National Library of Energy BETA

Sample records for life safety code

  1. Safety, Codes and Standards Technical Publications

    Broader source: Energy.gov [DOE]

    Technical information about safety, codes and standards published in technical reports, conference proceedings, journal articles, and websites is provided here.

  2. Safety, Codes, and Standards Fact Sheet | Department of Energy

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

    Fuel Cell Technologies Office describing hydrogen safety, codes, and standards. Safety, Codes, and Standards (781.31

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

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

    Safety, Codes, and Standards Safety, Codes, and Standards Hydrogen, in vast quantities, has been used safely for many years in chemical and metallurgical applications, the food industry, and the space program. As hydrogen and fuel cells begin to play a greater role in meeting the energy needs of our nation and the world, minimizing the safety hazards related to the use of hydrogen as a fuel is essential. DOE is working to develop and implement practices and procedures that will ensure safety in

  4. Energy Storage System Guide for Compliance with Safety Codes...

    Office of Environmental Management (EM)

    Guide for Compliance with Safety Codes and Standards 2016 Energy Storage System Guide for Compliance with Safety Codes and Standards 2016 Under the Energy Storage Safety Strategic ...

  5. Alternative Fuels Data Center: Biodiesel Codes, Standards, and Safety

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Codes, Standards, and Safety to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Codes, Standards, and Safety on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Codes, Standards, and Safety on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Codes, Standards, and Safety on Google Bookmark Alternative Fuels Data Center: Biodiesel Codes, Standards, and Safety on Delicious Rank Alternative Fuels Data Center: Biodiesel Codes, Standards, and Safety on Digg Find

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

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

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

  7. Radiological Safety Analysis Code System.

    Energy Science and Technology Software Center (OSTI)

    2009-12-22

    Version 03 RSAC-6.2 can be used to model complex accidents and radiological consequences to individuals from the release of radionuclides to the atmosphere. A user can generate a fission product inventory; decay and ingrow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Doses are calculated through the inhalation, immersion, ground surface and ingestion pathways. New to RSAC-6.2 are the abilitiesmore » to calculate inhalation from release to a room, inhalation from resuspension of activities, and a new model for dry deposition. Doses can now be calculated as close as 10 meters from the release point. RSAC-6.2 has been subjected to extensive independent verification and validation for use in performing safety-related dose calculations to support safety analysis reports. WinRP 2.0, a windows based overlay to RSAC-6.2, assists users in creating and running RSAC-6.2 input files. RSAC-6, Rev. 6.2 (03/11/02) corrects an earlier issue with RSAC-6, compiled with F77L-EM/32 Fortran 77 Version 5.10, which would not allow the executable to run with XP or VISTA Windows operating systems. Because this version is still in use at some facilities, it is being released through RSICC in addition to the new RSAC 7 (CCC-761).« less

  8. 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.

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

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

    Current Approaches to Safety, Codes & Standards » Hydrogen Safety, Codes and Standards Challenges Hydrogen Safety, Codes and Standards Challenges From a safety, codes and standards perspective, the fundamental challenges to the commercialization of hydrogen technologies are the lack of safety information on hydrogen components and systems used in a hydrogen fuel infrastructure, and the limited availability of appropriate codes and standards to ensure uniformity and facilitate deployment.

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

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

    Safety, Codes & Standards » Current Approaches to Safety, Codes and Standards Current Approaches to Safety, Codes and Standards Current approaches to hydrogen and fuel cells safety, codes and standards are based on existing practices, guidelines, and codes and standards developed as a result of hydrogen's use in the chemical and aerospace industries. While some codes and standards for hydrogen and hydrogen-related systems are already available, in many cases they do not fully address the

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

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

    Safety, Codes & Standards » DOE Safety, Codes, and Standards Activities DOE Safety, Codes, and Standards Activities DOE's safety R&D activities are aimed at developing sensors to detect hydrogen leaks in hydrogen and fuel cell systems. DOE's codes and standards activities are focused on coordinating and accelerating the efforts of major standards and model code development organizations and regulatory agencies so the required standards, codes, and regulations for hydrogen technologies

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

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

    Safety, Codes, and Standards Photo of person working with scientific equipment in a laboratory setting. NREL researcher works on sensor testing apparatus in the Safety Sensor Testing Laboratory. Photo by Dennis Schroeder, NREL NREL's hydrogen safety, codes, and standards projects focus on ensuring safe operation, handling, and use of hydrogen and hydrogen systems through safety sensors and codes and standards for buildings and equipment. Safety Sensors To facilitate hydrogen safety, NREL is

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

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

    Energy NUCLEAR SAFETY MANAGEMENT Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT This part governs the conduct of DOE contractors, DOE personnel, and other persons conducting activities (including providing items and services) that affect, or may affect, the safety of DOE nuclear facilities. Code of Federal Regulations NUCLEAR SAFETY MANAGEMENT (167.52 KB) More Documents & Publications Code of Federal Regulations TRESPASSING ON DEPARTMENT OF ENERGY PROPERTY Code of Federal

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

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

    Safety, Codes & Standards » Safety, Codes and Standards - Basics Safety, Codes and Standards - Basics Hydrogen has a long history of safe use in the chemical and aerospace industries. An understanding of hydrogen properties, proper safety precautions and engineering controls, and established rules, regulations, and standards are the keys to this successful track record. As the use of hydrogen and fuel cell systems expands, codes and standards will be needed to provide the information to

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

    Office of Environmental Management (EM)

    Department of Energy Standards, Safety Analysis Toolbox Codes - November 2003 Technical Standards, Safety Analysis Toolbox Codes - November 2003 November 2003 Software Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes Safety analysis software for the DOE "toolbox" was designated by DOE/EH in March 2003 (DOE/EH, 2003). The supporting basis for this designation was provided by a DOE-chartered Safety Analysis Software Group in the technical report, Selection of

  16. For Safety and Code Officials | Department of Energy

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

    Education » For 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 be used as safely as the other common fuels we use today. The Basics: DOE Hydrogen Safety Fact Sheet This hydrogen safety fact sheet provides basic facts about hydrogen properties and behavior to help users understand issues related to hydrogen safety. Visit our Increase Your H2IQ page for more basic

  17. Application of coupled codes for safety analysis and licensing issues

    SciTech Connect (OSTI)

    Langenbuch, S.; Velkov, K.

    2006-07-01

    An overview is given on the development and the advantages of coupled codes which integrate 3D neutron kinetics into thermal-hydraulic system codes. The work performed within GRS by coupling the thermal-hydraulic system code ATHLET and the 3D neutronics code QUABOX/CUBBOX is described as an example. The application of the coupled codes as best-estimate simulation tools for safety analysis is discussed. Some examples from German licensing practices are given which demonstrate how the improved analytical methods of coupled codes have contributed to solve licensing issues related to optimized and more economical use of fuel. (authors)

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

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

    and Standards | Department of Energy Safety Codes and Standards DOE Vehicle Technologies Program 2009 Merit Review Report - Safety Codes and Standards Merit review of DOE Vehicle Technologies Program research efforts 2009_merit_review_10.pdf (386.56 KB) More Documents & Publications DOE Vehicle Technologies Program 2009 Merit Review Report - Technology Validation DOE Vehicle Technologies Program 2009 Merit Review Report - Technology Integration and Education DOE Vehicle Technologies

  19. A Code for Probabilistic Safety Assessment

    Energy Science and Technology Software Center (OSTI)

    1997-10-10

    An integrated fault-event tree software package PSAPACK was developed for level-1 PSA using personal computers. It is a menu driven interactive modular system which permits different choices, depending on the user's purposes and needs. The event tree development module is capable of developing the logic accident sequences based on the user's specified relations between event tree headings. Identification of success sequences and core damage sequences is done automatically by the code based on the successmore » function input by the user. It links minimum cut sets (MCS) from system fault trees and performs the Boolean reduction. It can also retrieve data from the reliability data base to perform the quantification of accident sequences.« less

  20. 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.

  1. EV Everywhere: Electric Car Safety, Maintenance, and Battery Life |

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

    Department of Energy Electric Vehicle Basics » EV Everywhere: Electric Car Safety, Maintenance, and Battery Life EV Everywhere: Electric Car Safety, Maintenance, and Battery Life EV Everywhere: Electric Car Safety, Maintenance, and Battery Life Plug-in electric vehicles (also known as electric cars or EVs) are as safe and easy to maintain as conventional vehicles. While driving conditions and habits will impact vehicle operation and vehicle range, some best practices can help you maximize

  2. 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.

  3. 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

  4. Explosives Safety

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

    ... Schnetzer, Kimball O. Merewether, and Roy E. Jorgenson; May 1993 (current version 06 August 2002) Life Safety Code: NFPA 101, National Fire Protection Association (current version) ...

  5. 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...

  6. Safety, Codes, and Standards Fact Sheet | Department of Energy

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

    U.S. Department of Energy describing hydrogen safety. doe_h2_safety.pdf (653.64

  7. Validation and verification plan for safety and PRA codes. Revision 1

    SciTech Connect (OSTI)

    Ades, M.J.; Crowe, R.D.; Toffer, H.

    1991-04-01

    This report discusses a verification and validation (V&V) plan for computer codes used for safety analysis and probabilistic risk assessment calculations. The present plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River Office (DOE-SRO) to bring the essential safety analysis and probabilistic risk assessment codes in compliance with verification and validation requirements.

  8. 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.

  9. Code linkages for occupant safety during roadside impact simulations

    SciTech Connect (OSTI)

    Kay, G.J.; Logan, R.

    1994-01-11

    Current code linkage developments at Lawrence Livermore National Laboratory include coupling of the nonlinear explicit finite element analysis (FEA) code DYNA3D with rigid body crash victim simulation (CVS) codes. This coupling approach takes advantage of the structural response capabilities of DYNA3D and the validated occupant response abilities of the CVS codes. Two types of coupling are described and demonstrated in this paper and a description of the equilibrium initialization method which was employed in the coupling development is also presented.

  10. 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.

  11. Commercialization of Turbulent Combustion Code CREBCOM for Chemical Industry Safety

    SciTech Connect (OSTI)

    Rohatgi, Upendra

    2007-06-30

    This program developed the Kurchatov Institute’s CREBCOM (CRiteria and Experimentally Based COMbustion) code to the point where it could be commercialized and marketed for the special applications described above, as well as for general purpose combustion calculations. The CREBCOM code uses a different approach to model the explosion phenomenon. The code models, with full 3D gas dynamics, the development of an explosion in three characteristics regimes: a) slow flames, b) fast flames, and c) detonation. The transition from one regime to another is governed by a set of empirical criteria and correlations. As part of the commercialization, the code was validated with the use of experimental data. The experimental data covered a range of thermodynamic initial conditions and apparatus scale. Proprietary experimental data were provided to the Kurchatov Institute by the DuPont for this purpose. The flame acceleration and detonation data was obtained from experiments in methane and oxygen enriched air mixtures carried out in two vessels with diameters of 20 and 27 cm. The experimental data covers a wide spectrum of initial temperature (20-525C) and pressure (1-3 atm). As part of this program, the Kurchatov Institute performed experiments in a 52 cm vessel in mixtures of methane-air at room temperature and pressure to be used in the validation of the code. The objective of these tests was to obtain frame acceleration data at a scale close to that found in actual industrial processes. BNL was responsible for managing the DOE/IPP portion of the program, and for satisfying DOE reporting requirements. BNL also participated in an independent assessment of the CREBOM code. DuPont provided proprietary experimental data to the Kurchatov Institute on flame acceleration and detonation in high temperature methane and oxygen enriched air mixtures in addition to the matching fund. In addition, DuPont also supplied to KI instrumentation for pressure and temperature measurement

  12. 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.

  13. DNFSB 2002-1 Software Quality Assurance Improvement Plan Commitment 4.2.1.2: Safety Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes

    Office of Environmental Management (EM)

    EH-4.2.1.2-Criteria Defense Nuclear Facilities Safety Board Recommendation 2002-1 Software Quality Assurance Improvement Plan Commitment 4.2.1.2: Software Quality Assurance Plan and Criteria for the Safety Analysis Toolbox Codes U.S. Department of Energy Office of Environment, Safety and Health 1000 Independence Ave., S.W. Washington, DC 20585-2040 November 2003 Software Quality Assurance Criteria for Safety Analysis Codes November 2003 INTENTIONALLY BLANK ii Software Quality Assurance Criteria

  14. Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards

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

    HyRAM Software for Science-Based Safety, Codes, and Standards U.S. Department of Energy Fuel Cell Technologies Office April 26, 2016 Presenter: Katrina M. Groth - Sandia National Laboratories DOE Host: Will James - Program Manager: Hydrogen Safety, Codes, and Standards, Fuel Cell Technologies Office 2 | Fuel Cell Technologies Office eere.energy.gov Question and Answer * Please type your questions into the question box 2 Overview of HyRAM Software for Science- Based Safety, Codes, and Standards

  15. 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

  16. 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

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

    SciTech Connect (OSTI)

    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 with 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.

  18. Inventory of Safety-Related Codes and Standards for Energy Storage Systems and Related Experiences with System Approval and Acceptance

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

    PNNL-23618 Inventory of Safety-related Codes and Standards for Energy Storage Systems with some Experiences related to Approval and Acceptance DR Conover September 2014 Prepared for the U.S. Department of Energy Energy Storage Program under Contract DE-AC05-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 i ii Summary Purpose The purpose of this document is to identify laws; rules; model codes; and codes, standards, regulations (CSR) specifications related to safety

  19. TOOKUIL: A case study in user interface development for safety code application

    SciTech Connect (OSTI)

    Gray, D.L.; Harkins, C.K.; Hoole, J.G.

    1997-07-01

    Traditionally, there has been a very high learning curve associated with using nuclear power plant (NPP) analysis codes. Even for seasoned plant analysts and engineers, the process of building or modifying an input model for present day NPP analysis codes is tedious, error prone, and time consuming. Current cost constraints and performance demands place an additional burden on today`s safety analysis community. Advances in graphical user interface (GUI) technology have been applied to obtain significant productivity and quality assurance improvements for the Transient Reactor Analysis Code (TRAC) input model development. KAPL Inc. has developed an X Windows-based graphical user interface named TOOKUIL which supports the design and analysis process, acting as a preprocessor, runtime editor, help system, and post processor for TRAC. This paper summarizes the objectives of the project, the GUI development process and experiences, and the resulting end product, TOOKUIL.

  20. Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards Webinar

    Broader source: Energy.gov [DOE]

    Access the recording and download the presentation slides from the Fuel Cell Technologies Office webinar "Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards" held on April 26, 2016.

  1. 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.

  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. 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.

  4. Memorandum, CH2M HG Idaho, LLC, Request for Variance to Title 10 Code of Federal Regulations part 851, "Worker Safety and Health"

    Broader source: Energy.gov [DOE]

    CH2M HG Idaho, LLC, Request for Variance to Title 10 Code of Federal Regulations part 851, "Worker Safety and Health"

  5. 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"

  6. 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

  7. Webinar: Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards

    Broader source: Energy.gov [DOE]

    The Energy Department will present a live webinar titled "Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards" on Tuesday, April 26, from 12:00 to 1:00 p.m. Eastern Daylight Time (EDT).

  8. 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

    SAFETY, CODES AND STANDARDS SECTION Multi-Year Research, Development, and Demonstration Plan Page 3.7 - 1 3.7 Hydrogen Safety, Codes and Standards The United States and many other countries have established laws and regulations that require commercial products and infrastructure to meet all applicable codes and standards to demonstrate that they are safe, perform as designed and are compatible with the systems in which they are used. Hydrogen and fuel cell technologies have a history of safe use

  9. 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.

  10. SAS4A/SASSYS-1: Fast Reactor Safety Analysis Code | Argonne National...

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

    The original code development was for sodium-cooled fast reactors, and sodium boiling can be modeled. However, basic core thermal-hydraulics and systems analysis features are ...

  11. Project Safety Oversight Activities | Department of Energy

    Energy Savers [EERE]

    Safety, Codes & Standards Basics Current Approaches to Safety, Codes & Standards DOE Activities Hydrogen Safety R&D Projects Project Safety Oversight Activities Codes & Standards

  12. Thermal hydraulic codes for LWR safety analysis - present status and future perspective

    SciTech Connect (OSTI)

    Staedtke, H.

    1997-07-01

    The aim of the present paper is to give a review on the current status and future perspective of present best-estimate Thermal Hydraulic codes. Reference is made to internationally well-established codes which have reached a certain state of maturity. The first part of the paper deals with the common basic code features with respect to the physical modelling and their numerical methods used to describe complex two-phase flow and heat transfer processes. The general predictive capabilities are summarized identifying some remaining code deficiencies and their underlying limitations. The second part discusses various areas including physical modelling, numerical techniques and informatic structure where the codes could be substantially improved.

  13. 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.

  14. Equipment and codes matching and re-matching objectives, problems industry structure and life cycle, approach and enforcement

    SciTech Connect (OSTI)

    Kleinmann, A.J.

    1995-06-01

    Mandatory codes do not easily lead to giant steps forward in energy efficiency. We catalog the basic code and enforcement approaches. Using these, we begin to look at the relationship between code approaches (component, budget, or process), enforcement alternatives (testing standards, certification, inspections), the structure and life-cycle stage of the industry being {open_quotes}regulated{close_quotes} (e.g., lighting, medical devices, automobiles, construction), regulator and societal objectives (not necessarily the same), and real-world outcomes. We present a paradigm of the relationships and insights that result. We develop some implications to energy-efficient programs such as new construction and indicate research and application areas that could benefit from further attention.

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

    Broader source: Energy.gov [DOE]

    This fact sheet highlights the most recent activities and releases related to the protocol for measuring and expressing performance characteristics for energy storage systems. It covers the June 2014 revision to the protocol and some of the more recent and upcoming work related to safety.

  16. 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.

  17. Metal fueled long life fast reactor cores with inherent safety features

    SciTech Connect (OSTI)

    Yokoyama, Tsugio; Ninokata, Hisashi; Endo, Hiroshi

    2007-07-01

    A large fast reactor core concept is proposed that has inherent safety characteristics against both the Unprotected Loss of Flow (ULOF) event and the Unprotected Transient of Over-Power (UTOP) event, where commonly used zirconium alloy metal fuel (U-Pu- Zr) is adopted to achieve a long life cycle length up to 5 years. The burn-up reactivity of the core which is equivalent to the maximum insertion reactivity in the UTOP due to the control rod run-out event at the rated power, is reduced to less than 1 $ by introducing minor actinides to the fuel, while the sodium void reactivity is suppressed to be negative by applying a step core concept, where the inner core height is lower than the outer core height, and by deleting the upper axial blanket. (authors)

  18. Safety

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

    safety Safety All JLF participants must comply fully with all LLNL safety regulations and procedures by becoming a Registered User of the facility. All JLF participants must complete available LLNL safety training: HS5200-W Laser Safety HS4258-W Beryllium Awareness HS4261-W Lead Awareness HS5220-W Electrical Safety Awareness HS6001-W 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

  19. 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.

  20. 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.

  1. The SAS4A/SASSYS-1 Safety Analysis Code System

    Energy Science and Technology Software Center (OSTI)

    2012-01-31

    SAS4A/SASSYS-1 is a software simulation tool used to perform deterministic safety analysis of anticipated events as well as design basis and beyond design basis accidents for advanced nuclear reactors. This software can be used to assess the safety of a prescribed reactor design, but it cannot be used to configure a design to meet targeted performance objectives. Detailed, mechanistic models of steady-state and transient thermal,hydraulic, kinetic, and mechanical phenomena are employed to describe the responsemore » of the reactor core, the reactor primary and secondary coolant loops, the reactor control and protection systems and the balance-of-plant to accidents caused by changes in coolantflow, oss of heat rejection, or reactivity insertion. The consequences of single and double-fault accidents can be modeled, including fuel and coolant heating, fuel and cladding mechanical behavior, core reactivity feedbacks, coolant loop performance including natural circulation, and decay heat removal. Analyses are typically terminated upon demonstration of reactor and plant shutdown to permanently coolable conditions or upon violation of design basis margins. The objective of the analysis is to quantify accident consequences as measured by the transient behavior of system performance parameters, such as fuel and cladding temperatures, reactivity, and cladding strain. Originally developed for analysis of sodium cooled reactors with oxide fuel clad by stainless steel, the models In SAS4A/SASSYS-1 were subsequently extended and specialized to metallic fuel clad with advanced alloys and to several other coolant options including lead and LBE. METHOD OF SOLUTION: Each subassembly in the reactor core is represented with single or multiple-pin models. One channel represents one or more fuel pins and many channels are employed for a whole-core representation. Heat transfer in each pin is modeled with a two-dimensional (r/z) heat conduction equation. Single and two-phase coolant

  2. Safety

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

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  3. safety

    National Nuclear Security Administration (NNSA)

    contractor at the Nevada National Security Site, has been recognized by the Department of Energy for excellence in occupational safety and health protection. National Nuclear...

  4. Development of safety analysis codes and experimental validation for a very high temperature gas-cooled reactor Final report

    SciTech Connect (OSTI)

    Chang Oh

    2006-03-01

    The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has average coolant temperatures above 9000C and operational fuel temperatures above 12500C. The concept provides the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperature to support process heat applications, such as coal gasification, desalination or cogenerative processes, the VHTR’s higher temperatures allow broader applications, including thermochemical hydrogen production. However, the very high temperatures of this reactor concept can be detrimental to safety if a loss-of-coolant accident (LOCA) occurs. Following the loss of coolant through the break and coolant depressurization, air will enter the core through the break by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structure and fuel. The oxidation will accelerate heatup of the reactor core and the release of toxic gasses (CO and CO2) and fission products. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. Prior to the start of this Korean/United States collaboration, no computer codes were available that had been sufficiently developed and validated to reliably simulate a LOCA in the VHTR. Therefore, we have worked for the past three years on developing and validating advanced computational methods for simulating LOCAs in a VHTR. Research Objectives As described above, a pipe break may lead to significant fuel damage and fission product release in the VHTR. The objectives of this Korean/United States collaboration were to develop and validate advanced computational methods for VHTR safety analysis. The methods that have been developed are now

  5. 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

  6. 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

  7. Safety, Codes, and Standards

    Broader source: Energy.gov [DOE]

    2009 DOE Hydrogen Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting, May 18-22, 2009 -- Washington D.C.

  8. 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.

  9. Webinar April 26: Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards

    Broader source: Energy.gov [DOE]

    The Energy Department will present a live webinar titled "Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards" on Tuesday, April 26, from 12 to 1 p.m. Eastern Daylight Time. This webinar provides an introduction to the new HyRAM research software developed by Sandia National Laboratories and supported by the Fuel Cell Technologies Office.

  10. Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report

    SciTech Connect (OSTI)

    Chang Oh

    2005-09-01

    The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 9000C or operational fuel temperatures above 12500C. These concepts provide the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation and nuclear hydrogen generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperatures to support process heat applications, such as desalination and cogeneration, the VHTGR’s higher temperatures are suitable for particular applications such as thermochemical hydrogen production. However, the high temperature operation can be detrimental to safety following a loss-of-coolant accident (LOCA) initiated by pipe breaks caused by seismic or other events. Following the loss of coolant through the break and coolant depressurization, air from the containment will enter the core by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structures and fuel. The oxidation will release heat and accelerate the heatup of the reactor core. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. The Idaho National Laboratory (INL) has investigated this event for the past three years for the HTGR. However, the computer codes used, and in fact none of the world’s computer codes, have been sufficiently developed and validated to reliably predict this event. New code development, improvement of the existing codes, and experimental validation are imperative to narrow the uncertainty in the predictions of this type of accident. The objectives of this Korean/United States collaboration are to develop advanced computational methods for VHTGR safety analysis codes and to validate these computer codes.

  11. Safety Criticality Standards Using the French CRISTAL Code Package: Application to the AREVA NP UO{sub 2} Fuel Fabrication Plant

    SciTech Connect (OSTI)

    Doucet, M.; Durant Terrasson, L.; Mouton, J.

    2006-07-01

    Criticality safety evaluations implement requirements to proof of sufficient sub critical margins outside of the reactor environment for example in fuel fabrication plants. Basic criticality data (i.e., criticality standards) are used in the determination of sub critical margins for all processes involving plutonium or enriched uranium. There are several criticality international standards, e.g., ARH-600, which is one the US nuclear industry relies on. The French Nuclear Safety Authority (DGSNR and its advising body IRSN) has requested AREVA NP to review the criticality standards used for the evaluation of its Low Enriched Uranium fuel fabrication plants with CRISTAL V0, the recently updated French criticality evaluation package. Criticality safety is a concern for every phase of the fabrication process including UF{sub 6} cylinder storage, UF{sub 6}-UO{sub 2} conversion, powder storage, pelletizing, rod loading, assembly fabrication, and assembly transportation. Until 2003, the accepted criticality standards were based on the French CEA work performed in the late seventies with the APOLLO1 cell/assembly computer code. APOLLO1 is a spectral code, used for evaluating the basic characteristics of fuel assemblies for reactor physics applications, which has been enhanced to perform criticality safety calculations. Throughout the years, CRISTAL, starting with APOLLO1 and MORET 3 (a 3D Monte Carlo code), has been improved to account for the growth of its qualification database and for increasing user requirements. Today, CRISTAL V0 is an up-to-date computational tool incorporating a modern basic microscopic cross section set based on JEF2.2 and the comprehensive APOLLO2 and MORET 4 codes. APOLLO2 is well suited for criticality standards calculations as it includes a sophisticated self shielding approach, a P{sub ij} flux determination, and a 1D transport (S{sub n}) process. CRISTAL V0 is the result of more than five years of development work focusing on theoretical

  12. 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.

  13. 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.

  14. 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 ...

  15. code release

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

    code release - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear Energy

  16. Design Code Survey Form | Department of Energy

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

    Design Code Survey Form Design Code Survey Form Survey of Safety Software Used in Design of Structures, Systems, and Components 1. Introduction The Department's Implementation Plan ...

  17. 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; 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.

  18. 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.

    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)

  19. Brain surgery breathes new life into aging plants

    SciTech Connect (OSTI)

    Makansi, J.

    2006-04-15

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

  20. Mechanical code comparator

    DOE Patents [OSTI]

    Peter, Frank J.; Dalton, Larry J.; Plummer, David W.

    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.

  1. 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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  3. Industrial Safety | The Ames Laboratory

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

    Safety General Safety includes traditional safety disciplines such as machine guarding, personal protective equipment (PPE), electrical safety, accident prevention and investigation, building design and code review, fire safety, and Occupational Safety and Health Administration (OSHA) regulatory compliance. Safety's role is to protect the health and well-being of employees, visitors, and the public from hazards present at or created in the workplace. These factors may be present as a result of

  4. 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

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

    Energy Savers [EERE]

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

  6. Pretest predictions of the Fast Flux Test Facility Passive Safety Test Phase IIB transients using United States derived computer codes and methods

    SciTech Connect (OSTI)

    Heard, F.J.; Harris, R.A.; Padilla, A.

    1992-07-01

    The SASSYS/SAS4A systems analysis code was used to simulate a series of unprotected loss of flow (ULOF) tests planned at the Fast Flux Test Facility (FFTF). The subject tests were designed to investigate the transient performance of the FFTF during various ULOF scenarios for two different loading patterns designed to produce extremes in the assembly load pad clearance and the direction of the initial assembly bows. The tests are part of an international program designed to extend the existing data base on the performance of liquid metal reactors (LMR). The analyses demonstrate that a wide range of power-to-flow ratios can be reached during the transients and, therefore, will yield valuable data on the dynamic character of the structural feedbacks in LMRS. These analyses will be repeated once the actual FFTF core loadings for the tests are available. These predictions, similar ones obtained by other international participants in the FFTF program, and post-test analyses will be used to upgrade and further verify the computer codes used to predict the behavior of LMRS.

  7. Compiling Codes

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

    wrappers will automatically provide the necessary MPI include files and libraries. For Fortran source code use mpif90: % mpif90 -o example.x example.f90 For C source code use...

  8. 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.

  9. 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.

  10. Coding Archives - Nercenergy

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

    Coding What Certificates Should My Microsoft Exchange Server Have? Much like any other network application, in order to secure the functionality and safety of Microsoft Exchange Servers, it's essential to adopt specific certificates. Due to the literally thousands, if not millions, of security threats bombarding your Exchange Server every day, these certificates ensure users have a safe messaging experience while simultaneously safeguarding your data and sensitive information from being

  11. 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.

  12. Safety harness

    DOE Patents [OSTI]

    Gunter, Larry W.

    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.

  13. Risk Code?

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

    Identify the Task Risk Code >2 Determine if a Work Control Document is needed What is the Unmitigated Risk Code? Rev.1 09/05/14 Read and Agree to Comply with appropriate mitigation and sign Work Control Documents Is there an approved Work Control Document (WCD)? WORK PLANNING, CONTROL AND AUTHORIZATION FLOW DIAGRAM 1. Define Scope of Work 2. Analyze Hazards 3. Develop and Implement Hazard Controls 4. Perform Work Within Controls 5. Feedback and Continuous Improvement Analyze Hazards and

  14. Radiation Safety

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

    Safety Home MSDS Search MSDS Help Safety Training and Tests Contact Links LSU Campus Safety Glossary Radiation Safety Manual Radiation Safety Test NOTE: All Training and Testing Material is for LSU CAMD Users ONLY! **Please allow two weeks for your badge to be processed.** Regulations and Hierarchy The CAMD Safety Officer reports to two separate individuals regarding safety. These are the Radiation Safety Officer for the University, and the Campus Safety Officer in all other matters. Thus safety

  15. 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

  16. 2005 Elec. Safety-rev1.pmd

    Energy Savers [EERE]

    5 Electrical Safety During Excavations and Penetrations ... Abbreviations Used in This Report CFR Code of Federal ... LLNL Lawrence Livermore National Laboratory NNSA National ...

  17. 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

  18. Safety, Codes, and Standards Fact Sheet

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

    for diverse applications including specialty vehicles, combined heat and power (CHP), stationary, backup, and portable power. The number of fuel cell deployments continues to...

  19. Safety, Codes, and Standards Fact Sheet

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

    for diverse applications including spe- cialty vehicles, combined heat and power (CHP), stationary, backup, and portable power. The number of fuel cell deploy- ments continues to...

  20. Job Safety

    Office of Environmental Management (EM)

    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 ...

  1. Compiling Codes

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

    Compiling Codes Compiling Codes Overview Open Mpi is the the only MPI library available on Euclid. This implementation of MPI-2 is described at Open MPI: Open Source High Performance Computing. The default compiler suite is from the Portland Group which is loaded by default at login, along with the PGI compiled Open MPI environment. % module list Currently Loaded Modulefiles: 1) pgi/10.8 2) openmpi/1.4.2 Basic Example Open MPI provides a convenient set of wrapper commands which you should use in

  2. Interface requirements to couple thermal hydraulics codes to severe accident codes: ICARE/CATHARE

    SciTech Connect (OSTI)

    Camous, F.; Jacq, F.; Chatelard, P.

    1997-07-01

    In order to describe with the same code the whole sequence of severe LWR accidents, up to the vessel failure, the Institute of Protection and Nuclear Safety has performed a coupling of the severe accident code ICARE2 to the thermalhydraulics code CATHARE2. The resulting code, ICARE/CATHARE, is designed to be as pertinent as possible in all the phases of the accident. This paper is mainly devoted to the description of the ICARE2-CATHARE2 coupling.

  3. 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.

  4. Securing mobile code.

    SciTech Connect (OSTI)

    Link, Hamilton E.; Schroeppel, Richard Crabtree; Neumann, William Douglas; Campbell, Philip LaRoche; Beaver, Cheryl Lynn; Pierson, Lyndon George; Anderson, William Erik

    2004-10-01

    If software is designed so that the software can issue functions that will move that software from one computing platform to another, then the software is said to be 'mobile'. There are two general areas of security problems associated with mobile code. The 'secure host' problem involves protecting the host from malicious mobile code. The 'secure mobile code' problem, on the other hand, involves protecting the code from malicious hosts. This report focuses on the latter problem. We have found three distinct camps of opinions regarding how to secure mobile code. There are those who believe special distributed hardware is necessary, those who believe special distributed software is necessary, and those who believe neither is necessary. We examine all three camps, with a focus on the third. In the distributed software camp we examine some commonly proposed techniques including Java, D'Agents and Flask. For the specialized hardware camp, we propose a cryptographic technique for 'tamper-proofing' code over a large portion of the software/hardware life cycle by careful modification of current architectures. This method culminates by decrypting/authenticating each instruction within a physically protected CPU, thereby protecting against subversion by malicious code. Our main focus is on the camp that believes that neither specialized software nor hardware is necessary. We concentrate on methods of code obfuscation to render an entire program or a data segment on which a program depends incomprehensible. The hope is to prevent or at least slow down reverse engineering efforts and to prevent goal-oriented attacks on the software and execution. The field of obfuscation is still in a state of development with the central problem being the lack of a basis for evaluating the protection schemes. We give a brief introduction to some of the main ideas in the field, followed by an in depth analysis of a technique called 'white-boxing'. We put forth some new attacks and improvements

  5. MELCOR computer code manuals

    SciTech Connect (OSTI)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

    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.

  6. Regulations, Guidelines and Codes and Standards | Department of Energy

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

    Current Approaches to Safety, Codes & Standards » Regulations, Guidelines and Codes and Standards Regulations, Guidelines and Codes and Standards Many regulations, guidelines, and codes and standards have already been established through years of hydrogen use in industrial and aerospace applications. In addition, systems and organizations are already in place to establish codes and standards that facilitate hydrogen and fuel cell commercialization. Standards Development Organizations

  7. 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 &...

  8. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  9. 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...

  10. Safety, Security

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

    Safety, Security Safety, Security The Lab's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 We do not compromise safety for personal, programmatic, or operational reasons. Safety: we integrate safety, security, and environmental concerns into every step of our

  11. H2 Safety Snapshot Newsletter | Department of Energy

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

    Safety, Codes & Standards » H2 Safety Snapshot Newsletter H2 Safety Snapshot Newsletter The H2 Safety Snapshot is a hydrogen safety quarterly newsletter which outlines safety best practices and lessons learned to promote continued success in the safe operation of U.S. Department of Energy (DOE) hydrogen projects. The newsletter delineates the safe handling and use of hydrogen in a wide variety of applications and provides a listing of hydrogen safety resources. Links to newsletter issues

  12. Integrated Codes | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Integrated Codes Integrated codes contain the mathematical descriptions of the physical processes relating to nuclear weapon systems and describe what the nation knows about how nuclear weapons function. This subprogram funds the critical skills needed to develop, maintain and interpret the results of the large-scale integrated simulation codes that are needed for Stockpile Stewardship Program (SSP) maintenance, the Life Extension Programs (LEP), Significant Finding Investigation (SFI)

  13. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    NOTE: On March 9, 2016, the State Fire Prevention and Building Code Council adopted major updates to the State Uniform Code and the State Energy Code. The State Energy Code has been updated to 2015...

  14. Fact Sheet Available: Codes and Standards for Energy Storage System

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

    Performance and Safety (June 2014) | Department of Energy Fact Sheet Available: Codes and Standards for Energy Storage System Performance and Safety (June 2014) Fact Sheet Available: Codes and Standards for Energy Storage System Performance and Safety (June 2014) June 25, 2014 - 12:10pm Addthis The U.S. Department of Energy's Office of Electricity Delivery and Energy Reliability Energy Storage Systems Program, with the support of Pacific Northwest National Laboratory (PNNL) and Sandia

  15. 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.

  16. 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. This Page Change is limited in scope to changes necessary to invoke DOE-STD-1104, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Document, and revised DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis as required methods. DOE O 420.1C Chg 1, dated 2-27-15, supersedes DOE O 420.1C.

  17. 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.

  18. Energy Storage Safety Strategic Plan Now Available | Department of Energy

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

    Storage Safety Strategic Plan Now Available Energy Storage Safety Strategic Plan Now Available December 23, 2014 - 10:25am Addthis The Office of Electricity Delivery and Energy Reliability (OE) has worked with industry and other stakeholders to develop the Energy Storage Safety Strategic Plan, a roadmap for grid energy storage safety that highlights safety validation techniques, incident preparedness, safety codes, standards, and regulations. The Plan, which is now available for downloading,

  19. 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.

  20. Biological Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  1. 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.

  2. 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.

  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. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  5. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  6. 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...

  7. 11. CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    79120 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) Babcock & Wilcox Technical Services Pantex, LLC PO Box 30020 Amarillo, TX 79120 CODE I FACILITY ...

  8. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  9. 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...

  10. 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...

  11. 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...

  12. Safety Software Quality Assurance- Central Registry

    Broader source: Energy.gov [DOE]

    The Department of Energy maintains a list of "toolbox" codes that have been evaluated against DOE Safety Software Quality Assurance (SSQA) requirements of DOE O 414.1D, Quality Assurance, and its...

  13. Building Energy Codes: State and Local Code Implementation Overview

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

    Mark Lessans Fellow Building Energy Codes: State and Local Code Implementation Overview ... building code regarding energy efficiency to the revised model code and submit a ...

  14. New Code Compliance Briefs Assist in Resolving Codes and Standards...

    Energy Savers [EERE]

    New Code Compliance Briefs Assist in Resolving Codes and Standards Concerns in Energy Innovations New Code Compliance Briefs Assist in Resolving Codes and Standards Concerns in ...

  15. Regulatory impacts on code validation and use

    SciTech Connect (OSTI)

    McKamy, J.

    1994-09-01

    The Criticality Engineering Programs branch of Nuclear Safety Engineering at EG&G Rocky Flats is in the process of developing procedures for KENO code validation which demonstrate compliance with the requirements of DOE Order 5700.6B (NQA-1). Detailed and documented processes must be implemented to acquire, install, and validate the codes. Many of the requirements of DOE Order 5700.6B simply require documenting {open_quotes}good practices,{close_quotes} while others are not possible due to the nature of verifying and validating 20-year-old codes against 30-year-old benchmarks.

  16. 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.

  17. 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.

  18. GENII Code Guidance

    National Nuclear Security Administration (NNSA)

    ... Journal of the Air Pollution Control Association 23:491-495. DNFSB, 2000, Defense Nuclear Facilities Safety Board, Quality Assurance for Safety-Related Software at Department of ...

  19. Electrical Safety

    Office of Environmental Management (EM)

    Handbook that was originally issued in 1998, and revised in 2004. DOE handbooks are ... the National Fire Protection Association (NFPA) 70, the National Electrical Code (NEC), ...

  20. 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

  1. Manually operated coded switch

    DOE Patents [OSTI]

    Barnette, Jon H.

    1978-01-01

    The disclosure relates to a manually operated recodable coded switch in which a code may be inserted, tried and used to actuate a lever controlling an external device. After attempting a code, the switch's code wheels must be returned to their zero positions before another try is made.

  2. Fire and Life Safety Information - Hanford Site

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

    - U.S Fire Administration Website PDF, 182 Kb Fire Extinguishers - Flash Presentation Smoke Detectors Smoke Detector Icon PDF, 182 Kb Smoke Alarms - What You Need to Know (PDF)...

  3. Safety Issues

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

    Site Safety Orientation April, 2015 Atmospheric Radiation Measurement Climate Research Facility/ North Slope of Alaska/Adjacent Arctic Ocean (ACRF/NSA/AAO) Site Safety Orientation Purpose This document provides an overview and summary of safety issues and safe work practices associated with operations at the Atmospheric Radiation Measurement Climate Research Facility/North Slope of Alaska/Adjacent Arctic Ocean (ACRF/NSA/AAO) Sites. It is intended for site visitors as well as routine site

  4. Safety - 88-Inch Cyclotron

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

    Safety The Nuclear Sciences Division (NSD) is committed to providing a safe workplace for its employees, contractors, and guests and conducting its research and operations in a manner that protects the environment. In conducting its operations and research, NSD meets or exceeds Berkeley Lab, University of California, and U.S. Department of Energy policies and requirements. To report a life-threatening accident, call x7911 For all other accidents or near-hits, call x6999 For Emergency Status

  5. Explosives Safety

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

    2012-06-27

    The Standard provides the basic technical requirements for an explosives safety program necessary for operations involving explosives, explosives assemblies, pyrotechnics and propellants, and assemblies containing these materials.

  6. 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...

  7. 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.

  8. Job Safety and Health Poster | Department of Energy

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

    Job Safety and Health Poster Job Safety and Health Poster Department of Energy (DOE) Job Safety and Health poster. DOE Order 440.1B Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees and title 10, Code of Federal Regulations (CFR), part 851, Worker Safety and Health Program, both require that a worker safety and health poster be posted in a prominent location to inform employees of their rights and responsibilities. In the past, DOE has

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

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

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

  10. 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.

  11. 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...

  12. 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. In 2015, the AER...

  13. 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...

  14. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

  15. 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,...

  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]

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

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. Building Energy Code

    Broader source: Energy.gov [DOE]

    In November of 2015, the Commission adopted the 2015 International Building Code (IBC) with amendments. The Commission did not adopt the 2012 International Energy Conservation Code (IECC) as part...

  3. 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...

  4. 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 considera...

  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]

    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...

  7. 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...

  8. Building Energy Code

    Broader source: Energy.gov [DOE]

    Colorado is a home rule state, so no statewide energy code exists, although state government buildings do have specific requirements. Voluntary adoption of energy codes is encouraged and efforts...

  9. 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...

  10. 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...

  11. Cellulases and coding sequences

    DOE Patents [OSTI]

    Li, Xin-Liang; Ljungdahl, Lars G.; Chen, Huizhong

    2001-01-01

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

  12. Cellulases and coding sequences

    DOE Patents [OSTI]

    Li, Xin-Liang; Ljungdahl, Lars G.; Chen, Huizhong

    2001-02-20

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

  13. Building Energy Code

    Broader source: Energy.gov [DOE]

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

  14. Two New Energy Storage Safety Reports Now Available | Department of Energy

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

    Two New Energy Storage Safety Reports Now Available Two New Energy Storage Safety Reports Now Available October 14, 2014 - 5:33pm Addthis The Office of Electricity Delivery and Energy Reliability has released two reports on energy storage safety - "Overview of Development and Deployment of Codes, Standards and Regulations Affecting Energy Storage System Safety in the United States" and "Inventory of Safety-Related Codes and Standards for Energy Storage Systems." The first

  15. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  16. Thermal-hydraulic interfacing code modules for CANDU reactors

    SciTech Connect (OSTI)

    Liu, W.S.; Gold, M.; Sills, H.

    1997-07-01

    The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

  17. 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.

  18. Code cases for implementing risk-based inservice testing in the ASME OM code

    SciTech Connect (OSTI)

    Rowley, C.W.

    1996-12-01

    Historically inservice testing has been reasonably effective, but quite costly. Recent applications of plant PRAs to the scope of the IST program have demonstrated that of the 30 pumps and 500 valves in the typical plant IST program, less than half of the pumps and ten percent of the valves are risk significant. The way the ASME plans to tackle this overly-conservative scope for IST components is to use the PRA and plant expert panels to create a two tier IST component categorization scheme. The PRA provides the quantitative risk information and the plant expert panel blends the quantitative and deterministic information to place the IST component into one of two categories: More Safety Significant Component (MSSC) or Less Safety Significant Component (LSSC). With all the pumps and valves in the IST program placed in MSSC or LSSC categories, two different testing strategies will be applied. The testing strategies will be unique for the type of component, such as centrifugal pump, positive displacement pump, MOV, AOV, SOV, SRV, PORV, HOV, CV, and MV. A series of OM Code Cases are being developed to capture this process for a plant to use. One Code Case will be for Component Importance Ranking. The remaining Code Cases will develop the MSSC and LSSC testing strategy for type of component. These Code Cases are planned for publication in early 1997. Later, after some industry application of the Code Cases, the alternative Code Case requirements will gravitate to the ASME OM Code as appendices.

  19. Transportation Safety

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

    Safety - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear Energy

  20. XSOR codes users manual

    SciTech Connect (OSTI)

    Jow, Hong-Nian; Murfin, W.B.; Johnson, J.D.

    1993-11-01

    This report describes the source term estimation codes, XSORs. The codes are written for three pressurized water reactors (Surry, Sequoyah, and Zion) and two boiling water reactors (Peach Bottom and Grand Gulf). The ensemble of codes has been named ``XSOR``. The purpose of XSOR codes is to estimate the source terms which would be released to the atmosphere in severe accidents. A source term includes the release fractions of several radionuclide groups, the timing and duration of releases, the rates of energy release, and the elevation of releases. The codes have been developed by Sandia National Laboratories for the US Nuclear Regulatory Commission (NRC) in support of the NUREG-1150 program. The XSOR codes are fast running parametric codes and are used as surrogates for detailed mechanistic codes. The XSOR codes also provide the capability to explore the phenomena and their uncertainty which are not currently modeled by the mechanistic codes. The uncertainty distributions of input parameters may be used by an. XSOR code to estimate the uncertainty of source terms.

  1. DLLExternalCode

    Energy Science and Technology Software Center (OSTI)

    2014-05-14

    DLLExternalCode is the a general dynamic-link library (DLL) interface for linking GoldSim (www.goldsim.com) with external codes. The overall concept is to use GoldSim as top level modeling software with interfaces to external codes for specific calculations. The DLLExternalCode DLL that performs the linking function is designed to take a list of code inputs from GoldSim, create an input file for the external application, run the external code, and return a list of outputs, read frommore » files created by the external application, back to GoldSim. Instructions for creating the input file, running the external code, and reading the output are contained in an instructions file that is read and interpreted by the DLL.« less

  2. DLLExternalCode

    SciTech Connect (OSTI)

    Greg Flach, Frank Smith

    2014-05-14

    DLLExternalCode is the a general dynamic-link library (DLL) interface for linking GoldSim (www.goldsim.com) with external codes. The overall concept is to use GoldSim as top level modeling software with interfaces to external codes for specific calculations. The DLLExternalCode DLL that performs the linking function is designed to take a list of code inputs from GoldSim, create an input file for the external application, run the external code, and return a list of outputs, read from files created by the external application, back to GoldSim. Instructions for creating the input file, running the external code, and reading the output are contained in an instructions file that is read and interpreted by the DLL.

  3. Generating code adapted for interlinking legacy scalar code and extended vector code

    DOE Patents [OSTI]

    Gschwind, Michael K

    2013-06-04

    Mechanisms for intermixing code are provided. Source code is received for compilation using an extended Application Binary Interface (ABI) that extends a legacy ABI and uses a different register configuration than the legacy ABI. First compiled code is generated based on the source code, the first compiled code comprising code for accommodating the difference in register configurations used by the extended ABI and the legacy ABI. The first compiled code and second compiled code are intermixed to generate intermixed code, the second compiled code being compiled code that uses the legacy ABI. The intermixed code comprises at least one call instruction that is one of a call from the first compiled code to the second compiled code or a call from the second compiled code to the first compiled code. The code for accommodating the difference in register configurations is associated with the at least one call instruction.

  4. AFR-100 safety analyses

    SciTech Connect (OSTI)

    Sumner, T.; Moisseytsev, A.; Wei, T. Y. C.

    2012-07-01

    The Advanced Fast Reactor-100 (AFR-100) is Argonne National Laboratory's 250 MWth metal-fueled modular sodium-cooled pool-type fast reactor concept. [1] A series of accident sequences that focused on the AFR-100's ability to provide protection against reactor damage during low probability accident sequences resulting from multiple equipment failures were examined. Protected and Unprotected Loss of Flow (PLOF and ULOF) and Unprotected Transient Over-Power (UTOP) accidents were simulated using the SAS4A/SASSYS-1 safety analysis code. The large heat capacity of the sodium in the pool-type reactor allows the AFR-100 to absorb large amounts of energy during a PLOF with relatively small temperature increases throughout the system. During a ULOF with a 25-second flow halving time, coolant and cladding temperatures peak around 720 deg. C within the first minute before reactivity feedback effects decrease power to match the flow. Core radial expansion and fuel Doppler provide the necessary feedback during the UTOP to bring the system back to critical before system temperatures exceed allowable limits. Simulation results indicate that adequate ULOF safety margins exist for the AFR-100 design with flow halving times of twenty-five seconds. Significant safety margins are maintained for PLOF accidents as well as UTOP accidents if a rod stop is used. (authors)

  5. Code of Conduct

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

    Governance » Ethics, Accountability, Contract » Code of Conduct Code of Conduct Helping employees recognize and resolve the ethics and compliance issues that may arise in their daily work. Contact Ethics and Compliance Group (505) 667-7506 Email Code of Conduct Los Alamos National Laboratory is committed to operating in accordance with the highest standards of ethics and compliance and with its core values of service to our nation, ethical conduct and personal accountability, excellence in our

  6. Compiling Codes on Hopper

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

    Compiling Codes Compiling Codes on Hopper Overview Cray provides a convenient set of wrapper commands that should be used in almost all cases for compiling and linking parallel programs. Invoking the wrappers will automatically link codes with MPI libraries and other Cray system software. All MPI and Cray system include directories are also transparently imported. In addition the wrappers append the compiler's target processor arguments for the hopper compute node processors. NOTE: The intention

  7. Technical Standards, CFAST-Code Guidance - July 23, 2004 | Department of

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

    Energy CFAST-Code Guidance - July 23, 2004 Technical Standards, CFAST-Code Guidance - July 23, 2004 July 23, 2004 EPIcode Computer Code Application Guidance for Documented Safety Analysis The contents of this report are applicable in the interim period until measures are completed to bring EPIcode into compliance with defined SQA standards. The primary objective of the guidance report is to provide information on the use of EPIcode for supporting DOE safety basis accident analysis. Technical

  8. Shields - Code Coupling

    SciTech Connect (OSTI)

    Vernon, Louis James

    2015-03-02

    This PowerPoint presentation focuses on the history and benefits of the Space Weather Modeling Framework (SWMF) code and collaborative software development.

  9. 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...

  10. 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...

  11. 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...

  12. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Connecticut Office of the State Building Inspector establishes and enforces building, electrical, mechanical, plumbing and energy code requirements by reviewing, developing, adopting and...

  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. Building Energy Codes

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

    David Cohan Program Manager Building Energy Codes April 22, 2014 Presentation Outline * Mission * Goals * Program Organization * StrategiesRoles * Near-Term Focus * Measuring ...

  15. 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.

  16. Improving Code Compliance

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

    provisions in International Energy Conservation Code (IECC) through proof-of-concept ... This includes updating recommendations based on newer CBECs or BPD energy statistics. ...

  17. Top NAICS Codes

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

    and Related Products Manufacturing for Measuring, Displaying, Top Ten NAICS Codes Dollar Value 511210 Software Publishers 334516 Analytical Laboratory Instrument Manufacturing...

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

    SciTech Connect (OSTI)

    LaChance, Jeffrey L.; Houf, William G.; Fluer, Inc., Paso Robels, CA; Fluer, Larry; 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.

  19. HotSpot Health Physics Codes

    Energy Science and Technology Software Center (OSTI)

    2010-03-02

    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 incidents involving radioactive 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.

  20. HotSpot Health Physics Codes

    Energy Science and Technology Software Center (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.

  1. Building America Expert Meeting: Combustion Safety | Department of Energy

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

    Combustion Safety Building America Expert Meeting: Combustion Safety This expert meeting, The Best Approach to Combustion Safety in a Direct Vent World, was conducted by the Partnership for Advanced Residential Retrofit team on 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

  2. 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 ...

  3. September 10th Webinar for the Energy Storage Safety Working Group on Safety Validation and Risk Assessment R&D

    Broader source: Energy.gov [DOE]

    On Thursday, September 10, the Office of Electricity Delivery and Energy Reliability (OE), together with Sandia National Laboratories, will present a kick-off webinar for the Energy Storage Safety Working Group on Safety Validation and Risk Assessment Research and Development. Information on current energy storage safety R&D across government, industry and academia will be shared, as well as activities from the other two OE Energy Storage Safety working groups on Codes, Standards, and Regulations, and Outreach.

  4. DOE-STD-1172-2003; Safety Software Quality Assurance Functional...

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

    ... Supporting Knowledge, Skills, and Abilities a. Identify how functional requirements and applicability of safety analysis and design computer codes are defined, documented, and ...

  5. Lichenase and coding sequences

    DOE Patents [OSTI]

    Li, Xin-Liang; Ljungdahl, Lars G.; Chen, Huizhong

    2000-08-15

    The present invention provides a fungal lichenase, i.e., an endo-1,3-1,4-.beta.-D-glucanohydrolase, its coding sequence, recombinant DNA molecules comprising the lichenase coding sequences, recombinant host cells and methods for producing same. The present lichenase is from Orpinomyces PC-2.

  6. Building Energy Codes Program

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

    Program U.S. Department of Energy Building Technologies Office Jeremy Williams, Project Manager Building Technologies Peer Review April 2014 Presentation Overview: * Introduction * Statutory Requirements * Program Structure * Recent accomplishments 2 Introduction: Background NATIONAL STATE LOCAL Building codes are developed through national industry consensus processes with input from industry representatives, trade organizations, government officials, and the general public Model energy codes

  7. 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.

  8. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C.

    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.

  9. 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.

  10. Nuclear Safety Regulatory Framework

    Energy Savers [EERE]

    Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural ...

  11. Safety Management System Policy

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

    SAFETY MANAGEMENT POLICY PURPOSE AND SCOPE To establish the Department of Energy's (DOE) expectation for safety, 1 including integrated safety management that will enable ...

  12. 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.

  13. Current and anticipated uses of thermal hydraulic codes in Korea

    SciTech Connect (OSTI)

    Kim, Kyung-Doo; Chang, Won-Pyo

    1997-07-01

    In Korea, the current uses of thermal hydraulic codes are categorized into 3 areas. The first application is in designing both nuclear fuel and NSSS. The codes have usually been introduced based on the technology transfer programs agreed between KAERI and the foreign vendors. Another area is in the supporting of the plant operations and licensing by the utility. The third category is research purposes. In this area assessments and some applications to the safety issue resolutions are major activities using the best estimate thermal hydraulic codes such as RELAP5/MOD3 and CATHARE2. Recently KEPCO plans to couple thermal hydraulic codes with a neutronics code for the design of the evolutionary type reactor by 2004. KAERI also plans to develop its own best estimate thermal hydraulic code, however, application range is different from KEPCO developing code. Considering these activities, it is anticipated that use of the best estimate hydraulic analysis code developed in Korea may be possible in the area of safety evaluation within 10 years.

  14. 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 Ro

  15. Compressible Astrophysics Simulation Code

    Energy Science and Technology Software Center (OSTI)

    2007-07-18

    This is an astrophysics simulation code involving a radiation diffusion module developed at LLNL coupled to compressible hydrodynamics and adaptive mesh infrastructure developed at LBNL. One intended application is to neutrino diffusion in core collapse supernovae.

  16. Building Energy Code

    Office of Energy Efficiency and Renewable Energy (EERE)

    On May 2014, Delaware updated its energy code to 2012 IECC with amendments for residential sector and ASHRAE 90.1-2010 with amendments for the commercial sector. The Delaware specific amendments to...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. Building Energy Code

    Broader source: Energy.gov [DOE]

    Both State building codes adoption and enforcement efforts fall under the purview of the State Fire Marshal’s Office within the Department of Commerce and Insurance (C&I). Any changes to the...

  2. 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...

  3. 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...

  4. Tribal Green Building Codes

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

    with even amount of white space between photos and header Tribal Green Building Codes Chelsea Chee November 1 3, 2012 SAND 2012---9858C Photos placed in horizontal position with ...

  5. Compiling Codes on Cori

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

    wrappers will automatically link codes with MPI libraries and other Cray system software. ... NOTE: The intention is that programs are compiled on the login nodes and executed on the ...

  6. Compiling Codes on Hopper

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

    wrappers will automatically link codes with MPI libraries and other Cray system software. ... NOTE: The intention is that programs are compiled on the login nodes and executed on the ...

  7. National Energy Codes Conference

    Broader source: Energy.gov [DOE]

    Join us in Nashville, TN March 23-26, 2015 for the National Energy Codes Conference! Additional details, including registration information, a preliminary agenda, the application for the Jeffrey A...

  8. Direct Angular Representation Monte Carlo Code for Criticality Safety Analysis

    Energy Science and Technology Software Center (OSTI)

    1988-01-01

    Version 00 MKENO-DAR calculates the effective neutron multiplication factor and neutron flux distribution in a three dimensional media, solving multigroup neutron transport equation with a precise angular distribution function for neutron scattering. MKENO-DAR was developed from CCC-492/MULTI-KENO which was developed from KENO-IV. MULTI-KENO divides the system into many subsystem SUPER BOXES where the size of BOX TYPEs in each SUPER BOX can be selected independently. MKENO-DAR improves the representation of scattering angle over that inmore » MULTI-KENO.« less

  9. PNNL Energy Codes Portfolio

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

    PNNL Energy Codes Portfolio 2015 Building Technologies Office Peer Review ADOPT COMPLY DEVELOP Bing Liu bing.liu@pnnl.gov Rosemarie Bartlett rosemarie.bartlett@pnnl.gov Pacific Northwest National Laboratory Project Summary Timeline: Multi-year program in support of DOE statutory requirements Key Milestones: 1. DOE's Determinations on 90.1-2013 and 2015 IECC 2. Update DOE's Energy odes ost-Effectiveness Methodology 3. Commercial Codes Roadmap 4. 90.1-2013 and 2015 IECC Cost Analyses 5.

  10. Code of Federal Regulations Nuclear Activities | Department of Energy

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

    Code of Federal Regulations Nuclear Activities Code of Federal Regulations Nuclear Activities April 24,2010 This part sets forth the procedures to govern the conduct of persons involved in DOE nuclear activities and, in particular, to achieve compliance with the DOE Nuclear Safety Requirements by all persons subject to those requirements. 10 C.F.R. 820, Procedural Rules for DOE Nuclear Activities, sets forth the procedures to implement the provisions of the Price-Anderson Amendments Act of 1988

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

    SciTech Connect (OSTI)

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

    1997-12-01

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

  12. NREL: Hydrogen and Fuel Cells Research - Safety Sensor Testing Laboratory

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

    Safety Sensor Testing Laboratory The Safety Sensor Testing Laboratory at NREL's Energy Systems Integration Facility aims to ensure that hydrogen sensor technology is available to meet end-user needs and to foster the proper use of sensors. Hydrogen sensors are an important enabling technology for the safe implementation of the emerging hydrogen infrastructure. Codes require hydrogen detectors (e.g., NFPA 2-Hydrogen Technologies Code), but currently provide little guidance on deployment. In

  13. Generating code adapted for interlinking legacy scalar code and...

    Office of Scientific and Technical Information (OSTI)

    Mechanisms for intermixing code are provided. Source code is received for compilation using an extended Application Binary Interface (ABI) that extends a legacy ABI and uses a ...

  14. New Code Compliance Briefs Assist in Resolving Codes and Standards...

    Energy Savers [EERE]

    New Code Compliance Briefs Assist in Resolving Codes and Standards Concerns in Energy ... system knowledge that may limit effective implementation of new and existing standards. ...

  15. 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 BISONs unique ability to model discrete pellet behavior and accurately predict clad ridging from PCMI.

  16. Building Energy Code

    Broader source: Energy.gov [DOE]

    The Board of Building Standards is the primary state agency that protects the public's safety by: adopting rules governing the construction, repair, and rehabilitation of buildings in the state;...

  17. Nevada Energy Code for Buildings

    Office of Energy Efficiency and Renewable Energy (EERE)

    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,...

  18. 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.

  19. CRAD, Facility Safety - Unreviewed Safety Question Requirements |

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

    Department of Energy Facility Safety - Unreviewed Safety Question Requirements CRAD, Facility Safety - Unreviewed Safety Question Requirements 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.. CRADs provide a recommended approach and the types of information to

  20. Codes of practice and related issues in biomedical waste management

    SciTech Connect (OSTI)

    Moy, D.; Watt, C.

    1996-12-31

    This paper outlines the development of a National Code of Practice for biomedical waste management in Australia. The 10 key areas addressed by the code are industry mission statement; uniform terms and definitions; community relations - public perceptions and right to know; generation, source separation, and handling; storage requirements; transportation; treatment and disposal; disposal of solid and liquid residues and air emissions; occupational health and safety; staff awareness and education. A comparison with other industry codes in Australia is made. A list of outstanding issues is also provided; these include the development of standard containers, treatment effectiveness, and reusable sharps containers.

  1. 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.

  2. 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.

  3. FAA Smoke Transport Code

    Energy Science and Technology Software Center (OSTI)

    2006-10-27

    FAA Smoke Transport Code, a physics-based Computational Fluid Dynamics tool, which couples heat, mass, and momentum transfer, has been developed to provide information on smoke transport in cargo compartments with various geometries and flight conditions. The software package contains a graphical user interface for specification of geometry and boundary conditions, analysis module for solving the governing equations, and a post-processing tool. The current code was produced by making substantial improvements and additions to a codemore » obtained from a university. The original code was able to compute steady, uniform, isothermal turbulent pressurization. In addition, a preprocessor and postprocessor were added to arrive at the current software package.« less

  4. Electrical Circuit Simulation Code

    Energy Science and Technology Software Center (OSTI)

    2001-08-09

    Massively-Parallel Electrical Circuit Simulation Code. CHILESPICE is a massively-arallel distributed-memory electrical circuit simulation tool that contains many enhanced radiation, time-based, and thermal features and models. Large scale electronic circuit simulation. Shared memory, parallel processing, enhance convergence. Sandia specific device models.

  5. Evaluation of liquefaction potential for building code

    SciTech Connect (OSTI)

    Nunziata, C.; De Nisco, G.; Panza, G. F.

    2008-07-08

    The standard approach for the evaluation of the liquefaction susceptibility is based on the estimation of a safety factor between the cyclic shear resistance to liquefaction and the earthquake induced shear stress. Recently, an updated procedure based on shear-wave velocities (V{sub s}) has been proposed which could be more easily applied.These methods have been applied at La Plaja beach of Catania, that experienced liquefaction because of the 1693 earthquake. The detailed geotechnical and V{sub s} information and the realistic ground motion computed for the 1693 event let us compare the two approaches. The successful application of the V{sub s} procedure, slightly modified to fit historical and safety factor information, even if additional field performances are needed, encourages the development of a guide for liquefaction potential analysis, based on well defined V{sub s} profiles to be included in the italian seismic code.

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

    Office of Environmental Management (EM)

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

  7. Technical Standards, Guidance on MACCS2 Computer Code - June 30, 2004 |

    Office of Environmental Management (EM)

    Energy EPIcode Computer Code Application Guidance for Documented Safety Analysis The contents of this report are applicable in the interim period until measures are completed to bring EPIcode into compliance with defined SQA standards. The primary objective of the guidance report is to provide information on the use of EPIcode for supporting DOE safety basis accident analysis. Technical Standards, CFAST-Code Guidance (477.72 KB) More Documents & Publications Technical Standards,

  8. Commercial Vehicle Safety Alliance Commercial Vehicle Safety...

    Office of Environmental Management (EM)

    of Radioactive Material Carlisle Smith Director, Hazardous Materials Programs ... Safety Alliance QUESTIONS? Carlisle Smith Director, Hazardous Materials Programs ...

  9. Dam Safety 2015

    Broader source: Energy.gov [DOE]

    Make your plans now to attend Dam Safety 2015, in New Orleans! Dam Safety 2015 is one of the leading conferences in the United States dedicated to dam and levee safety engineering and technology...

  10. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

    ... facility and nuclear safety requirements defined in 10 CFR 830, Nuclear Safety Management, and worker safety requirements defined in 10 CFR 851, Worker Safety and Health Program. ...

  11. Criticality Safety | Department of Energy

    Office of Environmental Management (EM)

    Contact Garrett Smith 301-903-7440 DOE Employee Concerns Program Environment Worker Health & Safety Facility Safety Nuclear Safety Criticality Safety Quality Assurance Risk ...

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

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

    SENSITIVE DOE-STD-1104-2014 December 2014 Superseding DOE-STD-1104-2009 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2014 i FOREWORD 1. 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

  13. 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...

  14. Nuclear criticality safety guide

    SciTech Connect (OSTI)

    Pruvost, N.L.; Paxton, H.C.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

  15. Material Safety Data Sheets

    Broader source: Energy.gov [DOE]

    Material Safety Data Sheets (MSDSs) provide workers and emergency personnel with ways for handling and working with a hazardous substance and other health and safety information.

  16. DRAFT Bear Safety Plan

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

    Bear Safety Plan June 2010 NSAbspRev9.doc 1 Atmospheric Radiation Measurement Climate Research Facility North Slope of AlaskaAdjacent Arctic Ocean (ACRFNSAAAO) Bear Safety ...

  17. Safety | Department of Energy

    Energy Savers [EERE]

    On February 7, 2014, Deputy Assistant Secretary, Safety, Security, and Quality Programs Environmental Management, ... Serves as liaison to the Defense Nuclear Facilities Safety Board ...

  18. 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.

  19. Finite Element Analysis Code

    Energy Science and Technology Software Center (OSTI)

    2006-03-08

    MAPVAR-KD is designed to transfer solution results from one finite element mesh to another. MAPVAR-KD draws heavily from the structure and coding of MERLIN II, but it employs a new finite element data base, EXODUS II, and offers enhanced speed and new capabilities not available in MERLIN II. In keeping with the MERLIN II documentation, the computational algorithms used in MAPVAR-KD are described. User instructions are presented. Example problems are included to demonstrate the operationmore » of the code and the effects of various input options. MAPVAR-KD is a modification of MAPVAR in which the search algorithm was replaced by a kd-tree-based search for better performance on large problems.« less

  20. 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.

  1. Coded credentials: A primer

    SciTech Connect (OSTI)

    Wright, L.J.

    1988-02-01

    The need to identify people is an age-old requirement that has taken many forms over the ages. With the advent of the age of technology, the need has become more acute and many methods have been devised to help with the identification process. This report is designed to be a primer on one of those methods - the coded credential, e.g., a credential that is compatible with computerized access control systems.

  2. THREAT OF MALICIOUS CODE

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

    THREAT OF MALICIOUS CODE The Department of Energy (DOE) is strongly committed to the protection of all DOE assets from cyber attack and malicious exploitation. This includes information, networks, hardware, software, and mobile devices. DOE's continued diligence in this arena is critical in today's constantly-evolving cyber threat landscape. A recently cited incident involved senior officials receiving unsolicited free phone chargers. Luckily, the source was legitimate and did not result in a

  3. Interface requirements for coupling a containment code to a reactor system thermal hydraulic codes

    SciTech Connect (OSTI)

    Baratta, A.J.

    1997-07-01

    To perform a complete analysis of a reactor transient, not only the primary system response but the containment response must also be accounted for. Such transients and accidents as a loss of coolant accident in both pressurized water and boiling water reactors and inadvertent operation of safety relief valves all challenge the containment and may influence flows because of containment feedback. More recently, the advanced reactor designs put forth by General Electric and Westinghouse in the US and by Framatome and Seimens in Europe rely on the containment to act as the ultimate heat sink. Techniques used by analysts and engineers to analyze the interaction of the containment and the primary system were usually iterative in nature. Codes such as RELAP or RETRAN were used to analyze the primary system response and CONTAIN or CONTEMPT the containment response. The analysis was performed by first running the system code and representing the containment as a fixed pressure boundary condition. The flows were usually from the primary system to the containment initially and generally under choked conditions. Once the mass flows and timing are determined from the system codes, these conditions were input into the containment code. The resulting pressures and temperatures were then calculated and the containment performance analyzed. The disadvantage of this approach becomes evident when one performs an analysis of a rapid depressurization or a long term accident sequence in which feedback from the containment can occur. For example, in a BWR main steam line break transient, the containment heats up and becomes a source of energy for the primary system. Recent advances in programming and computer technology are available to provide an alternative approach. The author and other researchers have developed linkage codes capable of transferring data between codes at each time step allowing discrete codes to be coupled together.

  4. Bar coded retroreflective target

    DOE Patents [OSTI]

    Vann, Charles S.

    2000-01-01

    This small, inexpensive, non-contact laser sensor can detect the location of a retroreflective target in a relatively large volume and up to six degrees of position. The tracker's laser beam is formed into a plane of light which is swept across the space of interest. When the beam illuminates the retroreflector, some of the light returns to the tracker. The intensity, angle, and time of the return beam is measured to calculate the three dimensional location of the target. With three retroreflectors on the target, the locations of three points on the target are measured, enabling the calculation of all six degrees of target position. Until now, devices for three-dimensional tracking of objects in a large volume have been heavy, large, and very expensive. Because of the simplicity and unique characteristics of this tracker, it is capable of three-dimensional tracking of one to several objects in a large volume, yet it is compact, light-weight, and relatively inexpensive. Alternatively, a tracker produces a diverging laser beam which is directed towards a fixed position, and senses when a retroreflective target enters the fixed field of view. An optically bar coded target can be read by the tracker to provide information about the target. The target can be formed of a ball lens with a bar code on one end. As the target moves through the field, the ball lens causes the laser beam to scan across the bar code.

  5. Current and anticipated uses of thermalhydraulic and neutronic codes at PSI

    SciTech Connect (OSTI)

    Aksan, S.N.; Zimmermann, M.A.; Yadigaroglu, G.

    1997-07-01

    The thermalhydraulic and/or neutronic codes in use at PSI mainly provide the capability to perform deterministic safety analysis for Swiss NPPs and also serve as analysis tools for experimental facilities for LWR and ALWR simulations. In relation to these applications, physical model development and improvements, and assessment of the codes are also essential components of the activities. In this paper, a brief overview is provided on the thermalhydraulic and/or neutronic codes used for safety analysis of LWRs, at PSI, and also of some experiences and applications with these codes. Based on these experiences, additional assessment needs are indicated, together with some model improvement needs. The future needs that could be used to specify both the development of a new code and also improvement of available codes are summarized.

  6. Current and anticipated uses of the CATHARE code at EDF and FRAMATOME

    SciTech Connect (OSTI)

    Gandrille, J.L.; Vacher, J.L.; Poizat, F.

    1997-07-01

    This paper presents current industrial applications of the CATHARE code in the fields of Safety Studies and Simulators where the code is intensively used by FRAMATOME, EDF and CEA, the development partners of CATHARE. Future needs in these fields are also recapitulated.

  7. The role of the PIRT process in identifying code improvements and executing code development

    SciTech Connect (OSTI)

    Wilson, G.E.; Boyack, B.E.

    1997-07-01

    In September 1988, the USNRC issued a revised ECCS rule for light water reactors that allows, as an option, the use of best estimate (BE) plus uncertainty methods in safety analysis. The key feature of this licensing option relates to quantification of the uncertainty in the determination that an NPP has a {open_quotes}low{close_quotes} probability of violating the safety criteria specified in 10 CFR 50. To support the 1988 licensing revision, the USNRC and its contractors developed the CSAU evaluation methodology to demonstrate the feasibility of the BE plus uncertainty approach. The PIRT process, Step 3 in the CSAU methodology, was originally formulated to support the BE plus uncertainty licensing option as executed in the CSAU approach to safety analysis. Subsequent work has shown the PIRT process to be a much more powerful tool than conceived in its original form. Through further development and application, the PIRT process has shown itself to be a robust means to establish safety analysis computer code phenomenological requirements in their order of importance to such analyses. Used early in research directed toward these objectives, PIRT results also provide the technical basis and cost effective organization for new experimental programs needed to improve the safety analysis codes for new applications. The primary purpose of this paper is to describe the generic PIRT process, including typical and common illustrations from prior applications. The secondary objective is to provide guidance to future applications of the process to help them focus, in a graded approach, on systems, components, processes and phenomena that have been common in several prior applications.

  8. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01

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

  9. Propane Vehicle and Infrastructure Codes and Standards Chart (Revised) (Fact Sheet), NREL (National Renewable Energy Laboratory)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Many standards development organizations (SDOs) are working to develop codes and standards needed for the utilization of alternative fuel vehicle technologies. This chart shows the SDOs responsible for leading the support and development of key codes and standards for propane. Propane Vehicle and Infrastructure Codes and Standards Chart Vehicle Systems Safety: Vehicle Tanks and Piping: Vehicle Components: Vehicle Dispensing Systems: Vehicle Dispensing System Components: Storage Systems: Storage

  10. Methodology, status and plans for development and assessment of Cathare code

    SciTech Connect (OSTI)

    Bestion, D.; Barre, F.; Faydide, B.

    1997-07-01

    This paper presents the methodology, status and plans for the development, assessment and uncertainty evaluation of the Cathare code. Cathare is a thermalhydraulic code developed by CEA (DRN), IPSN, EDF and FRAMATOME for PWR safety analysis. First, the status of the code development and assessment is presented. The general strategy used for the development and the assessment of the code is presented. Analytical experiments with separate effect tests, and component tests are used for the development and the validation of closure laws. Successive Revisions of constitutive laws are implemented in successive Versions of the code and assessed. System tests or integral tests are used to validate the general consistency of the Revision. Each delivery of a code Version + Revision is fully assessed and documented. A methodology is being developed to determine the uncertainty on all constitutive laws of the code using calculations of many analytical tests and applying the Discrete Adjoint Sensitivity Method (DASM). At last, the plans for the future developments of the code are presented. They concern the optimization of the code performance through parallel computing - the code will be used for real time full scope plant simulators - the coupling with many other codes (neutronic codes, severe accident codes), the application of the code for containment thermalhydraulics. Also, physical improvements are required in the field of low pressure transients and in the modeling for the 3-D model.

  11. Operating Experience Level 3: Safety Concern: Occurrences of...

    Energy Savers [EERE]

    of crushing injuries faced by workers who operate various types of equipment, including electric cars, skid-steers, and life equipment. PDF icon OE-3 2012-05: Safety Concern:...

  12. Idaho Code | Open Energy Information

    Open Energy Info (EERE)

    Not provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Idaho Code Citation Idaho Code (2014). Retrieved from "http:en.openei.org...

  13. RBMK-LOCA-Analyses with the ATHLET-Code

    SciTech Connect (OSTI)

    Petry, A.; Domoradov, A.; Finjakin, A.

    1995-09-01

    The scientific technical cooperation between Germany and Russia includes the area of adaptation of several German codes for the Russian-designed RBMK-reactor. One point of this cooperation is the adaptation of the Thermal-Hydraulic code ATHLET (Analyses of the Thermal-Hydraulics of LEaks and Transients), for RBMK-specific safety problems. This paper contains a short description of a RBMK-1000 reactor circuit. Furthermore, the main features of the thermal-hydraulic code ATHLET are presented. The main assumptions for the ATHLET-RBMK model are discussed. As an example for the application, the results of test calculations concerning a guillotine type rupture of a distribution group header are presented and discussed, and the general analysis conditions are described. A comparison with corresponding RELAP-calculations is given. This paper gives an overview on some problems posed and experience by application of Western best-estimate codes for RBMK-calculations.

  14. Finite Element Analysis Code

    Energy Science and Technology Software Center (OSTI)

    2005-06-26

    Exotxt is an analysis code that reads finite element results data stored in an exodusII file and generates a file in a structured text format. The text file can be edited or modified via a number of text formatting tools. Exotxt is used by analysis to translate data from the binary exodusII format into a structured text format which can then be edited or modified and then either translated back to exodusII format or tomore » another format.« less

  15. Finite Element Analysis Code

    Energy Science and Technology Software Center (OSTI)

    2005-05-07

    CONEX is a code for joining sequentially in time multiple exodusll database files which all represent the same base mesh topology and geometry. It is used to create a single results or restart file from multiple results or restart files which typically arise as the result of multiple restarted analyses. CONEX is used to postprocess the results from a series of finite element analyses. It can join sequentially the data from multiple results databases intomore » a single database which makes it easier to postprocess the results data.« less

  16. JOY computer code

    SciTech Connect (OSTI)

    Couch, R.G.; Albright, E.L.; Alexander, N.B.

    1983-01-01

    JOY is a 3-dimensional multifluid Eulerian hydrocode in Cartesian coordinates. It contains an elastic-plastic treatment and a shock-initiation model for high explosives (HE). Development of JOY was funded by the Ballistic Missile Defense Advanced Technology Center (BMDATC). The intended use of the code was for the study of hypervelocity impacts. The ultimate goal was to perform a structural analysis of objects subject to such impacts. JOY was designed to treat the early-impact phases where material motion is complicated, and then transfer information to DYNA3D for the longer-timescale analysis.

  17. 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.

  18. Nuclear Safety Regulatory Framework

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

    Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting

  19. Experiment Safety Requirements

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

    Experiment Safety Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the

  20. Complete Safety Training

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

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  1. Complete Safety Training

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

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  2. Complete Safety Training

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

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  3. Complete Safety Training

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

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  4. Complete Safety Training

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

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

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

    SciTech Connect (OSTI)

    Mings, W.J. ); Koploy, M.A. )

    1992-01-01

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

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

    SciTech Connect (OSTI)

    Mings, W.J.; Koploy, M.A.

    1992-08-01

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

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

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

    Demonstration Case Study | Department of Energy (RISMC) Advanced Test Reactor Demonstration Case Study Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A

  8. 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

  9. Code Tables | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Code Tables U.S. Department of Energy / U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards System Code Tables Action Code The action code identifies the type of activity being reported in a transaction. The Action Code table shows the valid action codes. Nature of Transaction (TI) Code The financial code signifies the nature of the financial or contractual activity that is involved in the transaction. The Nature of Transaction (TI) Code table shows the valid action

  10. 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 ...

  11. Utah Code Annotated | Open Energy Information

    Open Energy Info (EERE)

    Code Ann. DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Utah Code Annotated Citation Utah Code Annotated (2014). Retrieved from...

  12. Product Service Codes @ Headquarters | Department of Energy

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

    Service Codes @ Headquarters A listing of Product Service Codes used at Headquarters Procurement Services PDF icon Produce Service Codes @ Headquarters.pdf More Documents &...

  13. Cal. Wat. Code 13376 | Open Energy Information

    Open Energy Info (EERE)

    Cal. Wat. Code 13376Legal Abstract Cal. Wat. Code 13376, current through August 14, 2014. Published NA Year Signed or Took Effect 2014 Legal Citation Cal. Wat. Code...

  14. Cal. Wat. Code 13320 | Open Energy Information

    Open Energy Info (EERE)

    Cal. Wat. Code 13320Legal Abstract Cal. Wat. Code 13320, current through August 13, 2014. Published NA Year Signed or Took Effect 1969 Legal Citation Cal. Wat. Code...

  15. Cal. Wat. Code 13369 | Open Energy Information

    Open Energy Info (EERE)

    Cal. Wat. Code 13369Legal Abstract Cal. Wat. Code 13369, current through August 13, 2014. Published NA Year Signed or Took Effect 1969 Legal Citation Cal. Wat. Code...

  16. Cal. Wat. Code 13373 | Open Energy Information

    Open Energy Info (EERE)

    Cal. Wat. Code 13373Legal Abstract Cal. Wat. Code 13373, current through August 14, 2014. Published NA Year Signed or Took Effect 1987 Legal Citation Cal. Wat. Code...

  17. Cal. Wat. Code 13160 | Open Energy Information

    Open Energy Info (EERE)

    Cal. Wat. Code 13160Legal Abstract Cal. Wat. Code 13160, current through August 13, 2014. Published NA Year Signed or Took Effect 1969 Legal Citation Cal. Wat. Code...

  18. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC (Nuclear Regulatory Commission) licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor.

  19. Notices Safety Commission, 4330 East West

    National Nuclear Security Administration (NNSA)

    20 Federal Register / Vol. 77, No. 8 / Thursday, January 12, 2012 / Notices Safety Commission, 4330 East West Highway, Bethesda, MD 20814, (301) 504-7923. Dated: January 10, 2012. Todd A Stevenson, Secretary. [FR Doc. 2012-625 Filed 1-10-12; 4:15 pm] BILLING CODE 6355-01-P CORPORATION FOR NATIONAL AND COMMUNITY SERVICE Information Collection; Submission for OMB Review, Comment Request AGENCY: Corporation for National and Community Service. ACTION: Notice. SUMMARY: The Corporation for National

  20. 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...

  1. 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.

  2. The Italian experience on T/H best estimate codes: Achievements and perspectives

    SciTech Connect (OSTI)

    Alemberti, A.; D`Auria, F.; Fiorino, E.

    1997-07-01

    Themalhydraulic system codes are complex tools developed to simulate the power plants behavior during off-normal conditions. Among the objectives of the code calculations the evaluation of safety margins, the operator training, the optimization of the plant design and of the emergency operating procedures, are mostly considered in the field of the nuclear safety. The first generation of codes was developed in the United States at the end of `60s. Since that time, different research groups all over the world started the development of their own codes. At the beginning of the `80s, the second generation codes were proposed; these differ from the first generation codes owing to the number of balance equations solved (six instead of three), the sophistication of the constitutive models and of the adopted numerics. The capabilities of available computers have been fully exploited during the years. The authors then summarize some of the major steps in the process of developing, modifying, and advancing the capabilities of the codes. They touch on the fact that Italian, and for that matter non-American, researchers have not been intimately involved in much of this work. They then describe the application of these codes in Italy, even though there are no operating or under construction nuclear power plants at this time. Much of this effort is directed at the general question of plant safety in the face of transient type events.

  3. Multimegawatt Space Reactor Safety

    SciTech Connect (OSTI)

    Stanley, M.L. )

    1989-01-01

    The Multimegawatt (MMW) Space Reactor Project supports the Strategic Defense Initiative Office requirement to provide reliable, safe, cost-effective, electrical power in the MMW range. Specifically, power may be used for neutral particle beams, free electron lasers, electromagnetic launchers, and orbital transfer vehicles. This power plant technology may also apply to the electrical power required for other uses such as deep-space probes and planetary exploration. The Multimegawatt Space Reactor Project, the Thermionic Fuel Element Verification Program, and Centaurus Program all support the Multimegawatt Space Nuclear Power Program and form an important part of the US Department of Energy's (DOE's) space and defense power systems activities. A major objective of the MMW project is the development of a reference flight system design that provides the desired levels of public safety, health protection, and special nuclear material (SNM) protection when used during its designated missions. The safety requirements for the MMW project are a hierarchy of requirements that consist of safety requirements/regulations, a safety policy, general safety criteria, safety technical specifications, safety design specifications, and the system design. This paper describes the strategy and philosophy behind the development of the safety requirements imposed upon the MMW concept developers. The safety organization, safety policy, generic safety issues, general safety criteria, and the safety technical specifications are discussed.

  4. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an...

  5. 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...

  6. 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.

  7. Office of Nuclear Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  8. Program Analyst (Transportation Safety)

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as a Program Analyst(Transportation Safety) supporting and advising management on safety and health matters for nuclear and non-nuclear activities.

  9. Safety Issues with Hydrogen as a Vehicle Fuel

    SciTech Connect (OSTI)

    Cadwallader, Lee Charles; Herring, James Stephen

    1999-10-01

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

  10. Safety Issues with Hydrogen as a Vehicle Fuel

    SciTech Connect (OSTI)

    L. C. Cadwallader; J. S. Herring

    1999-09-01

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

  11. 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

  12. Methodology, status, and plans for development and assessment of the RELAP5 code

    SciTech Connect (OSTI)

    Johnson, G.W.; Riemke, R.A.

    1997-07-01

    RELAP/MOD3 is a computer code used for the simulation of transients and accidents in light-water nuclear power plants. The objective of the program to develop and maintain RELAP5 was and is to provide the U.S. Nuclear Regulatory Commission with an independent tool for assessing reactor safety. This paper describes code requirements, models, solution scheme, language and structure, user interface validation, and documentation. The paper also describes the current and near term development program and provides an assessment of the code`s strengths and limitations.

  13. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  14. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  15. Safety | Argonne National Laboratory

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

    News Careers Education Community Diversity Directory Argonne National Laboratory About Safety News Careers Education Community Diversity Directory Energy Environment Security User Facilities Science Work with Argonne Safety Biosafety Safety Safety is integral to Argonne's scientific research and engineering technology mission. As a leading U.S. Department of Energy multi-program research laboratory, our obligation to the American people demands that we conduct our research and operations safely

  16. 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.

  17. 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.

  18. Index of /safety

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

    safety Icon Name Last modified Size Description [DIR] Parent Directory - [DIR] hazardousradioactive..> 17-Apr-2013 12:29 -

  19. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  20. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  1. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  2. Experiment Safety Requirements

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

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  3. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

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

  4. Integrated Safety Management Policy

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

    INTEGRATED SAFETY MANAGEMENT SYSTEM DESCRIPTION U.S. DEPARTMENT OF ENERGY Office of Environmental Management Headquarters May 2008 Preparation: Braj K. sin& Occupational Safety and Health Manager Office of Safety Management Concurrence: Chuan-Fu wu Director, Offlce of Safety Management Deputy Assistant Secretary for safe& Management andoperations Operations Officer for 1 Environmental Management Approval: Date p/-g Date Environmental Management TABLE OF CONTENTS

  5. Explosive Formulation Code Naming SOP

    SciTech Connect (OSTI)

    Martz, H. E.

    2014-09-19

    The purpose of this SOP is to provide a procedure for giving individual HME formulations code names. A code name for an individual HME formulation consists of an explosive family code, given by the classified guide, followed by a dash, -, and a number. If the formulation requires preparation such as packing or aging, these add additional groups of symbols to the X-ray specimen name.

  6. Safety and Health

    Broader source: Energy.gov [DOE]

    PPPO’s Safety and Health (S&H) program integrates safety and health requirements and controls into all work activities and oversees implementation of Integrated Safety Management (ISM) within contractor activities to ensure protection to workers, the public, and the environment.

  7. Integrated Safety Management

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

    Safety Management BEHAVIOR (SAFETY CULTURE) - principles of behavior (values) - align motivations PLAN WORK define project scope define facility functional requirements define and analyze hazards mitigate hazards develop & implement controls authorize work assess & improve work execution reaction to changed conditions LEVELS - INSTITUTIONAL - site wide programs - DOE directives & requirements, cultural values - DOE/contractor interface - FACILITY OR PROJECT - Documented Safety

  8. NEEP Building Energy Codes Project

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

    * Markets value and prioritize energy efficiency - Rating and Disclosure ( VT, Cambridge, MA) * Robust & qualified building energy code work force: DE, RI, MA, MD, NY * ...

  9. City of Austin- Zoning Code

    Broader source: Energy.gov [DOE]

    The Zoning Code also allows for preservation plans in historic districts to incorporate sustainability measures such as solar technologies and other energy generation and efficiency measures.

  10. Technical Assistance: Increasing Code Compliance

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

    Technologies Office Peer Review Rosemarie Bartlett ... energy codes resulting in higher-performing buildings that ... feedback * Provide education and training materials in ...

  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

    Broader source: Energy.gov [DOE]

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

  13. Nuclear Safety | Department of Energy

    Office of Environmental Management (EM)

    Criticality Safety The Nuclear Facility Safety Program establishes and maintains the DOE requirements for nuclear criticality safety. The DOE detailed requirements for criticality ...

  14. Environment/Health/Safety (EHS)

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

    Safety Advisory Committee SAC Home Charter Sub-Committees Membership Minutes Annual Report ESH Peer Review Questions Welcome to the Safety Advisory Committee Web Site The Safety...

  15. Liquefied Natural Gas Safety Research

    Office of Environmental Management (EM)

    May 2012 Liquefied Natural Gas (LNG) Safety Research | Page 1 Liquefied Natural Gas Safety ... Energy | May 2012 Liquefied Natural Gas (LNG) Safety Research | Page i Message from the ...

  16. Radiation Safety Poster | Y-12 National Security Complex

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

    Radiation Safety Poster Radiation Safety Poster Radiation Safety Poster

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

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

    SciTech Connect (OSTI)

    Carbajo, Juan J; Qualls, A L

    2008-01-01

    The transient analysis 3-dimensional (3-D) computer code RELAP5-3D/ATHENA has been employed to model and analyze a space reactor of 180 kW(thermal), 40 kW (net, electrical) with eight Stirling engines (SEs). Each SE will generate over 6 kWe; the excess power will be needed for the pumps and other power management devices. The reactor will be cooled by NaK (a eutectic mixture of sodium and potassium which is liquid at ambient temperature). This space reactor is intended to be deployed over the surface of the Moon or Mars. The reactor operating life will be 8 to 10 years. The RELAP5-3D/ATHENA code is being developed and maintained by Idaho National Laboratory. The code can employ a variety of coolants in addition to water, the original coolant employed with early versions of the code. The code can also use 3-D volumes and 3-D junctions, thus allowing for more realistic representation of complex geometries. A combination of 3-D and 1-D volumes is employed in this study. The space reactor model consists of a primary loop and two secondary loops connected by two heat exchangers (HXs). Each secondary loop provides heat to four SEs. The primary loop includes the nuclear reactor with the lower and upper plena, the core with 85 fuel pins, and two vertical heat exchangers (HX). The maximum coolant temperature of the primary loop is 900 K. The secondary loops also employ NaK as a coolant at a maximum temperature of 877 K. The SEs heads are at a temperature of 800 K and the cold sinks are at a temperature of ~400 K. Two radiators will be employed to remove heat from the SEs. The SE HXs surrounding the SE heads are of annular design and have been modeled using 3-D volumes. These 3-D models have been used to improve the HX design by optimizing the flows of coolant and maximizing the heat transferred to the SE heads. The transients analyzed include failure of one or more Stirling engines, trip of the reactor pump, and trips of the secondary loop pumps feeding the HXs of the

  19. Sandia, NREL Release Wave Energy Converter Modeling and Simulation Code:

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

    WEC-Sim NREL Release Wave Energy Converter Modeling and Simulation Code: WEC-Sim - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing

  20. Telescope Adaptive Optics Code

    Energy Science and Technology Software Center (OSTI)

    2005-07-28

    The Telescope AO Code has general adaptive optics capabilities plus specialized models for three telescopes with either adaptive optics or active optics systems. It has the capability to generate either single-layer or distributed Kolmogorov turbulence phase screens using the FFT. Missing low order spatial frequencies are added using the Karhunen-Loeve expansion. The phase structure curve is extremely dose to the theoreUcal. Secondly, it has the capability to simulate an adaptive optics control systems. The defaultmore » parameters are those of the Keck II adaptive optics system. Thirdly, it has a general wave optics capability to model the science camera halo due to scintillation from atmospheric turbulence and the telescope optics. Although this capability was implemented for the Gemini telescopes, the only default parameter specific to the Gemini telescopes is the primary mirror diameter. Finally, it has a model for the LSST active optics alignment strategy. This last model is highly specific to the LSST« less

  1. 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.

  2. 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.

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

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

    What Can We Learn from Hydrogen Safety Event Databases? Webinar Moderator: Jay Keller Consultant U.S. DOE Fuel Cell Technologies Office Safety, Codes and Standards September 10, 2013 2 | Fuel Cell Technologies Office eere.energy.gov * Clean Energy Patent Growth Index [1] shows growth in all clean energy technology patents * More than 1,000 fuel cell patents issued in 2012 Overview Fuel Cells - An Emerging Global Industry [1]

  4. 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.

  5. Recent improvements of reactor physics codes in MHI

    SciTech Connect (OSTI)

    Kosaka, Shinya Yamaji, Kazuya; Kirimura, Kazuki; Kamiyama, Yohei; Matsumoto, Hideki

    2015-12-31

    This paper introduces recent improvements for reactor physics codes in Mitsubishi Heavy Industries, Ltd(MHI). MHI has developed a new neutronics design code system Galaxy/Cosmo-S(GCS) for PWR core analysis. After TEPCO’s Fukushima Daiichi accident, it is required to consider design extended condition which has not been covered explicitly by the former safety licensing analyses. Under these circumstances, MHI made some improvements for GCS code system. A new resonance calculation model of lattice physics code and homogeneous cross section representative model for core simulator have been developed to apply more wide range core conditions corresponding to severe accident status such like anticipated transient without scram (ATWS) analysis and criticality evaluation of dried-up spent fuel pit. As a result of these improvements, GCS code system has very wide calculation applicability with good accuracy for any core conditions as far as fuel is not damaged. In this paper, the outline of GCS code system is described briefly and recent relevant development activities are presented.

  6. System Safety Common Cause Analysis

    Energy Science and Technology Software Center (OSTI)

    1992-03-10

    The COMCAN fault tree analysis codes are designed to analyze complex systems such as nuclear plants for common causes of failure. A common cause event, or common mode failure, is a secondary cause that could contribute to the failure of more than one component and violates the assumption of independence. Analysis of such events is an integral part of system reliability and safety analysis. A significant common cause event is a secondary cause common tomore » all basic events in one or more minimal cut sets. Minimal cut sets containing events from components sharing a common location or a common link are called common cause candidates. Components share a common location if no barrier insulates any one of them from the secondary cause. A common link is a dependency among components which cannot be removed by a physical barrier (e.g.,a common energy source or common maintenance instructions).« less

  7. Safety Cinema: Safety Videos: Los Alamos National Laboratory

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

    linked in Search Safety CinemaTM VideosINDUSTRIAL HYGIENE AND SAFETY Safety Videos » Safety Cinema Safety Videos Home Safety Cinema Human Beings Beryllium Integrated Safety CONTACTS Occupational Safety and Health Division Office 505 606-0295 Video Contact Lorrie Bonds Lopez safetyvideos@lanl.gov 505 667-0216 Safety Cinema Play videos - download flyers and more Safety practices for work and home, supporting the well-being of every worker throughout each day. safety cinema logo "Let's take

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. Local invariants of stabilizer codes

    SciTech Connect (OSTI)

    Nest, Maarten van den; Dehaene, Jeroen; Moor, Bart de

    2004-09-01

    In Phys. Rev. A 58, 1833 (1998), Grassl et al. presented a family of polynomial invariants which separate the orbits of multiqubit density operators {rho} under the action of the local unitary group. We consider this family of invariants for the class of those {rho} that are the projection operators describing stabilizer codes and give a complete translation of these invariants into the binary framework in which stabilizer codes are usually described. Such an investigation of local invariants of quantum codes is of natural importance in quantum coding theory, since locally equivalent codes have the same error-correcting capabilities and local invariants are powerful tools to explore their structure. Moreover, the present result is relevant in the context of multipartite entanglement and the development of the measurement-based model of quantum computation known as the one-way quantum computer.

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

    SciTech Connect (OSTI)

    Chang Oh

    2007-05-01

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

  14. Fusion safety program Annual report, Fiscal year 1995

    SciTech Connect (OSTI)

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

    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.

  15. Building Codes Resources | Department of Energy

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

    Codes Resources Building Codes Resources Some commercial and/or residential construction codes mandate certain energy performance requirements for the design, materials, and equipment used in new construction and renovations. State-wide minimum codes may be amended by local jurisdictions to be more stringent if energy performance requirements are lacking or liberal. Find building codes resources below. DOE Resources Building Energy Codes Program: Resource Center Building Energy Codes Program:

  16. Codes and Standards Activities | Department of Energy

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

    DOE Activities » Codes and Standards Activities Codes and Standards Activities The Fuel Cell Technologies Office works with code development organizations, code officials, industry experts, and national laboratory scientists to draft new model codes and equipment standards that cover emerging hydrogen technologies for consideration by the various code enforcing jurisdictions. DOE's codes and standards activities are focused on: Developing training programs for state and local officials that

  17. Methodology, status and plans for development and assessment of TUF and CATHENA codes

    SciTech Connect (OSTI)

    Luxat, J.C.; Liu, W.S.; Leung, R.K.

    1997-07-01

    An overview is presented of the Canadian two-fluid computer codes TUF and CATHENA with specific focus on the constraints imposed during development of these codes and the areas of application for which they are intended. Additionally a process for systematic assessment of these codes is described which is part of a broader, industry based initiative for validation of computer codes used in all major disciplines of safety analysis. This is intended to provide both the licensee and the regulator in Canada with an objective basis for assessing the adequacy of codes for use in specific applications. Although focused specifically on CANDU reactors, Canadian experience in developing advanced two-fluid codes to meet wide-ranging application needs while maintaining past investment in plant modelling provides a useful contribution to international efforts in this area.

  18. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    This document is a compilation and source list of nuclear safety criteria that the Nuclear Regulatory Commission (NRC) applies to licensed reactors; it can be used by DOE and DOE contractors to identify NRC criteria to be evaluated for application to the DOE reactors under their cognizance. The criteria listed are those that are applied to the areas of nuclear safety addressed in the safety analysis report of a licensed reactor. They are derived from federal regulations, USNRC regulatory guides, Standard Review Plan (SRP) branch technical positions and appendices, and industry codes and standards.

  19. 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.

  20. Seismic Life Safety, Modernization, and Replacement of General...

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

    71510 Draft Environmental Impact Report (EIR) Public Hearing - 22510 CEQA Public ... 62910 Notice of Errata - Final EIR 62310 Notice of Availability - Final EIR ...

  1. 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.

  2. New Code Compliance Briefs Assist in Resolving Codes and Standards...

    Energy Savers [EERE]

    Codes and Standards Concerns in Energy Innovations February 24, 2016 3:00PM to 4:30PM EST The Building America Program is hosting a free webinar that will provide an overview ...

  3. Natural Gas Vehicle and Infrastructure Codes and Standards Chart (Revised) (Fact Sheet), NREL (National Renewable Energy Laboratory)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Natural Gas Vehicle and Infrastructure Codes and Standards Chart Many standards development organizations (SDOs) are working to develop codes and standards needed for the utilization of alternative fuel vehicle technologies. This chart shows the SDOs responsible for leading the support and development of key codes and standards for natural gas. Vehicle Safety: Vehicle Fuel Systems: Vehicle Containers: Vehicle Fuel System Components: Dispensing Component Standards: Dispensing Operations:

  4. Comparison of linac simulation codes

    SciTech Connect (OSTI)

    Nath, S.; Ryne, Robert D.; Stovall, J.; Takeda, H.; Xiang, J.; Young, L.; Pichoff, N.; Uriot, D.; Crandall, K.

    2001-01-25

    The Spallation Neutron Source (SNS) project is a collaborative effort between Brookhaven, Argonne, Jefferson, Lawrence Berkeley, Los Alamos and Oak Ridge National Laboratories. Los Alamos is responsible for the design of the linac for this accelerator complex. The code PARMILA, developed at Los Alamos is widely used for proton linac design and beam dynamics studies. The most updated version includes superconducting structures among others. In recent years, some other codes have also been developed which primarily focuses on the studies of the beam dynamics. In this paper, we compare the simulation results and discuss physics aspects of the different linac design and beam dynamics simulation codes.

  5. State building energy codes status

    SciTech Connect (OSTI)

    1996-09-01

    This document contains the State Building Energy Codes Status prepared by Pacific Northwest National Laboratory for the U.S. Department of Energy under Contract DE-AC06-76RL01830 and dated September 1996. The U.S. Department of Energy`s Office of Codes and Standards has developed this document to provide an information resource for individuals interested in energy efficiency of buildings and the relevant building energy codes in each state and U.S. territory. This is considered to be an evolving document and will be updated twice a year. In addition, special state updates will be issued as warranted.

  6. 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.

  7. WIPP Documents - Nuclear Safety

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

    Nuclear Safety DOE/WIPP-07-3372, Revision 5b, WIPP Documented Safety Analysis Approved April 2016 The Documented Safety Analysis addresses all hazards (both radiological and nonradiological) and the controls necessary to provide adequate protection to the public, workers, and the environment. The WIPP DSA demonstrates the extent to which the Waste Isolation Pilot Plant can be operated safely with respect to workers, the public, and the environment. DOE/WIPP-07-3373, Revision 5b, WIPP Technical

  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. Integrated Safety Management Safety Culture Resources | Department of

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

    Energy Safety Culture Resources Integrated Safety Management Safety Culture Resources A collection of resources available in implementing ISM safety culture activities Safety from the Operator's Perspective: We are All in This Together (2005) Transcript, Keeping the Edge: Enhancing Performance Through Managing Culture (2003), Edgar H. Schein, Ph.D. Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop (2003) Safety Culture in Nuclear Installations: Guidance for

  10. Unreviewed Safety Question Requirements

    Office of Environmental Management (EM)

    DOE G 424.1-1, Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation 1. The USQ ...

  11. Organized for safety

    SciTech Connect (OSTI)

    McCleary, M.D.; Schuberth, P.C.; Hining, D.E.

    1996-11-01

    The Exxon Company, International Drilling Organization (ECIDO) is committed to an injury-free workplace through continuous efforts by identifying and eliminating or managing safety risks associated with drilling activities. The newly developed and recently completed ECIDO Safety Management Program (SMP) strengthens this commitment by defining a comprehensive, management approved, organized framework for drill teams from which operations safety is managed both effectively and consistently worldwide. The SMP is proactive, focuses on positive recognition, promotes greater individual involvement, and gives part ownership of the safety program at the rig level to the crews.

  12. 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.

  13. safety analysis report

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

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  14. safety of space

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

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  15. FEOSH Annual Safety Training

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Department of Energy (DOE) has developed an annual safety training course that is mandatory for all current DOE Federal employees and for each new hire.

  16. Complete Safety Training

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

    EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B4 laser EHS 0302 Macromolecular ...

  17. H. UNREVIEWED SAFETY QUESTIONS

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

    3 Department of Energy Pt. 835 H. UNREVIEWED SAFETY QUESTIONS 1. The USQ process is an important tool to evaluate whether changes affect the safety basis. A contractor must use the USQ proc- ess to ensure that the safety basis for a DOE nuclear facility is not undermined by changes in the facility, the work performed, the associated hazards, or other factors that support the adequacy of the safety basis. 2. The USQ process permits a contractor to make physical and procedural changes to a nuclear

  18. 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.

  19. 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.

  20. Lift truck safety review

    SciTech Connect (OSTI)

    Cadwallader, L.C.

    1997-03-01

    This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.

  1. Risk and Safety Assessment

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

    Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal ... Natural Gas Supercritical CO2-Brayton Cycle Geothermal Safety, Security & ...

  2. SSRL Safety Office Memo

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

    new regulations (NFPA70E) which outline the "Standard for Electrical Safety in the Workplace". Specifically it requires that the Arc Flash Hazard be categorized and PPE stated...

  3. Safety & Quality Assurance

    Broader source: Energy.gov [DOE]

    Together, our Facility Operations Division and Engineering, Safety and Quality Division work to ensure EM conducts its operations and cleanup safely through sound practices. These divisions ensure...

  4. 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.

  5. 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.

  6. 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.

  7. NAICS Codes @ Headquarters | Department of Energy

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

    NAICS Codes @ Headquarters NAICS Codes @ Headquarters A listing of NAICS codes used at Headquarters Procurement Services NAICS Codes @ Headquarters.pdf (37.93 KB) More Documents & Publications Product Service Codes @ Headquarters Management & Operating Subcontract Reporting Capability (MOSRC) Downloads Historical Procurement Information

  8. Safety of Decommissioning of Nuclear Facilities

    SciTech Connect (OSTI)

    Batandjieva, B.; Warnecke, E.; Coates, R.

    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.

  9. code | OpenEI Community

    Open Energy Info (EERE)

    by Graham7781(2017) Super contributor 14 April, 2014 - 09:48 National Day of Civic Hacking code community data Event hacking international national OpenEI The National Day of...

  10. The Integrated TIGER Series Codes

    Energy Science and Technology Software Center (OSTI)

    2006-01-15

    ITS is a powerful and user-friendly software package permitting state-of-the-art Monte Carlo solution of linear time-independent coupled electron/photon radiation transport problems, with or without the presence of macroscopic electric and magnetic fields of arbitrary spatial dependence. Our goal has been to simultaneously maximize operational simplicity and physical accuracy. Through a set of preprocessor directives, the user selects one of the many ITS codes. The ease with which the makefile system is applied combines with anmore » input scheme based on order-independent descriptive keywords that makes maximum use of defaults and intemal error checking to provide experimentalists and theorists alike with a method for the routine but rigorous solution of sophisticated radiation transport problems. Physical rigor is provided by employing accurate cross sections, sampling distributions, and physical models for describing the production and transport of the electron/photon cascade from 1.0 GeV down to 1.0 keV. The availability of source code permits the more sophisticated user to tailor the codes to specific applications and to extend the capabilities of the codes to more complex applications. Version 5.0, the latest version of ITS, contains (1) improvements to the ITS 3.0 continuous-energy codes, (2) multigroup codes with adjoint transport capabilities, (3) parallel implementations of all ITS codes, (4) a general purpose geometry engine for linking with CAD or other geometry formats, and (5) the Cholla facet geometry library. Moreover, the general user friendliness of the software has been enhanced through increased internal error checking and improved code portability.« less

  11. electromagnetics, eddy current, computer codes

    Energy Science and Technology Software Center (OSTI)

    2002-03-12

    TORO Version 4 is designed for finite element analysis of steady, transient and time-harmonic, multi-dimensional, quasi-static problems in electromagnetics. The code allows simulation of electrostatic fields, steady current flows, magnetostatics and eddy current problems in plane or axisymmetric, two-dimensional geometries. TORO is easily coupled to heat conduction and solid mechanics codes to allow multi-physics simulations to be performed.

  12. Edge equilibrium code for tokamaks

    SciTech Connect (OSTI)

    Li, Xujing; Drozdov, Vladimir V.

    2014-01-15

    The edge equilibrium code (EEC) described in this paper is developed for simulations of the near edge plasma using the finite element method. It solves the Grad-Shafranov equation in toroidal coordinate and uses adaptive grids aligned with magnetic field lines. Hermite finite elements are chosen for the numerical scheme. A fast Newton scheme which is the same as implemented in the equilibrium and stability code (ESC) is applied here to adjust the grids.

  13. A National Set of Hydrogen Codes and Standards for the US (Presentation)

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

    National Set of Hydrogen Codes and Standards for the US 3 rd International Conference on Hydrogen Safety Carl H. Rivkin, P.E. September 16, 2009 Ajaccio, France NREL/PR-560-46604 National Renewable Energy Laboratory Innovation for Our Energy Future Overview The US has a national set of codes and standards that address the use of hydrogen technologies These documents are published by several organizations and are not all directly adopted by government authorities The US Department of Energy (DOE)

  14. Ethanol Vehicle and Infrastructure Codes and Standards Chart (Revised) (Fact Sheet), NREL (National Renewable Energy Laboratory)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    pipeline safety) CONTROLLING AUTHORITIES: State and Local Government (zoning, building permits) CONTROLLING AUTHORITIES: State and Local Government (zoning, building permits) CONTROLLING AUTHORITIES: DOT/NHTS (crashworthiness) EPA (emissions) Many standards development organizations (SDOs) are working to develop codes and standards needed for the utilization of alternative fuel vehicle technologies. This chart shows the SDOs responsible for leading the support and development of key codes and

  15. National Template: Hydrogen Vehicle and Infrastructure Codes and Standards (Fact Sheet), NREL (National Renewable Energy Laboratory)

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    pipeline safety) CONTROLLING AUTHORITIES: State and Local Government (zoning, building permits) CONTROLLING AUTHORITIES: DOT/NHTS (crashworthiness) EPA (emissions) Many standards development organizations (SDOs) are working to develop codes and standards needed to prepare for the commercialization of alternative fuel vehicle technologies. This graphic template shows the SDOs responsible for leading the support and development of key codes and standards for hydrogen. National Template: Hydrogen

  16. Facility Safety | Department of Energy

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

    Facility Safety Facility Safety In addition to establishing nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities, the U.S. Department of Energy's (DOE) Office of Nuclear Facility Safety works proactively with headquarters and field offices to foster continuous improvement and nuclear safety excellence. In addition, the Office provides high quality, customer-oriented assistance that enables improved DOE program and field

  17. 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.

  18. Fusion Safety Program annual report, fiscal year 1994

    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.

    1995-03-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. 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, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much 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 of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities.

  19. 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)

  20. 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 Energys 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.

  1. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE)

    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.

  2. CRAD, Facility Safety- Technical Safety Requirements

    Office of Energy Efficiency and Renewable Energy (EERE)

    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).

  3. CRAD, Facility Safety- Documented Safety Analysis

    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 Documented Safety Analysis.

  4. RBMK coupled neutronics/thermal-hydraulics analyses by two independent code systems

    SciTech Connect (OSTI)

    Parisi, C.; D'Auria, F.; Malofeev, V.; Ivanov, B.; Ivanov, K.

    2006-07-01

    This paper presents the coupled neutronics/thermal-hydraulics activities carried out in the framework of the part B of the TACIS project R2.03/97, 'Software development for accident analysis of RBMK reactors in Russia'. Two independent code systems were assembled, one from the Russian side and the other from the Western side, for studying RBMK core transients. The Russian code system relies on the use of code UNK for neutron data libraries generation and the three-dimensional neutron kinetics thermal-hydraulics coupled codes BARS-KORSAR for plant transient analyses. The Western code system is instead based on the lattice physics code HELIOS and on the RELAP5-3D C code. Several activities were performed for testing code system's capabilities: the neutron data libraries were calculated and verified by precise Monte Carlo calculations, the coupled codes' steady state results were compared with plant detectors' data, and calculations of several transients were compared. Finally, both code systems proved to have all the capabilities for addressing reliable safety analyses of RBMK reactors. (authors)

  5. 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

  6. Fire Safety Committee

    Broader source: Energy.gov [DOE]

    The purpose of the Department of Energy /National Nuclear Security Administration (DOE) Fire Safety Committee is to provide a forum to facilitate the interaction between the DOE, its program offices and contractor personnel with common interests regarding the identification and resolution of fire safety-related issues including the development of appropriate fire protection Orders, Guides, and Technical Standards.

  7. The color of safety

    SciTech Connect (OSTI)

    Carter, R.A.

    2006-06-15

    The industry's workforce is getting grayer as veteran miners approach retirement, and greener as new hires come onboard. Will the changing complexion of the industry affect future safety technology? The article discusses problems of noise, vibration, and communication faced by coal miners and reports some developments by manufacturers of mining equipment to improve health and safety. 1 fig., 4 photos.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. Software reliability and safety in nuclear reactor protection systems

    SciTech Connect (OSTI)

    Lawrence, J.D.

    1993-11-01

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

  13. K Basin safety analysis

    SciTech Connect (OSTI)

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

    1994-12-16

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

  14. SPEERs Building Energy Codes Program

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

    ... of the REEO's, we are learning quickly, responding to ... Energy Code Compliance Collaborative in Oklahoma. *Double ... regional code datastrategies - provide technical ...

  15. Finite Element Scalar Diffraction Theory Code

    Energy Science and Technology Software Center (OSTI)

    1993-08-18

    This computer code calculates the optical diffraction field for diffraction through two-dimensional apertures to aid optical system design. The code allows plotting of the diffraction field.

  16. Building Energy Code | Open Energy Information

    Open Energy Info (EERE)

    Building Energy Code Jump to: navigation, search Building energy codes adopted by states (and some local governments) require commercial andor residential construction to adhere...

  17. Building Energy Codes | Open Energy Information

    Open Energy Info (EERE)

    Building Energy Codes Jump to: navigation, search Building energy codes adopted by states (and some local governments) require commercial andor residential construction to adhere...

  18. Building Energy Codes Collaborative Technical Assistance for...

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

    Collaborative Technical Assistance for States Building Energy Codes Collaborative Technical ... 2014 BTO Peer Review Southeast Energy Efficiency Alliance's Building Energy Codes ...

  19. National Template: Hydrogen Vehicle and Infrastructure Codes...

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

    Hydrogen Vehicle and Infrastructure Codes and Standards (Fact Sheet), NREL (National Renewable Energy Laboratory) National Template: Hydrogen Vehicle and Infrastructure Codes and ...

  20. Laboratory Equipment Donation Program - LEDP Widget Code

    Office of Scientific and Technical Information (OSTI)

    Widget Inclusion Code Copy the code below and paste it to your website or blog: