Code) Cryogenic systems not open to the atmosphere at all times comply with Title 10, Code of Federal Regulations, "Energy", Chapter 3, "Department of Energy", Part 851, "Worker Safety and Health Program" (10 CFR 851 Appendix A.4) and all applicable codes and standards

  13. Codes and Standards

    Broader source: Energy.gov [DOE]

    A primary objective of DOE's technology validation efforts is developing testing, monitoring, and analysis protocols for validating the performance, reliability, and safety of solar photovoltaic ...

  14. Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

    SciTech Connect (OSTI)

    Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E. [Sandia National Labs., Albuquerque, NM (United States)] Sandia National Labs., Albuquerque, NM (United States); Tills, J. [J. Tills and Associates, Inc., Sandia Park, NM (United States)] J. Tills and Associates, Inc., Sandia Park, NM (United States)

    1997-12-01T23:59:59.000Z

    The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions.

  15. Coal Mine Safety Act (Virginia)

    Broader source: Energy.gov [DOE]

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

  16. Nuclear Safety Research and Development...

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

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

  17. Optimizing safety by inherent offshore platform design

    SciTech Connect (OSTI)

    Mansfield, D.P. [AEA Technology, Risley (United Kingdom); Kletz, T.A. [Kletz (T.A.), Cheadle (United Kingdom); Al-Hassan, T. [HSE Offshore Safety Div., Bootle (United Kingdom)

    1996-12-31T23:59:59.000Z

    Following the Cullen Report into the Piper Alpha Disaster, UK Operators and the Health and Safety Executive Offshore Safety Division (OSD) have been working together to bring in a new safety regime, progressively replacing prescriptive requirements with goal setting regulations to enable a more integrated approach to hazard management. This is allowing the industry to be more flexible and specific about the way it manages hazards throughout the life of the installation. In particular it is encouraging a hazards based focus to design which is changing the way installations are designed and which would promote the use of inherently safer design. Conventional installation design often relies on standard specification engineered safety systems such as shutdown systems and water deluge to control hazards, with less attention paid to minimizing the hazards at source. These add-on safety systems can be expensive to install and maintain, and may only be effective in some circumstances. This paper reports on a pilot study sponsored by OSD, involving offshore operators and design contractors, to assess the status of inherent safety in offshore installation design in the UK and to encourage its further use spreading best practice and examples of the benefits of the approach. The paper outlines the key considerations for implementation of inherently safer design, and describes some of the benefits these can bring to the industry. It also highlights the role regulations, industry initiatives and guidance can play in promoting inherently safer design both now and in the future. The study`s findings suggest that awareness of the inherent safety principles is limited to some safety specialists and designers, but that the industry is beginning to recognize the role and benefits of inherent safety. As a result its principles are starting to appear in some design procedures and hazard management guides.

  18. Magnetic Field Safety Magnetic Field Safety

    E-Print Network [OSTI]

    McQuade, D. Tyler

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

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

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

    2010-04-08T23:59:59.000Z

    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.

  20. Verification of the BISON fuel performance code

    SciTech Connect (OSTI)

    D. M. Perez; R. J. Gardner; J. D. Hales; S. R. Novascone; G. Pastore; B. W. Spencer; R. L. Williamson

    2014-09-01T23:59:59.000Z

    BISON is a modern finite element-based nuclear fuel performance code that has been under development at Idaho National Labo- ratory (USA) since 2009. The code is applicable to both steady and transient fuel behavior and is used to analyze 1D spherical, 2D axisymmetric, or 3D geometries. BISON has been applied to a variety of fuel forms including LWR fuel rods, TRISO-coated fuel particles, and metallic fuel in both rod and plate geometries. Code validation is currently in progress, principally by comparison to instrumented LWR fuel rods and other well known fuel performance codes. Results from several assessment cases are reported, with emphasis on fuel centerline temperatures at various stages of fuel life, fission gas release, and clad deformation during pellet clad mechanical interaction (PCMI). BISON comparisons to fuel centerline temperature measurements are very good at beginning of life and reasonable at high burnup. Although limited to date, fission gas release comparisons are very good. Comparisons of rod diameter following significant power ramping are also good and demonstrate BISON’s unique ability to model discrete pellet behavior and accurately predict clad ridging from PCMI.

  1. Sandia National Laboratories: Hydrogen Safety, Codes and Standards

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

    Biofuels Biofuels Publications Biochemical Conversion Program Lignocellulosic Biomass Microalgae Thermochemical Conversion Sign up for our E-Newsletter Required.gif?3.21 Email...

  2. Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT | Department of

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'sEnergyTexas1. FeedstockCLEAN AIR ACTClosedfor

  3. Current Approaches to Safety, Codes and Standards | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'sEnergyTexas1.SpaceFluorControlsEnergyRev.Curiosity Mars

  4. For Safety and Code Officials | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO2: FinalOffers3.pdf0-45.pdf Flash2010-45.pdfFlash2011-43andPropertyFor Early Adopters

  5. Current Approaches to Safety, Codes and Standards | 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 onYouTube YouTube Note: Since the YouTube platformBuildingCoalComplex(GC-72)Columbia GovernmentCumberlandJuneCurrent

  6. Technical Standards, Safety Analysis Toolbox Codes - November 2003 |

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed offOCHCO Overview OCHCOSystems Analysis Success Stories SystemsTara TrujilloDepartment of Energy

  7. DOE Vehicle Technologies Program 2009 Merit Review Report - Safety Codes

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof"WaveInteractionsMaterials | Department of Energy Propulsionand

  8. For Safety and Code Officials | 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 onYouTube YouTube Note: Since the.pdf Flash2006-52.pdf0.pdfDepartment of Energy's Financial Assistance forCost

  9. Safety, Codes and Standards - Basics | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn April 23, 2014, anEnergyDepartmentDepartmentEnergy Performed

  10. Safety, Codes and Standards Technical Publications | 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 onYouTube YouTube Note: Since the.pdfBreakingMay 2015 <Department of iiBiodieselWATER,Program

  11. Safety, Codes, and Standards Fact 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 onYouTube YouTube Note: Since the.pdfBreakingMay 2015 <Department of iiBiodieselWATER,ProgramFuel Cell Technologies

  12. Safety, Codes, and Standards Fact 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 onYouTube YouTube Note: Since the.pdfBreakingMay 2015 <Department of iiBiodieselWATER,ProgramFuel Cell TechnologiesU.S.

  13. Hydrogen Safety, Codes and Standards Challenges | 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 onYouTube YouTube Note: Since the.pdfBreaking of Blythe SolarContamination DetectorofThermochemical WaterEducationCurrent

  14. NREL: Hydrogen and Fuel Cells Research - Safety, Codes, and Standards

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

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

  15. 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

  16. 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.

  17. Pipeline Safety Rule (Tennessee)

    Broader source: Energy.gov [DOE]

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

  18. Dam Safety Program (Maryland)

    Broader source: Energy.gov [DOE]

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

  19. Dam Safety (Delaware)

    Broader source: Energy.gov [DOE]

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

  20. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03T23:59:59.000Z

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

  1. Banner Index Codes The Index code is a data-entry shortcut for the Fund code, Org code, and Program code in Banner

    E-Print Network [OSTI]

    Banner Index Codes The Index code is a data-entry shortcut for the Fund code, Org code, and Program code in Banner Finance (FO-P's). Implementation of the Index has greatly decreased data entry coding ­ Account (object) - Program (FOAP) code numbers on any of your accounting forms (Contracts, Purchase Orders

  2. Fusion safety program Annual report, Fiscal year 1995

    SciTech Connect (OSTI)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J. [and others

    1995-12-01T23:59:59.000Z

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities.

  3. Nuclear Explosive Safety Manual

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

    2009-04-14T23:59:59.000Z

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

  4. DOE handbook electrical safety

    SciTech Connect (OSTI)

    NONE

    1998-01-01T23:59:59.000Z

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

  5. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

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

  6. Sandia National Laboratories: Codes

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

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

  7. Tokamak Systems Code

    SciTech Connect (OSTI)

    Reid, R.L.; Barrett, R.J.; Brown, T.G.; Gorker, G.E.; Hooper, R.J.; Kalsi, S.S.; Metzler, D.H.; Peng, Y.K.M.; Roth, K.E.; Spampinato, P.T.

    1985-03-01T23:59:59.000Z

    The FEDC Tokamak Systems Code calculates tokamak performance, cost, and configuration as a function of plasma engineering parameters. This version of the code models experimental tokamaks. It does not currently consider tokamak configurations that generate electrical power or incorporate breeding blankets. The code has a modular (or subroutine) structure to allow independent modeling for each major tokamak component or system. A primary benefit of modularization is that a component module may be updated without disturbing the remainder of the systems code as long as the imput to or output from the module remains unchanged.

  8. A Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System

    E-Print Network [OSTI]

    &C system in nuclear power plants consists of various safety and non-safety components. This paper triesA Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System Jong-gu Republic of Korea (e-mail: {kirdess, atang34, jbyoo}@konkuk.ac.kr) **Korea Atomic Energy Research Institute

  9. Graph Concatenation for Quantum Codes

    E-Print Network [OSTI]

    Salman Beigi; Isaac Chuang; Markus Grassl; Peter Shor; Bei Zeng

    2010-02-03T23:59:59.000Z

    Graphs are closely related to quantum error-correcting codes: every stabilizer code is locally equivalent to a graph code, and every codeword stabilized code can be described by a graph and a classical code. For the construction of good quantum codes of relatively large block length, concatenated quantum codes and their generalizations play an important role. We develop a systematic method for constructing concatenated quantum codes based on "graph concatenation", where graphs representing the inner and outer codes are concatenated via a simple graph operation called "generalized local complementation." Our method applies to both binary and non-binary concatenated quantum codes as well as their generalizations.

  10. Message Broadcast using Optical Orthogonal Codes in Vehicular Communication Systems

    E-Print Network [OSTI]

    Valaee, Shahrokh

    1 Message Broadcast using Optical Orthogonal Codes in Vehicular Communication Systems Farzad-mail:{frd,behnam,valaee}@comm.utoronto.ca Abstract--Broadcast communication is considered to be es- pecially important in delivering safety messages in vehicular environments. In this paper, we introduce and explore a new method for message broadcast based

  11. 46 Home Power #28 April / May 1992 Code Corner

    E-Print Network [OSTI]

    Johnson, Eric E.

    to the equipment grounding conductor. In the nonstandardized DC world of renewable energy, equipment can be found" of proper grounding including safety, performance, and legal issues were discussed. Grounding a renewable energy system requires a knowledge of what the codes say, how the system is configured, the internal

  12. Environmental Health & Safety

    E-Print Network [OSTI]

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

  13. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

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

  14. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

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

  15. Applications of nuclear data covariances to criticality safety and spent fuel characterization

    SciTech Connect (OSTI)

    Williams, Mark L [ORNL] [ORNL; Ilas, Germina [ORNL] [ORNL; Marshall, William BJ J [ORNL] [ORNL; Rearden, Bradley T [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    Covariance data computational methods and data used for sensitivity and uncertainty analysis within the SCALE nuclear analysis code system are presented. Applications in criticality safety calculations and used nuclear fuel analysis are discussed.

  16. Quantitative Phenomena Identification and Ranking Table (QPIRT) for Reactor Safety Analysis

    E-Print Network [OSTI]

    Yurko, Joseph P.

    Next generation reactor safety analysis codes are intended to make use of advanced numerical methods and higher fidelity models with built-in sensitivity analysis (SA) and uncertainty quantification (UQ) [1]. However, due ...

  17. 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

  18. Center for Intermodal Transportation Safety

    E-Print Network [OSTI]

    Fernandez, Eduardo

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

  19. Safety Manual Prepared by the

    E-Print Network [OSTI]

    Alpay, S. Pamir

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

  20. Protecting Life on Earth

    E-Print Network [OSTI]

    Anderson, Byron P.

    2011-01-01T23:59:59.000Z

    Review: Protecting Life on Earth: An Introduction to thePeter B. Protecting Life on Earth: An Introduction to theof Protecting Life on Earth is “to explain to an intelligent

  1. Sandia National Laboratories: Transportation Safety

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

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

  2. PHENOMENON OF CORROSION AND THE INDUSTRIAL SAFETY

    E-Print Network [OSTI]

    Bensaada S; Bouziane M. T; Mohammedi F; Achour B

    The problem of corrosion has taken nowadays a considerable importance considering the great use more and more of metals and alloys in our modern life. From the economic point of view and safety, the corrosion is a real thread. The replacement of corroded material composes for the industrie a financial burden which is very high. I taws estimated that more than 100 milliards of dollars constituting the yearly lusts caused by the corrosion in the American economy. The corrosion also can be translated by a modification and weakening of mechanical properties of corroded materials, consequentially it can’t fill in all safety its functions to which it is distinated. The aim of this study is to evident links which existed between corrosion and safety of materials and persons.

  3. Reed-Muller Codes: Spherically-Punctured Codes and Decoding Algorithms

    E-Print Network [OSTI]

    Kapralova, Olga

    2013-01-01T23:59:59.000Z

    Linear codes . . . . . . . . . . . . . . . . . . . . . . .3.3 Code parameters . . . . . . . . . . . . . .of linear codes . . . . . . . . . . . . 1.5 Reed-Muller

  4. Safety of Department of Energy-Owned Nuclear Reactors

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

    1986-09-23T23:59:59.000Z

    To establish reactor safety program requirements assure that the safety of each Department of Energy-owned (DOE-owned) reactor is properly analyzed, evaluated, documented, and approved by DOE; and reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate protection for health and safety and will be in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. Cancels Chap. 6 of DOE O 5480.1A. Paragraphs 7b(3), 7e(3) & 8c canceled by DOE O 5480.23 & canceled by DOE N 251.4 of 9-29-95.

  5. Software reliability and safety in nuclear reactor protection systems

    SciTech Connect (OSTI)

    Lawrence, J.D. [Lawrence Livermore National Lab., CA (United States)

    1993-11-01T23:59:59.000Z

    Planning the development, use and regulation of computer systems in nuclear reactor protection systems in such a way as to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Computer Safety and Reliability Group, Lawrence Livermore that investigates different aspects of computer software in reactor National Laboratory, that investigates different aspects of computer software in reactor protection systems. There are two central themes in the report, First, software considerations cannot be fully understood in isolation from computer hardware and application considerations. Second, the process of engineering reliability and safety into a computer system requires activities to be carried out throughout the software life cycle. The report discusses the many activities that can be carried out during the software life cycle to improve the safety and reliability of the resulting product. The viewpoint is primarily that of the assessor, or auditor.

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

    SciTech Connect (OSTI)

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

    1991-07-01T23:59:59.000Z

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

  7. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Batandjieva, B.; Warnecke, E.; Coates, R. [International Atomic Energy Agency, Vienna (Austria)

    2008-01-15T23:59:59.000Z

    Full text of publication follows: ensuring safety during all stages of facility life cycle is a widely recognised responsibility of the operators, implemented under the supervision of the regulatory body and other competent authorities. As the majority of the facilities worldwide are still in operation or shutdown, there is no substantial experience in decommissioning and evaluation of safety during decommissioning in majority of Member States. The need for cooperation and exchange of experience and good practices on ensuring and evaluating safety of decommissioning was one of the outcomes of the Berlin conference in 2002. On this basis during the last three years IAEA initiated a number of international projects that can assist countries, in particular small countries with limited resources. The main IAEA international projects addressing safety during decommissioning are: (i) DeSa Project on Evaluation and Demonstration of Safety during Decommissioning; (ii) R{sup 2}D{sup 2}P project on Research Reactors Decommissioning Demonstration Project; and (iii) Project on Evaluation and Decommissioning of Former Facilities that used Radioactive Material in Iraq. This paper focuses on the DeSa Project activities on (i) development of a harmonised methodology for safety assessment for decommissioning; (ii) development of a procedure for review of safety assessments; (iii) development of recommendations on application of the graded approach to the performance and review of safety assessments; and (iv) application of the methodology and procedure to the selected real facilities with different complexities and hazard potentials (a nuclear power plant, a research reactor and a nuclear laboratory). The paper also outlines the DeSa Project outcomes and planned follow-up activities. It also summarises the main objectives and activities of the Iraq Project and introduces the R{sup 2}D{sup 2} Project, which is a subject of a complementary paper.

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

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

    1998-05-01T23:59:59.000Z

    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.

  9. Universal space-time codes from demultiplexed trellis codes

    E-Print Network [OSTI]

    Kose, Cenk; Wesel, R D

    2006-01-01T23:59:59.000Z

    and A. R. Calderbank, “Space-time codes for high data ratePerformance criteria and code construction,” IEEE Trans.of space–time trellis codes,” IEEE Trans. Commun. , vol. 51,

  10. Relation Between Surface Codes and Hypermap-Homology Quantum Codes

    E-Print Network [OSTI]

    Pradeep Sarvepalli

    2014-03-14T23:59:59.000Z

    Recently, a new class of quantum codes based on hypermaps were proposed. These codes are obtained from embeddings of hypergraphs as opposed to surface codes which are obtained from the embeddings of graphs. It is natural to compare these two classes of codes and their relation to each other. In this context two related questions are addressed in this paper: Can the parameters of hypermap-homology codes be superior to those of surface codes and what is precisely the relation between these two classes of quantum codes? We show that a canonical hypermap code is identical to a surface code while a noncanonical hypermap code can be transformed to a surface code by CNOT gates alone. Our approach is constructive; we construct the related surface code and the transformation involving CNOT gates.

  11. Application of the ASME code in the design of the GA-4 and GA-9 casks

    SciTech Connect (OSTI)

    Mings, W.J. (USDOE Idaho Field Office, Idaho Falls, ID (United States)); Koploy, M.A. (General Atomics, San Diego, CA (United States))

    1992-01-01T23:59:59.000Z

    General Atomics (GA) is developing two spent fuel shipping casks for transport by legal weight truck (LWT). The casks are designed to the loading, environmental conditions and safety requirements defined in Title 10 of the Code of Federal Regulations, Part 71 (10CFR71). To ensure that all components of the cask meet the 10CFR71 rules, GA established structural design criteria for each component based on NRC Regulatory Guides and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). This paper discusses the criteria used for different cask components, how they were applied and the conservatism and safety margins built into the criteria and assumption.

  12. Application of the ASME code in the design of the GA-4 and GA-9 casks

    SciTech Connect (OSTI)

    Mings, W.J. [USDOE Idaho Field Office, Idaho Falls, ID (United States); Koploy, M.A. [General Atomics, San Diego, CA (United States)

    1992-08-01T23:59:59.000Z

    General Atomics (GA) is developing two spent fuel shipping casks for transport by legal weight truck (LWT). The casks are designed to the loading, environmental conditions and safety requirements defined in Title 10 of the Code of Federal Regulations, Part 71 (10CFR71). To ensure that all components of the cask meet the 10CFR71 rules, GA established structural design criteria for each component based on NRC Regulatory Guides and the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). This paper discusses the criteria used for different cask components, how they were applied and the conservatism and safety margins built into the criteria and assumption.

  13. Reactor accident consequence analysis code (MACCS)

    SciTech Connect (OSTI)

    Jow, Hong-Nian; Sprung, J.L.; Chanin, D.I.; Helton, J.C.; Rollstin, J.A. (Sandia National Labs., Albuquerque, NM (USA); Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA); Arizona State Univ., Tempe, AZ (USA); GRAM, Inc., Albuquerque, NM (USA))

    1990-01-01T23:59:59.000Z

    Sandia National Laboratories has been involved in the performance of risk assessments for the US Nuclear Regulatory Commission for more than a decade. As part of this effort, Sandia developed the reactor consequence analysis codes, CRAC2, and more recently, MACCS. CRAC2 is an improved version of CRAC, which was used in the Reactor Safety Study (also known as WASH-1400). MACCS was used in recent risk assessments for five nuclear power plants (NUREG-1150). MACCS incorporates many model improvements over CRAC2. Some of these improvements are discussed. A comparison of results obtained with CRAC2 and MACCS is also presented. 19 refs., 3 tabs.

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

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

    2006-12-27T23:59:59.000Z

    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.

  15. ME 379M-Nuclear Safety and Security ABET EC2000 syllabus

    E-Print Network [OSTI]

    Ben-Yakar, Adela

    ME 379M- Nuclear Safety and Security Page 1 ABET EC2000 syllabus ME 379M Nuclear Safety assessment models and nuclear non-proliferation. Failure classifications, failure modes, effects, and criticality analysis (FMECA), fault and event trees, reliability block diagrams. Specific areas from the code

  16. Water Reactor Safety Research Division. Quarterly progress report, October 1-December 31, 1980

    SciTech Connect (OSTI)

    Cerbone, R.J.; Saha, P.; van Rooyen, D.

    1981-02-01T23:59:59.000Z

    The Water Reactor Safety Research Programs Quarterly Report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: Stress Corrosion Cracking of PWR Steam Generator Tubing, Advanced Code Evaluation, Simulator Improvement Program, and LWR Assessment and Application.

  17. Runtime Detection of C-Style Errors in UPC Code

    SciTech Connect (OSTI)

    Pirkelbauer, P; Liao, C; Panas, T; Quinlan, D

    2011-09-29T23:59:59.000Z

    Unified Parallel C (UPC) extends the C programming language (ISO C 99) with explicit parallel programming support for the partitioned global address space (PGAS), which provides a global memory space with localized partitions to each thread. Like its ancestor C, UPC is a low-level language that emphasizes code efficiency over safety. The absence of dynamic (and static) safety checks allows programmer oversights and software flaws that can be hard to spot. In this paper, we present an extension of a dynamic analysis tool, ROSE-Code Instrumentation and Runtime Monitor (ROSECIRM), for UPC to help programmers find C-style errors involving the global address space. Built on top of the ROSE source-to-source compiler infrastructure, the tool instruments source files with code that monitors operations and keeps track of changes to the system state. The resulting code is linked to a runtime monitor that observes the program execution and finds software defects. We describe the extensions to ROSE-CIRM that were necessary to support UPC. We discuss complications that arise from parallel code and our solutions. We test ROSE-CIRM against a runtime error detection test suite, and present performance results obtained from running error-free codes. ROSE-CIRM is released as part of the ROSE compiler under a BSD-style open source license.

  18. Report number codes

    SciTech Connect (OSTI)

    Nelson, R.N. (ed.)

    1985-05-01T23:59:59.000Z

    This publication lists all report number codes processed by the Office of Scientific and Technical Information. The report codes are substantially based on the American National Standards Institute, Standard Technical Report Number (STRN)-Format and Creation Z39.23-1983. The Standard Technical Report Number (STRN) provides one of the primary methods of identifying a specific technical report. The STRN consists of two parts: The report code and the sequential number. The report code identifies the issuing organization, a specific program, or a type of document. The sequential number, which is assigned in sequence by each report issuing entity, is not included in this publication. Part I of this compilation is alphabetized by report codes followed by issuing installations. Part II lists the issuing organization followed by the assigned report code(s). In both Parts I and II, the names of issuing organizations appear for the most part in the form used at the time the reports were issued. However, for some of the more prolific installations which have had name changes, all entries have been merged under the current name.

  19. Recent advances in the CONTAIN code

    SciTech Connect (OSTI)

    Bergeron, K.D.; Carroll, D.E.; Gelbard, F.; Murata, K.K.; Valdez, G.D.; Washington, K.E.

    1987-10-01T23:59:59.000Z

    An update is given on very recent developments involving CONTAIN, the USNRC's principal mechanistic code for severe accident containment analysis. First, the features are outlined in two major new releases of CONTAIN. Revision 1.06 was released in February; the major improvements include full integration of the CORCON and VANESA models for debris concrete interactions and concomitant aerosol generation, more detailed and more flexible radiation heat transfer options, and a number of minor improvements. The most recent new version of the code is CONTAIN 1.1, which was released in October. The principal new features relate to the Boiling Water Reactor. In particular, working models are included for Pressure Suppression Pools and Safety Relief Valves. In addition, this version of the code has a much-improved treatment of fision product hosting, user-defined material property options, and a number of other improvements. A second major area of progress involves the aerosol models. Previously, numerical diffusion limited the accuracy of the calculation of the concentration of the smallest particles and, there was no accounting for the effects of soluble salts or surface tension on the equilibrium water vapor pressure. All of these problems have now been solved with a stand-alone aerosol modeling code which uses a suite of new numerical approaches. The new methods have been incorporated into CONTAIN. Example calculations are presented. 7 refs., 4 figs., 1 tab.

  20. Quantum stabilizer codes and beyond

    E-Print Network [OSTI]

    Pradeep Kiran Sarvepalli

    2008-10-14T23:59:59.000Z

    The importance of quantum error correction in paving the way to build a practical quantum computer is no longer in doubt. This dissertation makes a threefold contribution to the mathematical theory of quantum error-correcting codes. Firstly, it extends the framework of an important class of quantum codes -- nonbinary stabilizer codes. It clarifies the connections of stabilizer codes to classical codes over quadratic extension fields, provides many new constructions of quantum codes, and develops further the theory of optimal quantum codes and punctured quantum codes. Secondly, it contributes to the theory of operator quantum error correcting codes also called as subsystem codes. These codes are expected to have efficient error recovery schemes than stabilizer codes. This dissertation develops a framework for study and analysis of subsystem codes using character theoretic methods. In particular, this work establishes a close link between subsystem codes and classical codes showing that the subsystem codes can be constructed from arbitrary classical codes. Thirdly, it seeks to exploit the knowledge of noise to design efficient quantum codes and considers more realistic channels than the commonly studied depolarizing channel. It gives systematic constructions of asymmetric quantum stabilizer codes that exploit the asymmetry of errors in certain quantum channels.

  1. WRITTEN INJURY AND ILLNESS PREVENTION PROGRAM Completion of this form indicates that it is the policy of the employer to fully comply with Labor Code

    E-Print Network [OSTI]

    Kolner, Brian H.

    that it is the policy of the employer to fully comply with Labor Code §6401.7(SB 198) and General Industry Safety Order Industry Safety Orders and other Safety Orders that apply to the operation. Review of industry and general materials, boxes, etc., may be left in walkways, inside or outside of the building. 10. Exposure to heavy

  2. Rateless Codes for AVC Models

    E-Print Network [OSTI]

    Sarwate, A D; Gastpar, M

    2010-01-01T23:59:59.000Z

    2004. [7] M. Luby, “LT codes,” in Proc. 43rd Ann. IEEE Symp.8] A. Shokrollahi, “Fountain codes,” in Proc. 41st AllertonChannel capacities for list codes,” J. Appl. Probabil. ,

  3. Unequal Error Protection Turbo Codes

    E-Print Network [OSTI]

    Henkel, Werner

    Unequal Error Protection Turbo Codes Diploma Thesis Neele von Deetzen Arbeitsbereich Nachrichtentechnik School of Engineering and Science Bremen, February 28th, 2005 #12;Unequal Error Protection Turbo Convolutional Codes / Turbo Codes 18 3.1 Structure

  4. LNG Safety Research: FEM3A Model Development

    SciTech Connect (OSTI)

    Iraj A. Salehi

    2004-09-30T23:59:59.000Z

    This quarterly report for DE-FG26-04NT42030 covers a period from July 1, 2004 to September 30, 2004. Activity during this period included preparation of a CD containing the FEM3a FORTRAN code for distribution and organization of an LNG safety workshop. Contract negotiation between GTI and University of Arkansas continued.

  5. Quantum Error Correcting Subsystem Codes From Two Classical Linear Codes

    E-Print Network [OSTI]

    Dave Bacon; Andrea Casaccino

    2006-10-17T23:59:59.000Z

    The essential insight of quantum error correction was that quantum information can be protected by suitably encoding this quantum information across multiple independently erred quantum systems. Recently it was realized that, since the most general method for encoding quantum information is to encode it into a subsystem, there exists a novel form of quantum error correction beyond the traditional quantum error correcting subspace codes. These new quantum error correcting subsystem codes differ from subspace codes in that their quantum correcting routines can be considerably simpler than related subspace codes. Here we present a class of quantum error correcting subsystem codes constructed from two classical linear codes. These codes are the subsystem versions of the quantum error correcting subspace codes which are generalizations of Shor's original quantum error correcting subspace codes. For every Shor-type code, the codes we present give a considerable savings in the number of stabilizer measurements needed in their error recovery routines.

  6. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

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

  7. No Code: Null Programs

    E-Print Network [OSTI]

    Montfort, Nick

    2014-06-05T23:59:59.000Z

    To continue the productive discussion of uninscribed artworks in Craig Dworkin’s No Medium, this report discusses, in detail, those computer programs that have no code, and are thus empty or null. Several specific examples ...

  8. Climate Code Foundation

    E-Print Network [OSTI]

    Barnes, Nick; Jones, David

    2011-07-05T23:59:59.000Z

    Climate Code Foundation - who are we? A non-profit organisation founded in August 2010; our goal is to promote the public understanding of climate science, by increasing the visibility and clarity of the software used in climate science...

  9. Building Energy Code

    Broader source: Energy.gov [DOE]

    Authority for adopting the state energy codes was previously vested in the Energy Security Office of the Department of Commerce (originally the Department of Public Services). In 1999-2000, the...

  10. Aviation Management and Safety

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

    2011-06-15T23:59:59.000Z

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

  11. Dam Safety Program (Florida)

    Broader source: Energy.gov [DOE]

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

  12. Battery Safety Testing

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

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

  13. BNL | ATF Laser Safety

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

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

  14. Coiled Tubing Safety Manual

    SciTech Connect (OSTI)

    Crow, W.

    1999-04-06T23:59:59.000Z

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

  15. Safety Hazards of Batteries

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

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

  16. Pipeline Safety (Maryland)

    Broader source: Energy.gov [DOE]

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

  17. Intrastate Pipeline Safety (Minnesota)

    Broader source: Energy.gov [DOE]

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

  18. Pipeline Safety (South Dakota)

    Broader source: Energy.gov [DOE]

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

  19. Gas Safety Law (Florida)

    Broader source: Energy.gov [DOE]

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

  20. DOE Explosives Safety Manual

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

    1996-03-29T23:59:59.000Z

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

  1. Quantum error control codes

    E-Print Network [OSTI]

    Abdelhamid Awad Aly Ahmed, Sala

    2008-10-10T23:59:59.000Z

    QUANTUM ERROR CONTROL CODES A Dissertation by SALAH ABDELHAMID AWAD ALY AHMED Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY May 2008 Major... Subject: Computer Science QUANTUM ERROR CONTROL CODES A Dissertation by SALAH ABDELHAMID AWAD ALY AHMED Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY...

  2. Modeling and Analysis of a Lunar Space Reactor with the Computer Code RELAP5-3D/ATHENA

    SciTech Connect (OSTI)

    Carbajo, Juan J [ORNL; Qualls, A L [ORNL

    2008-01-01T23:59:59.000Z

    The transient analysis 3-dimensional (3-D) computer code RELAP5-3D/ATHENA has been employed to model and analyze a space reactor of 180 kW(thermal), 40 kW (net, electrical) with eight Stirling engines (SEs). Each SE will generate over 6 kWe; the excess power will be needed for the pumps and other power management devices. The reactor will be cooled by NaK (a eutectic mixture of sodium and potassium which is liquid at ambient temperature). This space reactor is intended to be deployed over the surface of the Moon or Mars. The reactor operating life will be 8 to 10 years. The RELAP5-3D/ATHENA code is being developed and maintained by Idaho National Laboratory. The code can employ a variety of coolants in addition to water, the original coolant employed with early versions of the code. The code can also use 3-D volumes and 3-D junctions, thus allowing for more realistic representation of complex geometries. A combination of 3-D and 1-D volumes is employed in this study. The space reactor model consists of a primary loop and two secondary loops connected by two heat exchangers (HXs). Each secondary loop provides heat to four SEs. The primary loop includes the nuclear reactor with the lower and upper plena, the core with 85 fuel pins, and two vertical heat exchangers (HX). The maximum coolant temperature of the primary loop is 900 K. The secondary loops also employ NaK as a coolant at a maximum temperature of 877 K. The SEs heads are at a temperature of 800 K and the cold sinks are at a temperature of ~400 K. Two radiators will be employed to remove heat from the SEs. The SE HXs surrounding the SE heads are of annular design and have been modeled using 3-D volumes. These 3-D models have been used to improve the HX design by optimizing the flows of coolant and maximizing the heat transferred to the SE heads. The transients analyzed include failure of one or more Stirling engines, trip of the reactor pump, and trips of the secondary loop pumps feeding the HXs of the Stirling engines. Loss of one radiator sink has also been simulated. The effects of reduced gravity on the transients have also been investigated. The transients studied have been used to demonstrate the safety and the operability of the system. The results of the transients will be used to evaluate which transients the system can survive without damage and can continue operating at nominal or reduced power levels for the intended life time of the reactor.

  3. ACTION MEMO: Technical Position on the Use of National Consensus and Building Codes to Meet DOE Order 420. I B.

    Broader source: Energy.gov [DOE]

    The attached technical position on the Use of National Consensus and Building Codes to meet Department of Energy (DOE) Order 420.1b Facility Safety, clarifies the use of national consensus and...

  4. 3698 A. Hernandez-Solis et al. / Nuclear Engineering and Design 241 (2011) 36973706 The need to validate and refine BE codes that are used in

    E-Print Network [OSTI]

    Demazière, Christophe

    to validate and refine BE codes that are used in the predictions of relevant reactor safety parameters, led), and offers a good opportunity to assess the accuracy of thermal­hydraulic codes in predicting, among other of thermal hydraulic codes in predicting radial and axial assembly void dis- tributions, under both steady

  5. WEB-BASED RESOURCES ENHANCE HYDROGEN SAFETY KNOWLEDGE

    SciTech Connect (OSTI)

    Weiner, Steven C.; Fassbender, Linda L.; Blake, Chad; Aceves, Salvador; Somerday, Brian P.; Ruiz, Antonio

    2013-06-18T23:59:59.000Z

    The U.S. Department of Energy’s Fuel Cell Technologies Program addresses key technical challenges and institutional barriers facing the development and deployment of hydrogen and fuel cell technologies with the goal of decreasing dependence on oil, reducing carbon emissions and enabling reliable power generation. The Safety, Codes & Standards program area seeks to develop and implement the practices and procedures that will ensure safety in the operation, handling and use of hydrogen and hydrogen systems for all projects and utilize these practices and lessons learned to promote the safe use of hydrogen. Enabling the development of codes and standards for the safe use of hydrogen in energy applications and facilitating the development and harmonization of international codes and standards are integral to this work.

  6. Nested Quantum Error Correction Codes

    E-Print Network [OSTI]

    Zhuo Wang; Kai Sun; Hen Fan; Vlatko Vedral

    2009-09-28T23:59:59.000Z

    The theory of quantum error correction was established more than a decade ago as the primary tool for fighting decoherence in quantum information processing. Although great progress has already been made in this field, limited methods are available in constructing new quantum error correction codes from old codes. Here we exhibit a simple and general method to construct new quantum error correction codes by nesting certain quantum codes together. The problem of finding long quantum error correction codes is reduced to that of searching several short length quantum codes with certain properties. Our method works for all length and all distance codes, and is quite efficient to construct optimal or near optimal codes. Two main known methods in constructing new codes from old codes in quantum error-correction theory, the concatenating and pasting, can be understood in the framework of nested quantum error correction codes.

  7. Accumulate-Repeat-Accumulate Codes: Systematic Codes Achieving the Binary

    E-Print Network [OSTI]

    Sason, Igal

    Accumulate-Repeat-Accumulate Codes: Systematic Codes Achieving the Binary Erasure Channel Capacity@ee.technion.ac.il Abstract The paper introduces ensembles of accumulate-repeat-accumulate (ARA) codes which asymp- totically by the first capacity-achieving ensembles of ir- regular repeat-accumulate (IRA) codes with bounded complexity

  8. Code: A Lightweight and Flexible Mobile Code Toolkit

    E-Print Network [OSTI]

    Picco, Gian Pietro

    evaluation of mobile code technology does not exist yet, some studies already evidenced that the powerful of client­server and mobile code in reducing the network traffic generated by management. The theoretical¯Code: A Lightweight and Flexible Mobile Code Toolkit Gian Pietro Picco Dip. Automatica e

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

    E-Print Network [OSTI]

    Machel, Hans

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

  10. 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...

  11. 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.

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

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

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

  13. University Life Strategic Plan UNIVERSITY LIFE

    E-Print Network [OSTI]

    for the demands of work, social responsibility, and life in an ever-changing global society. Through a range well-being, post-graduation success Increased retention and timely degree completion Increased Engagement) #12;2 University Life is committed to preparing students for the demands of work, social

  14. Integrated Safety Management Policy

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

    2011-04-25T23:59:59.000Z

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

  15. SECURITY AND FIRE SAFETY

    E-Print Network [OSTI]

    Barrash, Warren

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

  16. Safety of Accelerator Facilities

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

    2004-07-23T23:59:59.000Z

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

  17. Safety of Accelerator Facilities

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

    2011-07-21T23:59:59.000Z

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

  18. Safety of Accelerator Facilities

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

    2001-01-08T23:59:59.000Z

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

  19. Department of Energy Office of Nuclear Safety and Environmental Policy Technical Position NSEP-TP-2007- 1, Technical Position on the Requirement in DOE 0 420.1B to Use National Consensus Industry Standards and the Model Building CodesTechnical Position NS

    Broader source: Energy.gov [DOE]

    All new construction required to follow the provisions of Department of Energy(DOE) Order 420. lB, Facility Safety, must comply with national consensus industrystandards and the model building...

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

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-03-01T23:59:59.000Z

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

  1. K Basin safety analysis

    SciTech Connect (OSTI)

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

    1994-12-16T23:59:59.000Z

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

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

    E-Print Network [OSTI]

    Machel, Hans

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

  3. Safety of Hydrogen Systems Installed in Outdoor Enclosures

    SciTech Connect (OSTI)

    Barilo, Nick F.

    2013-11-06T23:59:59.000Z

    The Hydrogen Safety Panel brings a broad cross-section of expertise from the industrial, government, and academic sectors to help advise the U.S. Department of Energy’s (DOE) Fuel Cell Technologies Office through its work in hydrogen safety, codes, and standards. The Panel’s initiatives in reviewing safety plans, conducting safety evaluations, identifying safety-related technical data gaps, and supporting safety knowledge tools and databases cover the gamut from research and development to demonstration and deployment. The Panel’s recent work has focused on the safe deployment of hydrogen and fuel cell systems in support of DOE efforts to accelerate fuel cell commercialization in early market applications: vehicle refueling, material handling equipment, backup power for warehouses and telecommunication sites, and portable power devices. This paper resulted from observations and considerations stemming from the Panel’s work on early market applications. This paper focuses on hydrogen system components that are installed in outdoor enclosures. These enclosures might alternatively be called “cabinets,” but for simplicity, they are all referred to as “enclosures” in this paper. These enclosures can provide a space where a flammable mixture of hydrogen and air might accumulate, creating the potential for a fire or explosion should an ignition occur. If the enclosure is large enough for a person to enter, and ventilation is inadequate, the hydrogen concentration could be high enough to asphyxiate a person who entered the space. Manufacturers, users, and government authorities rely on requirements described in codes to guide safe design and installation of such systems. Except for small enclosures used for hydrogen gas cylinders (gas cabinets), fuel cell power systems, and the enclosures that most people would describe as buildings, there are no hydrogen safety requirements for these enclosures, leaving gaps that must be addressed. This paper proposes that a technical basis be developed to enable code bodies to write requirements for the range of enclosures from the smallest to the largest.

  4. 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.

  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. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

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

  7. Normalization of Process Safety Metrics

    E-Print Network [OSTI]

    Wang, Mengtian

    2012-10-19T23:59:59.000Z

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

  8. Child Passenger Safety http://passengersafety.tamu.edu

    E-Print Network [OSTI]

    in the United States in motor vehicle crashes during 2011. · Minority children are more likely to be fatally injured in car crashes than white children. · Rural areas have a higher crash incidence and death rate Safety Project at the Texas A&M AgriLife Extension Service works to reduce deaths and injuries from motor

  9. MHD Generation Code

    E-Print Network [OSTI]

    Frutos-Alfaro, Francisco

    2015-01-01T23:59:59.000Z

    A program to generate codes in Fortran and C of the full Magnetohydrodynamic equations is shown. The program used the free computer algebra system software REDUCE. This software has a package called EXCALC, which is an exterior calculus program. The advantage of this program is that it can be modified to include another complex metric or spacetime. The output of this program is modified by means of a LINUX script which creates a new REDUCE program to manipulate the MHD equations to obtain a code that can be used as a seed for a MHD code for numerical applications. As an example, we present part of output of our programs for Cartesian coordinates and how to do the discretization.

  10. Environmental Health and Safety Department

    E-Print Network [OSTI]

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

  11. Safety Culture in Nuclear Installations

    Broader source: Energy.gov [DOE]

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

  12. Gordon wins NNSA Safety Professional

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

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

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

    E-Print Network [OSTI]

    Eisen, Michael

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

  14. Cyclic simplex coded OTDR SNR enhancement of coded optical time domain reflectometry using cyclic simplex codes

    E-Print Network [OSTI]

    Park, Namkyoo

    Cyclic simplex coded OTDR SNR enhancement of coded optical time domain reflectometry using cyclic simplex codes *, , , e-mail : nkpark@plaza.snu.ac.kr Abstract: We propose and experimentally demonstrate the performance improvement of a coded optical time domain reflectometry using cyclic simplex

  15. Extended quantum color coding

    SciTech Connect (OSTI)

    Hayashi, A.; Hashimoto, T.; Horibe, M. [Department of Applied Physics, Fukui University, Fukui 910-8507 (Japan)

    2005-01-01T23:59:59.000Z

    The quantum color coding scheme proposed by Korff and Kempe [e-print quant-ph/0405086] is easily extended so that the color coding quantum system is allowed to be entangled with an extra auxiliary quantum system. It is shown that in the extended scheme we need only {approx}2{radical}(N) quantum colors to order N objects in large N limit, whereas {approx}N/e quantum colors are required in the original nonextended version. The maximum success probability has asymptotics expressed by the Tracy-Widom distribution of the largest eigenvalue of a random Gaussian unitary ensemble (GUE) matrix.

  16. CONCEPT computer code

    SciTech Connect (OSTI)

    Delene, J.

    1984-01-01T23:59:59.000Z

    CONCEPT is a computer code that will provide conceptual capital investment cost estimates for nuclear and coal-fired power plants. The code can develop an estimate for construction at any point in time. Any unit size within the range of about 400 to 1300 MW electric may be selected. Any of 23 reference site locations across the United States and Canada may be selected. PWR, BWR, and coal-fired plants burning high-sulfur and low-sulfur coal can be estimated. Multiple-unit plants can be estimated. Costs due to escalation/inflation and interest during construction are calculated.

  17. Safety Assessment of PowerBeam Flywheel Technology

    SciTech Connect (OSTI)

    Starbuck, J Michael [ORNL; Hansen, James Gerald [ORNL

    2009-11-01T23:59:59.000Z

    The greatest technical challenge facing the developer of vehicular flywheel systems is the issue of safety. The PowerBeam flywheel system concept, developed by HyKinesys Inc., employs a pair of high aspect ratio, counter-rotating flywheels to provide surge power for hybrid vehicle applications. The PowerBeam approach to safety is to design flywheels conservatively so as to avoid full rotor burst failure modes. A conservative point design was sized for use in a mid-size sedan such as a Chevrolet Malibu. The PowerBeam rotor rims were designed with a steel tube covered by a carbon fiber reinforced composite tube. ORNL conducted rotor design analyses using both nested ring and finite element analysis design codes. The safety factor of the composite material was 7, while that of the steel was greater than 3. The design exceeded the PNGV recommendation for a safety factor of at least 4 for composite material to prevent flywheel burst.

  18. Fast reactor safety: proceedings of the international topical meeting. Volume 2. [R

    SciTech Connect (OSTI)

    Not Available

    1985-07-01T23:59:59.000Z

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 2 include: safety design concepts; operational transient experiments; analysis of seismic and external events; HCDA-related codes, analysis, and experiments; sodium fires; instrumentation and control/PPS design; whole-core accident analysis codes; and impact of safety design considerations on future LMFBR developments.

  19. Housing and Residential Life

    E-Print Network [OSTI]

    Fernandez, Eduardo

    1 Housing and Residential Life Guidebook 2014-2015 LivingCampus #12;2 fau.edu/housing Welcome! The Housing & Residential Life staff is excited that you've moved home! Florida Atlantic University residence halls and apartments are your home for the 2014-2015 school year. The Housing & Residential Life staff

  20. Life Cycle Cost Estimate

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

    1997-03-28T23:59:59.000Z

    Life-cycle costs (LCCs) are all the anticipated costs associated with a project or program alternative throughout its life. This includes costs from pre-operations through operations or to the end of the alternative.This chapter discusses life cycle costs and the role they play in planning.

  1. Globalization of ASME Nuclear Codes and Standards

    SciTech Connect (OSTI)

    Swayne, Rick [Reedy Engineering, 3425 South Bascom Ave. Suite E, Campbell, CA 95008 (United States); Erler, Bryan A. [Erler Engineering, Ltd., North Vernon, Indiana (United States)

    2006-07-01T23:59:59.000Z

    With the globalization of the nuclear industry, it is clear that the reactor suppliers are based in many countries around the world (such as United States, France, Japan, Canada, South Korea, South Africa) and they will be marketing their reactors to many countries around the world (such as US, China, South Korea, France, Canada, Finland, Taiwan). They will also be fabricating their components in many different countries around the world. With this situation, it is clear that the requirements of ASME Nuclear Codes and Standards need to be adjusted to accommodate the regulations, fabricating processes, and technology of various countries around the world. It is also very important for the American Society of Mechanical Engineers (ASME) to be able to assure that products meeting the applicable ASME Code requirements will provide the same level of safety and quality assurance as those products currently fabricated under the ASME accreditation process. To do this, many countries are in the process of establishing or changing their regulations, and it is important for ASME to interface with the appropriate organizations in those countries, in order to ensure there is effective use of ASME Codes and standards around the world. (authors)

  2. Overview of the CONTAIN LMR code

    SciTech Connect (OSTI)

    Carroll, D.E.

    1988-01-01T23:59:59.000Z

    The use of containments in proposed US Liquid Metal Reactors (LMR) will require that a computational tool be available for safety analysis. As a result of an international cooperative effort, such a tool has been produced in the CONTAIN-LMR computer code. This is a version of the CONTAIN code that has been enhanced with extra capabilities for LMR applications. CONTAIN is the NRC's best-estimate code for the evaluation of the conditions that may exist inside a reactor containment building during a severe accident. Included in the phenomena modeled are thermal-hydraulics, radiant and convective heat transfer, aerosol loading and transient response, fission product transport and heating effects, and interactions of sodium and corium with the containment atmosphere and structures. CONTAIN-LMR includes models for sodium-concrete interactions, debris bed phenomena and other LMR-specific models in an integrated manner. This paper summarizes the current state of CONTAIN-LMR. A brief description of the physical models is presented. As an example of model integration in CONTAIN-LMR, recent work on the debris bed models will be discussed. Recent applications of CONTAIN-LMR are discussed. 9 refs., 5 figs.

  3. Perceptions of quality of life: gender differences across the life course

    E-Print Network [OSTI]

    Scott, Jacqueline; Plagnol, Anke C.; Nolan, Jane

    2010-01-01T23:59:59.000Z

    : home comforts, roof over head, regular meals, domestic hygiene. 8. Employment: employment, job satisfaction. 9. Misc other: Safety, lack of fear, neighbours, pets, other relationships, other positive mentions, other. 10. Freedom: freedom... , independence. 11. Time self: time for self, not too overworked, life in balance, sleep, no stress. 12. Other material: consumption, shopping, getting new things, car, transport, education (own, children’s, standard of system in general), other material...

  4. Advanced transport codes for nuclear thermal rocket analysis

    SciTech Connect (OSTI)

    Perry, R.T.; Buksa, J.J.; Houts, M.G. (Los Alamos National Lab., NM (United States))

    1992-01-01T23:59:59.000Z

    Nuclear thermal rocket (NTR) propulsion systems will enable the manned exploration of our solar system. In the context of current and future safety standards and environmental constraints, the likelihood of any large nuclear engine testing program similar in scope to the ROVER/NERVA program is remote. Consequently, extensive computational verification of the safety, reliability, and performance of the reactor and spacecraft will be required. Fortunately, the development of new codes coupled with computer hardware advances will make this feasible and cost-effective. Although coupled-phenomena and separate-effects modeling at the component and system levels will be necessary, this paper addresses only radiation transport modeling of NTR systems and reviews the status and applicability of several codes that Los Alamos National Laboratory (LANL) is using.

  5. Coding for Transmission Coding for Compression Bonus Section CMPSCI 240: Reasoning about Uncertainty

    E-Print Network [OSTI]

    McGregor, Andrew

    Coding for Transmission Coding for Compression Bonus Section CMPSCI 240: Reasoning about: April 29, 2014 #12;Coding for Transmission Coding for Compression Bonus Section Information Theory. #12;Coding for Transmission Coding for Compression Bonus Section Encoding Messages with Redundancy

  6. Lecture notes for criticality safety

    SciTech Connect (OSTI)

    Fullwood, R.

    1992-03-01T23:59:59.000Z

    These lecture notes for criticality safety are prepared for the training of Department of Energy supervisory, project management, and administrative staff. Technical training and basic mathematics are assumed. The notes are designed for a two-day course, taught by two lecturers. Video tapes may be used at the options of the instructors. The notes provide all the materials that are necessary but outside reading will assist in the fullest understanding. The course begins with a nuclear physics overview. The reader is led from the macroscopic world into the microscopic world of atoms and the elementary particles that constitute atoms. The particles, their masses and sizes and properties associated with radioactive decay and fission are introduced along with Einstein's mass-energy equivalence. Radioactive decay, nuclear reactions, radiation penetration, shielding and health-effects are discussed to understand protection in case of a criticality accident. Fission, the fission products, particles and energy released are presented to appreciate the dangers of criticality. Nuclear cross sections are introduced to understand the effectiveness of slow neutrons to produce fission. Chain reactors are presented as an economy; effective use of the neutrons from fission leads to more fission resulting in a power reactor or a criticality excursion. The six-factor formula is presented for managing the neutron budget. This leads to concepts of material and geometric buckling which are used in simple calculations to assure safety from criticality. Experimental measurements and computer code calculations of criticality are discussed. To emphasize the reality, historical criticality accidents are presented in a table with major ones discussed to provide lessons-learned. Finally, standards, NRC guides and regulations, and DOE orders relating to criticality protection are presented.

  7. Status of the MELTSPREAD-1 computer code for the analysis of transient spreading of core debris melts

    SciTech Connect (OSTI)

    Farmer, M.T.; Sienicki, J.J.; Spencer, B.W.; Chu, C.C.

    1992-01-01T23:59:59.000Z

    A transient, one dimensional, finite difference computer code (MELTSPREAD-1) has been developed to predict spreading behavior of high temperature melts flowing over concrete and/or steel surfaces submerged in water, or without the effects of water if the surface is initially dry. This paper provides a summary overview of models and correlations currently implemented in the code, code validation activities completed thus far, LWR spreading-related safety issues for which the code has been applied, and the status of documentation for the code.

  8. Status of the MELTSPREAD-1 computer code for the analysis of transient spreading of core debris melts

    SciTech Connect (OSTI)

    Farmer, M.T.; Sienicki, J.J.; Spencer, B.W.; Chu, C.C.

    1992-04-01T23:59:59.000Z

    A transient, one dimensional, finite difference computer code (MELTSPREAD-1) has been developed to predict spreading behavior of high temperature melts flowing over concrete and/or steel surfaces submerged in water, or without the effects of water if the surface is initially dry. This paper provides a summary overview of models and correlations currently implemented in the code, code validation activities completed thus far, LWR spreading-related safety issues for which the code has been applied, and the status of documentation for the code.

  9. 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

  10. Safety Criteria and Safety Lifecycle for Artificial Neural Networks

    E-Print Network [OSTI]

    Kelly, Tim

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

  11. The Woodland Carbon Code

    E-Print Network [OSTI]

    The Woodland Carbon Code While society must continue to make every effort to reduce greenhouse gas a role by removing carbon dioxide from the atmosphere. The potential of woodlands to soak up carbon to help compensate for their carbon emissions. But before investing in such projects, people want to know

  12. Chaotic Turbo Codes

    E-Print Network [OSTI]

    S. Adrian Barbulescu; Andrew Guidi; Steven S. Pietrobon

    This paper describes a new class of codes, chaotic turbo codes. They were born from a symbiosis between a chaotical digital encoder and a turbo code. This paper investigates the most important properties of both chaotic digital encoders and turbo encoders in order to understand how the two complement each other. A Chaotic Turbo Encoder is then described and initial results will be presented. I. INTRODUCTION A chaotic digital encoder was defined for the first time in [1] as a non--linear digital filter with finite precision (8 bits) which behaves in a quasi--chaotic fashion, both with zero and nonzero input sequences. A simple chaotic encoder is shown in Figure 1 [1]. D Y k X k LCIRC D Figure 1: Chaotic Digital Encoder Mapper L L L L L L 1 The main features of chaotic digital encoders that are used in this paper are: # The system is digital which makes possible its integration with a turbo code. # The output of a chaotic digital encoder with arbitrary inputs has a broad...

  13. Laser Safety Management Policy Statement ............................................................................................................1

    E-Print Network [OSTI]

    Davidson, Fordyce A.

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

  14. Aviation Management and Safety

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

    2011-06-15T23:59:59.000Z

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

  15. Carbon Monoxide Safety Tips

    E-Print Network [OSTI]

    Shaw, Bryan W.; Garcia, Monica L.

    1999-07-26T23:59:59.000Z

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

  16. Dam Safety Regulation (Mississippi)

    Broader source: Energy.gov [DOE]

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

  17. High Voltage Safety Act

    Broader source: Energy.gov [DOE]

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

  18. Packaging and Transportation Safety

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

    1995-09-27T23:59:59.000Z

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

  19. Packaging and Transportation Safety

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

    1995-09-27T23:59:59.000Z

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

  20. Packaging and Transportation Safety

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

    1996-10-02T23:59:59.000Z

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

  1. Promulgating Nuclear Safety Requirements

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

    1996-05-15T23:59:59.000Z

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

  2. 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,...

  3. Nuclear Explosive Safety

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

    2015-01-26T23:59:59.000Z

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

  4. Nuclear Explosive Safety

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

    2014-07-10T23:59:59.000Z

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

  5. Complete Experiment Safety Documentation

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

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

  6. Safety | Argonne National Laboratory

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

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

  7. Nuclear Safety (Pennsylvania)

    Broader source: Energy.gov [DOE]

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

  8. Nuclear Explosive Safety

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

    2006-06-12T23:59:59.000Z

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

  9. Erasure Techniques in MRD codes

    E-Print Network [OSTI]

    W. B. Vasantha Kandasamy; Florentin Smarandache; R. Sujatha; R. S. Raja Durai

    2012-05-03T23:59:59.000Z

    This book is organized into six chapters. The first chapter introduces the basic algebraic structures essential to make this book a self contained one. Algebraic linear codes and their basic properties are discussed in chapter two. In chapter three the authors study the basic properties of erasure decoding in maximum rank distance codes. Some decoding techniques about MRD codes are described and discussed in chapter four of this book. Rank distance codes with complementary duals and MRD codes with complementary duals are introduced and their applications are discussed. Chapter five introduces the notion of integer rank distance codes. The final chapter introduces some concatenation techniques.

  10. Safety Basis Report

    SciTech Connect (OSTI)

    R.J. Garrett

    2002-01-14T23:59:59.000Z

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

  11. REDUCED-COMPLEXITY DECODING FOR CONCATENATED CODES BASED ON RECTANGULAR PARITY-CHECK CODES AND TURBO CODES

    E-Print Network [OSTI]

    Wong, Tan F.

    AND TURBO CODES John M. Shea and Tan F. Wong University of Florida Department of Electrical and Computer-check code (RPCC) with a turbo code. These concatenated codes are referred to as RPCC+turbo codes. RPCC+turbo codes have been shown to significantly outperform turbo codes in several scenarios [1],[2]. One

  12. Radiation Safety Annual Refresher Training

    E-Print Network [OSTI]

    Thomas, David D.

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

  13. 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

  14. School of Forest Safety Training

    E-Print Network [OSTI]

    Thomas, Andrew

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

  15. Coded modulation with Low Density Parity Check codes

    E-Print Network [OSTI]

    Narayanaswami, Ravi

    2001-01-01T23:59:59.000Z

    This thesis proposes the design of Low Density Parity Check (LDPC) codes for cases where coded modulation is used. We design these codes by extending the idea of Density Evolution (DE) that has been introduced as a powerful tool to analyze LDPC...

  16. Generating Code for High-Level Operations through Code Composition

    E-Print Network [OSTI]

    Generating Code for High-Level Operations through Code Composition James M. Stichnoth August 1997 of the authors and should not be interpreted as necessarily representing the official policies or endorsements: Compilers, code generation, parallelism, communication generation #12;Abstract A traditional compiler

  17. Nuclear criticality safety tools in the Chernobyl-4 accident analysis

    SciTech Connect (OSTI)

    Landeyro, P.A.

    1988-01-01T23:59:59.000Z

    The collaboration with the Italian Safety Authority (DISP), started in July 1986, has the aim of studying, from a neutronic point of view, the possible initiator event and the accident dynamics in unit four of the Chernobly nuclear power plant. This report was produced within the framework of that collaboration. A main condition of the present work was making use of standard calculational methods employed in nuclear criticality safety analysis. This means that the neutron multiplication factor calculation should be made with the modules and the cross-section libraries of the SCALE system or in any case with some KENO IV version and the burnup calculation with the ORIGEN code.

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

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

    2010-04-08T23:59:59.000Z

    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. Admin Chg 2, dated 6-12-13, cancels DOE G 424.1-1B Admin Chg 1.

  19. Course Code: Course Title

    E-Print Network [OSTI]

    Painter, Kevin

    which encompasses the software development lifecycle To enable students to reinforce their knowledge and knowledge of the various development and programming paradigms, software development life-cycles, teamwork To build students understanding, knowledge and skills in teamwork, software development in groups

  20. Multiclass learning with simplex coding

    E-Print Network [OSTI]

    Mroueh, Youssef

    In this paper we discuss a novel framework for multiclass learning, defined by a suitable coding/decoding strategy, namely the simplex coding, that allows us to generalize to multiple classes a relaxation approach commonly ...

  1. Distributed control of coded networks

    E-Print Network [OSTI]

    Zhao, Fang, Ph. D. Massachusetts Institute of Technology

    2010-01-01T23:59:59.000Z

    The introduction of network coding has the potential to revolutionize the way people operate networks. For the benefits of network coding to be realized, distributed solutions are needed for various network problems. In ...

  2. Nevada Energy Code for Buildings

    Broader source: Energy.gov [DOE]

    ''Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  3. Final Technical Report: Hydrogen Codes and Standards Outreach

    SciTech Connect (OSTI)

    Hall, Karen I.

    2007-05-12T23:59:59.000Z

    This project contributed significantly to the development of new codes and standards, both domestically and internationally. The NHA collaborated with codes and standards development organizations to identify technical areas of expertise that would be required to produce the codes and standards that industry and DOE felt were required to facilitate commercialization of hydrogen and fuel cell technologies and infrastructure. NHA staff participated directly in technical committees and working groups where issues could be discussed with the appropriate industry groups. In other cases, the NHA recommended specific industry experts to serve on technical committees and working groups where the need for this specific industry expertise would be on-going, and where this approach was likely to contribute to timely completion of the effort. The project also facilitated dialog between codes and standards development organizations, hydrogen and fuel cell experts, the government and national labs, researchers, code officials, industry associations, as well as the public regarding the timeframes for needed codes and standards, industry consensus on technical issues, procedures for implementing changes, and general principles of hydrogen safety. The project facilitated hands-on learning, as participants in several NHA workshops and technical meetings were able to experience hydrogen vehicles, witness hydrogen refueling demonstrations, see metal hydride storage cartridges in operation, and view other hydrogen energy products.

  4. HUDU: The Hanford Unified Dose Utility computer code

    SciTech Connect (OSTI)

    Scherpelz, R.I.

    1991-02-01T23:59:59.000Z

    The Hanford Unified Dose Utility (HUDU) computer program was developed to provide rapid initial assessment of radiological emergency situations. The HUDU code uses a straight-line Gaussian atmospheric dispersion model to estimate the transport of radionuclides released from an accident site. For dose points on the plume centerline, it calculates internal doses due to inhalation and external doses due to exposure to the plume. The program incorporates a number of features unique to the Hanford Site (operated by the US Department of Energy), including a library of source terms derived from various facilities' safety analysis reports. The HUDU code was designed to run on an IBM-PC or compatible personal computer. The user interface was designed for fast and easy operation with minimal user training. The theoretical basis and mathematical models used in the HUDU computer code are described, as are the computer code itself and the data libraries used. Detailed instructions for operating the code are also included. Appendices to the report contain descriptions of the program modules, listings of HUDU's data library, and descriptions of the verification tests that were run as part of the code development. 14 refs., 19 figs., 2 tabs.

  5. Confocal coded aperture imaging

    DOE Patents [OSTI]

    Tobin, Jr., Kenneth William (Harriman, TN); Thomas, Jr., Clarence E. (Knoxville, TN)

    2001-01-01T23:59:59.000Z

    A method for imaging a target volume comprises the steps of: radiating a small bandwidth of energy toward the target volume; focusing the small bandwidth of energy into a beam; moving the target volume through a plurality of positions within the focused beam; collecting a beam of energy scattered from the target volume with a non-diffractive confocal coded aperture; generating a shadow image of said aperture from every point source of radiation in the target volume; and, reconstructing the shadow image into a 3-dimensional image of the every point source by mathematically correlating the shadow image with a digital or analog version of the coded aperture. The method can comprise the step of collecting the beam of energy scattered from the target volume with a Fresnel zone plate.

  6. MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) code description and User's Manual

    SciTech Connect (OSTI)

    Avci, H.I.; Raghuram, S.; Baybutt, P.

    1985-04-01T23:59:59.000Z

    A new computer code called MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) has been developed to replace the CORRAL-2 computer code which was written for the Reactor Safety Study (WASH-1400). This report is a User's Manual for MATADOR. MATADOR is intended for use in system risk studies to analyze radionuclide transport and deposition in reactor containments. The principal output of the code is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and by engineered safety systems such as sprays. It is capable of analyzing the behavior of radionuclides existing either as vapors or aerosols in the containment. The code requires input data on the source terms into the containment, the geometry of the containment, and thermal-hydraulic conditions in the containment.

  7. Travel Codes Traveler Is Employee

    E-Print Network [OSTI]

    Arnold, Jonathan

    Travel Codes Traveler Is Employee: 64100-Domestic Travel 64150-Mileage 64200-International Travel Supplies & Expense Codes 71410-Office Supplies 71430-Lab/Research Supplies (dollar value of each item less Charges Equipment Codes 84320-Equipment (non-computer & peripherals) with a cost of $5,000.00 or more per

  8. Rotationally invariant multilevel block codes

    E-Print Network [OSTI]

    Kulandaivelu, Anita

    1993-01-01T23:59:59.000Z

    The objective of this thesis is to evaluate the performance of block codes that are designed to be rotationally invariant, in a multilevel coding scheme, over a channel modelled to be white gaussian noise. Also, the use of non-binary codes...

  9. Design of proximity detecting codes

    E-Print Network [OSTI]

    Perisetty, Srinivas

    1997-01-01T23:59:59.000Z

    delay insensitive, codes like unordered codes have been proposed. Although these codes are delay insensitive, the receiver still has to wait for all the 1s in the transmitted data to be received before sending an acknowledge signal to the sender. A new...

  10. Code for Hydrogen Hydrogen Pipeline

    E-Print Network [OSTI]

    #12;2 Code for Hydrogen Pipelines Hydrogen Pipeline Working Group Workshop Augusta, Georgia August development · Charge from BPTCS to B31 Standards Committee for Hydrogen Piping/Pipeline code development · B31.12 Status & Structure · Hydrogen Pipeline issues · Research Needs · Where Do We Go From Here? #12;4 Code

  11. Energy Codes and Standards: Facilities

    SciTech Connect (OSTI)

    Bartlett, Rosemarie; Halverson, Mark A.; Shankle, Diana L.

    2007-01-01T23:59:59.000Z

    Energy codes and standards play a vital role in the marketplace by setting minimum requirements for energy-efficient design and construction. They outline uniform requirements for new buildings as well as additions and renovations. This article covers basic knowledge of codes and standards; development processes of each; adoption, implementation, and enforcement of energy codes and standards; and voluntary energy efficiency programs.

  12. PERFORMANCE EVALUATION OF TURBO CODES

    E-Print Network [OSTI]

    Alajaji, Fady

    PERFORMANCE EVALUATION OF TURBO CODES by Guangchong Zhu A project submitted to the Department named ``Turbo codes'' which claims an extraordinary performance with reasonable decoding complexity. In this project, we begin with a study on the structure and principle of Turbo codes. We then investigate

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

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

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

  14. Nuclear safety | Princeton Plasma Physics Lab

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

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

  15. Southeast Energy Efficiency Alliance's Building Energy Codes...

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

    Southeast Energy Efficiency Alliance's Building Energy Codes Project Southeast Energy Efficiency Alliance's Building Energy Codes Project Building Codes Project for the 2013...

  16. 2013 Reporting Unit Codes | Department of Energy

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

    2013 Reporting Unit Codes 2013 Reporting Unit Codes CFC Reporting Unit Codes 2013.pdf More Documents & Publications EA-0372: Final Environmental Assessment Alignment: Achieving...

  17. Error Floors of LDPC Codes and Related Topics

    E-Print Network [OSTI]

    Butler, Brian K.

    Code . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2.2 LDPC Codes . . . . . . . .2.1 Binary Linear Block Codes . . . . . . .

  18. DOE explosives safety manual

    SciTech Connect (OSTI)

    Not Available

    1991-10-01T23:59:59.000Z

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

  19. AG-325 (11/12) Texas A&M AgriLife

    E-Print Network [OSTI]

    AG-325 (11/12) Texas A&M AgriLife Administrative Services ­ Inventory/Property Texas AgriLife Research Building Record Texas A&M University ­ Office of Facilities Coordination Building Number: Building ­ Lightweight Metal Walls 8 ­ Glass (Greenhouse) Location Codes: A1 ­ Main Campus A3 ­ Airport Area B1 ­ West

  20. Pressure Safety of JLAB 12GeV Upgrade Cryomodule

    SciTech Connect (OSTI)

    Cheng, Gary [JLAB; Wiseman, Mark A. [JLAB; Daly, Ed [JLAB

    2009-11-01T23:59:59.000Z

    This paper reviews pressure safety considerations, per the US Department of Energy (DOE) 10CFR851 Final Rule [1], which are being implemented during construction of the 100 Megavolt Cryomodule (C100 CM) for Jefferson Lab’s 12 GeV Upgrade Project. The C100 CM contains several essential subsystems that require pressure safety measures: piping in the supply and return end cans, piping in the thermal shield and the helium headers, the helium vessel assembly which includes high RRR niobium cavities, the end cans, and the vacuum vessel. Due to the vessel sizes and pressure ranges, applicable national consensus code rules are applied. When national consensus codes are not applicable, equivalent design and fabrication approaches are identified and implemented. Considerations for design, material qualification, fabrication, inspection and examination are summarized. In addition, JLAB’s methodologies for implementation of the 10 CFR 851 requirements are described.

  1. Seismic Safety Guide

    SciTech Connect (OSTI)

    Eagling, D.G. (ed.)

    1983-09-01T23:59:59.000Z

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

  2. Safety for Users

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

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

  3. Safety in Numbers

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

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

  4. Safety aspects of EB melting

    SciTech Connect (OSTI)

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

    1994-12-31T23:59:59.000Z

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

  5. Genetic Algorithms Artificial Life

    E-Print Network [OSTI]

    Mitchell, Melanie

    of artificial systems is an important component of artificial life, providing an important modeling tool of evolution in artificial-life systems. GAs have been used both as tools for solving practical problems a system with lifelike properties, even though this is certainly an important role for GAs in artificial

  6. Genetic Algorithms Artificial Life

    E-Print Network [OSTI]

    Forrest, Stephanie

    systems tremendously. Likewise, evolution of artificial systems is an important component of artificial) are currently the most promi­ nent and widely used models of evolution in artificial­life systems. GAs have beenGenetic Algorithms and Artificial Life Melanie Mitchell Santa Fe Institute 1660 Old Pecos Tr

  7. Photovoltaics Life Cycle Analysis

    E-Print Network [OSTI]

    (air, water, solid) M, Q E PV array Photovoltaic modules Balance of System (BOS) (Inverters & Environmental Engineering Department Columbia University and National Photovoltaic (PV) EHS Research Center Brookhaven National Laboratory www.clca.columbia.edu www.pv.bnl.gov #12;2 The Life Cycle of PVThe Life Cycle

  8. Fuel Storage Facility Final Safety Analysis Report. Revision 1

    SciTech Connect (OSTI)

    Linderoth, C.E.

    1984-03-01T23:59:59.000Z

    The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

  9. DEPARTMENT OF RESIDENTIAL LIFE Residential Life Staff Manual.

    E-Print Network [OSTI]

    Missouri-Rolla, University of

    1 Appendix A DEPARTMENT OF RESIDENTIAL LIFE Residential Life Staff Manual. Residential Life Program Listing #12;2 MISSOURI S&T RESIDENTIAL LIFE DEPARTMENT Staff Resource Manual 2010--2012 Department of Residential Life Mission: To create educational environments emphasizing learning and development. Service

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

    SciTech Connect (OSTI)

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

    2006-09-15T23:59:59.000Z

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

  11. PACER -- A fast running computer code for the calculation of short-term containment/confinement loads following coolant boundary failure. Volume 1: Code models and correlations

    SciTech Connect (OSTI)

    Sienicki, J.J.

    1997-06-01T23:59:59.000Z

    A fast running and simple computer code has been developed to calculate pressure loadings inside light water reactor containments/confinements under loss-of-coolant accident conditions. PACER was originally developed to calculate containment/confinement pressure and temperature time histories for loss-of-coolant accidents in Soviet-designed VVER reactors and is relevant to the activities of the US International Nuclear Safety Center. The code employs a multicompartment representation of the containment volume and is focused upon application to early time containment phenomena during and immediately following blowdown. Flashing from coolant release, condensation heat transfer, intercompartment transport, and engineered safety features are described using best estimate models and correlations often based upon experiment analyses. Two notable capabilities of PACER that differ from most other containment loads codes are the modeling of the rates of steam and water formation accompanying coolant release as well as the correlations for steam condensation upon structure.

  12. T ID CODE I

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA Approved:AdministrationAnalysisDarby Dietrich5 | NUMBER 1 | MARCHT ID CODE I

  13. Coding for Transmission Coding for Compression Bonus Section CMPSCI 240: Reasoning about Uncertainty

    E-Print Network [OSTI]

    McGregor, Andrew

    Coding for Transmission Coding for Compression Bonus Section CMPSCI 240: Reasoning about 1, 2013 #12;Coding for Transmission Coding for Compression Bonus Section Information Theory Encoding for Transmission Coding for Compression Bonus Section Encoding Messages with Redundancy: Error Correcting Suppose

  14. Nuclear Safety Information Dashboard | Department of Energy

    Office of Environmental Management (EM)

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

  15. Safety Interlocks Group - Advanced Photon Source

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

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

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

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

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

  17. Multi-componenet diffusion analysis and assessment of Gamma code and improved RELAP5 code

    SciTech Connect (OSTI)

    Chang Oh

    2007-05-01T23:59:59.000Z

    A loss-of-coolant accident (LOCA) has been considered a critical event for very high temperature gas-cooled reactor (VHTR). Following helium depressurization, it is anticipated that unless countermeasures are taken, air will enter the core through the break by molecular diffusion and ultimately by natural convection leading to oxidation of the in-core graphite structure. Thus, without any mitigating features, a LOCA will lead to an air ingress event, which will lead to exothermic chemical reactions of graphite with oxygen, potentially resulting in significant increases of the core temperature. New and safer nuclear reactors (Generation IV) are now in the early planning stages in many countries throughout the world. One of the reactor concepts being seriously considered is the VHTR. To achieve public acceptance, these reactor concepts must show an increased level of inherent safety over current reactor designs (i.e., a system must be designed to eliminate any concerns of large radiological releases outside the site boundary). A computer code developed from this study, gas multi-component mixture analysis (GAMMA) code, was assessed using a two-bulb experiment and in addition the molecular diffusion behavior in the prismatic-core gas-cooled reactor was investigated following the guillotine break of the main pipe between the reactor vessel and the power conversion unit. The RELAP5 code was improved for the VHTR air ingress analysis and was assessed using inverse U-tube and NACOK natural circulation data.

  18. Life Before Earth

    E-Print Network [OSTI]

    Alexei A. Sharov; Richard Gordon

    2013-03-28T23:59:59.000Z

    An extrapolation of the genetic complexity of organisms to earlier times suggests that life began before the Earth was formed. Life may have started from systems with single heritable elements that are functionally equivalent to a nucleotide. The genetic complexity, roughly measured by the number of non-redundant functional nucleotides, is expected to have grown exponentially due to several positive feedback factors: gene cooperation, duplication of genes with their subsequent specialization, and emergence of novel functional niches associated with existing genes. Linear regression of genetic complexity on a log scale extrapolated back to just one base pair suggests the time of the origin of life 9.7 billion years ago. This cosmic time scale for the evolution of life has important consequences: life took ca. 5 billion years to reach the complexity of bacteria; the environments in which life originated and evolved to the prokaryote stage may have been quite different from those envisaged on Earth; there was no intelligent life in our universe prior to the origin of Earth, thus Earth could not have been deliberately seeded with life by intelligent aliens; Earth was seeded by panspermia; experimental replication of the origin of life from scratch may have to emulate many cumulative rare events; and the Drake equation for guesstimating the number of civilizations in the universe is likely wrong, as intelligent life has just begun appearing in our universe. Evolution of advanced organisms has accelerated via development of additional information-processing systems: epigenetic memory, primitive mind, multicellular brain, language, books, computers, and Internet. As a result the doubling time of complexity has reached ca. 20 years. Finally, we discuss the issue of the predicted technological singularity and give a biosemiotics perspective on the increase of complexity.

  19. US Department of Energy DOE Nevada Operations Office, Nevada Test Site: Underground safety and health standards

    SciTech Connect (OSTI)

    Not Available

    1993-05-01T23:59:59.000Z

    The Nevada Test Site Underground Safety and Health Standards Working Group was formed at the direction of John D. Stewart, Director, Nevada Test Site Office in April, 1990. The objective of the Working Group was to compile a safety and health standard from the California Tunnel Safety Orders and OSHA for the underground operations at the NTS, (excluding Yucca Mountain). These standards are called the NTS U/G Safety and Health Standards. The Working Group submits these standards as a RECOMMENDATION to the Director, NTSO. Although the Working Group considers these standards to be the most integrated and comprehensive standards that could be developed for NTS Underground Operations, the intent is not to supersede or replace any relevant DOE orders. Rather the intent is to collate the multiple safety and health references contained in DOE Order 5480.4 that have applicability to NTS Underground Operations into a single safety and heath standard to be used in the underground operations at the NTS. Each portion of the standard was included only after careful consideration by the Working Group and is judged to be both effective and appropriate. The specific methods and rationale used by the Working Group are outlined as follows: The letter from DOE/HQ, dated September 28, 1990 cited OSHA and the CTSO as the safety and health codes applicable to underground operations at the NTS. These mandated codes were each originally developed to be comprehensive, i.e., all underground operations of a particular type (e.g., tunnels in the case of the CTSO) were intended to be adequately regulated by the appropriate code. However, this is not true; the Working Group found extensive and confusing overlap in the codes in numerous areas. Other subjects and activities were addressed by the various codes in cursory fashion or not at all.

  20. Enhancing the safety of tailings management facilities

    SciTech Connect (OSTI)

    Meggyes, T.; Niederleithinger, E.; Witt, K.J.; Csovari, M.; Kreft-Burman, K.; Engels, J.; McDonald, C.; Roehl, K.E. [BAM, Berlin (Germany). Federal Institute for Material Research & Testing

    2008-07-01T23:59:59.000Z

    Unsafe tailings management facilities (TMFs) have caused serious accidents in Europe threatening human health/life and the environment. While advanced design, construction and management procedures are available, their implementation requires greater emphasis. An integrated research project funded by the European Union was carried out between 2002 and 2005 with the overall goal of improving the safety of TMFs (Sustainable Improvement in Safety of Tailings Facilities - TAILSAFE, http://www.tailsafe.com/). The objective of TAILSAFE was to develop and apply methods of parameter evaluation and measurement for the assessment and improvement of the safety state of tailings facilities, with particular attention to the stability of tailings dams and slurries, the special risks inherent when such materials include toxic or hazardous wastes, and authorization and management procedures for tailings facilities. Aspects of tailings facilities design, water management and slurry transport, non-destructive and minimally intrusive testing methods, monitoring and the application of sensors, intervention and remediation options were considered in TAILSAFE. A risk reduction framework (the TAILSAFE Parameter Framework) was established to contribute to the avoidance of catastrophic accidents and hazards from tailings facilities. Tailings from the mining and primary processing of metals, minerals and coal were included within the scope of TAILSAFE. The project focused on the avoidance of hazards by developing procedures and methods for investigating and improving the stability of tailings dams and tailings bodies.

  1. 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

  2. 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

  3. Radiation Safety Manual Dec 2012 Page 1 RADIATION SAFETY

    E-Print Network [OSTI]

    Grishok, Alla

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

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

    E-Print Network [OSTI]

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

  5. Software Safety Tutorial Status Update 1 Software Safety Tutorial

    E-Print Network [OSTI]

    Tian, Jeff

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

  6. Safety Lifecycle for Developing Safety Critical Artificial Neural Networks

    E-Print Network [OSTI]

    Kelly, Tim

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

  7. Integrated Safety Management

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

    2011-04-25T23:59:59.000Z

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

  8. Nuclear Explosive Safety Manual

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

    2009-04-14T23:59:59.000Z

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

  9. 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

  10. Packaging and Transportation Safety

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

    2003-04-04T23:59:59.000Z

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

  11. DOE Explosives Safety Manual

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

    2006-01-09T23:59:59.000Z

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

  12. Packaging and Transportation Safety

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

    2010-05-14T23:59:59.000Z

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

  13. Nuclear Explosive Safety

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

    2006-06-12T23:59:59.000Z

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

  14. Nuclear Explosive Safety

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

    2009-04-14T23:59:59.000Z

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

  15. Nuclear Explosive Safety

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

    2009-04-14T23:59:59.000Z

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

  16. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11T23:59:59.000Z

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

  17. Module Safety Issues (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2012-02-01T23:59:59.000Z

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

  18. Safety research programs sponsored by Office of Nuclear Regulatory Research: Quarterly progress report, July 1-September 30, 1986

    SciTech Connect (OSTI)

    Bari, R.A.; Bezler, P.; Boccio, J.L.; Ginsberg, T.; Greene, G.A.; Guppy, J.G.; Hall, R.E.; Hofmayer, C.H.; Khatib-Rahbar, H.; Luckas, W.J. Jr.

    1987-03-01T23:59:59.000Z

    This progress report will describe current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Accident Evaluation, Division of Engineering Technology, and Division of Risk Analysis and Operations of the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The projects reported are the following: High Temperature Reactor Research, SSC code improvements, Thermal-Hydraulic Reactor Safety Experiments, Thermodynamic Core-Concrete Interaction Experiments and Analysis, Plant Analyzer, Code Assessment and Application, Code Maintenance (RAMONA-3B), MELCOR Verification and Benchmarking, Source Term Code Package Verification and Benchmarking, Uncertainty Analysis of the Source Term; Stress Corrosion Cracking of PWR Steam Generator Tubing, Soil-Structure Interaction Evaluation and Structural Benchmarks, Identification of Age Related Failure Modes; Application of HRA/PRA Results to Support Resolution of Generic Safety Issues Involving Human Performance, Protective Action Decisionmaking, Rebaseling of Risk for Zion, Containment Performance Design Objective, and Operational Safety Reliability Research.

  19. Quantum serial turbo-codes

    E-Print Network [OSTI]

    David Poulin; Jean-Pierre Tillich; Harold Ollivier

    2009-06-10T23:59:59.000Z

    We present a theory of quantum serial turbo-codes, describe their iterative decoding algorithm, and study their performances numerically on a depolarization channel. Our construction offers several advantages over quantum LDPC codes. First, the Tanner graph used for decoding is free of 4-cycles that deteriorate the performances of iterative decoding. Secondly, the iterative decoder makes explicit use of the code's degeneracy. Finally, there is complete freedom in the code design in terms of length, rate, memory size, and interleaver choice. We define a quantum analogue of a state diagram that provides an efficient way to verify the properties of a quantum convolutional code, and in particular its recursiveness and the presence of catastrophic error propagation. We prove that all recursive quantum convolutional encoder have catastrophic error propagation. In our constructions, the convolutional codes have thus been chosen to be non-catastrophic and non-recursive. While the resulting families of turbo-codes have bounded minimum distance, from a pragmatic point of view the effective minimum distances of the codes that we have simulated are large enough not to degrade the iterative decoding performance up to reasonable word error rates and block sizes. With well chosen constituent convolutional codes, we observe an important reduction of the word error rate as the code length increases.

  20. Conjugate Codes and Applications to Cryptography

    E-Print Network [OSTI]

    Mitsuru Hamada

    2006-10-23T23:59:59.000Z

    A conjugate code pair is defined as a pair of linear codes such that one contains the dual of the other. The conjugate code pair represents the essential structure of the corresponding Calderbank-Shor-Steane (CSS) quantum code. It is argued that conjugate code pairs are applicable to quantum cryptography in order to motivate studies on conjugate code pairs.

  1. Turbo and LDPC Codes: Implementation, Simulation,

    E-Print Network [OSTI]

    Valenti, Matthew C.

    1 Turbo and LDPC Codes: Implementation, Simulation, and Standardization June 7, 2006 Matthew/7/2006 Turbo and LDPC Codes 2/133 Tutorial Overview Channel capacity Convolutional codes ­ the MAP algorithm Turbo codes ­ Standard binary turbo codes: UMTS and cdma2000 ­ Duobinary CRSC turbo codes: DVB

  2. Nuclear Explosive Safety Evaluation Processes

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

    2009-04-14T23:59:59.000Z

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

  3. Nuclear Engineering Nuclear Criticality Safety

    E-Print Network [OSTI]

    Kemner, Ken

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

  4. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

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

  5. Radiation Safety (Revised March 2010)

    E-Print Network [OSTI]

    Kay, Mark A.

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

  6. ANNUAL SECURITY FIRE SAFETY REPORT

    E-Print Network [OSTI]

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

  7. TUFTS UNIVERSITY LASER SAFETY PROGRAM

    E-Print Network [OSTI]

    Dennett, Daniel

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

  8. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    SciTech Connect (OSTI)

    GARVIN, L J; JENSEN, M A

    2004-04-13T23:59:59.000Z

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

  9. Combustion Safety for Appliances Using Indoor Air (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-05-01T23:59:59.000Z

    This measure guideline covers how to assess and carry out the combustion safety procedures for appliances and heating equipment that uses indoor air for combustion in low-rise residential buildings. Only appliances installed in the living space, or in an area freely communicating with the living space, vented alone or in tandem with another appliance are considered here. A separate measure guideline addresses combustion appliances located either within the living space in enclosed closets or side rooms or outside the living space in an adjacent area like an attic or garage that use outdoor air for combustion. This document is for inspectors, auditors, and technicians working in homes where energy upgrades are being conducted whether or not air infiltration control is included in the package of measures being applied. In the indoor combustion air case, guidelines summarized here are based on language provided in several of the codes to establish minimum requirements for the space using simplified prescriptive measures. In addition, building performance testing procedures are provided by testing agencies. The codes in combination with the test procedures offer comprehensive combustion safety coverage to address safety concerns, allowing inexperienced residential energy retrofit inspectors to effectively address combustion safety issues and allow energy retrofits to proceed.

  10. Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide

    SciTech Connect (OSTI)

    Ritchie, L.T.; Johnson, J.D.; Blond, R.M.

    1983-02-01T23:59:59.000Z

    The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significant modeling improvements in the areas of weather sequence sampling and emergency response, and refinements to the plume rise, atmospheric dispersion, and wet deposition models. New output capabilities have also been added. This guide is to facilitate the informed and intelligent use of CRAC2. It includes descriptions of the input data, the output results, the file structures, control information, and five sample problems.

  11. CONSTRUCTION SAFETY MANUAL ADMINISTRATIVE POLICIES

    E-Print Network [OSTI]

    Knowles, David William

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

  12. 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

  13. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

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

  14. pamphlet04.doc SAFETY INFORMATION

    E-Print Network [OSTI]

    Oliver, Douglas L.

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

  15. Health and Safety Training Reciprocity

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

    2014-04-14T23:59:59.000Z

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

  16. 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

  17. Clark County- Energy Conservation Code

    Broader source: Energy.gov [DOE]

    In September 2010, Clark County adopted Ordinance 3897, implementing the Southern Nevada version of the 2009 International Energy Conservation Code for both residential and commercial buildings...

  18. Nonbinary Codeword Stabilized Quantum Codes

    E-Print Network [OSTI]

    Xie Chen; Bei Zeng; Isaac L. Chuang

    2008-08-22T23:59:59.000Z

    The codeword stabilized (CWS) quantum codes formalism presents a unifying approach to both additive and nonadditive quantum error-correcting codes (arXiv:0708.1021 [quant-ph]), but only for binary states. Here we generalize the CWS framework to the nonbinary case (of both prime and nonprime dimension) and map the search for nonbinary quantum codes to a corresponding search problem for classical nonbinary codes with specific error patterns. We show that while the additivity properties of nonbinary CWS codes are similar to the binary case, the structural properties of the nonbinary codes differ substantially from the binary case, even for prime dimensions. In particular, we identify specific structure patterns of stabilizer groups, based on which efficient constructions might be possible for codes that encode more dimensions than any stabilizer codes of the same length and distance; similar methods cannot be applied in the binary case. Understanding of these structural properties can help prune the search space and facilitate the identification of good nonbinary CWS codes.

  19. Marin County- Solar Access Code

    Broader source: Energy.gov [DOE]

    Marin County's Energy Conservation Code is designed to assure new subdivisions provide for future passive or natural heating or cooling opportunities in the subdivision to the extent feasible. ...

  20. Quantum Quasi-Cyclic LDPC Codes

    E-Print Network [OSTI]

    Manabu Hagiwara; Hideki Imai

    2010-08-28T23:59:59.000Z

    In this paper, a construction of a pair of "regular" quasi-cyclic LDPC codes as ingredient codes for a quantum error-correcting code is proposed. That is, we find quantum regular LDPC codes with various weight distributions. Furthermore our proposed codes have lots of variations for length, code rate. These codes are obtained by a descrete mathematical characterization for model matrices of quasi-cyclic LDPC codes. Our proposed codes achieve a bounded distance decoding (BDD) bound, or known as VG bound, and achieve a lower bound of the code length.

  1. Super Special Codes using Super Matrices

    E-Print Network [OSTI]

    W. B. Vasantha Kandasamy; Florentin Smarandache; K. Ilanthenral

    2010-06-30T23:59:59.000Z

    The new classes of super special codes are constructed in this book using the specially constructed super special vector spaces. These codes mainly use the super matrices. These codes can be realized as a special type of concatenated codes. This book has four chapters. In chapter one basic properties of codes and super matrices are given. A new type of super special vector space is constructed in chapter two of this book. Three new classes of super special codes namely, super special row code, super special column code and super special codes are introduced in chapter three. Applications of these codes are given in the final chapter.

  2. On the logical operators of quantum codes

    E-Print Network [OSTI]

    Mark M. Wilde

    2009-03-30T23:59:59.000Z

    I show how applying a symplectic Gram-Schmidt orthogonalization to the normalizer of a quantum code gives a different way of determining the code's logical operators. This approach may be more natural in the setting where we produce a quantum code from classical codes because the generator matrices of the classical codes form the normalizer of the resulting quantum code. This technique is particularly useful in determining the logical operators of an entanglement-assisted code produced from two classical binary codes or from one classical quaternary code. Finally, this approach gives additional formulas for computing the amount of entanglement that an entanglement-assisted code requires.

  3. Every sign of life

    E-Print Network [OSTI]

    Gerasimov, Vadim, 1969-

    2003-01-01T23:59:59.000Z

    Every Sign of Life introduces an approach to and motivational schema for personal health monitoring. It is an exploration of how to make information collected by personal health-monitoring devices fun and engaging, and ...

  4. Enhancing Railroad Hazardous Materials Transportation Safety...

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

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

    Office of Environmental Management (EM)

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

  7. The Front Lines of Patient Safety

    E-Print Network [OSTI]

    Soloveichik, David

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

  8. Life Cycle Inventory of a CMOS Chip

    E-Print Network [OSTI]

    Boyd, Sarah; Dornfeld, David; Krishnan, Nikhil

    2006-01-01T23:59:59.000Z

    are shown. Keywords- Life Cycle Assessment (LCA); Life Cycleindustry, and Life Cycle Assessment (LCA) is emerging as a

  9. Non-Residential Energy Code National and Regional Codes

    E-Print Network [OSTI]

    Non-Residential Energy Code Comparison National and Regional Codes David Baylon Mike Kennedy #12 2003 · ASHRAE 90.1 2001 & addenda · E-Benchmark Guidelines (NBI) #12;Approach · Comparison of the State;Approach (cont.) · Provisions compared ­ Lighting power ­ Lighting controls ­ Mechanical systems ­ Building

  10. Building and Facility Codes Code Building Location Bldg # Coordinates

    E-Print Network [OSTI]

    Russell, Lynn

    Building and Facility Codes Code Building Location Bldg # Coordinates APM Applied Physics & Mathematics Building Muir 249 F7 ASANT Asante Hall Eleanor Roosevelt 446 F5 BIO Biology Building Muir 259 F7 BIRCH Birch Aquarium SIO 2300 S-D7 BONN Bonner Hall Revelle 131 G8 BSB Biomedical Sciences Building

  11. Space time coded code division multiplexing on SC140 DSP

    E-Print Network [OSTI]

    Menon, Murali P

    2001-01-01T23:59:59.000Z

    The aim of this research is to design a high data rate wireless communication system for multi-path fading channels. Code-division multiplexing is proposed as a modulation scheme for a space-time coded multiple antenna system that would guarantee...

  12. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01T23:59:59.000Z

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

  13. Safety review advisor

    SciTech Connect (OSTI)

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

    1989-01-01T23:59:59.000Z

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

  14. Physics of reactor safety. Quarterly report, October-December 1982. [LMFBR; Argonne National Laboratory

    SciTech Connect (OSTI)

    Not Available

    1983-02-01T23:59:59.000Z

    This Quarterly progress report summarizes work done during the months of October-December 1982 in Argonne National Laboratory's Applied Physics and Components Technology Divisions for the Division of Reactor Safety Research of the US Nuclear Regulatory Commission. The work in the Applied Physics Division includes reports on reactor safety modeling and assessment by members of the Reactor Safety Appraisals Section. Work on reactor core thermal-hydraulics is performed in ANL's Components Technology Division, emphasizing 3-dimensional code development for LMFBR accidents under natural convection conditions. An executive summary is provided including a statement of the findings and recommendations of the report.

  15. Mars mission safety

    SciTech Connect (OSTI)

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

    1989-06-01T23:59:59.000Z

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

  16. Health and safety

    SciTech Connect (OSTI)

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

    1990-05-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    Szilard, Ronaldo H; Smith, Curtis L

    2014-09-01T23:59:59.000Z

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

  18. Plant maintenance and plant life extension issue, 2007

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2007-03-15T23:59:59.000Z

    The focus of the March-April issue is on plant maintenance and plant life extension. Major articles/reports in this issue include: Three proposed COLs expected in 2007, by Dale E. Klein, U.S. Nuclear Regulatory Commission; Delivering behaviors that our customers value, by Jack Allen, Westinghouse Electric Company; Facilitating high-level and fuel waste disposal technologies, by Malcolm Gray, IAEA, Austria; Plant life management and long-term operation, by Pal Kovacs, OECD-NEA, France; Measuring control rod position, by R. Taymanov, K. Sapozhnikova, I. Druzhinin, D.I. Mendeleyev, Institue for Metrology, Russia; and, 'Modernization' means higher safety, by Svetlana Genova, Kozluduy NPP plc, Bulgaria.

  19. Environment, Safety, and Health Reporting Notice

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

    2002-01-15T23:59:59.000Z

    To set forth the requirements and responsibilities for Department of Energy (DOE) elements, including the National Nuclear Security Administration (NNSA), for preparation of annual summary reports to the Secretary of Energy on the results of environment, safety, and health (ES&H) assessments conducted in the previous year. To implement the revised requirements of Title 29 Code of Federal Regulations (CFR) Part 1904, "Recording and Reporting Occupational Injuries and Illnesses," within DOE, including NNSA. Cancels 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 of DOE M 231.1-1. DOE N 231.2 extends this Notice until 1-15-2004. Cancels: DOE M 231.1-1. in part.

  20. Weight Distribution of a Class of Binary Linear Block Codes Formed from RCPC Codes

    E-Print Network [OSTI]

    Shen, Yushi Dr.; Cosman, Pamela C; Milstein, Laurence B

    2006-01-01T23:59:59.000Z

    formed from convolutional codes,” IEEE Trans. Commun. , vol.terminated convolutional codes,” IEEE Trans. Inform. Theory,decoding of linear block codes and related soft- decision

  1. Introduction Space Time Codes Space Time Coding with Feedback New Thoughts Summary Space-Time Coding for Multi-Antenna

    E-Print Network [OSTI]

    Veeravalli, Venugopal

    Introduction Space Time Codes Space Time Coding with Feedback New Thoughts Summary Space 2007 #12;Introduction Space Time Codes Space Time Coding with Feedback New Thoughts Summary MIMO: Diversity vs Multiplexing Multiplexing Diversity Pictures taken from lectures notes on Space Time Coding

  2. Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module

    SciTech Connect (OSTI)

    Merrill, Brad; Reyes, Susana; Sawan, Mohamed; Wong, Clement

    2006-07-01T23:59:59.000Z

    The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

  3. LFSC - Linac Feedback Simulation Code

    SciTech Connect (OSTI)

    Ivanov, Valentin; /Fermilab

    2008-05-01T23:59:59.000Z

    The computer program LFSC (Code>) is a numerical tool for simulation beam based feedback in high performance linacs. The code LFSC is based on the earlier version developed by a collective of authors at SLAC (L.Hendrickson, R. McEwen, T. Himel, H. Shoaee, S. Shah, P. Emma, P. Schultz) during 1990-2005. That code was successively used in simulation of SLC, TESLA, CLIC and NLC projects. It can simulate as pulse-to-pulse feedback on timescale corresponding to 5-100 Hz, as slower feedbacks, operating in the 0.1-1 Hz range in the Main Linac and Beam Delivery System. The code LFSC is running under Matlab for MS Windows operating system. It contains about 30,000 lines of source code in more than 260 subroutines. The code uses the LIAR ('Linear Accelerator Research code') for particle tracking under ground motion and technical noise perturbations. It uses the Guinea Pig code to simulate the luminosity performance. A set of input files includes the lattice description (XSIF format), and plane text files with numerical parameters, wake fields, ground motion data etc. The Matlab environment provides a flexible system for graphical output.

  4. Stabilizer Codes over Frobenius Rings

    E-Print Network [OSTI]

    Nadella, Sushma

    2012-07-16T23:59:59.000Z

    now, the methods for quantum error correction were mainly based on quantum codes that rely on the arithmetic in finite fields. In contrast, this thesis aims to develop a basic framework for quantum error correcting codes over a class of rings known...

  5. Electronic Safety Resource Tools – Supporting Hydrogen and Fuel Cell Commercialization

    SciTech Connect (OSTI)

    Barilo, Nick F.

    2014-09-29T23:59:59.000Z

    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.

  6. Entanglement boosts quantum turbo codes

    E-Print Network [OSTI]

    Wilde, Mark M

    2010-01-01T23:59:59.000Z

    One of the unexpected breakdowns in the existing theory of quantum serial turbo coding is that a quantum convolutional encoder cannot simultaneously be recursive and non-catastrophic. These properties are essential for a quantum turbo code to have an unbounded minimum distance and for its iterative decoding algorithm to converge, respectively. Here, we show that the entanglement-assisted paradigm gives a theoretical and practical "turbo boost" to these codes, in the sense that an entanglement-assisted quantum (EAQ) convolutional encoder can possess both of the aforementioned desirable properties, and simulation results indicate that entanglement-assisted turbo codes can operate reliably in a noise regime 5.5 dB beyond that of standard quantum turbo codes. Entanglement is the resource that enables a convolutional encoder to satisfy both properties because an encoder acting on only information qubits, classical bits, gauge qubits, and ancilla qubits cannot simultaneously satisfy them. We give several examples o...

  7. On Quantum and Classical BCH Codes

    E-Print Network [OSTI]

    Salah A. Aly; Andreas Klappenecker; Pradeep Kiran Sarvepalli

    2006-04-14T23:59:59.000Z

    Classical BCH codes that contain their (Euclidean or Hermitian) dual codes can be used to construct quantum stabilizer codes; this correspondence studies the properties of such codes. It is shown that a BCH code of length n can contain its dual code only if its designed distance d=O(sqrt(n)), and the converse is proved in the case of narrow-sense codes. Furthermore, the dimension of narrow-sense BCH codes with small design distance is completely determined, and - consequently - the bounds on their minimum distance are improved. These results make it possible to determine the parameters of quantum BCH codes in terms of their design parameters.

  8. San Francisco Building Code Amendments to the

    E-Print Network [OSTI]

    Green Building Standards Code 2010 California Residential Code Operative date: January 1, 2011 #12;2 #121 2010 San Francisco Building Code Amendments to the 2010 California Building Code 2010 California;3 CHAPTER 1 SCOPE AND ADMINISTRATION DIVISION I CALIFORNIA ADMINISTRATION No San Francisco Building Code

  9. Remarkable Degenerate Quantum Stabilizer Codes Derived from Duadic Codes

    E-Print Network [OSTI]

    Salah A. Aly; Andreas Klappenecker; Pradeep Kiran Sarvepalli

    2006-01-18T23:59:59.000Z

    Good quantum codes, such as quantum MDS codes, are typically nondegenerate, meaning that errors of small weight require active error-correction, which is--paradoxically--itself prone to errors. Decoherence free subspaces, on the other hand, do not require active error correction, but perform poorly in terms of minimum distance. In this paper, examples of degenerate quantum codes are constructed that have better minimum distance than decoherence free subspaces and allow some errors of small weight that do not require active error correction. In particular, two new families of [[n,1,>= sqrt(n)

  10. The Secret Life of Patches: A Firefox Case Study Olga Baysal, Oleksii Kononenko, Reid Holmes, and Michael W. Godfrey

    E-Print Network [OSTI]

    Godfrey, Michael W.

    The Secret Life of Patches: A Firefox Case Study Olga Baysal, Oleksii Kononenko, Reid Holmes future community contri- butions. Keywords-Open source software, code review, patch lifecycle. I. INTRODUCTION Code review is a key element of any mature software development process. It is particularly

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

    E-Print Network [OSTI]

    Lee, Dongwon

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

  12. Applying Human Factors during the SIS Life Cycle

    SciTech Connect (OSTI)

    Avery, K.

    2010-05-05T23:59:59.000Z

    Safety Instrumented Systems (SIS) are widely used in U.S. Department of Energy's (DOE) nonreactor nuclear facilities for safety-critical applications. Although use of the SIS technology and computer-based digital controls, can improve performance and safety, it potentially introduces additional complexities, such as failure modes that are not readily detectable. Either automated actions or manual (operator) actions may be required to complete the safety instrumented function to place the process in a safe state or mitigate a hazard in response to an alarm or indication. DOE will issue a new standard, Application of Safety Instrumented Systems Used at DOE Nonreactor Nuclear Facilities, to provide guidance for the design, procurement, installation, testing, maintenance, operation, and quality assurance of SIS used in safety significant functions at DOE nonreactor nuclear facilities. The DOE standard focuses on utilizing the process industry consensus standard, American National Standards Institute/ International Society of Automation (ANSI/ISA) 84.00.01, Functional Safety: Safety Instrumented Systems for the Process Industry Sector, to support reliable SIS design throughout the DOE complex. SIS design must take into account human-machine interfaces and their limitations and follow good human factors engineering (HFE) practices. HFE encompasses many diverse areas (e.g., information display, user-system interaction, alarm management, operator response, control room design, and system maintainability), which affect all aspects of system development and modification. This paper presents how the HFE processes and principles apply throughout the SIS life cycle to support the design and use of SIS at DOE nonreactor nuclear facilities.

  13. Thermodynamic Origin of Life

    E-Print Network [OSTI]

    Michaelian, K

    2009-01-01T23:59:59.000Z

    Understanding the thermodynamic function of life may shed light on its origin. Out of equilibrium structuring in space and time is contingent on continuous entropy production. Entropy production is a measure of the rate of the natural tendency of Nature to explore all available microstates. The process producing the greatest amount of entropy in the biosphere is the absorption and transformation of sunlight, leading to the transpiration of water by plants and cyanobacteria. Here we hypothesize that life began, and exists today, as a dynamic catalyst for the absorption and transformation of sunlight into heat, which could then be efficiently harvested by the water cycle, hurricanes, and ocean and wind currents. RNA and DNA are the most efficient of all known molecules for absorbing the ultraviolet light that could have penetrated the dense early atmosphere, and are extremely rapid in transforming this light into heat that can be readily absorbed by liquid water. The origin and evolution of life was thus driven...

  14. What matters for well-being: Individual perceptions of quality of life before and after important life events.

    E-Print Network [OSTI]

    Scott, Jacqueline; Plagnol, Anke C.

    2009-11-22T23:59:59.000Z

    hygiene 8. Employment: employment, job satisfaction 9. Misc other: Safety, lack of fear, neighbors, pets, other relationships, other positive mentions, other 10. Freedom: freedom, independence 11. Time self: time for self, not too overworked, life... in balance, sleep, no stress 12. Other material: consumption, shopping, getting new things, car, transport, educa- tion (own, children’s, standard of system in general), other material benefits 13. Other personal: Other personal characteristics (not elsewhere...

  15. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation

    SciTech Connect (OSTI)

    NONE

    1997-03-01T23:59:59.000Z

    This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U.S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This manual covers an array of modules written for the SCALE package, consisting of drivers, system libraries, cross section and materials properties libraries, input/output routines, storage modules, and help files.

  16. Lawn Maintenance Safety

    E-Print Network [OSTI]

    Smith, David

    2005-07-12T23:59:59.000Z

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

  17. Perspectives on reactor safety

    SciTech Connect (OSTI)

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

    1994-03-01T23:59:59.000Z

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

  18. Complete Safety Training

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

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

  19. Complete Safety Training

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

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

  20. Nuclear Safety Regulatory Framework

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

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