National Library of Energy BETA

Sample records for life safety code

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

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

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

  2. 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...

  3. Genome: Unlocking Life's Code for Teachers of

    E-Print Network [OSTI]

    Miller, Scott

    GENOME CODE LIFE'S UNLOCKING Genome: Unlocking Life's Code Educator's Guide for Teachers of Grades Glossary 30 Other Resources 32 What the Exhibit Offers Genomics--the study of the entire genome. It is important that students understand what genomics is and what it teaches us about ourselves and the rest

  4. Health and Safety Policy Category: Campus Life

    E-Print Network [OSTI]

    Health and Safety Policy Category: Campus Life 1. PURPOSE To provide a healthy and safe workplace to providing and maintaining high standards of health and safety in the workplace. It is our belief that all injuries are preventable. 2.2. Health and safety is the responsibility of everyone and that all workers

  5. Safety, codes and standards for hydrogen installations :

    SciTech Connect (OSTI)

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

    2014-04-01

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

  6. 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

  7. Safety, Codes and Standards - Basics | Department of Energy

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

    Office Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel Cells Technology Validation Manufacturing Safety, Codes & Standards Basics Safe Use of Hydrogen Codes...

  8. For Safety and Code Officials | Department of Energy

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

    Safety and Code Officials For Safety and Code Officials Like gasoline and natural gas, hydrogen is a fuel that must be handled appropriately. When guidelines are observed, it can...

  9. 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)

    2014-09-30

    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.

  10. Health and Safety Responsibilities Procedures Category: Campus Life

    E-Print Network [OSTI]

    24/04/2013 Health and Safety Responsibilities Procedures Category: Campus Life 1. LEGISLATION/ENTERPRISE AGREEMENT/POLICY SUPPORTED Health and Safety Policy Occupational Safety and Health Act 1984 Occupational Safety and Health Regulations 1996 2. IMPLEMENTATION PRINCIPLES 2.1. Curtin University Management

  11. Code of Practice Safety of Load on Vehicles 

    E-Print Network [OSTI]

    Anonymous

    1972-01-01

    The object of the Code is to provide operators, drivers and loading staff with guidance as to the basic safety principles that must be followed generally, and as to some particular precautions that can be taken to ensure ...

  12. NHA HYDROGEN SAFETY CODES AND STANDARDS ACTIVITIES

    E-Print Network [OSTI]

    ;putting U.S. manufacturers of hydrogen energy systems and components at risk of competitive disadvantage activity to develop and write new standards for hydrogen technologies. This includes such items as storage needed to move hydrogen into the energy sector. The NHA supports the development of codes and standards

  13. 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 on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 -RobSSL IN PRACTICERENEWABLEExample Safetyand FuelsSafety,

  14. 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 on Delicious Rank EERE: Alternative Fuels Data CenterFinancialInvesting inServicesRecoveryRhodeHealth Safety and

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

    SciTech Connect (OSTI)

    Clarno, Kevin; Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth; Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01

    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.

  16. 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...

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

    SciTech Connect (OSTI)

    Blaise Collin

    2012-05-01

    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.

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

    SciTech Connect (OSTI)

    Putman, Valerie Lee

    2003-01-01

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

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

    SciTech Connect (OSTI)

    Blaise Collin

    2014-09-01

    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.

  20. Three computer codes for safety and stability of large superconducting magnets

    SciTech Connect (OSTI)

    Turner, L.R.

    1985-01-01

    For analyzing the safety and stability of large superconducting magnets, three computer codes TASS, SHORTURN, and SSICC have been developed, applicable to bath-cooled magnets, bath-cooled magnets with shorted turns, and magnets with internally cooled conductors respectively. The TASS code is described, and the use of the three codes is reviewed.

  1. 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

  2. TRAC Code Modifications Made for APT Blanket Safety Analyses

    SciTech Connect (OSTI)

    Hamm, L.L.

    1998-10-07

    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.

  3. 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 the transition to large scale hydrogen distribution. · NIST is working with DOT, DOE, ASME, British Petroleum (BP

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

    E-Print Network [OSTI]

    Hydrogen Pipeline Safety METALS Our goal is to establish the codes and standards necessary the transition to large-scale hydrogen distribution. · NIST is working with DOT, DOE, ASME, British Petroleum (BP

  5. Fire Safety Code of Vienna University of Technology 1 General provisions

    E-Print Network [OSTI]

    Nawratil, Georg

    Fire Safety Code of Vienna University of Technology § 1 General provisions § 2 Scope of application of members of Vienna University of Technology § 6 Obligations to cooperate in preventive fire safety § 7 Conduct in case of fire § 8 Gathering point § 9 Measures after a fire § 1 General provisions (1) Purpose

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

    SciTech Connect (OSTI)

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

    2015-08-01

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

  7. Applicability of reactor code WIMS for nuclear criticality safety studies

    SciTech Connect (OSTI)

    Matausek, M.V.; Marinkovic, N.

    1995-12-31

    The purpose of this paper is to examine applicability of the reactor code WIMS for calculating criticality parameters of nonreactor configurations containing fissile materials. Results are given and discussed for some typical configurations containing {sup 235}U.

  8. ENCYCLOPEDIA OF LIFE SCIENCES Population genetics: multilocus (article reference code: 1783)

    E-Print Network [OSTI]

    Gavrilets, Sergey

    Page 1 ENCYCLOPEDIA OF LIFE SCIENCES Population genetics: multilocus (article reference code: 1783) Sergey Gavrilets Departments of Ecology and Evolutionary Biology and Mathematics University of Tennessee variation at several loci in biological populations. Haplotypes Even the simplest known biological organisms

  9. 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 on Delicious Rank EERE: Alternative FuelsofProgram: Report AppendicesA TokenCommercialSTEM VolunteerSafety AlertsSafety,

  10. 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 on Delicious Rank EERE: Alternative Fuels DataEnergy Webinar:IAbout Us »Buildings DOEDOEProgramSettlementofSafety,

  11. Frequently Asked Questions 1. What is a Life Safety Evaluation?

    E-Print Network [OSTI]

    He, Chuan

    of fire origin by passive means such as fire barriers and to extinguish the fire by active means using of building occupants to escape to a safe location within or outside of the building in case of a fire. · General Safety is a measure of the overall fire safety level of the building. 2. How will my apartment

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

    SciTech Connect (OSTI)

    Carbajo, Juan; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Schmidt, Rodney Cannon; Thomas, Justin; Wei, Tom; Sofu, Tanju; Ludewig, Hans; Tobita, Yoshiharu; Ohshima, Hiroyuki; Serre, Frederic

    2011-06-01

    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.

  13. Residence Hall Fire Safety

    E-Print Network [OSTI]

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

  14. POPCYCLE: a computer code for calculating nuclear and fossil plant levelized life-cycle power costs

    SciTech Connect (OSTI)

    Hardie, R.W.

    1982-02-01

    POPCYCLE, a computer code designed to calculate levelized life-cycle power costs for nuclear and fossil electrical generating plants is described. Included are (1) derivations of the equations and a discussion of the methodology used by POPCYCLE, (2) a description of the input required by the code, (3) a listing of the input for a sample case, and (4) the output for a sample case.

  15. Demonstration of emulator-based Bayesian calibration of safety analysis codes: Theory and formulation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Yurko, Joseph P.; Buongiorno, Jacopo; Youngblood, Robert

    2015-05-28

    System codes for simulation of safety performance of nuclear plants may contain parameters whose values are not known very accurately. New information from tests or operating experience is incorporated into safety codes by a process known as calibration, which reduces uncertainty in the output of the code and thereby improves its support for decision-making. The work reported here implements several improvements on classic calibration techniques afforded by modern analysis techniques. The key innovation has come from development of code surrogate model (or code emulator) construction and prediction algorithms. Use of a fast emulator makes the calibration processes used here withmore »Markov Chain Monte Carlo (MCMC) sampling feasible. This study uses Gaussian Process (GP) based emulators, which have been used previously to emulate computer codes in the nuclear field. The present work describes the formulation of an emulator that incorporates GPs into a factor analysis-type or pattern recognition-type model. This “function factorization” Gaussian Process (FFGP) model allows overcoming limitations present in standard GP emulators, thereby improving both accuracy and speed of the emulator-based calibration process. Calibration of a friction-factor example using a Method of Manufactured Solution is performed to illustrate key properties of the FFGP based process.« less

  16. 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

  17. Current algorithms used in reactor safety codes and the impact of future computer development on these algorithms

    SciTech Connect (OSTI)

    Mahaffy, J.H.; Liles, D.R.; Woodruff, S.B.

    1985-01-01

    Computational methods and solution procedures used in the US Nuclear Regulatory Commission's reactor safety systems codes, Transient Reactor Analysis Code (TRAC) and Reactor Leak and Power Safety Excursion Code (RELAP), are reviewed. Methods used in TRAC-PF1/MOD1, including the stability-enhancing two-step (SETS) technique, which permits fast computations by allowing time steps larger than the material Courant stability limit, are described in detail, and the differences from RELAP5/MOD2 are noted. Developments in computing, including parallel and vector processing, and their applicability to nuclear reactor safety codes are described. These developments, coupled with appropriate numerical methods, make detailed faster-than-real-time reactor safety analysis a realistic near-term possibility.

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

    E-Print Network [OSTI]

    Yurko, Joseph Paul

    2014-01-01

    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 ...

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

    SciTech Connect (OSTI)

    Schultz, Peter Andrew

    2011-12-01

    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.

  20. Memorandum CH2M WG Idaho, LLC, Request for Variance to Title 10, Code of Federal Regulations Part 851, "Worker Safety and Health Program"

    Broader source: Energy.gov [DOE]

    Memorandum CH2M WG Idaho, LLC, Request for Variance to Title 10, Code of Federal Regulations Part 851, "Worker Safety and Health Program"

  1. 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.

    2014-08-22

    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.

  2. 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.

    2014-09-11

    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.

  3. The Passenger Safety Project at the Texas A&M AgriLife Extension Service works to reduce deaths and

    E-Print Network [OSTI]

    killed and 462 were injured every day in the United States in motor vehicle crashes during 2012 have a higher crash incidence and death rate than urban areas. Response The Passenger Safety ProjectThe Passenger Safety Project at the Texas A&M AgriLife Extension Service works to reduce deaths

  4. 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

    2011-03-01

    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.

  5. 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

    2014-09-01

    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.

  6. 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)]

    1999-03-17

    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.

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

    E-Print Network [OSTI]

    Neirotti, Juan Pablo

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

  8. Code development incorporating environmental, safety, and economic aspects of fusion reactors (FY 89--91)

    SciTech Connect (OSTI)

    Ho, S.K.; Fowler, T.K.; Holdren, J.P. (eds.)

    1991-11-01

    This report discusses the following aspects of Fusion reactors.: Activation Analysis; Tritium Inventory; Environmental and Safety Indices and Their Graphical Representation; Probabilistic Risk Assessment (PRA) and Decision Analysis; Plasma Burn Control -- Application to ITER; and Other Applications.

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

    SciTech Connect (OSTI)

    Robert Youngblood

    2011-02-01

    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.

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

    SciTech Connect (OSTI)

    Robert Youngblood

    2011-01-01

    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.

  11. 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

    2011-02-01

    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.

  12. 1. Mineral Exploration Regulation in British Columbia Health, Safety and Reclamation Code

    E-Print Network [OSTI]

    Bolch, Tobias

    for or to produce coal, mineral bearing substances, placer minerals, rock, limestone, earth, clay, sand or gravel mineral, coal, sand, gravel or rock, or (b) the production of a mineral, a placer mineral, coal, sand under the Criminal Code of Canada for criminal acts or negligence in the workplace. Further information

  13. Pedigree Analysis of the MELCOR 1.8.2 Code to be Used for ITER’s Report Preliminary on Safety

    SciTech Connect (OSTI)

    Richard L. Moore; Brad J. Merrill

    2007-06-01

    This report documents the pedigree analysis of the MELCOR 1.8.2 code to be used for ITER’s Report Preliminary on Safety. To pedigree the code the process involved four steps. First, taking the modified MELCOR 1.8.2 code used by the ITER Joint Central Team (JCT) for analyses in previous ITER Safety Assessments and compared the FORTRAN code of this version line-by-line to the original 1.8.2 version of MELCOR. The second step was a non-regression analysis which involves comparing the results from the pedigreed version against those predicted by the original, unmodified version of MELCOR 1.8.2. The third step involved comparing the pedigreed version results to results from the MELCOR version used by the ITER JCT for the Generic Site Safety Report (GSSR) against a set of accident problems analyzed for the safety report. The fourth and final step involved a comparison between the pedigreed version of the code and the developmental test problems cited in the change documents referenced in this report. The results from the pedigree process are described in this report.

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

    SciTech Connect (OSTI)

    Salim, Mohd Faiz; Roslan, Ridha; Ibrahim, Mohd Rizal Mamat

    2014-02-12

    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.

  15. Safety

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

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

  16. Assessment of standard point-wise neutron data libraries for criticality safety analysis with a Monte Carlo code

    SciTech Connect (OSTI)

    Kolbe, E.; Vasiliev, A.; Zimmermann, M. A. [Laboratory for Reactor Physics and Systems Behaviour, Paul Scherrer Institut, CH 5232 Villigen PSI (Switzerland)

    2006-07-01

    This study addresses the assessment of standard continuous-energy neutron data libraries using the Monte Carlo radiation transport code MCNPX for light water reactor criticality safety applications based on a suite of low-enriched, thermal, compound uranium benchmarks and represents a continuation of previously performed analysis using the JEF-2.2 and JENDL-3.3 nuclear data libraries. The new work enhancing the previous study includes the application of the ENDF/B-6.8 neutron data library and employs the most recent official release of the code (MCNPX-2.5.0) with an improved S({alpha}, {beta}) thermal neutron scattering treatment. Particular attention is paid to the analysis of the spectrum-related characteristics of the modeled critical experimental configurations to define the range of applicability of the reported estimates of lower tolerance bounds for k{sub eff}. Inspection of trends in k{sub eff} versus the spectrum-related characteristics or design parameters has also been performed. (authors)

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

    SciTech Connect (OSTI)

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

    1988-01-01

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

  18. East Carolina University ENVIRONMENTAL SAFETY COMMITTEE

    E-Print Network [OSTI]

    Gopalakrishnan, K.

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

  19. Life safety and seismic hazards: Selecting buildings for review and questions still to answer

    SciTech Connect (OSTI)

    Keller, M.D.

    1993-11-01

    Los Alamos National Laboratory (LANL) is situated on the eastern flank of the Jemez Mountains in which lies the Valles Caldera, a volcanic center that erupted 1.1 to 1.5 million years ago. Los Alamos is also situated within the western margin of the Rio Grande Rift system, where there is a possibility for seismic activity. Within the Los Alamos area are numerous faults, some within a kilometer or two of LANL structures, some even closer. Many of the permanent structures within Los Alamos were designed and constructed in accordance with applicable building codes in the 1950s. These codes have now been determined to be deficient with respect to both forcing functions of seismic events and structure design. LANL, in response to a letter from the University of California dated October 29, 1990, began the Seismic Hazards Investigation Program to determine the characteristics of a probable seismic event at Los Alamos and to determine the ability of the existing structures to withstand the forces generated by such an event. In the Seismic Hazards Investigation Program, paleoseismic methods are used to determine seismic characterization and a systematic method is needed to investigate existing structures, systems, and components for the ability to resist seismic forces. This paper presents the methodology for determining seismic characterizations and structure prioritization and analysis at LANL for the Seismic Hazards Investigation Program.

  20. 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.

    2010-09-01

    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.

  1. Radiation physics and shielding codes and analyses applied to design-assist and safety analyses of CANDU{sup R} and ACR{sup TM} reactors

    SciTech Connect (OSTI)

    Aydogdu, K.; Boss, C. R. [Atomic Energy of Canada Limited, Sheridan Science and Technology Park, Mississauga, Ont. L5K 1B2 (Canada)

    2006-07-01

    This paper discusses the radiation physics and shielding codes and analyses applied in the design of CANDU and ACR reactors. The focus is on the types of analyses undertaken rather than the inputs supplied to the engineering disciplines. Nevertheless, the discussion does show how these analyses contribute to the engineering design. Analyses in radiation physics and shielding can be categorized as either design-assist or safety and licensing (accident) analyses. Many of the analyses undertaken are designated 'design-assist' where the analyses are used to generate recommendations that directly influence plant design. These recommendations are directed at mitigating or reducing the radiation hazard of the nuclear power plant with engineered systems and components. Thus the analyses serve a primary safety function by ensuring the plant can be operated with acceptable radiation hazards to the workers and public. In addition to this role of design assist, radiation physics and shielding codes are also deployed in safety and licensing assessments of the consequences of radioactive releases of gaseous and liquid effluents during normal operation and gaseous effluents following accidents. In the latter category, the final consequences of accident sequences, expressed in terms of radiation dose to members of the public, and inputs to accident analysis, e.g., decay heat in fuel following a loss-of-coolant accident, are also calculated. Another role of the analyses is to demonstrate that the design of the plant satisfies the principle of ALARA (as low as reasonably achievable) radiation doses. This principle is applied throughout the design process to minimize worker and public doses. The principle of ALARA is an inherent part of all design-assist recommendations and safety and licensing assessments. The main focus of an ALARA exercise at the design stage is to minimize the radiation hazards at the source. This exploits material selection and impurity specifications and relies heavily on experience and engineering judgement, consistent with the ALARA philosophy. Special care is taken to ensure that the best estimate dose rates are used to the extent possible when applying ALARA. Provisions for safeguards equipment are made throughout the fuel-handling route in CANDU and ACR reactors. For example, the fuel bundle counters rely on the decay gammas from the fission products in spent-fuel bundles to record the number of fuel movements. The International Atomic Energy Agency (IAEA) Safeguards system for CANDU and ACR reactors is based on item (fuel bundle) accounting. It involves a combination of IAEA inspection with containment and surveillance, and continuous unattended monitoring. The spent fuel bundle counter monitors spent fuel bundles as they are transferred from the fuelling machine to the spent fuel bay. The shielding and dose-rate analysis need to be carried out so that the bundle counter functions properly. This paper includes two codes used in criticality safety analyses. Criticality safety is a unique phenomenon and codes that address criticality issues will demand specific validations. However, it is recognised that some of the codes used in radiation physics will also be used in criticality safety assessments. (authors)

  2. Fuel Cell Technologies Program Multi-Year Research, Development and Demonstration Plan - Section 3.7 Hydrogen Safety, Codes and Standards

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Financing Tool Fits the Bill Financing Tool Fits theSunShot Prize:4 FuelAboutExecutiveSAFETY, CODES

  3. Code development incorporating environmental, safety, and economic aspects of fusion reactors (FY 89--91). Final report

    SciTech Connect (OSTI)

    Ho, S.K.; Fowler, T.K.; Holdren, J.P. [eds.

    1991-11-01

    This report discusses the following aspects of Fusion reactors.: Activation Analysis; Tritium Inventory; Environmental and Safety Indices and Their Graphical Representation; Probabilistic Risk Assessment (PRA) and Decision Analysis; Plasma Burn Control -- Application to ITER; and Other Applications.

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

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

    Sheet: 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)...

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

    Office of Environmental Management (EM)

    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...

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

    SciTech Connect (OSTI)

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

    2008-07-15

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

  7. 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

    2011-01-01

    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.

  8. Hydrogen Technologies Safety Guide

    SciTech Connect (OSTI)

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

    2015-01-01

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

  9. Safety Training for the Hydrogen Economy

    SciTech Connect (OSTI)

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

    2006-04-11

    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.

  10. H.R. 1126: A Bill to strengthen and improve the pipeline safety provisions of chapter 601 of title 49, United States Code, and for other purposes. Introduced in the House of Representatives, One Hundred Fourth Congress, First Session, March 3, 1995

    SciTech Connect (OSTI)

    NONE

    1995-12-31

    The report H.R. 1126 is a bill to strengthen and improve the pipeline safety provisions of chapter 601 of title 49, United Stated Code. The proposed legislative text is included.

  11. 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

  12. Technical Standards, CFAST-Code Guidance- July 23, 2004

    Broader source: Energy.gov [DOE]

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

  13. DOE Coordination Meeting CODES & STANDARDS

    E-Print Network [OSTI]

    industry and code officials, develop templates of commercially viable footprints for fueling stations-order continuing education for code officials. 3 Date (FY)DescriptionMilestone #12;Hydrogen Safety Neil RossmeisslDOE Coordination Meeting DELIVERY FUEL CELLS STORAGE PRODUCTION TECHNOLOGY VALIDATION CODES

  14. 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, ...

  15. Coding theory basics Toric codes

    E-Print Network [OSTI]

    Little, John B.

    Coding theory basics Toric codes Tools from the toric world Higher-dimensional polytopes. Little Toric Varieties in Coding Theory #12;Coding theory basics Toric codes Tools from the toric world(!) John B. Little Toric Varieties in Coding Theory #12;Coding theory basics Toric codes Tools from

  16. Environmental, safety, and health engineering

    SciTech Connect (OSTI)

    Woodside, G.; Kocurek, D.

    1997-12-31

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

  17. Mechanical code comparator

    DOE Patents [OSTI]

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

    2002-01-01

    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.

  18. An Industry Approach to Sealed Source Management at the End of Useful Life

    SciTech Connect (OSTI)

    Malkoske, G.; Gray, P.; Fasten, W.

    2008-07-01

    Radioactive sources provide significant benefits which enhance the general welfare of mankind. These beneficial applications include medical treatment, sterilization of single use medical devices, food safety and agriculture, as well as industrial safety and exploration. The radioisotope sector is broad, diverse, and well established, with a culture of safety and security. ISSPA's mission is to ensure that the beneficial use of radioactive sources continues to be regarded by the public, the media, legislators, and regulators as a safe, secure, viable technology for medical, industrial, and research applications. A key consideration of a vibrant safety and security culture is the comprehensive life cycle management of radioactive sources which ensures effective control throughout their life span. Closely linked to this is the commitment by responsible suppliers to take back radioactive sources at the end of their useful life. This is an essential obligation of ISSPA members, as stated in the framework for the ISSPA Code of Good Practice. This presentation will discuss the above topics and will provide some examples which demonstrate how ISSPA members have effectively managed sources at the end of their useful life. In conclusion: Sealed radioactive sources play a major and very important role in global industry and health. Their applications are varied and they are produced and shipped in the thousands each year around the world. The importance of an effective life cycle management is imperative to the safety and security of these sources. A multi-faceted approach to sealed source life cycle management between manufacturers/distributors, shippers, customers/users, and those involved in disposition of disused sources is critical. The IAEA Code of Conduct, from a regulatory perspective, and the ISSPA Code of Good Practice, from an industry perspective, will help to ensure that sealed sources are able to be effectively utilized to the benefit of mankind for generations to come. (authors)

  19. Residential Fire Safety Policies Introduction

    E-Print Network [OSTI]

    Johnson Jr.,, Ray

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

  20. Facility Safety

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

    1996-10-24

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

  1. Facility Safety

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

    1995-11-16

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

  2. University of Toronto -Office for Environmental Health and Safety; Radiation Protection Service 215 Huron St. Toronto, Ontario, Canada, Postal Code M5S 1A2;

    E-Print Network [OSTI]

    Chan, Hue Sun

    University of Toronto - Office for Environmental Health and Safety; Radiation Protection Service: Permit Number: Permit Holder Printed Name: Signature: Date: Phone: THE RADIATION LEVEL AT ANY POINT RADIATION LABELS HAVE BEEN REMOVED U of T agent: Printed Name: Signature: Title: Date: #12;

  3. Safety harness

    DOE Patents [OSTI]

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

    1993-01-01

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

  4. H.R. 432: A Bill to amend chapter 601 of title 49, United States Code, to improve natural gas and hazardous liquid pipeline safety, in response to the natural gas pipeline accident in Edison, New Jersey, and for other purposes. Introduced in the House of Representatives, One Hundred Fourth Congress, First session

    SciTech Connect (OSTI)

    NONE

    1995-12-31

    This document contains H.R. 432, A Bill to amend chapter 601 of title 49, United States Code, to improve natural gas and hazardous liquid pipeline safety, in response to the natural gas pipeline accident in Edison, New Jersey, and for other purposes. This Bill was introduced in the House of Representatives, 104th Congress, First Session, January 5, 1995.

  5. Job Safety

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

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

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

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

    2014-12-19

    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.

  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. 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

  9. Guidance on GENII computer code - July 6, 2004 | Department of...

    Office of Environmental Management (EM)

    Documented Safety Analysis applications. Information is provided herein that supplements information found in the GENII documentation provided by the code developer. GENII...

  10. Fact Sheet Available: Codes and Standards for Energy Storage...

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

    Codes and Standards for Energy Storage System Performance and Safety (June 2014) Wave Energy Simulation Team Carries Home International Award Now Available: Evaluating...

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

    E-Print Network [OSTI]

    Ketkar, Avanti Ulhas

    2005-11-01

    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...

  12. Health & Safety

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

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

  13. Implementation Guide for Use in Developing Technical Safety Requirements

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

    2014-09-08

    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.

  14. Facility Safety

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

    2000-11-20

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

  15. 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 Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 -RobSSL IN PRACTICERENEWABLEExample Safetyand Fuels inProcess

  16. 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 Data Center Home Page on Delicious RankADVANCED MANUFACTURINGEnergy BillsNo. 195 -RobSSL IN PRACTICERENEWABLEExample Safetyand Fuels

  17. 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

  18. 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

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

    E-Print Network [OSTI]

    Griggs, D. P.

    1981-01-01

    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 ...

  20. Sandia Energy - Transportation Safety

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

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

  1. Facility Safety

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

    2005-12-22

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

  2. Biological Safety

    Broader source: Energy.gov [DOE]

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

  3. Facility Safety

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

    1995-10-13

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

  4. Facility Safety

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

    2005-12-22

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

  5. Facility Safety

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

    2012-12-04

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

  6. Building America Expert Meeting. Combustion Safety

    SciTech Connect (OSTI)

    Brand, Larry

    2013-03-01

    This is an overview of "The Best Approach to Combustion Safety in a Direct Vent World," held June 28, 2012, in San Antonio, TX. 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.

  7. Building America Expert Meeting: Combustion Safety

    SciTech Connect (OSTI)

    Brand, L.

    2013-03-01

    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.

  8. Pressure Safety Program Implementation at ORNL

    SciTech Connect (OSTI)

    Lower, Mark; Etheridge, Tom; Oland, C. Barry

    2013-01-01

    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.

  9. Speech coding

    SciTech Connect (OSTI)

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

    1998-05-08

    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.

  10. Elec 331 -Hospital Safety Power Distribution

    E-Print Network [OSTI]

    Pulfrey, David L.

    - Hospital Safety 7 Ground Fault Interrupter Test Reset Gnd Ref Hot Ref Hot Test / Reset Relay Relay : 5 to 30 mA, Test Plug Z Downstream GFI Protection #12;Elec 331 - Hospital Safety 8 = get-out-of-jail-free card · Test it before you touch it ­ Done to code? ­ Breaker labels accurate

  11. 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.

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

    E-Print Network [OSTI]

    ) are not propped open. Fire sprinkler spray patterns are not blocked by equipment or furnishings. Emergency shut-down. Emergency shut-offs (ventilation, electrical and gas) are clearly visible and have unobstructed access unobstructed access. Emergency eyewashes and showers are in good condition, clearly visible and have

  13. 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)

    1995-03-01

    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.

  14. Fire and Life Safety Information - Hanford Site

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room NewsInformation Current HABFES OctoberEvanServices » IncentivesStocks 7,171Fire Department

  15. Safety Engineer

    Broader source: Energy.gov [DOE]

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

  16. Department of Energy Construction Safety Reference Guide

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    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.

  17. 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.

  18. Building Energy Code

    Broader source: Energy.gov [DOE]

    Georgia's Department of Community Affairs periodically reviews, amends and/or updates the state minimum standard codes. Georgia has "mandatory" and "permissive" codes. Georgia State Energy Code...

  19. Hydrogen, Fuel Cells & Infrastructure Technologies ProgramHydrogen, Fuel Cells & Infrastructure Technologies Program Hydrogen Codes &

    E-Print Network [OSTI]

    safety standard as a regulation. 30 1Q, 2004With industry and code officials, develop templates and NFPA to develop first-order continuing education for code officials. 3 Date (FY Technologies Program Hydrogen Codes & Standards #12;Hydrogen Codes & Standards: Goal & Objectives Goal

  20. AUGUST AND SEPTEMBER SYSTEM SAFETY PROGRESS REPORT

    E-Print Network [OSTI]

    Rathbun, Julie A.

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

  1. Compiling Codes

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room News PublicationsAuditsCluster Compatibilitydefault SignEnvironmentAprilCompilerCompiling Codes

  2. Safety, Security

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12University SafetyHealthSafetySafety,

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

    E-Print Network [OSTI]

    Minnesota, University of

    . Serious, potentially life-threatening illness can strike fast. DO NOT TAKE HEAT STRESS LIGHTLY! Here the victim liquids to drink. Treat for shock until professional medical help arrives. Heat Stress Safety Tip Facts 2004, between 300 to 600 people die annually because of natural (hot weather) heat stress. OSHA

  4. Facility Safety

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

    2002-05-20

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

  5. 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

  6. Review of Management of Safety Systems at the Hanford Tank Farms...

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

    reviews of DSA changes and of safety system compliance with design requirements and codes. Additionally, ORP has adequately completed several efforts directly related to...

  7. 1 INTRODUCTION Seismic design provisions in building codes aim

    E-Print Network [OSTI]

    Baker, Jack W.

    1 INTRODUCTION Seismic design provisions in building codes aim to provide adequate collapse safety uncertainty for collapse safety assessment. A variety of reliability methods are explored and compared behavior of its components and its assessment requires non- linear analysis models that capture large

  8. ACADEMIC PLAN ENGAE-MA OLD CURRICULUM CODE_188_

    E-Print Network [OSTI]

    Qiu, Weigang

    ACADEMIC PLAN ENGAE-MA OLD CURRICULUM CODE_188_ DEGREE CODE _24__ Hunter College of the City, DEGREE AUDIT DIVISION. Student's Signature Date ____________________ #12;ACADEMIC PLAN ENGAE-MA OLD and Safety 1 Fall Spring Summer SEDC 711 Advanced Study of Young Adult Literature in our Diverse Population

  9. Life sciences

    SciTech Connect (OSTI)

    Day, L. (ed.)

    1991-04-01

    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)

  10. Building Energy Code

    Broader source: Energy.gov [DOE]

    Tennessee is a "home rule" state which leaves adoption of codes up to the local codes jurisdictions. State energy codes are passed through the legislature, apply to all construction and must be...

  11. Quantum convolutional stabilizer codes 

    E-Print Network [OSTI]

    Chinthamani, Neelima

    2004-09-30

    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...

  12. 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...

  13. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Kentucky Building Code (KBC) is updated every three years on a cycle one year behind the publication year for the International Building Code. Any changes to the code by the state of Kentucky...

  14. Building Energy Code

    Broader source: Energy.gov [DOE]

    The State Building Code Council revised the Washington State Energy Code (WESC) in February 2013, effective July 1, 2013. The WESC is a state-developed code based upon ASHRAE 90.1-2010 and the...

  15. Building Energy Code

    Broader source: Energy.gov [DOE]

    Mississippi's existing state code is based on the 1977 Model Code for Energy Conservation (MCEC). The existing law does not mandate enforcement by localities, and any revised code will probably...

  16. Texas Energy Code Compliance Collaborative 

    E-Print Network [OSTI]

    Herbert, C.

    2013-01-01

    wide cross section of E.E. industries ESL-KT-13-12-29 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16-18 In 2012, Texas reported more new building starts than any other state – the next highest... seat. No enforcement is permitted, but builders report inspections are performed. 11 ESL-KT-13-12-29 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16-18 Texas Health and Safety Code, Section 388.003 (c) A...

  17. 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...

  18. Building Energy Code

    Broader source: Energy.gov [DOE]

    The North Carolina State Building Code Council is responsible for developing all state codes. By statute, the Commissioner of Insurance has general supervision over the administration and...

  19. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Rhode Island Building Code Standards Committee adopts, promulgates and administers the state building code. Compliance is determined through the building permit and inspection process by local...

  20. OCCUPATIONAL HEALTH AND SAFETY

    E-Print Network [OSTI]

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

  1. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C. (Malmoe, SE)

    1984-01-01

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

  2. Facility Safety

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

    2013-06-21

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

  3. 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

    2009-03-01

    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.

  4. 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

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

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

    2006-07-24

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

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

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

    2001-10-24

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

  7. Safety Share from National Safety Council

    Broader source: Energy.gov [DOE]

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

  8. Delivering safety

    SciTech Connect (OSTI)

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

    2007-07-01

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

  9. Safety Issues

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 of 6Site Safety

  10. Radiation Safety

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMassR&D100 Winners * Impacts on GlobalRachel Ruggirello RachelRadiation DrySafety Home

  11. Job Safety

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i nA Guidephysics_today_article.pdf MoreEnergy JulyTemansonupdatedJob Safety

  12. Recent Use of Covariance Data for Criticality Safety Assessment

    SciTech Connect (OSTI)

    Rearden, Bradley T [ORNL; Mueller, Don [ORNL

    2008-01-01

    The TSUNAMI codes of the Oak Ridge National Laboratory SCALE code system were applied to a burnup credit application to demonstrate the use of sensitivity and uncertainty analysis with recent cross section covariance data for criticality safety code and data validation. The use of sensitivity and uncertainty analysis provides for the assessment of a defensible computational bias, bias uncertainty, and gap analysis for a complex system that otherwise could be assessed only through the use of expert judgment and conservative assumptions.

  13. ENVIRONMENTAL, HEALTH AND SAFETY

    E-Print Network [OSTI]

    California at Davis, University of

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

  14. Unfolding the color code

    E-Print Network [OSTI]

    Aleksander Kubica; Beni Yoshida; Fernando Pastawski

    2015-03-06

    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.

  15. HotSpot Health Physics Codes

    SciTech Connect (OSTI)

    2013-04-18

    The HotSpot Health Physics Codes were created to provide emergency response personnel and emergency planners with a fast, field-portable set of software tools for evaluating insidents involving redioactive material. The software is also used for safety-analysis of facilities handling nuclear material. HotSpot provides a fast and usually conservative means for estimation the radiation effects associated with the short-term (less than 24 hours) atmospheric release of radioactive materials.

  16. Nuclear Safety | Department of Energy

    Office of Environmental Management (EM)

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

  17. Coding AuthentiCity

    E-Print Network [OSTI]

    Mercier, Rachel Havens

    2008-01-01

    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 ...

  18. Building Energy Code

    Broader source: Energy.gov [DOE]

    New Hampshire adopted a mandatory statewide building code in 2002 based on the 2000 IECC. SB 81 was enacted in July 2007, and it upgraded the New Hampshire Energy Code to the 2006 IECC. In...

  19. 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 deta...

  20. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Indiana Residential Building Code is based on the 2003 IRC with state amendments (eff. 9/11/05). This code applies to 1 and 2 family dwellings and townhouses. During the adoption process,...

  1. Building Energy Code

    Broader source: Energy.gov [DOE]

    Changes to the energy code are submitted to the Uniform Building Code Commission. The proposed change is reviewed by the Commission at a monthly meeting to decide if it warrants further...

  2. Guam- 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...

  3. Building Energy Code

    Broader source: Energy.gov [DOE]

    In 2006 Iowa enacted H.F. 2361, requiring the State Building Commissioner to adopt energy conservation requirements based on a nationally recognized building energy code. The State Building Code...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. Building Energy Code

    Broader source: Energy.gov [DOE]

    The 2012 IECC is in effect for all residential and commercial buildings, Idaho schools, and Idaho jurisdictions that adopt and enforce building codes, unless a local code exists that is more...

  9. Building Energy Code

    Broader source: Energy.gov [DOE]

    Delaware Energy Code is reviewed by Delaware Energy Office every three years for potential updates to the most recent version of International Energy Conservation Code (IECC) and ASHRAE Standard ...

  10. Building Energy Code

    Broader source: Energy.gov [DOE]

    Legislation passed in March 2010 authorized the Alabama Energy and Residential Code (AERC) Board to adopt mandatory residential and commercial energy codes for all jurisdictions. This is the firs...

  11. 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...

  12. Building Energy Code

    Broader source: Energy.gov [DOE]

    In September 2011 the Nebraska Building Energy Code was updated to the 2009 International Energy Conservation Code (IECC) standards.  As with the previous 2003 IECC standards, which had been in...

  13. Green Construction Codes 

    E-Print Network [OSTI]

    Blake, S.

    2011-01-01

    The network coding is a new paradigm that has been shown to improve throughput, fault tolerance, and other quality of service parameters in communication networks. The basic idea of the network coding techniques is to ...

  14. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Florida Building Commission (FBC) is directed to adopt, revise, update, and maintain the Florida Building Code in accordance with Chapter 120 of the state statutes. The code is mandatory...

  15. Building Energy Code

    Broader source: Energy.gov [DOE]

    A mandatory energy code is not enforced at the state level. If a local energy code is adopted, it is enforced at the local level. Builders or sellers of new residential buildings (single-family or...

  16. Building Energy Code

    Broader source: Energy.gov [DOE]

    The 1993 State Legislature updated the state energy code to the 1989 Model Energy Code (MEC) and established a procedure to update the standard. Then in 1995, following consultation with an...

  17. Building Energy Code

    Broader source: Energy.gov [DOE]

    Public Act 093-0936 (Illinois Energy Conservation Code for Commercial Buildings) was signed into law in August, 2004. The Illinois Energy Conservation Code for Commercial Buildings became effective...

  18. Coding with side information 

    E-Print Network [OSTI]

    Cheng, Szeming

    2005-11-01

    Source coding and channel coding are two important problems in communications. Although side information exists in everyday scenario, the e?ect of side information is not taken into account in the conventional setups. ...

  19. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Virginia Uniform Statewide Building Code (USBC) is a statewide minimum requirement that local jurisdictions cannot amend. The code is applicable to all new buildings in the commonwealth. The...

  20. Building Energy Code

    Broader source: Energy.gov [DOE]

    In March 2006, SB 459 was enacted to promote renewable energy and update the state's building energy codes.

  1. SHIPBOARD LABORATORY SAFETY PROGRAM

    E-Print Network [OSTI]

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

  2. Joint nuclear safety research projects between the US and Russian Federation International Nuclear Safety Centers

    SciTech Connect (OSTI)

    Bougaenko, S.E.; Kraev, A.E. [International Nuclear Safety Center of the Russian MINATOM, Moscow (Russian Federation); Hill, D.L.; Braun, J.C.; Klickman, A.E. [Argonne National Lab., IL (United States). International Nuclear Safety Center

    1998-08-01

    The Russian Federation Ministry for Atomic Energy (MINATOM) and the US Department of Energy (USDOE) formed international Nuclear Safety Centers in October 1995 and July 1996, respectively, to collaborate on nuclear safety research. Since January 1997, the two centers have initiated the following nine joint research projects: (1) INSC web servers and databases; (2) Material properties measurement and assessment; (3) Coupled codes: Neutronic, thermal-hydraulic, mechanical and other; (4) Severe accident management for Soviet-designed reactors; (5) Transient management and advanced control; (6) Survey of relevant nuclear safety research facilities in the Russian Federation; (8) Advanced structural analysis; and (9) Development of a nuclear safety research and development plan for MINATOM. The joint projects were selected on the basis of recommendations from two groups of experts convened by NEA and from evaluations of safety impact, cost, and deployment potential. The paper summarizes the projects, including the long-term goals, the implementing strategy and some recent accomplishments for each project.

  3. Commercial Vehicle Safety Alliance Commercial Vehicle Safety...

    Office of Environmental Management (EM)

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

  4. Above Code: What does that mean? 

    E-Print Network [OSTI]

    Muns, S.

    2007-01-01

    with electronic ballast ?? “Super-T8” systems L.E.D. - Light Emitting Diode ?? Pros: • Energy Efficient • Super-Long Life - 100,000 hrs ?? Cons: Expensive• • Difficult to Produce “White” Light • Icing in outdoor applicationsgpp ??Consume as much as 75% less energy... construction ?? The average home emits twice as many greenhouse SourceSource:: 2002 US Census gases (GHG) as the average car National Perspective ?? Energy savings potential in the 15 states with least efficient codes (or no code) • 18.5 trillion Btu...

  5. Cost and code study of underground buildings

    SciTech Connect (OSTI)

    Sterling, R.L.

    1981-01-01

    Various regulatory and financial implications for earth-sheltered houses and buildings are discussed. Earth-sheltered houses are covered in the most detail including discussions of building-code restrictions, HUD Minimum Property Standards, legal aspects, zoning restrictions, taxation, insurance, and home financing. Examples of the initial-cost elements in earth-sheltered houses together with projected life-cycle costs are given and compared to more-conventional energy-conserving houses. For larger-scale underground buildings, further information is given on building code, fire protection, and insurance provisions. Initial-cost information for five large underground buildings is presented together with energy-use information where available.

  6. Hydrogen Safety Panel

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

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

  7. August 2012 Safety Forecast

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

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

  8. FIRE SAFETY REPORT ENVIRONMENTAL HEALTH & SAFETY SERVICES

    E-Print Network [OSTI]

    Hong, Don

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

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

    SciTech Connect (OSTI)

    Cerruti, S.J.

    1997-06-26

    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.

  10. Coding theory basics Evaluation codes from algebraic varieties

    E-Print Network [OSTI]

    Little, John B.

    Coding theory basics Evaluation codes from algebraic varieties Interlude ­ counting rational points theory basics Evaluation codes from algebraic varieties Interlude ­ counting rational points on varieties Cubic surfaces and codes Outline 1 Coding theory basics 2 Evaluation codes from algebraic varieties 3

  11. 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 ...

  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. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Office of the State Fire Marshal is granted the authority to promulgate amendments, revisions, and alternative compliance methods for the code.

  14. 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.

    1985-03-01

    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.

  15. Building Energy Code

    Broader source: Energy.gov [DOE]

    Kansas adopted the 2006 International Energy Conservation Code (IECC) as "the applicable state standard" for commercial and industrial buildings. Enforcement is provided by local jurisdictions; t...

  16. Building Energy Code

    Broader source: Energy.gov [DOE]

    Pennsylvania Department of Labor and Industry (DLI) has the authority to upgrade commercial and residential energy standards through the regulatory process. The current code, the 2009 UCC, became...

  17. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Energy Conservation Construction Code of New York State (ECCCNYS) requires that all government, commercial and residential buildings, including renovations involving building system replaceme...

  18. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Maryland Building Performance Standards (MBPS) are adopted by the Maryland Department of Housing and Community Development (DHCD) Codes Administration. As required by legislation passed in...

  19. 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

    2014-09-01

    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.

  20. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01

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

  1. 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 on Delicious Rank EERE:Financing Tool Fits the Bill FinancingDepartment ofPowerScenarioCoalThermochemical

  2. 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: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration wouldMass map shines light on771/6/14RecentGeospatialReliabilityWorkingResearch Staff

  3. 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 on Delicious Rank EERE:Financing Tool FitsProjectData Dashboard RutlandSTEAB's Priorities

  4. 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 on Delicious Rank EERE:Financing Tool FitsProjectData Dashboard RutlandSTEAB's PrioritiesFuel Cell Technologies Office

  5. 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 on Delicious Rank EERE:Financing Tool FitsProjectData Dashboard RutlandSTEAB's PrioritiesFuel Cell Technologies OfficeU.S.

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustmentsShirleyEnergyTher i n c i p aDepartment of Energyof the CleanClient educationCoalbedFurar,

  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 Data Center Home Page on Delicious Rank EERE:FinancingPetroleum Based| Department8, 2015 GATEWAY Takes

  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 on Delicious Rank EERE: Alternative Fuelsof Energy Services » ProgramPolicySenateFlyer, Title VI Flyer,

  9. 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 on Delicious Rank EERE: Alternative Fuels DataEnergy Webinar:IAbout Us » ContactCounty Aims toAppropriation FYSafety,

  10. Coding Hazardous Tree Failures for a Data Management System

    E-Print Network [OSTI]

    Standiford, Richard B.

    Terms: hazard trees; hazard reduction; recreation areas; urban forestry; safety standards; dataCoding Hazardous Tree Failures for a Data Management System Lee A. Paine PACIFIC SOUTHWEST hazardous tree failures for a data management system. Gen. Tech. Rep. PSW-29, 108 p., illus. Pacific

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

    E-Print Network [OSTI]

    Li, X. Rong

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

  12. Environmental Health and Safety Department

    E-Print Network [OSTI]

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

  13. Student Honor Code Responsible Administrative Unit: Student Life

    E-Print Network [OSTI]

    of academic excellence and personal integrity regarding my schoolwork, exams, academic projects, and research in the area of academic integrity. As a Mines student, I am expected to adhere to the highest standards endeavors. I will act honestly, responsibly, and above all, with honor and integrity in all aspects of my

  14. Georgia Institute of Laboratory Safety

    E-Print Network [OSTI]

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

  15. Criticality Safety | Department of Energy

    Office of Environmental Management (EM)

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

  16. Occupational Health and Safety Manual

    E-Print Network [OSTI]

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

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

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

    2010-04-08

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

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

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

    2010-04-08

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

  19. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03

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

  20. 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

  1. Optical Safety of LEDs

    SciTech Connect (OSTI)

    none,

    2013-06-01

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

  2. Aviation safety analysis

    E-Print Network [OSTI]

    Ausrotas, Raymond A.

    1984-01-01

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

  3. Complete Safety Training

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

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

  4. Hydrogen Safety Knowledge Tools

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

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

  5. Preliminary Safety Design RM

    Office of Environmental Management (EM)

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

  6. 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.

  7. CORCON-MOD1 preliminary evaluation and application to safety analysis of a large LMFBR plant

    SciTech Connect (OSTI)

    Chen, K.H.; Ray, K.S.

    1981-06-30

    The CORCON-MOD1 core material-concrete interaction code, developed at the Sandia Laboratories for LWR safety analysis, was adapted for analyzing a postulated LMFBR core melt accident.

  8. 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

    2014-01-01

    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.

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

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

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

  10. Report number codes

    SciTech Connect (OSTI)

    Nelson, R.N.

    1985-05-01

    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.

  11. Fusion safety program Annual report, Fiscal year 1995

    SciTech Connect (OSTI)

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

    1995-12-01

    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.

  12. Generic safety documentation model

    SciTech Connect (OSTI)

    Mahn, J.A.

    1994-04-01

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

  13. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

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

  14. Nuclear Explosive Safety Manual

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

    2009-04-14

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

  15. DOE handbook electrical safety

    SciTech Connect (OSTI)

    1998-01-01

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

  16. Protecting Life on Earth

    E-Print Network [OSTI]

    Anderson, Byron P.

    2011-01-01

    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

  17. Still Life Architecture

    E-Print Network [OSTI]

    Özdamar, Esen Gökçe

    2014-01-01

    Still-Life Architecture By Esen Gökçe Özdamar Edited by Lanaturned into “still-life architecture. ” Many of the homes3. Author photo. Still-Life Architecture Figure 4. Tepekent

  18. TRANSF code user manual

    SciTech Connect (OSTI)

    Weaver, H.J.

    1981-11-01

    The TRANSF code is a semi-interactive FORTRAN IV program which is designed to calculate the model parameters of a (structural) system by performing a least square parameter fit to measured transfer function data. The code is available at LLNL on both the 7600 and the Cray machines. The transfer function data to be fit is read into the code via a disk file. The primary mode of output is FR80 graphics, although, it is also possible to have results written to either the TTY or to a disk file.

  19. Annual Fire Safety Report

    E-Print Network [OSTI]

    Al Faruque, Mohammad Abdullah

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

  20. Annual Fire Safety Report

    E-Print Network [OSTI]

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

  1. Fire Safety January 2011

    E-Print Network [OSTI]

    Lennard, William N.

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

  2. SYSTEM SAFETY PROGRESS REPORT,

    E-Print Network [OSTI]

    Rathbun, Julie A.

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

  3. Health, Safety & Wellbeing Policy

    E-Print Network [OSTI]

    Mottram, Nigel

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

  4. OCCUPATIONAL SAFETY and HEALTH

    E-Print Network [OSTI]

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

  5. Nevada Energy Code for Buildings

    Broader source: Energy.gov [DOE]

    Legislation signed in 2009 changed the process of adopting building codes in the state. Previously, the statewide code would only apply to local governments that had not already adopted a code,...

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

    SciTech Connect (OSTI)

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

    2011-09-29

    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.

  7. Safety Criteria and Safety Lifecycle for Artificial Neural Networks

    E-Print Network [OSTI]

    Kelly, Tim

    Safety Criteria and Safety Lifecycle for Artificial Neural Networks Zeshan Kurd, Tim Kelly and Jim performance based techniques that aim to improve the safety of neural networks for safety critical for safety assurance. As a result, neural networks are typically restricted to advisory roles in safety

  8. 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

  9. Compiling Codes on Euclid

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

    example.x example.c For C++ source code use mpiCC: % mpiCC -o example.x example.C PGI Compilers (CC++Fortran) See PGI compiler for information about this compiler. GNU Compilers...

  10. Compiling Codes on Hopper

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

    example.x example.c For C++ source code use CC % CC -fast -o example.x example.C All compilers on Hopper, PGI, Pathscale, Cray, GNU, and Intel, are provided via five programming...

  11. Climate Code Foundation

    E-Print Network [OSTI]

    Barnes, Nick; Jones, David

    2011-07-05

    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...

  12. Building Energy Code

    Broader source: Energy.gov [DOE]

    Missouri does not have a statewide building or energy code for private residential and commercial buildings, and there currently is no state regulatory agency authorized to promulgate, adopt, or...

  13. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Oregon Energy Code amendments were most recently updated for both residential and non-residential construction in 2014. In October 2010 Oregon also adopted the Oregon Solar Installation...

  14. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Texas State Energy Conservation Office (SECO) by rule may choose to adopt the latest published editions of the energy efficiency provisions of the International Residential Code (IRC) or the...

  15. 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...

  16. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Massachusetts Board of Building Regulations and Standards has authority to promulgate the Massachusetts State Building Code (MSBC). The energy provisions in the MSBC were developed by the Boa...

  17. Systematic wireless network coding

    E-Print Network [OSTI]

    Shrader, Brooke E.

    We present a systematic network coding strategy for cooperative communication, in which some nodes may replicate-and-forward packets in addition to sending random linear combinations of the packets. We argue that if this ...

  18. Safety of Department of Energy-Owned Nuclear Reactors

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

    1986-09-23

    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.

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

    SciTech Connect (OSTI)

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

    2000-05-05

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

  20. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

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

    2008-01-15

    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.

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

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

    1998-05-01

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

  2. Integrating S6 Code Search and Code Bubbles

    E-Print Network [OSTI]

    Reiss, Steven P.

    the results of the search. Index Terms--Code search, integrated development envi- ronments, test-based searchIntegrating S6 Code Search and Code Bubbles Steven P. Reiss Department of Computer Science Brown search over open source repositories as part of the Code Bub- bles integrated development environment

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

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

    2006-12-27

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

  4. LNG Safety Research: FEM3A Model Development

    SciTech Connect (OSTI)

    Iraj A. Salehi

    2004-09-30

    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. Family Quality of Life: A Qualitative Inquiry

    E-Print Network [OSTI]

    Poston, Denise J.; Turnbull, Ann P.; Park, Jiyeon; Mannan, Hasheem; Marquis, Janet; Wang, Mian

    2003-01-01

    with disabilities: Emotional Well-Being, Interpersonal Relations, Material Well- Being, Personal Development, Physical Well-Being, Self-Determination, Social Inclusion, and Rights. Although individual quality of life research has produced sufficient momentum... support from disability-related services into the particular domain to which the support was related (e.g., we coded support from physicians within the Health domain). Our study pointed to the importance of Physical Environment (subdomains of Home...

  6. Integrating Loran and GNSS for Safety of Life Applications

    E-Print Network [OSTI]

    Stanford University

    London, CT. After his retirement from the Coast Guard, he founded Peterson Integrated Geopositioning, LLC on the Department of Transportation's technical evaluation of Loran. Per Enge is a professor in the Department

  7. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

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

  8. TWRS safety management plan

    SciTech Connect (OSTI)

    Popielarczyk, R.S., Westinghouse Hanford

    1996-08-01

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

  9. Quantum error control codes 

    E-Print Network [OSTI]

    Abdelhamid Awad Aly Ahmed, Sala

    2008-10-10

    by SALAH ABDELHAMID AWAD ALY AHMED Submitted to the O–ce of Graduate Studies of Texas A&M University in partial fulflllment of the requirements for the degree of DOCTOR OF PHILOSOPHY May 2008 Major Subject: Computer Science QUANTUM ERROR CONTROL CODES A... Members, Mahmoud M. El-Halwagi Anxiao (Andrew) Jiang Rabi N. Mahapatra Head of Department, Valerie Taylor May 2008 Major Subject: Computer Science iii ABSTRACT Quantum Error Control Codes. (May 2008) Salah Abdelhamid Awad Aly Ahmed, B.Sc., Mansoura...

  10. 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

    2013-06-18

    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.

  11. DOE Explosives Safety Manual

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

    1996-03-29

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

  12. Coiled Tubing Safety Manual

    SciTech Connect (OSTI)

    Crow, W.

    1999-04-06

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

  13. Aviation Management and Safety

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

    2011-06-15

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

  14. Aviation Management and Safety

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

    2011-06-15

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

  15. 1 Food Safety Policy July 2010 Food Safety Policy

    E-Print Network [OSTI]

    Sussex, University of

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

  16. Upgrading the HFIR Thermal-Hydraulic Legacy Code Using COMSOL

    SciTech Connect (OSTI)

    Bodey, Isaac T [ORNL] [ORNL; Arimilli, Rao V [ORNL] [ORNL; Freels, James D [ORNL] [ORNL

    2010-01-01

    Modernization of the High Flux Isotope Reactor (HFIR) thermal-hydraulic (TH) design and safety analysis capability is an important step in preparation for the conversion of the HFIR core from a high enriched uranium (HEU) fuel to a low enriched uranium (LEU) fuel. Currently, an important part of the HFIR TH analysis is based on the legacy Steady State Heat Transfer Code (SSHTC), which adds much conservatism to the safety analysis. The multi-dimensional multi-physics capabilities of the COMSOL environment allow the analyst to relax the number and magnitude of conservatisms, imposed by the SSHTC, to present a more physical model of the TH aspect of the HFIR.

  17. 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...

  18. 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)

    2006-07-01

    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)

  19. Student Code Number: Thermodynamics

    E-Print Network [OSTI]

    Feeny, Brian

    Student Code Number: Thermodynamics Ph.D. Qualifying Exam Department of Mechanical Engineering;Thermodynamics Qualifier January 2013 Problem 1 Air is compressed in an axial-flow compressor operating at steady of exergy destruction within the compressor, in kJ per kg of air flowing. #12;Thermodynamics Qualifier

  20. Introduction to Algebraic Codes

    E-Print Network [OSTI]

    Purdue University. W.Lafayette, Indiana ..... information. It motivated many scientists to study the codes transmitted by living beings, ...... We have the following diagram, where lines indicate inclusion relation,. ?. Fp4 Fp6 Fp10 ...... K over. the field K. There is a serious problem of being incomplete for the affine spaces: 69 ...

  1. Safety of Accelerator Facilities

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

    2004-07-23

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

  2. Integrated Safety Management Policy

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

    2011-04-25

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

  3. Safety of Accelerator Facilities

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

    2011-07-21

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

  4. Safety of Accelerator Facilities

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

    2001-01-08

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

  5. Safety of Hydrogen Systems Installed in Outdoor Enclosures

    SciTech Connect (OSTI)

    Barilo, Nick F.

    2013-11-06

    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.

  6. Photovoltaics Life Cycle Analysis

    E-Print Network [OSTI]

    1 Photovoltaics Life Cycle Analysis Vasilis Fthenakis Center of Life Cycle Analysis Earth & Environmental Engineering Department Columbia University and National Photovoltaic (PV) EHS Research Center (air, water, solid) M, Q E PV array Photovoltaic modules Balance of System (BOS) (Inverters

  7. 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...

  8. 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.

  9. 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))

    1992-01-01

    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.

  10. 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).

  11. CRAD, Facility Safety- Unreviewed Safety Question Requirements

    Broader source: Energy.gov [DOE]

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

  12. 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.

  13. 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

  14. Life Cycle Cost Estimate

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

    1997-03-28

    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.

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

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-03-01

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

  16. Normalization of Process Safety Metrics 

    E-Print Network [OSTI]

    Wang, Mengtian

    2012-10-19

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

  17. What's the Code? Automatic Classification of Source Code Archives

    E-Print Network [OSTI]

    Giles, C. Lee

    show that source code can be accurately and automatically classified into topical categories and canWhat's the Code? Automatic Classification of Source Code Archives Secil Ugurel1, Robert Krovetz2, C.psu.edu 2NECResearchInstitute 4 IndependenceWay, Princeton,NJ 08540 {krovetz, dpennock, compuman} @research

  18. Space time coded code division multiplexing on SC140 DSP 

    E-Print Network [OSTI]

    Menon, Murali P

    2001-01-01

    is implemented on StarCore's SC140 fixed-point DSP core. The very large instruction word architecture of the SC140 is utilized to efficiently implement space-time coded code-division multiplexing system. The goal is to evaluate the suitability of space-time coded...

  19. 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

  20. Adaptive code generators for tree coding of speech 

    E-Print Network [OSTI]

    Dong, Hui

    1998-01-01

    Tree coding is a promising way of obtaining good performance for medium-to-low rate speech coding. The key part of a tree coder is the code generator which consists of a short-term predictor and a long-term predictor. The ...

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

    SciTech Connect (OSTI)

    Not Available

    1985-07-01

    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.

  2. Origin of Life prebiotic before life

    E-Print Network [OSTI]

    Houde, Peter

    of rock that often preserves fossils stratigraphy ­ the study of sedimentary layers superposition chain #12;Seismic Activity #12;vectors and rates of plate movement #12;fossil record of life on earth

  3. Code Completion From Abbreviated Input

    E-Print Network [OSTI]

    Miller, Robert C.

    Abbreviation Completion is a novel technique to improve the efficiency of code-writing by supporting code completion of multiple keywords based on non-predefined abbreviated input - a different approach from conventional ...

  4. Network coding for anonymous broadcast

    E-Print Network [OSTI]

    Sergeev, Ivan A

    2013-01-01

    This thesis explores the use of network coding for anonymous broadcast. Network coding, the technique of transmitting or storing mixtures of messages rather than individual messages, can provide anonymity with its mixing ...

  5. Rotationally invariant multilevel block codes 

    E-Print Network [OSTI]

    Kulandaivelu, Anita

    1993-01-01

    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 ...

  6. Safety Assessment of PowerBeam Flywheel Technology

    SciTech Connect (OSTI)

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

    2009-11-01

    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.

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

    E-Print Network [OSTI]

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

  8. SECTION 9-DRIVER SAFETY PROGRAM AND VEHICLE OPERATION/ AND MAINTENANCE

    E-Print Network [OSTI]

    Selmic, Sandra

    SECTION 9- DRIVER SAFETY PROGRAM AND VEHICLE OPERATION/ AND MAINTENANCE INTRODUCTION Driving, driving statistically exposes you to the single greatest degree of risk in your everyday life. The driving in a vehicular accident while conducting State business. · Make recommendations on how to operate a vehicle

  9. Confocal coded aperture imaging

    DOE Patents [OSTI]

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

    2001-01-01

    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.

  10. Chemical Hygiene and Safety Plan

    E-Print Network [OSTI]

    Ricks Editor, R.

    2009-01-01

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

  11. Half-Product Codes 

    E-Print Network [OSTI]

    Emmadi, Santosh Kumar

    2014-12-11

    for their continuous, granted for life, love and support. I would like to thank my extended family, my more-than-friends here at College Station, Sriharsha Madala, Shantanu Deshpande, Abhishek Yada, Amruth Juturu, Vamseedhar Raja, Srikanth PVK, and Sindhu Chittireddy...

  12. Improving Code Compliance

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:FinancingPetroleum12,ExecutiveFinancingREnergy ToolsCoordinationDepartmentImproving Code

  13. Design of proximity detecting codes 

    E-Print Network [OSTI]

    Perisetty, Srinivas

    1997-01-01

    class of codes called Proximity Detecting Codes can be used to overcome this problem associated with asynchronous channels. A t-proximity detecting (t-PD) code can detect when a received word is within distance t from the transmitted codeword, when using...

  14. A Mechanically Verified Code Generator

    E-Print Network [OSTI]

    Boyer, Robert Stephen

    A Mechanically Verified Code Generator William D. Young Technical Report 37 January, 1989, one which generates semantically equivalent target language code for any given source language program we describe the implementation and proof of a code generator, a major component of a compiler

  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. HUDU: The Hanford Unified Dose Utility computer code

    SciTech Connect (OSTI)

    Scherpelz, R.I.

    1991-02-01

    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.

  17. Final Technical Report: Hydrogen Codes and Standards Outreach

    SciTech Connect (OSTI)

    Hall, Karen I.

    2007-05-12

    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.

  18. Safety shutdown separators

    DOE Patents [OSTI]

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

    2015-06-30

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

  19. Lecture notes for criticality safety

    SciTech Connect (OSTI)

    Fullwood, R.

    1992-03-01

    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.

  20. Code requirements for concrete repository and processing facilities

    SciTech Connect (OSTI)

    Hookham, C.J. [Black & Veatch, Ann Arbor, MI (United States); Palaniswamy, R. [Bechtel Savannah River, Inc., North Augusta, SC (United States)

    1993-04-01

    The design and construction of facilities and structures for the processing and safe long-term storage of low- and high-level radioactive wastes will likely employ structural concrete. This concrete will be used for many purposes including structural support, shielding, and environmental protection. At the present time, there are no design costs, standards or guidelines for repositories, waste containers, or processing facilities. Recently, the design and construction guidelines contained in American Concrete Institute (ACI), Code Requirements for Nuclear Safety Related Concrete Structures (ACI 349), have been cited for low-level waste (LLW) repositories. Conceptual design of various high-level (HLW) repository surface structures have also cited the ACI 349 Code. However, the present Code was developed for nuclear power generating facilities and its application to radioactive waste repositories was not intended. For low and medium level radioactive wastes, concrete has a greater role and use in processing facilities, engineered barriers, and repository structures. Because of varied uses and performance/safety requirements this review of the current ACI 349 Code document was required to accommodate these special classes of structures.

  1. SECTION 4-FIRE SAFETY, INCLUDING LIFE SAFETY STANDARDS FIRE HAZARDS ON CAMPUS

    E-Print Network [OSTI]

    Selmic, Sandra

    laid down while they are on or used to dry clothes. · Portable space heaters placed near combustibles

  2. Social Media: Flood #FloodSafety #SummerSafety

    E-Print Network [OSTI]

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

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

    E-Print Network [OSTI]

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

  4. 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

  5. Health and Safety Policy Statement4 Health and Safety Policy

    E-Print Network [OSTI]

    Haase, Markus

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

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

    E-Print Network [OSTI]

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

  7. Packaging and Transportation Safety

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

    1995-09-27

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

  8. Packaging and Transportation Safety

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

    2010-05-14

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

  9. Earth Sciences Safety Handbook

    E-Print Network [OSTI]

    Cambridge, University of

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

  10. 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,...

  11. Nuclear Explosive Safety

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

    2014-07-10

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

  12. Packaging and Transportation Safety

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

    1995-09-27

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

  13. Packaging and Transportation Safety

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

    1996-10-02

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

  14. Nuclear Explosive Safety

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

    2006-06-12

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

  15. Promulgating Nuclear Safety Requirements

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

    1996-05-15

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

  16. LABORATORY SAFETY October 2012

    E-Print Network [OSTI]

    Chan, Hue Sun

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

  17. Wyner-Ziv coding based on TCQ and LDPC codes and extensions to multiterminal source coding 

    E-Print Network [OSTI]

    Yang, Yang

    2005-11-01

    performs only 0.2 dB away from the Wyner-Ziv limit D??W Z(R) at high rate, which mirrors the performance of entropy-coded TCQ in classic source coding. Practical designs perform 0.83 dB away from D??W Z(R) at medium rates. With 2-D trellis-coded vector...

  18. Fusion Safety Program annual report, Fiscal Year 1993

    SciTech Connect (OSTI)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1993-12-01

    This report summarizes the major activities of the Fusion Safety Program in Fiscal Year 1993. The Idaho National Engineering Laboratory (INEL) has been designated by DOE as the lead laboratory for fusion safety, and EG&G Idaho, Inc., is the prime contractor for INEL operations. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL and in participating organizations, including universities and private companies. Technical areas covered in the report include tritium safety, beryllium safety, activation product release, reactions involving potential plasma-facing materials, safety of fusion magnet systems, plasma disruptions and edge physics modeling, risk assessment failure rates, computer codes for reactor transient analysis, and regulatory support. These areas include work completed in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed at the INEL for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor projects at the Princeton Plasma Physics Laboratory and a summary of the technical support for the ARIES/PULSAR commercial reactor design studies.

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

    SciTech Connect (OSTI)

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

    1994-01-01

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

  20. 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

  1. COLUMBIA UNIVERSITY Radiation Safety Program

    E-Print Network [OSTI]

    Jia, Songtao

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

  2. 2015 Construction Safety Workshop Presentations

    Broader source: Energy.gov [DOE]

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

  3. HEALTH AND SAFETY INDUCTION Introduction

    E-Print Network [OSTI]

    Mucina, Ladislav

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

  4. Coding Archives - Nercenergy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room News PublicationsAuditsCluster Compatibility Mode Cluster CompatibilityCoalCode of

  5. Chapter 7 -Rotary Agricultural Mower An accident with a rotary mower can cost you your life! A rotary agricultural mower can

    E-Print Network [OSTI]

    Tullos, Desiree

    138 Chapter 7 - Rotary Agricultural Mower Safety An accident with a rotary mower can cost you your life! A rotary agricultural mower can also injure innocent bystanders, so it is also important and following safety practices are the best ways to prevent accidents. Safety Practices for Rotary Mowers Use

  6. Pressure Safety of JLAB 12GeV Upgrade Cryomodule

    SciTech Connect (OSTI)

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

    2009-11-01

    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.

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

    E-Print Network [OSTI]

    Eberhard, Marc O.

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

  8. What's coming in 2012 codes 

    E-Print Network [OSTI]

    Lacey, E

    2011-01-01

    The 2012 IECC America?s Model Building Energy Code November 9, 2011 Presentation to Clean Air Through Energy Efficiency Conference Dallas, TX Eric Lacey Responsible Energy Codes Alliance Responsible Energy Codes Alliance ? A broad... Texas Building Energy Performance Standards What is effective now? ? 2009 IRC ? January 1, 2012 ? Applies to all 1- and 2-family dwellings ? 2009 IECC ? April 1, 2011 ? Applies to all other buildings Texas Websites ? http://www.seco.cpa.s tate...

  9. RECOMMENDED TRITIUM OXIDE DEPOSITION VELOCITY FOR USE IN SAVANNAH RIVER SITE SAFETY ANALYSES

    SciTech Connect (OSTI)

    Lee, P.; Murphy, C.; Viner, B.; Hunter, C.; Jannik, T.

    2012-04-03

    The Defense Nuclear Facilities Safety Board (DNFSB) has recently questioned the appropriate value for tritium deposition velocity used in the MELCOR Accident Consequence Code System Ver. 2 (Chanin and Young 1998) code when estimating bounding dose (95th percentile) for safety analysis (DNFSB 2011). The purpose of this paper is to provide appropriate, defensible values of the tritium deposition velocity for use in Savannah River Site (SRS) safety analyses. To accomplish this, consideration must be given to the re-emission of tritium after deposition. Approximately 85% of the surface area of the SRS is forested. The majority of the forests are pine plantations, 68%. The remaining forest area is 6% mixed pine and hardwood and 26% swamp hardwood. Most of the path from potential release points to the site boundary is through forested land. A search of published studies indicate daylight, tritiated water (HTO) vapor deposition velocities in forest vegetation can range from 0.07 to 2.8 cm/s. Analysis of the results of studies done on an SRS pine plantation and climatological data from the SRS meteorological network indicate that the average deposition velocity during daylight periods is around 0.42 cm/s. The minimum deposition velocity was determined to be about 0.1 cm/s, which is the recommended bounding value. Deposition velocity and residence time (half-life) of HTO in vegetation are related by the leaf area and leaf water volume in the forest. For the characteristics of the pine plantation at SRS the residence time corresponding to the average, daylight deposition velocity is 0.4 hours. The residence time corresponding to the night-time deposition velocity of 0.1 cm/s is around 2 hours. A simple dispersion model which accounts for deposition and re-emission of HTO vapor was used to evaluate the impact on exposure to the maximally exposed offsite individual (MOI) at the SRS boundary (Viner 2012). Under conditions that produce the bounding, 95th percentile MOI exposure, i.e., low wind speed, weak turbulence, night, low deposition velocity, the effect of deposition and re-emission on MOI exposure was found to be very small. The exposure over the two hour period following arrival of the plume was found to be decreased by less than 0.05 %. Furthermore the sensitivity to deposition velocity was low. Increasing deposition velocity to 0.5 cm/s reduced exposure to 0.3 %. After a 24 hour period, an MOI would have been exposed to all of the released material. Based on the low sensitivity of MOI exposure to the value of deposition velocity when re-emission is considered, it is appropriately conservative to use a 0.0 cm/s effective deposition velocity for safety analysis in the MACCS2 code.

  10. GENII Code | Department of Energy

    Office of Environmental Management (EM)

    For more information on GENII to: http:radiologicalsciences.pnl.govresourceshardware.asp The GENII code-specific guidance report has been issued identifying applicable...

  11. 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...

  12. Marin County- Solar Access Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    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. ...

  13. Life Before Earth

    E-Print Network [OSTI]

    Alexei A. Sharov; Richard Gordon

    2013-03-28

    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.

  14. An evaluation of the nuclear fuel performance code BISON

    SciTech Connect (OSTI)

    Perez, D. M.; Williamson, R. L.; Novascone, S. R.; Larson, T. K.; Hales, J. D.; Spencer, B. W.; Pastore, G.

    2013-07-01

    BISON is a modern finite-element based nuclear fuel performance code that has been under development at the Idaho National Laboratory (USA) since 2009. The code is applicable to both steady and transient fuel behavior and is used to analyze either 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. (authors)

  15. Seismic Safety Guide

    SciTech Connect (OSTI)

    Eagling, D.G.

    1983-09-01

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

  16. Measuring Process Safety Management

    SciTech Connect (OSTI)

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

    1992-04-01

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

  17. SSC Safety Review Document

    SciTech Connect (OSTI)

    Toohig, T.E. [ed.

    1988-11-01

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

  18. Safety Staff Contact Information

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12University Safety NumerousSafety

  19. What's the code? Automatic Classification of Source Code Archives

    E-Print Network [OSTI]

    Giles, C. Lee

    What's the code? Automatic Classification of Source Code Archives Secil Ugurel 1 , Robert Krovetz 2, zha} @cse.psu.edu 2 NEC Research Institute 4 Independence Way, Princeton, NJ 08540 {krovetz, dpennock, compuman} @research.nj.nec.com 3 School of Information Sciences and Technology The Pennsylvania State

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    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.

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

    SciTech Connect (OSTI)

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

    2006-07-01

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

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

    SciTech Connect (OSTI)

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

    2006-09-15

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

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

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

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

  4. BASIC TERM LIFE INSURANCE ANTHEM LIFE INSURANCE COMPANY

    E-Print Network [OSTI]

    - 35 - BASIC TERM LIFE INSURANCE ANTHEM LIFE INSURANCE COMPANY Maximum Benefits The amount of life and your family is important, especially in the event of a death or accident. Therefore, the CHEIBA Trust

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

    SciTech Connect (OSTI)

    Linderoth, C.E.

    1984-03-01

    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.

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

    Office of Environmental Management (EM)

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

  7. Commercial Vehicle Safety Alliance | Department of Energy

    Office of Environmental Management (EM)

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

  8. Community Pedestrian Safety Engagement Workshops in California

    E-Print Network [OSTI]

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

    2011-01-01

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

  9. Laser Pointer Safety INTRODUCTION

    E-Print Network [OSTI]

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

  10. DOE Explosives Safety Manual

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

    2006-01-09

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

  11. Nuclear Explosive Safety Manual

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

    2009-04-14

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

  12. Nuclear Explosive Safety

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

    2006-06-12

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

  13. Nuclear Explosive Safety

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

    2009-04-14

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

  14. Nuclear Explosive Safety

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

    2015-01-26

    This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs). Supersedes DOE O 452.2D and DOE M 452.2-1A.

  15. Nuclear Explosive Safety

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

    2009-04-14

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

  16. 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

  17. Integrated Safety Management

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

    2011-04-25

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

  18. Module Safety Issues (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2012-02-01

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

  19. Packaging and Transportation Safety

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

    2003-04-04

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

  20. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11

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

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

    SciTech Connect (OSTI)

    Not Available

    2014-05-01

    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.

  2. ACCELERATION PHYSICS CODE WEB REPOSITORY.

    SciTech Connect (OSTI)

    WEI, J.

    2006-06-26

    In the framework of the CARE HHH European Network, we have developed a web-based dynamic accelerator-physics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.

  3. Accelerator Physics Code Web Repository

    SciTech Connect (OSTI)

    Zimmermann, F.; Basset, R.; Bellodi, G.; Benedetto, E.; Dorda, U.; Giovannozzi, M.; Papaphilippou, Y.; Pieloni, T.; Ruggiero, F.; Rumolo, G.; Schmidt, F.; Todesco, E.; Zotter, B.W.; Payet, J.; Bartolini, R.; Farvacque, L.; Sen, T.; Chin, Y.H.; Ohmi, K.; Oide, K.; Furman, M.; /LBL, Berkeley /Oak Ridge /Pohang Accelerator Lab. /SLAC /TRIUMF /Tech-X, Boulder /UC, San Diego /Darmstadt, GSI /Rutherford /Brookhaven

    2006-10-24

    In the framework of the CARE HHH European Network, we have developed a web-based dynamic accelerator-physics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.

  4. Secure Symmetrical Multilevel Diversity Coding 

    E-Print Network [OSTI]

    Li, Shuo

    2012-07-16

    Secure symmetrical multilevel diversity coding (S-SMDC) is a source coding problem, where a total of L - N discrete memoryless sources (S1,...,S_L-N) are to be encoded by a total of L encoders. This thesis considers a natural generalization of SMDC...

  5. LFSC - Linac Feedback Simulation Code

    SciTech Connect (OSTI)

    Ivanov, Valentin; /Fermilab

    2008-05-01

    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.

  6. Publications NODC Taxonomic Code and

    E-Print Network [OSTI]

    Center (NODC) has announced the availability of the third edition of its Taxonomic Code. This expanded edition has nearly 28,000 entries giving the sci- entific names and corresponding numer- ical codes (MESA) project and the Outer Conti- nental Shelf Environmental Assessment Program (OCSEAP) conducted

  7. Safety Lifecycle for Developing Safety Critical Artificial Neural Networks

    E-Print Network [OSTI]

    Kelly, Tim

    Safety Lifecycle for Developing Safety Critical Artificial Neural Networks Zeshan Kurd, Tim Kelly.kelly}@cs.york.ac.uk Abstract. Artificial neural networks are employed in many areas of industry such as medicine and defence. There are many techniques that aim to improve the performance of neural networks for safety-critical systems

  8. 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

  9. 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

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

    E-Print Network [OSTI]

    Huang, Zhisheng

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

  11. Technology development: HEPA filter service life test plan

    SciTech Connect (OSTI)

    Kirchner, K.N.; Cummings, K.G.; Leck, W.C.; Fretthold, J.K.

    1995-05-31

    Rocky Flats Environmental Technology Site (the Site) has approximately 10,000 High Efficiency Particulate Air (HEPA) Filters installed in a variety of filter plenums. These ventilation/filtration plenum systems are used to control the release of airborne particulate contaminates to the environment during normal operations and also during potential design-based accidents. The operational integrity of the HEPA filter plenums is essential to maintaining the margins of safety as required by building specific Final Safety Analysis Reports (FSARS) for protection of the public and environment. An Unreviewed Safety Question Determination (USQD), USDQ-RFP94.0615-ARS, was conducted in 1994 addressing the potential inadequacy of the safety envelope for Protected Area building HEPA plenums. While conducting this USQD, questions were raised concerning the maximum service life criteria for HEPA filters. Accident scenarios in existing FSARs identify conditions that could potentially cause plugging or damage of down stream HEPA filters as a result of impaction from failed filters. Additionally, available data indicates that HEPA filters experience structural degradation due to the effects of age. The Unresolved Safety Question (USQ) compensatory measures thus require testing and analysis of used HEPA filters in order to determine and implement service life criteria.

  12. Portable code development in C

    SciTech Connect (OSTI)

    Brown, S.A.

    1990-11-06

    With a new generation of high performance computers appearing around us on a time scale of months, a new challenge for developers of simulation codes is to write and maintain production codes that are both highly portable and maximally efficient. My contention is that C is the language that is both best suited to that goal and is widely available today. GLF is a new code written mainly in C which is intended to have all of the XRASER physics and run on any platform of interest. It demonstrates the power of the C paradigm for code developers and flexibility and ease of use for the users. Three fundamental problems are discussed: the C/UNIX development environment; the supporting tools and libraries which handle data and graphics portability issues; and the advantages of C in numerical simulation code development.

  13. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    SciTech Connect (OSTI)

    GARVIN, L J; JENSEN, M A

    2004-04-13

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

  14. Safety Training for Shop Personnel

    E-Print Network [OSTI]

    Sniadecki, Nathan J.

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

  15. Nuclear Explosive Safety Evaluation Processes

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

    2009-04-14

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

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

    E-Print Network [OSTI]

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

  17. CRAD, NNSA- Safety Basis (SB)

    Broader source: Energy.gov [DOE]

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

  18. pamphlet04.doc SAFETY INFORMATION

    E-Print Network [OSTI]

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

  19. Every sign of life

    E-Print Network [OSTI]

    Gerasimov, Vadim, 1969-

    2003-01-01

    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 ...

  20. Life Extension Programs

    National Nuclear Security Administration (NNSA)

    in the U.S. and abroad.

    B61-12 Life Extension Program Undergoes First Full-Scale Wind Tunnel Test http:www.nnsa.energy.govmediaroompressreleaseswindtunnel

  1. LASER Safety Manual August 2007

    E-Print Network [OSTI]

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

  2. San Francisco Building Code Amendments to the

    E-Print Network [OSTI]

    . The California San Francisco Green Building Standards Code is Part 11 of twelve parts Chapter 13C of the official1 2010 San Francisco Building Code Amendments to the 2010 California Green Building Standards Code (Omitting amendments to 2010 California Building Code and 2010 California Residential Code which do

  3. ANNUAL FIRE SAFETY RESIDENCE HALLS

    E-Print Network [OSTI]

    Fernandez, Eduardo

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

  4. CHEMICAL LABORATORY SAFETY AND METHODOLOGY

    E-Print Network [OSTI]

    Northern British Columbia, University of

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

  5. Toolbox Safety Talk Heat Stress

    E-Print Network [OSTI]

    Pawlowski, Wojtek

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

  6. Health and Safety Training Reciprocity

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

    2014-04-14

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

  7. Safety-Critical Universit at

    E-Print Network [OSTI]

    Peleska, Jan - Fachbereich 3

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

  8. Fermilab at Work | Lab Life

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

    Lab Life Abri Benefits Office Car and Vanpool Program Chez Leon Conference Office Cultural Events DASTOW Diversity Graduate Student Association (GSA) GSA's Guide to Life Housing...

  9. Multiterminal source coding: sum-rate loss, code designs, and applications to video sensor networks 

    E-Print Network [OSTI]

    Yang, Yang

    2009-05-15

    Driven by a host of emerging applications (e.g., sensor networks and wireless video), distributed source coding (i.e., Slepian-Wolf coding, Wyner-Ziv coding and various other forms of multiterminal source coding), has ...

  10. 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

  11. ETR/ITER systems code

    SciTech Connect (OSTI)

    Barr, W.L.; Bathke, C.G.; Brooks, J.N.; Bulmer, R.H.; Busigin, A.; DuBois, P.F.; Fenstermacher, M.E.; Fink, J.; Finn, P.A.; Galambos, J.D.; Gohar, Y.; Gorker, G.E.; Haines, J.R.; Hassanein, A.M.; Hicks, D.R.; Ho, S.K.; Kalsi, S.S.; Kalyanam, K.M.; Kerns, J.A.; Lee, J.D.; Miller, J.R.; Miller, R.L.; Myall, J.O.; Peng, Y-K.M.; Perkins, L.J.; Spampinato, P.T.; Strickler, D.J.; Thomson, S.L.; Wagner, C.E.; Willms, R.S.; Reid, R.L.

    1988-04-01

    A tokamak systems code capable of modeling experimental test reactors has been developed and is described in this document. The code, named TETRA (for Tokamak Engineering Test Reactor Analysis), consists of a series of modules, each describing a tokamak system or component, controlled by an optimizer/driver. This code development was a national effort in that the modules were contributed by members of the fusion community and integrated into a code by the Fusion Engineering Design Center. The code has been checked out on the Cray computers at the National Magnetic Fusion Energy Computing Center and has satisfactorily simulated the Tokamak Ignition/Burn Experimental Reactor II (TIBER) design. A feature of this code is the ability to perform optimization studies through the use of a numerical software package, which iterates prescribed variables to satisfy a set of prescribed equations or constraints. This code will be used to perform sensitivity studies for the proposed International Thermonuclear Experimental Reactor (ITER). 22 figs., 29 tabs.

  12. Life Cycle Inventory of a CMOS Chip

    E-Print Network [OSTI]

    Boyd, Sarah; Dornfeld, David; Krishnan, Nikhil

    2006-01-01

    E. ; Zappa, S. ; “Life cycle assessment of an integratedare shown. Keywords- Life Cycle Assessment (LCA); Life Cycleindustry, and Life Cycle Assessment (LCA) is emerging as a

  13. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01

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

  14. Safety review advisor

    SciTech Connect (OSTI)

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

    1989-01-01

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

  15. OSHA`s process safety management standard

    SciTech Connect (OSTI)

    Morelli, J.A.

    1994-12-31

    On February 24, 1992, OSHA published the final rule for its Process Safety Management Standard (PSM) mandated by the Clean Air Act Amendments of 1990. (see Federal Register 57 FR 6356-6417). This standard imposes several responsibilities upon employers whose processes can cause large accident releases that could result in processes can cause large accident releases that could result in catastrophes. In contrast to OSHA`s Hazard Communication standard which focuses on routine daily exposures to hazardous materials, the PSM Standard is concerned with processes whereby the use, storage, manufacturing, handling or on-site movement of highly hazardous chemicals which exceed threshold quantities, provides potential for a catastrophic release. The PSM Standard requires: a written program, plans, training, hazard analysis and compliance auditing. This paper outlines the provisions under this Standard pursuant to OSHA regulation 29 Code of Federal Regulation 1910.119.

  16. Environment, Safety, and Health Reporting Notice

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

    2002-01-15

    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.

  17. Testing of Passive Safety System Performance for Higher Power Advanced Reactors

    SciTech Connect (OSTI)

    brian G. Woods; Jose Reyes, Jr.; John Woods; John Groome; Richard Wright

    2004-12-31

    This report describes the results of NERI research on the testing of advanced passive safety performance for the Westinghouse AP1000 design. The objectives of this research were: (a) to assess the AP1000 passive safety system core cooling performance under high decay power conditions for a spectrum of breaks located at a variety of locations, (b) to compare advanced thermal hydraulic computer code predictions to the APEX high decay power test data and (c) to develop new passive safety system concepts that could be used for Generation IV higher power reactors.

  18. Enhancing Railroad Hazardous Materials Transportation Safety...

    Office of Environmental Management (EM)

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

  19. Example of Environmental Restoration Code of Accounts

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

    1997-03-28

    This chapter describes the fundamental structure of an example remediation cost code system, lists and describes the Level 1 cost codes, and lists the Level 2 and Level 3 cost codes.

  20. Multiterminal Video Coding: From Theory to Application 

    E-Print Network [OSTI]

    Zhang, Yifu

    2012-10-19

    Multiterminal (MT) video coding is a practical application of the MT source coding theory. For MT source coding theory, two problems associated with achievable rate regions are well investigated into in this thesis: a new ...

  1. Mars mission safety

    SciTech Connect (OSTI)

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

    1989-06-01

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

  2. Integrated Safety Management Policy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on DeliciousMathematicsEnergy HeadquartersFuelBConservationEnergy5975-01 REPORTDepartment ofINTEGRATED SAFETY

  3. Safety | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsofProgram: Report AppendicesA TokenCommercialSTEM VolunteerSafety Alerts

  4. High Temperature Gas Reactors: Assessment of Applicable Codes and Standards

    SciTech Connect (OSTI)

    McDowell, Bruce K.; Nickolaus, James R.; Mitchell, Mark R.; Swearingen, Gary L.; Pugh, Ray

    2011-10-31

    Current interest expressed by industry in HTGR plants, particularly modular plants with power up to about 600 MW(e) per unit, has prompted NRC to task PNNL with assessing the currently available literature related to codes and standards applicable to HTGR plants, the operating history of past and present HTGR plants, and with evaluating the proposed designs of RPV and associated piping for future plants. Considering these topics in the order they are arranged in the text, first the operational histories of five shut-down and two currently operating HTGR plants are reviewed, leading the authors to conclude that while small, simple prototype HTGR plants operated reliably, some of the larger plants, particularly Fort St. Vrain, had poor availability. Safety and radiological performance of these plants has been considerably better than LWR plants. Petroleum processing plants provide some applicable experience with materials similar to those proposed for HTGR piping and vessels. At least one currently operating plant - HTR-10 - has performed and documented a leak before break analysis that appears to be applicable to proposed future US HTGR designs. Current codes and standards cover some HTGR materials, but not all materials are covered to the high temperatures envisioned for HTGR use. Codes and standards, particularly ASME Codes, are under development for proposed future US HTGR designs. A 'roadmap' document has been prepared for ASME Code development; a new subsection to section III of the ASME Code, ASME BPVC III-5, is scheduled to be published in October 2011. The question of terminology for the cross-duct structure between the RPV and power conversion vessel is discussed, considering the differences in regulatory requirements that apply depending on whether this structure is designated as a 'vessel' or as a 'pipe'. We conclude that designing this component as a 'pipe' is the more appropriate choice, but that the ASME BPVC allows the owner of the facility to select the preferred designation, and that either designation can be acceptable.

  5. DOE G 414.1-4, Safety Software Guide for Use with 10 CFR 830 Subpart A, Quality Assurance Requirements, and DOE O 414.1C, Quality Assurance

    Broader source: Energy.gov [DOE]

    "This Department of Energy (DOE or Department) Guide provides information plus acceptable methods for implementing the safety software quality assurance (SQA) requirements of DOE O 414.1C, Quality Assurance, dated 6-17-05. DOE O 414.1C requirements supplement the quality assurance program (QAP) requirements of Title 10 Code of Federal Regulations (CFR) 830, Subpart A, Quality Assurance, for DOE nuclear facilities and activities. The safety SQA requirements for DOE, including the National Nuclear Security Administration (NNSA), and its contractors are necessary to implement effective quality assurance (QA) processes and achieve safe nuclear facility operations. DOE promulgated the safety software requirements and this guidance to control or eliminate the hazards and associated postulated accidents posed by nuclear operations, including radiological operations. Safety software failures or unintended output can lead to unexpected system or equipment failures and undue risks to the DOE/NNSA mission, the environment, the public, and the workers. Thus DOE G 414.1-4 has been developed to provide guidance on establishing and implementing effective QA processes tied specifically to nuclear facility safety software applications. DOE also has guidance1 for the overarching QA program, which includes safety software within its scope. This Guide includes software application practices covered by appropriate national and international consensus standards and various processes currently in use at DOE facilities.2 This guidance is also considered to be of sufficient rigor and depth to ensure acceptable reliability of safety software at DOE nuclear facilities. This guidance should be used by organizations to help determine and support the steps necessary to address possible design or functional implementation deficiencies that might exist and to reduce operational hazards-related risks to an acceptable level. Attributes such as the facility life-cycle stage and the hazardous nature of each facility’s operations should be considered when using this Guide. Alternative methods to those described in this Guide may be used provided they result in compliance with the requirements of 10 CFR 830 Subpart A and DOE O 414.1C. Another objective of this guidance is to encourage robust software quality methods to enable the development of high quality safety applications."

  6. Plant maintenance and plant life extension issue, 2007

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2007-03-15

    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.

  7. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation

    SciTech Connect (OSTI)

    1997-03-01

    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.

  8. The First ASME Code Stamped Cryomodule at SNS

    SciTech Connect (OSTI)

    Howell, M P; Crofford, M T; Douglas, D L; Kim, S -H; Steward, S T; Strong, W H; Afanador, R; Hannah, B S; Saunders, J

    2012-07-01

    The first spare cryomodule for the Spallation Neutron Source (SNS) has been designed, fabricated, and tested by SNS personnel. The approach to design for this cryomodule was to hold critical design features identical to the original design such as bayonet positions, coupler positions, cold mass assembly, and overall footprint. However, this is the first SNS cryomodule that meets the pressure requirements put forth in the 10 CFR 851: Worker Safety and Health Program. The most significant difference is that Section VIII of the ASME Boiler and Pressure Vessel Code was applied to the vacuum vessel of this cryomodule. Applying the pressure code to the helium vessels within the cryomodule was considered. However, it was determined to be schedule prohibitive because it required a code case for materials that are not currently covered by the code. Good engineering practice was applied to the internal components to verify the quality and integrity of the entire cryomodule. The design of the cryomodule, fabrication effort, and cryogenic test results will be reported in this paper.

  9. The Cost of Enforcing Building Energy Codes: Phase 1

    E-Print Network [OSTI]

    Williams, Alison

    2013-01-01

    practices among code officials. Stakeholders recommendboth applicants and code officials and help to inform thecomply with the code and code officials to enforce the new

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

    SciTech Connect (OSTI)

    Szilard, Ronaldo H; Smith, Curtis L

    2014-09-01

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

  11. Program School/ Career: Descripton ISIS Program Codes

    E-Print Network [OSTI]

    Wisconsin at Madison, University of

    Program School/ Career: Descripton ISIS Program Codes Program Career: Descripton College School;Program School/ Career: Descripton ISIS Program Codes Program Career: Descripton College School/ College 1

  12. Towards secure multiresolution network coding

    E-Print Network [OSTI]

    Medard, Muriel

    Emerging practical schemes indicate that algebraic mixing of different packets by means of random linear network coding can increase the throughput and robustness of streaming services over wireless networks. However, ...

  13. Commercial Building Codes and Standards

    Broader source: Energy.gov [DOE]

    Once an energy-efficient technology or practice is widely available in the market, it can become the baseline of performance through building energy codes and equipment standards. The Building...

  14. Gas Code of Conduct (Connecticut)

    Broader source: Energy.gov [DOE]

    The Gas Code of Conduct sets forth the standard of conduct for transactions, direct or indirect, between gas companies and their affiliates. The purpose of these regulations is to promote...

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

    SciTech Connect (OSTI)

    Barilo, Nick F.

    2014-09-29

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

  16. Quantum stabilizer codes and beyond 

    E-Print Network [OSTI]

    Sarvepalli, Pradeep Kiran

    2008-10-10

    Dissertation by PRADEEP KIRAN SARVEPALLI 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 August 2008 Major Subject: Computer Science QUANTUM STABILIZER CODES... Committee Members, Donald K. Friesen Jennifer L. Welch Scott L. Miller Head of Department, Valerie E. Taylor August 2008 Major Subject: Computer Science iii ABSTRACT Quantum Stabilizer Codes and Beyond. (August 2008) Pradeep Kiran Sarvepalli, B.Tech., Indian...

  17. Application of the MELCOR code to design basis PWR large dry containment analysis.

    SciTech Connect (OSTI)

    Phillips, Jesse; Notafrancesco, Allen (USNRC, Office of Nuclear Regulatory Research, Rockville, MD); Tills, Jack Lee (Jack Tills & Associates, Inc., Sandia Park, NM)

    2009-05-01

    The MELCOR computer code has been developed by Sandia National Laboratories under USNRC sponsorship to provide capability for independently auditing analyses submitted by reactor manufactures and utilities. MELCOR is a fully integrated code (encompassing the reactor coolant system and the containment building) that models the progression of postulated accidents in light water reactor power plants. To assess the adequacy of containment thermal-hydraulic modeling incorporated in the MELCOR code for application to PWR large dry containments, several selected demonstration designs were analyzed. This report documents MELCOR code demonstration calculations performed for postulated design basis accident (DBA) analysis (LOCA and MSLB) inside containment, which are compared to other code results. The key processes when analyzing the containment loads inside PWR large dry containments are (1) expansion and transport of high mass/energy releases, (2) heat and mass transfer to structural passive heat sinks, and (3) containment pressure reduction due to engineered safety features. A code-to-code benchmarking for DBA events showed that MELCOR predictions of maximum containment loads were equivalent to similar predictions using a qualified containment code known as CONTAIN. This equivalency was found to apply for both single- and multi-cell containment models.

  18. Thermodynamic Origin of Life

    E-Print Network [OSTI]

    Michaelian, K

    2009-01-01

    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...

  19. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Functional modules, F9-F11

    SciTech Connect (OSTI)

    NONE

    1997-03-01

    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 volume consists of the section of the manual dealing with three of the functional modules in the code. Those are the Morse-SGC for the SCALE system, Heating 7.2, and KENO V.a. The manual describes the latest released versions of the codes.

  20. ASME code considerations for the compact heat exchanger

    SciTech Connect (OSTI)

    Nestell, James; Sham, Sam

    2015-08-31

    The mission of the U.S. Department of Energy (DOE), Office of Nuclear Energy is to advance nuclear power in order to meet the nation's energy, environmental, and energy security needs. Advanced high temperature reactor systems such as sodium fast reactors and high and very high temperature gas-cooled reactors are being considered for the next generation of nuclear reactor plant designs. The coolants for these high temperature reactor systems include liquid sodium and helium gas. Supercritical carbon dioxide (sCO?), a fluid at a temperature and pressure above the supercritical point of CO?, is currently being investigated by DOE as a working fluid for a nuclear or fossil-heated recompression closed Brayton cycle energy conversion system that operates at 550°C (1022°F) at 200 bar (2900 psi). Higher operating temperatures are envisioned in future developments. All of these design concepts require a highly effective heat exchanger that transfers heat from the nuclear or chemical reactor to the chemical process fluid or the to the power cycle. In the nuclear designs described above, heat is transferred from the primary to the secondary loop via an intermediate heat exchanger (IHX) and then from the intermediate loop to either a working process or a power cycle via a secondary heat exchanger (SHX). The IHX is a component in the primary coolant loop which will be classified as "safety related." The intermediate loop will likely be classified as "not safety related but important to safety." These safety classifications have a direct bearing on heat exchanger design approaches for the IHX and SHX. The very high temperatures being considered for the VHTR will require the use of very high temperature alloys for the IHX and SHX. Material cost considerations alone will dictate that the IHX and SHX be highly effective; that is, provide high heat transfer area in a small volume. This feature must be accompanied by low pressure drop and mechanical reliability and robustness. Classic shell and tube designs will be large and costly, and may only be appropriate in steam generator service in the SHX where boiling inside the tubes occurs. For other energy conversion systems, all of these features can be met in a compact heat exchanger design. This report will examine some of the ASME Code issues that will need to be addressed to allow use of a Code-qualified compact heat exchanger in IHX or SHX nuclear service. Most effort will focus on the IHX, since the safety-related (Class A) design rules are more extensive than those for important-to-safety (Class B) or commercial rules that are relevant to the SHX.

  1. 004.29.2010 | Presented by Joe Wong, P.Eng. DOE Tank Safety Workshop

    E-Print Network [OSTI]

    #12;1 POWERTECH ­ Hydrogen & CNG Services Certification testing of individual high pressure Discuss CNG Field Performance Data Discuss Safety Testing of Type 4 Tanks Current work to support Codes;5 CNG Experience In-service Failures Powertech has been testing CNG storage systems since 1983

  2. Applying Human Factors during the SIS Life Cycle

    SciTech Connect (OSTI)

    Avery, K.

    2010-05-05

    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.

  3. Perspectives on reactor safety

    SciTech Connect (OSTI)

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

    1994-03-01

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

  4. Radiation Safety System

    SciTech Connect (OSTI)

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

    2012-04-04

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

  5. Lawn Maintenance Safety (Spanish) 

    E-Print Network [OSTI]

    Smith, David

    2005-07-12

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

  6. Conceptual Safety Design RM

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of Natural GasAdjustments (BillionProvedTravel TravelChallenges |1-01Concentrating Solar Power ConcentratingConceptual Safety

  7. Complete Safety Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submit the following commentsMethods for Estimating:I Overview ofComplete Safety

  8. Complete Safety Training

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home Room News PublicationsAuditsCluster Compatibilitydefault Changes from Tukey toComplete Safety

  9. Safety - 88-Inch Cyclotron

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid youOxygen GenerationTechnologies |Education STEM Education LosSafety The

  10. Safety | Argonne National Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid youOxygen GenerationTechnologies |Education STEM Education LosSafetyNews

  11. Safety Staff Contact Information

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 ofSafety Staff

  12. Safety Staff Contact Information

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 ofSafety

  13. Safety and the APM

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember29/2011 Page 1 ofSafety

  14. Experiment Safety Requirements

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunitiesof Energy8) WignerEnergyAboutExperiment Safety

  15. SSRL Safety Office Memo

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12 Page 1NEWS MEDIA16,30879543332Safety

  16. Safety Staff Contact Information

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II) byMultidayAlumni > The2/01/12University Safety

  17. Sandia Energy - Safety

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity ofkandz-cm11 Outreach Home RoomPreservation of Fe(II)Geothermal EnergyRenewable EnergyWAves Nearshore)OperationsSafety Home

  18. Life With Energy

    K-12 Energy Lesson Plans and Activities Web site (EERE)

    Students will describe ways in which technology affects the environment, both negatively and positively, and identify different forms of energy and their advantages/disadvantages. They will also determine the benefits as well as the environmental harms of using energy to improve our quality of life.

  19. Agriculture and Life Sciences

    E-Print Network [OSTI]

    Virginia Tech

    Responsibility 7 Virginia Tech Principles of Community 7 STUDENTS ARE ~ 8 University/College Policy and Procedures 9 Absences 9 Personal Illness: 9 Death/Illness in the Family 9 Attendance of a Professional of Agriculture and Life Sciences that advising is a collaborative effort between the student and faculty advisor

  20. LWR codes capability to address SFR BDBA scenarios: Modeling of the ABCOVE tests

    SciTech Connect (OSTI)

    Herranz, L. E.; Garcia, M.; Morandi, S.

    2012-07-01

    The sound background built-up in LWR source term analysis in case of a severe accident, make it worth to check the capability of LWR safety analysis codes to model accident SFR scenarios, at least in some areas. This paper gives a snapshot of such predictability in the area of aerosol behavior in containment. To do so, the AB-5 test of the ABCOVE program has been modeled with 3 LWR codes: ASTEC, ECART and MELCOR. Through the search of a best estimate scenario and its comparison to data, it is concluded that even in the specific case of in-containment aerosol behavior, some enhancements would be needed in the LWR codes and/or their application, particularly with respect to consideration of particle shape. Nonetheless, much of the modeling presently embodied in LWR codes might be applicable to SFR scenarios. These conclusions should be seen as preliminary as long as comparisons are not extended to more experimental scenarios. (authors)

  1. Validation of a plant dynamics code for 4S - Test analysis of natural circulation behavior

    SciTech Connect (OSTI)

    Sebe, F.; Horie, H.; Matsumiya, H.; Fanning, T. H.

    2012-07-01

    A plant transient dynamics code for a sodium-cooled fast reactor was developed by Toshiba. The code is used to evaluate the safety performance of Super-Safe, Small, and Simple reactor (4S) for Anticipated Operational Occurrences (AOOs), Design Basis Accident (DBA) and Beyond DBA (BDBA). The code is currently undergoing verification and validation (V and V). As one of the validation, test analysis of the Shutdown Heat Removal Test (SHRT)-17 performed in the Experimental Breeder Reactor (EBR)-II was conducted. The SHRT-17 is protected loss of flow test. The purpose of this validation is to confirm capability of the code to simulate natural circulation behavior of the plant. As a result, good agreements are shown between the analytical results and the measured data which were available from instrumented subassembly. The detailed validation result of the natural circulation behavior is described in this paper. (authors)

  2. Nuclear explosive safety study process

    SciTech Connect (OSTI)

    NONE

    1997-01-01

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

  3. Nuclear data to support computer code validation

    SciTech Connect (OSTI)

    Fisher, S.E.; Broadhead, B.L.; DeHart, M.D.; Primm, R.T. III

    1997-04-01

    The rate of plutonium disposition will be a key parameter in determining the degree of success of the Fissile Materials Disposition Program. Estimates of the disposition rate are dependent on neutronics calculations. To ensure that these calculations are accurate, the codes and data should be validated against applicable experimental measurements. Further, before mixed-oxide (MOX) fuel can be fabricated and loaded into a reactor, the fuel vendors, fabricators, fuel transporters, reactor owners and operators, regulatory authorities, and the Department of Energy (DOE) must accept the validity of design calculations. This report presents sources of neutronics measurements that have potential application for validating reactor physics (predicting the power distribution in the reactor core), predicting the spent fuel isotopic content, predicting the decay heat generation rate, certifying criticality safety of fuel cycle facilities, and ensuring adequate radiation protection at the fuel cycle facilities and the reactor. The U.S. in-reactor experience with MOX fuel is first presented, followed by information related to other aspects of the MOX fuel performance information that is valuable to this program, but the data base remains largely proprietary. Thus, this information is not reported here. It is expected that the selected consortium will make the necessary arrangements to procure or have access to the requisite information.

  4. MAE 124/ESYS 103 Discussion: Week 9 Buildings, Building Codes, Land Use

    E-Print Network [OSTI]

    Gille, Sarah T.

    MAE 124/ESYS 103 Discussion: Week 9 Buildings, Building Codes, Land Use 0. Let's consider apartment complex under construction August 1, 2003 "If you build it we will burn it. The E.L.F.s are mad of life and the planet." Is ELF pursuing a sustainable "smart growth" strategy? 2. Is open space near

  5. CNG Cylinder Safety - Education, Outreach, and Next Steps (Presentation)

    SciTech Connect (OSTI)

    Smith, M.; Schroeder, A.

    2014-01-01

    Mr. Schroeder discussed the work that NREL is performing for the U.S. Department of Transportation on compressed natural gas cylinder end-of-life requirements. CNG vehicles are different from most other vehicles in that the CNG fuel storage cylinders have a pre-determined lifetime that may be shorter than the expected life of the vehicle. The end-of-life date for a cylinder is based on construction and test protocols, and is specific to the construction and material of each cylinder. The end-of-life date is important because it provides a safe margin of error against catastrophic cylinder failure or rupture. The end-of-life dates range from 15 to 25 years from the date of manufacture. NREL worked to develop outreach materials to increase awareness of cylinder end-of-life dates, has provided technical support for individual efforts related to cylinder safety and removal, and also worked with CVEF to document best practices for cylinder removal or inspection after an accident. Mr. Smith discussed the engagement of the DOE Clean Fleets Partners, which were surveyed to identify best practices on managing cylinder inventories and approached to provide initial data on cylinder age in a fleet environment. Both DOE and NREL will continue to engage these fleets and other stakeholders to determine how to best address this issue moving forward.

  6. @ Ontario 2006 Building Code Structural Design

    E-Print Network [OSTI]

    Sheikh, Shamim A.

    @ Ontario 2006 Building Code Part 4 Structural Design Structural Losds and P r o ~ d u l r;2006 Building Code @Ontario Division B -Part 4 #12;@Ontario 2006 Building Code Part 4 Structural Design Section #12;2006 Building Code @Ontario 4.q.2. Spsclfled Loads and Effects 4 . . 2 Loads and Effects (See

  7. Arithmetic completely regular codes J. H. Koolen

    E-Print Network [OSTI]

    Martin, Bill

    Arithmetic completely regular codes J. H. Koolen W. S. Lee W. J. Martin December 4, 2013 Abstract In this paper, we explore completely regular codes in the Hamming graphs and related graphs. Experimental evidence suggests that many completely regular codes have the property that the eigenvalues of the code

  8. Energy Consumption of Minimum Energy Coding in

    E-Print Network [OSTI]

    Johansson, Karl Henrik

    Energy Consumption of Minimum Energy Coding in CDMA Wireless Sensor Networks Benigno Zurita Ares://www.ee.kth.se/control Abstract. A theoretical framework is proposed for accurate perfor- mance analysis of minimum energy coding energy consumption is analyzed for two coding schemes proposed in the literature: Minimum Energy coding

  9. Transient Safety Analysis of Fast Spectrum TRU Burning LWRs with Internal Blankets

    SciTech Connect (OSTI)

    Downar, Thomas; Zazimi, Mujid; Hill, Bob

    2015-01-31

    The objective of this proposal was to perform a detailed transient safety analysis of the Resource-Renewable BWR (RBWR) core designs using the U.S. NRC TRACE/PARCS code system. This project involved the same joint team that has performed the RBWR design evaluation for EPRI and therefore be able to leverage that previous work. And because of their extensive experience with fast spectrum reactors and parfait core designs, ANL was also part the project team. The principal outcome of this project was the development of a state-of-the-art transient analysis capability for GEN-IV reactors based on Monte Carlo generated cross sections and the US NRC coupled code system TRACE/PARCS, and a state-of-the-art coupled code assessment of the transient safety performance of the RBWR.

  10. Facility Safety | Department of Energy

    Office of Environmental Management (EM)

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

  11. Design Considerations for Fire Safety 

    E-Print Network [OSTI]

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

    1971-01-28

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

  12. Aviation Safety Council Taipei, Taiwan

    E-Print Network [OSTI]

    Ladkin, Peter B.

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

  13. Gordon wins NNSA Safety Professional

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

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

  14. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

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

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

    SciTech Connect (OSTI)

    Robert W Youngblood

    2010-09-01

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

  16. Seismic Safety Study

    SciTech Connect (OSTI)

    Tokarz, F J; Coats, D W

    2006-05-16

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

  17. Safety research programs sponsored by Office of Nuclear Regulatory Research. Quarterly progress report, July 1-September 30, 1983. Volume 3, No. 3

    SciTech Connect (OSTI)

    Weiss, A J [comp.

    1984-01-01

    The projects reported are the following: HTGR Safety Evaluation, SSC Development, Validation and Application, CRBR Balance of Plant Modeling, Thermal-Hydraulic Reactor Safety Experiments, LWR Plant Analyzer Development, LWR Code Assessment and Application, Thermal Reactor Code Development (RAMONA-3B); Stress Corrosion Cracking of PWR Steam Generator Tubing, Bolting Failure Analysis, Probability Based Load Combinations for Design of Category I Structures, Mechanical Piping Benchmark Problems; Human Error Data for Nuclear Power Plant Safety-Related Events, and Human Factors in Nuclear Power Plant Safeguards.

  18. Fault tree synthesis for software design analysis of PLC based safety-critical systems

    SciTech Connect (OSTI)

    Koo, S. R.; Cho, C. H. [Corporate R and D Inst., Doosan Heavy Industries and Construction Co., Ltd., 39-3, Seongbok-Dong, Yongin-Si, Gyeonggi-Do 449-795 (Korea, Republic of); Seong, P. H. [Dept. of Nuclear and Quantum Engineering, Korea Advanced Inst. of Science and Technology, 373-3 Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

    2006-07-01

    As a software verification and validation should be performed for the development of PLC based safety-critical systems, a software safety analysis is also considered in line with entire software life cycle. In this paper, we propose a technique of software safety analysis in the design phase. Among various software hazard analysis techniques, fault tree analysis is most widely used for the safety analysis of nuclear power plant systems. Fault tree analysis also has the most intuitive notation and makes both qualitative and quantitative analyses possible. To analyze the design phase more effectively, we propose a technique of fault tree synthesis, along with a universal fault tree template for the architecture modules of nuclear software. Consequently, we can analyze the safety of software on the basis of fault tree synthesis. (authors)

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

    SciTech Connect (OSTI)

    Curtis Smith

    2014-06-01

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

  20. 242-A evaporator safety analysis report

    SciTech Connect (OSTI)

    CAMPBELL, T.A.

    1999-05-17

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

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

    E-Print Network [OSTI]

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

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

    E-Print Network [OSTI]

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

  3. Software Safety Tutorial Status Update 1 Software Safety Tutorial

    E-Print Network [OSTI]

    Tian, Jeff

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

  4. Radiation Safety Manual March 21, 2015 RADIATION SAFETY

    E-Print Network [OSTI]

    Lance, Veronica P.

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

  5. Optimal Bacon-Shor codes

    E-Print Network [OSTI]

    John Napp; John Preskill

    2012-09-04

    We study the performance of Bacon-Shor codes, quantum subsystem codes which are well suited for applications to fault-tolerant quantum memory because the error syndrome can be extracted by performing two-qubit measurements. Assuming independent noise, we find the optimal block size in terms of the bit-flip error probability p_X and the phase error probability p_Z, and determine how the probability of a logical error depends on p_X and p_Z. We show that a single Bacon-Shor code block, used by itself without concatenation, can provide very effective protection against logical errors if the noise is highly biased (p_Z / p_X >> 1) and the physical error rate p_Z is a few percent or below. We also derive an upper bound on the logical error rate for the case where the syndrome data is noisy.

  6. ASME Code Efforts Supporting HTGRs

    SciTech Connect (OSTI)

    D.K. Morton

    2011-09-01

    In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. The U.S. Department of Energy has supported this effort by pursuing the development of the Next Generation Nuclear Plant, a high temperature gas-cooled reactor. This support has included research and development of pertinent data, initial regulatory discussions, and engineering support of various codes and standards development. This report discusses the various applicable American Society of Mechanical Engineers (ASME) codes and standards that are being developed to support these high temperature gascooled reactors during construction and operation. ASME is aggressively pursuing these codes and standards to support an international effort to build the next generation of advanced reactors so that all can benefit.

  7. ASME Code Efforts Supporting HTGRs

    SciTech Connect (OSTI)

    D.K. Morton

    2010-09-01

    In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. The U.S. Department of Energy has supported this effort by pursuing the development of the Next Generation Nuclear Plant, a high temperature gas-cooled reactor. This support has included research and development of pertinent data, initial regulatory discussions, and engineering support of various codes and standards development. This report discusses the various applicable American Society of Mechanical Engineers (ASME) codes and standards that are being developed to support these high temperature gascooled reactors during construction and operation. ASME is aggressively pursuing these codes and standards to support an international effort to build the next generation of advanced reactors so that all can benefit.

  8. ASME Code Efforts Supporting HTGRs

    SciTech Connect (OSTI)

    D.K. Morton

    2012-09-01

    In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. The U.S. Department of Energy has supported this effort by pursuing the development of the Next Generation Nuclear Plant, a high temperature gas-cooled reactor. This support has included research and development of pertinent data, initial regulatory discussions, and engineering support of various codes and standards development. This report discusses the various applicable American Society of Mechanical Engineers (ASME) codes and standards that are being developed to support these high temperature gascooled reactors during construction and operation. ASME is aggressively pursuing these codes and standards to support an international effort to build the next generation of advanced reactors so that all can benefit.

  9. SASSYS LMFBR systems analysis code

    SciTech Connect (OSTI)

    Dunn, F.E.; Prohammer, F.G.

    1982-01-01

    The SASSYS code provides detailed steady-state and transient thermal-hydraulic analyses of the reactor core, inlet and outlet coolant plenums, primary and intermediate heat-removal systems, steam generators, and emergency shut-down heat removal systems in liquid-metal-cooled fast-breeder reactors (LMFBRs). The main purpose of the code is to analyze the consequences of failures in the shut-down heat-removal system and to determine whether this system can perform its mission adequately even with some of its components inoperable. The code is not plant-specific. It is intended for use with any LMFBR, using either a loop or a pool design, a once-through steam generator or an evaporator-superheater combination, and either a homogeneous core or a heterogeneous core with internal-blanket assemblies.

  10. Arithmetic Coding for Data Compression

    E-Print Network [OSTI]

    Howard, Paul G.; Vitter, Jeffrey Scott

    1994-01-01

    of the particular sequence of events in the #0Cle. The #0Cnal step uses at most b,log 2 pc + 2 bits to distinguish the #0Cle fromall other possible #0Cles. We need some mechanism to indicate the end ofthe #0Cle, either a special end- of-#0Cle event coded just once... of the particular sequence of events in the #0Cle. The #0Cnal step uses at most b,log 2 pc + 2 bits to distinguish the #0Cle fromall other possible #0Cles. We need some mechanism to indicate the end ofthe #0Cle, either a special end- of-#0Cle event coded just once...

  11. Validation issues for SSI codes

    SciTech Connect (OSTI)

    Philippacopoulos, A.J.

    1995-02-01

    The paper describes the results of a recent work which was performed to verify computer code predictions in the SSI area. The first part of the paper is concerned with analytic solutions of the system response. The mathematical derivations are reasonably reduced by the use of relatively simple models which capture fundamental ingredients of the physics of the system motion while allowing for the response to be obtained analytically. Having established explicit forms of the system response, numerical solutions from three computer codes are presented in comparative format.

  12. Renewable Energy Requirements for Future Building Codes: Options for Compliance

    SciTech Connect (OSTI)

    Dillon, Heather E.; Antonopoulos, Chrissi A.; Solana, Amy E.; Russo, Bryan J.

    2011-09-30

    As the model energy codes are improved to reach efficiency levels 50 percent greater than current codes, use of on-site renewable energy generation is likely to become a code requirement. This requirement will be needed because traditional mechanisms for code improvement, including envelope, mechanical and lighting, have been pressed to the end of reasonable limits. Research has been conducted to determine the mechanism for implementing this requirement (Kaufman 2011). Kaufmann et al. determined that the most appropriate way to structure an on-site renewable requirement for commercial buildings is to define the requirement in terms of an installed power density per unit of roof area. This provides a mechanism that is suitable for the installation of photovoltaic (PV) systems on future buildings to offset electricity and reduce the total building energy load. Kaufmann et al. suggested that an appropriate maximum for the requirement in the commercial sector would be 4 W/ft{sup 2} of roof area or 0.5 W/ft{sup 2} of conditioned floor area. As with all code requirements, there must be an alternative compliance path for buildings that may not reasonably meet the renewables requirement. This might include conditions like shading (which makes rooftop PV arrays less effective), unusual architecture, undesirable roof pitch, unsuitable building orientation, or other issues. In the short term, alternative compliance paths including high performance mechanical equipment, dramatic envelope changes, or controls changes may be feasible. These options may be less expensive than many renewable systems, which will require careful balance of energy measures when setting the code requirement levels. As the stringency of the code continues to increase however, efficiency trade-offs will be maximized, requiring alternative compliance options to be focused solely on renewable electricity trade-offs or equivalent programs. One alternate compliance path includes purchase of Renewable Energy Credits (RECs). Each REC represents a specified amount of renewable electricity production and provides an offset of environmental externalities associated with non-renewable electricity production. The purpose of this paper is to explore the possible issues with RECs and comparable alternative compliance options. Existing codes have been examined to determine energy equivalence between the energy generation requirement and the RECs alternative over the life of the building. The price equivalence of the requirement and the alternative are determined to consider the economic drivers for a market decision. This research includes case studies that review how the few existing codes have incorporated RECs and some of the issues inherent with REC markets. Section 1 of the report reviews compliance options including RECs, green energy purchase programs, shared solar agreements and leases, and other options. Section 2 provides detailed case studies on codes that include RECs and community based alternative compliance methods. The methods the existing code requirements structure alternative compliance options like RECs are the focus of the case studies. Section 3 explores the possible structure of the renewable energy generation requirement in the context of energy and price equivalence. The price of RECs have shown high variation by market and over time which makes it critical to for code language to be updated frequently for a renewable energy generation requirement or the requirement will not remain price-equivalent over time. Section 4 of the report provides a maximum case estimate for impact to the PV market and the REC market based on the Kaufmann et al. proposed requirement levels. If all new buildings in the commercial sector complied with the requirement to install rooftop PV arrays, nearly 4,700 MW of solar would be installed in 2012, a major increase from EIA estimates of 640 MW of solar generation capacity installed in 2009. The residential sector could contribute roughly an additional 2,300 MW based on the same code requirement levels of 4 W/ft{sup 2} of r

  13. LASER SAFETY MANUAL 2014 RICE UNIVERSITY 1

    E-Print Network [OSTI]

    Natelson, Douglas

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

  14. HEALTH AND SAFETY POLICY UNIVERSITY OF ABERDEEN

    E-Print Network [OSTI]

    Neri, Peter

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

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

    Office of Environmental Management (EM)

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

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

    E-Print Network [OSTI]

    Saskatchewan, University of

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

  17. Ferrocyanide safety study

    SciTech Connect (OSTI)

    Wegeng, R.S.

    1989-05-01

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

  18. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, E.

    1983-08-15

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

  19. Life forms: A keyword entry

    E-Print Network [OSTI]

    Helmreich, Stefan

    We deliver a "keyword" account of the term life form as it has been used in natural philosophy and biology over the last two hundred years, beginning with its appearance in German as Lebensform. We argue that life form ...

  20. Green Building- Efficient Life Cycle 

    E-Print Network [OSTI]

    Kohns, R.

    2008-01-01

    the components “Sustainable Building Design”, “Life Cycle Cost Analysis”, “Green Building Certification” and “Natural Resources Management”. These components are deliberately arranged around the life cycle of the real estate concerned. This allows a different...