National Library of Energy BETA

Sample records for first-served basis determined

  1. SRS FTF Section 3116 Basis for Determination

    Broader source: Energy.gov [DOE]

    Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site. In accordance with NDAA Section 3116, certain waste from reprocessing of spent nuclear fuel is not high...

  2. F tank draft basis determination press release 092910 _2_......

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

    place. The FTF is a 22-acre site, which consists of 22 underground radioactive waste storage tanks and supporting ancillary structures. The Secretary's decision only determines...

  3. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Office of Environmental Management (EM)

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  4. Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) published in the Federal Register (January 24, 2006), a Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site.

  5. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Broader source: Energy.gov [DOE]

    The Secretary of Energy is making this 3116 Determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) [1]. This 3116...

  6. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

    Office of Environmental Management (EM)

    NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 DOE/NE-ID-11226 Revision 0 Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility November 2006 ii CONTENTS ACRONYMS.............................................................................................................................................. vii 1. INTRODUCTION AND

  7. TU-F-18A-04: Use of An Image-Based Material-Decomposition Algorithm for Multi-Energy CT to Determine Basis Material Densities

    SciTech Connect (OSTI)

    Li, Z; Leng, S; Yu, L; McCollough, C

    2014-06-15

    Purpose: Published methods for image-based material decomposition with multi-energy CT images have required the assumption of volume conservation or accurate knowledge of the x-ray spectra and detector response. The purpose of this work was to develop an image-based material-decomposition algorithm that can overcome these limitations. Methods: An image-based material decomposition algorithm was developed that requires only mass conservation (rather than volume conservation). With this method, using multi-energy CT measurements made with n=4 energy bins, the mass density of each basis material and of the mixture can be determined without knowledge of the tube spectra and detector response. A digital phantom containing 12 samples of mixtures from water, calcium, iron, and iodine was used in the simulation (Siemens DRASIM). The calibration was performed by using pure materials at each energy bin. The accuracy of the technique was evaluated in noise-free and noisy data under the assumption of an ideal photon-counting detector. Results: Basis material densities can be estimated accurately by either theoretic calculation or calibration with known pure materials. The calibration approach requires no prior information about the spectra and detector response. Regression analysis of theoretical values versus estimated values results in excellent agreement for both noise-free and noisy data. For the calibration approach, the R-square values are 0.9960+/−0.0025 and 0.9476+/−0.0363 for noise-free and noisy data, respectively. Conclusion: From multi-energy CT images with n=4 energy bins, the developed image-based material decomposition method accurately estimated 4 basis material density (3 without k-edge and 1 with in the range of the simulated energy bins) even without any prior information about spectra and detector response. This method is applicable to mixtures of solutions and dissolvable materials, where volume conservation assumptions do not apply. CHM receives research support from NIH and Siemens Healthcare.

  8. Safety Basis Report

    SciTech Connect (OSTI)

    R.J. Garrett

    2002-01-14

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

  9. Basis for Section 3116 Determination for the Idaho Nuclear Technology and Engineering Center Tank Farm Facility at the Idaho National Laboratory

    Broader source: Energy.gov [DOE]

    This 3116 Basis Document addresses the disposal of stabilized residuals in the TFF, and the TFF tank system, and disposal of the tanks, vaults, and associated piping and ancillary equipment at...

  10. Molecular Basis for Complement Recognition and Inhibition Determined by Crystallographic Studies of the Staphylococcal Complement Inhibitor (SCIN) Bound to C3c and C3b

    SciTech Connect (OSTI)

    Garcia, Brandon L.; Ramyar, Kasra X.; Tzekou, Apostolia; Ricklin, Daniel; McWhorter, William J.; Lambris, John D.; Geisbrecht, Brian V.

    2010-10-22

    The human complement system plays an essential role in innate and adaptive immunity by marking and eliminating microbial intruders. Activation of complement on foreign surfaces results in proteolytic cleavage of complement component 3 (C3) into the potent opsonin C3b, which triggers a variety of immune responses and participates in a self-amplification loop mediated by a multi-protein assembly known as the C3 convertase. The human pathogen Staphylococcus aureus has evolved a sophisticated and potent complement evasion strategy, which is predicated upon an arsenal of potent inhibitory proteins. One of these, the staphylococcal complement inhibitor (SCIN), acts at the level of the C3 convertase (C3bBb) and impairs downstream complement function by trapping the convertase in a stable but inactive state. Previously, we have shown that SCIN binds C3b directly and competitively inhibits binding of human factor H and, to a lesser degree, that of factor B to C3b. Here, we report the co-crystal structures of SCIN bound to C3b and C3c at 7.5 and 3.5 {angstrom} limiting resolution, respectively, and show that SCIN binds a critical functional area on C3b. Most significantly, the SCIN binding site sterically occludes the binding sites of both factor H and factor B. Our results give insight into SCIN binding to activated derivatives of C3, explain how SCIN can recognize C3b in the absence of other complement components, and provide a structural basis for the competitive C3b-binding properties of SCIN. In the future, this may suggest templates for the design of novel complement inhibitors based upon the SCIN structure.

  11. Determination

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

    Determination of a Minimum Soiling Level to Affect Photovoltaic Devices Patrick D. Burton and Bruce H. King Sandia National Laboratories, Albuquerque, NM 87185 USA...

  12. Technical Planning Basis

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

    2007-07-11

    The Guide assists DOE/NNSA field elements and operating contractors in identifying and analyzing hazards at facilities and sites to provide the technical planning basis for emergency management programs. Supersedes DOE G 151.1-1, Volume 2.

  13. Basis

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

    operator bispectral analysis D. A. Baver, 1 P. W. Terry, 1 and C. Holland 2 1 Department of Physics, University of Wisconsin, Madison, Wisconsin 53706, USA 2 Center for Energy Research, University of California, San Diego, California 92093, USA ͑Received 11 September 2008; accepted 12 February 2009; published online 30 March 2009͒ A new procedure for calculating model coefficients from fluctuation data for fully developed turbulence is derived. This procedure differs from previous related

  14. Basis

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

    that this equation is a difference- equation representation in the temporal domain of a first- order-in-time nonlinear partial differential equation. The co- efficient L k...

  15. CRAD, NNSA- Safety Basis (SB)

    Broader source: Energy.gov [DOE]

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

  16. The Basis Code Development System

    Energy Science and Technology Software Center (OSTI)

    1994-03-15

    BASIS9.4 is a system for developing interactive computer programs in Fortran, with some support for C and C++ as well. Using BASIS9.4 you can create a program that has a sophisticated programming language as its user interface so that the user can set, calculate with, and plot, all the major variables in the program. The program author writes only the scientific part of the program; BASIS9.4 supplies an environment in which to exercise that scientificmore » programming which includes an interactive language, an interpreter, graphics, terminal logs, error recovery, macros, saving and retrieving variables, formatted I/O, and online documentation.« less

  17. TECHNICAL BASIS DOCUMENT FOR NATURAL EVENT HAZARDS

    SciTech Connect (OSTI)

    KRIPPS, L.J.

    2006-07-31

    This technical basis document was developed to support the documented safety analysis (DSA) and describes the risk binning process and the technical basis for assigning risk bins for natural event hazard (NEH)-initiated accidents. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the frequency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR-level controls.

  18. Safety Basis Information System | Department of Energy

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

    Basis Information System Safety Basis Information System Safety Basis Report (Public Access) Click on the above link to see the current Safety Basis report. This report provides a list of all DOE nuclear facilities with the safety basis status, hazard categorization, and safety basis type. Safety Basis Login Click on the above link to log in to the Safety Basis web interface. "RESTRICTED; access only to DOE and DOE contractors" Safety Basis Account Request Click on the above link to

  19. Sculpting bespoke mountains: Determining free energies with basis...

    Office of Scientific and Technical Information (OSTI)

    ; McGovern, Michael 2 ; de Pablo, Juan J. 3 + Show Author Affiliations Department of Chemical and Biomolecular Engineering, University of Notre Dame du Lac, Notre Dame,...

  20. Authorization basis requirements comparison report

    SciTech Connect (OSTI)

    Brantley, W.M.

    1997-08-18

    The TWRS Authorization Basis (AB) consists of a set of documents identified by TWRS management with the concurrence of DOE-RL. Upon implementation of the TWRS Basis for Interim Operation (BIO) and Technical Safety Requirements (TSRs), the AB list will be revised to include the BIO and TSRs. Some documents that currently form part of the AB will be removed from the list. This SD identifies each - requirement from those documents, and recommends a disposition for each to ensure that necessary requirements are retained when the AB is revised to incorporate the BIO and TSRs. This SD also identifies documents that will remain part of the AB after the BIO and TSRs are implemented. This document does not change the AB, but provides guidance for the preparation of change documentation.

  1. Hanford Generic Interim Safety Basis

    SciTech Connect (OSTI)

    Lavender, J.C.

    1994-09-09

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

  2. OSR encapsulation basis -- 100-KW

    SciTech Connect (OSTI)

    Meichle, R.H.

    1995-01-27

    The purpose of this report is to provide the basis for a change in the Operations Safety Requirement (OSR) encapsulated fuel storage requirements in the 105 KW fuel storage basin which will permit the handling and storing of encapsulated fuel in canisters which no longer have a water-free space in the top of the canister. The scope of this report is limited to providing the change from the perspective of the safety envelope (bases) of the Safety Analysis Report (SAR) and Operations Safety Requirements (OSR). It does not change the encapsulation process itself.

  3. Beyond Design Basis Events | Department of Energy

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

    Beyond Design Basis Events Beyond Design Basis Events Beyond Design Basis Events Following the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to beyond design basis events (BDBEs). These initiatives included issuing Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis, and conducting two DOE nuclear safety workshops. DOE also issued two reports documenting the

  4. Internal dosimetry technical basis manual

    SciTech Connect (OSTI)

    Not Available

    1990-12-20

    The internal dosimetry program at the Savannah River Site (SRS) consists of radiation protection programs and activities used to detect and evaluate intakes of radioactive material by radiation workers. Examples of such programs are: air monitoring; surface contamination monitoring; personal contamination surveys; radiobioassay; and dose assessment. The objectives of the internal dosimetry program are to demonstrate that the workplace is under control and that workers are not being exposed to radioactive material, and to detect and assess inadvertent intakes in the workplace. The Savannah River Site Internal Dosimetry Technical Basis Manual (TBM) is intended to provide a technical and philosophical discussion of the radiobioassay and dose assessment aspects of the internal dosimetry program. Detailed information on air, surface, and personal contamination surveillance programs is not given in this manual except for how these programs interface with routine and special bioassay programs.

  5. BASIS Set Exchange (BSE): Chemistry Basis Sets from the William R. Wiley Environmental Molecular Sciences Laboratory (EMSL) Basis Set Library

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

    Feller, D; Schuchardt, Karen L.; Didier, Brett T.; Elsethagen, Todd; Sun, Lisong; Gurumoorthi, Vidhya; Chase, Jared; Li, Jun

    The Basis Set Exchange (BSE) provides a web-based user interface for downloading and uploading Gaussian-type (GTO) basis sets, including effective core potentials (ECPs), from the EMSL Basis Set Library. It provides an improved user interface and capabilities over its predecessor, the EMSL Basis Set Order Form, for exploring the contents of the EMSL Basis Set Library. The popular Basis Set Order Form and underlying Basis Set Library were originally developed by Dr. David Feller and have been available from the EMSL webpages since 1994. BSE not only allows downloading of the more than 200 Basis sets in various formats; it allows users to annotate existing sets and to upload new sets. (Specialized Interface)

  6. Tank characterization technical sampling basis

    SciTech Connect (OSTI)

    Brown, T.M.

    1998-04-28

    Tank Characterization Technical Sampling Basis (this document) is the first step of an in place working process to plan characterization activities in an optimal manner. This document will be used to develop the revision of the Waste Information Requirements Document (WIRD) (Winkelman et al. 1997) and ultimately, to create sampling schedules. The revised WIRD will define all Characterization Project activities over the course of subsequent fiscal years 1999 through 2002. This document establishes priorities for sampling and characterization activities conducted under the Tank Waste Remediation System (TWRS) Tank Waste Characterization Project. The Tank Waste Characterization Project is designed to provide all TWRS programs with information describing the physical, chemical, and radiological properties of the contents of waste storage tanks at the Hanford Site. These tanks contain radioactive waste generated from the production of nuclear weapons materials at the Hanford Site. The waste composition varies from tank to tank because of the large number of chemical processes that were used when producing nuclear weapons materials over the years and because the wastes were mixed during efforts to better use tank storage space. The Tank Waste Characterization Project mission is to provide information and waste sample material necessary for TWRS to define and maintain safe interim storage and to process waste fractions into stable forms for ultimate disposal. This document integrates the information needed to address safety issues, regulatory requirements, and retrieval, treatment, and immobilization requirements. Characterization sampling to support tank farm operational needs is also discussed.

  7. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2009-12-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  8. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

    2008-03-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules—23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

  9. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

    2007-04-01

    This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules—24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

  10. Advanced Test Reactor Design Basis Reconstitution Project Issue Resolution Process

    SciTech Connect (OSTI)

    Steven D. Winter; Gregg L. Sharp; William E. Kohn; Richard T. McCracken

    2007-05-01

    The Advanced Test Reactor (ATR) Design Basis Reconstitution Program (DBRP) is a structured assessment and reconstitution of the design basis for the ATR. The DBRP is designed to establish and document the ties between the Document Safety Analysis (DSA), design basis, and actual system configurations. Where the DBRP assessment team cannot establish a link between these three major elements, a gap is identified. Resolutions to identified gaps represent configuration management and design basis recovery actions. The proposed paper discusses the process being applied to define, evaluate, report, and address gaps that are identified through the ATR DBRP. Design basis verification may be performed or required for a nuclear facility safety basis on various levels. The process is applicable to large-scale design basis reconstitution efforts, such as the ATR DBRP, or may be scaled for application on smaller projects. The concepts are applicable to long-term maintenance of a nuclear facility safety basis and recovery of degraded safety basis components. The ATR DBRP assessment team has observed numerous examples where a clear and accurate link between the DSA, design basis, and actual system configuration was not immediately identifiable in supporting documentation. As a result, a systematic approach to effectively document, prioritize, and evaluate each observation is required. The DBRP issue resolution process provides direction for consistent identification, documentation, categorization, and evaluation, and where applicable, entry into the determination process for a potential inadequacy in the safety analysis (PISA). The issue resolution process is a key element for execution of the DBRP. Application of the process facilitates collection, assessment, and reporting of issues identified by the DBRP team. Application of the process results in an organized database of safety basis gaps and prioritized corrective action planning and resolution. The DBRP team follows the ATR DBRP issue resolution process which provides a method for the team to promptly sort and prioritize questions and issues between those that can be addressed as a normal part of the reconstitution project and those that are to be handle as PISAs. Presentation of the DBRP issue resolution process provides an example for similar activities that may be required at other facilities within the Department of Energy complex.

  11. Beyond Design Basis Event Pilot Evaluations

    Broader source: Energy.gov [DOE]

    This document provides Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities based upon Beyond Design Basis Event Pilot Evaluations

  12. Property:ExplorationBasis | Open Energy Information

    Open Energy Info (EERE)

    Text Description Exploration Basis Why was exploration work conducted in this area (e.g., USGS report of a geothermal resource, hot springs with geothemmetry indicating...

  13. design basis threat | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    design basis threat | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the...

  14. Structural basis for Tetrahymena telomerase processivity factor...

    Office of Scientific and Technical Information (OSTI)

    DNA Citation Details In-Document Search Title: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Authors: ...

  15. PARFUME Theory and Model basis Report

    SciTech Connect (OSTI)

    Darrell L. Knudson; Gregory K Miller; G.K. Miller; D.A. Petti; J.T. Maki; D.L. Knudson

    2009-09-01

    The success of gas reactors depends upon the safety and quality of the coated particle fuel. The fuel performance modeling code PARFUME simulates the mechanical, thermal and physico-chemical behavior of fuel particles during irradiation. This report documents the theory and material properties behind vari¬ous capabilities of the code, which include: 1) various options for calculating CO production and fission product gas release, 2) an analytical solution for stresses in the coating layers that accounts for irradiation-induced creep and swelling of the pyrocarbon layers, 3) a thermal model that calculates a time-dependent temperature profile through a pebble bed sphere or a prismatic block core, as well as through the layers of each analyzed particle, 4) simulation of multi-dimensional particle behavior associated with cracking in the IPyC layer, partial debonding of the IPyC from the SiC, particle asphericity, and kernel migration (or amoeba effect), 5) two independent methods for determining particle failure probabilities, 6) a model for calculating release-to-birth (R/B) ratios of gaseous fission products that accounts for particle failures and uranium contamination in the fuel matrix, and 7) the evaluation of an accident condition, where a particle experiences a sudden change in temperature following a period of normal irradiation. The accident condi¬tion entails diffusion of fission products through the particle coating layers and through the fuel matrix to the coolant boundary. This document represents the initial version of the PARFUME Theory and Model Basis Report. More detailed descriptions will be provided in future revisions.

  16. Safety Basis Information System | Department of Energy

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

    Request Click on the above link to access the form to request access to the Safety Basis web interface. If you need assistance logging in, please AU UserSupport. Contact Nimi Rao...

  17. Basis for UCNI | Department of Energy

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

    UCNI Basis for UCNI What documents contain the legal and policy foundations for the UCNI program? Section 148 of the Atomic Energy Act of 1954, as amended (42 U.S.C. 2011 et seq.), is the statutory basis for the UCNI program. 10 CFR Part 1017, Identification and Protection of Unclassified Controlled Nuclear Information specifies many detailed policies and requirements concerning the UCNI program. DOE O 471.1B, Identification and Protection of Unclassified Controlled Nuclear Information,

  18. Nanoplasmonics simulations at the basis set limit through completeness-optimized, local numerical basis sets

    SciTech Connect (OSTI)

    Rossi, Tuomas P. Sakko, Arto; Puska, Martti J.; Lehtola, Susi; Nieminen, Risto M.

    2015-03-07

    We present an approach for generating local numerical basis sets of improving accuracy for first-principles nanoplasmonics simulations within time-dependent density functional theory. The method is demonstrated for copper, silver, and gold nanoparticles that are of experimental interest but computationally demanding due to the semi-core d-electrons that affect their plasmonic response. The basis sets are constructed by augmenting numerical atomic orbital basis sets by truncated Gaussian-type orbitals generated by the completeness-optimization scheme, which is applied to the photoabsorption spectra of homoatomic metal atom dimers. We obtain basis sets of improving accuracy up to the complete basis set limit and demonstrate that the performance of the basis sets transfers to simulations of larger nanoparticles and nanoalloys as well as to calculations with various exchange-correlation functionals. This work promotes the use of the local basis set approach of controllable accuracy in first-principles nanoplasmonics simulations and beyond.

  19. Solar Power Tower Design Basis Document, Revision 0

    SciTech Connect (OSTI)

    ZAVOICO,ALEXIS B.

    2001-07-01

    This report contains the design basis for a generic molten-salt solar power tower. A solar power tower uses a field of tracking mirrors (heliostats) that redirect sunlight on to a centrally located receiver mounted on top a tower, which absorbs the concentrated sunlight. Molten nitrate salt, pumped from a tank at ground level, absorbs the sunlight, heating it up to 565 C. The heated salt flows back to ground level into another tank where it is stored, then pumped through a steam generator to produce steam and make electricity. This report establishes a set of criteria upon which the next generation of solar power towers will be designed. The report contains detailed criteria for each of the major systems: Collector System, Receiver System, Thermal Storage System, Steam Generator System, Master Control System, and Electric Heat Tracing System. The Electric Power Generation System and Balance of Plant discussions are limited to interface requirements. This design basis builds on the extensive experience gained from the Solar Two project and includes potential design innovations that will improve reliability and lower technical risk. This design basis document is a living document and contains several areas that require trade-studies and design analysis to fully complete the design basis. Project- and site-specific conditions and requirements will also resolve open To Be Determined issues.

  20. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Structural Basis for Activation of Cholera Toxin Print Wednesday, 30 November 2005 00:00 Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit

  1. TWRS authorization basis configuration control summary

    SciTech Connect (OSTI)

    Mendoza, D.P.

    1997-12-26

    This document was developed to define the Authorization Basis management functional requirements for configuration control, to evaluate the management control systems currently in place, and identify any additional controls that may be required until the TWRS [Tank Waste Remediation System] Configuration Management system is fully in place.

  2. 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.

  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. Cold Vacuum Drying facility design basis accident analysis documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  5. Radioactive Waste Management BasisApril 2006

    SciTech Connect (OSTI)

    Perkins, B K

    2011-08-31

    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  6. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  7. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  8. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  9. Design Basis Threat | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Design Basis Threat NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM) and nuclear weapons in its custody. NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special nuclear material, or SNM) and nuclear weapons in its custody. NNSA has taken aggressive action to improve the security of its nuclear weapons material (often referred to as special

  10. Structural Basis for Activation of Cholera Toxin

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

    Structural Basis for Activation of Cholera Toxin Print Cholera is a serious disease that claims thousands of victims each year in third-world, war-torn, and disaster-stricken nations. The culprit is the bacterium Vibrio cholerae, which can be ingested through contaminated food or water and colonizes the mucous membrane of the human small intestine. There, it secretes cholera toxin (CT), a protein whose A1 subunit (CTA1) triggers a series of events culminating in the massive efflux of

  11. Review and Approval of Nuclear Facility Safety Basis and Safety...

    Office of Environmental Management (EM)

    DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS ... Neither a reviewer nor the preparer has veto power over ultimate resolution or ...

  12. ORISE: The Medical Basis for Radiation-Accident Preparedness...

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

    The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident ...

  13. Structural Basis for the Interaction between Pyk2-FAT Domain...

    Office of Scientific and Technical Information (OSTI)

    Structural Basis for the Interaction between Pyk2-FAT Domain and Leupaxin LD Repeats Citation Details In-Document Search Title: Structural Basis for the Interaction between ...

  14. Nuclear Safety Basis Program Review Overview and Management Oversight...

    Office of Environmental Management (EM)

    Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review ...

  15. Structural basis for substrate specificity in the Escherichia...

    Office of Scientific and Technical Information (OSTI)

    Structural basis for substrate specificity in the Escherichia coli maltose transport system Citation Details In-Document Search Title: Structural basis for substrate specificity in ...

  16. Los Alamos National Laboratory fission basis (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Los Alamos National Laboratory fission basis Citation Details In-Document Search Title: Los Alamos National Laboratory fission basis You are accessing a document from the ...

  17. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Polymer ...

  18. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Life Cycle ...

  19. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus ...

  20. Heavy quarkonium in a holographic basis (Journal Article) | DOE...

    Office of Scientific and Technical Information (OSTI)

    Heavy quarkonium in a holographic basis Title: Heavy quarkonium in a holographic basis Authors: Li, Yang Search DOE PAGES for author "Li, Yang" Search DOE PAGES for ORCID ...

  1. A molecular basis for advanced materials in water treatment....

    Office of Scientific and Technical Information (OSTI)

    A molecular basis for advanced materials in water treatment. Citation Details In-Document Search Title: A molecular basis for advanced materials in water treatment. Authors: Rempe, ...

  2. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    SciTech Connect (OSTI)

    KOZLOWSKI, S.D.

    2007-05-30

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

  3. Technical Basis for PNNL Beryllium Inventory

    SciTech Connect (OSTI)

    Johnson, Michelle Lynn

    2014-07-09

    The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.

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

    Energy Savers [EERE]

    SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 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-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD

  5. A radial basis function Galerkin method for inhomogeneous nonlocal diffusion

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

    Lehoucq, Richard B.; Rowe, Stephen T.

    2016-02-01

    We introduce a discretization for a nonlocal diffusion problem using a localized basis of radial basis functions. The stiffness matrix entries are assembled by a special quadrature routine unique to the localized basis. Combining the quadrature method with the localized basis produces a well-conditioned, sparse, symmetric positive definite stiffness matrix. We demonstrate that both the continuum and discrete problems are well-posed and present numerical results for the convergence behavior of the radial basis function method. As a result, we explore approximating the solution to anisotropic differential equations by solving anisotropic nonlocal integral equations using the radial basis function method.

  6. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-03-20

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the U.S. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QA/G4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1A, Vol. IV, Section 4.16 (Banning 1999).

  7. Interim Basis for PCB Sampling and Analyses

    SciTech Connect (OSTI)

    BANNING, D.L.

    2001-01-18

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the US. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QAlG4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842, Rev. 1 A, Vol. IV, Section 4.16 (Banning 1999).

  8. Office of Nuclear Safety Basis and Facility Design

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety Basis & Facility Design establishes safety basis and facility design requirements and expectations related to analysis and design of nuclear facilities to ensure protection of workers and the public from the hazards associated with nuclear operations.

  9. Enterprise Assessments Targeted Review of the Safety Basis at...

    Office of Environmental Management (EM)

    Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 Enterprise Assessments Targeted Review of the Safety Basis at the Savannah River Site F-Area ...

  10. Authorization basis status report (miscellaneous TWRS facilities, tanks and components)

    SciTech Connect (OSTI)

    Stickney, R.G.

    1998-04-29

    This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

  11. Review and Approval of Nuclear Facility Safety Basis and Safety...

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

    104-2014, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents by Website Administrator This Standard describes a framework and the criteria to be...

  12. CRAD, Integrated Safety Basis and Engineering Design Review ...

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

    Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA CRAD 31-4, Rev. 0) CRAD, Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA...

  13. CRAD, Engineering Design and Safety Basis- December 22, 2009

    Broader source: Energy.gov [DOE]

    Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0)

  14. Award Fee Determination Summary

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

    2 CH2M Hill Plateau Remediation Company Contract Number: DE-AC06-08RL14788 Final Fee Determination for Base funded Performance Measures Basis of Evaluation: Completion of Performance Measures contained in Section J, Attachment J.4, Performance Evaluation and Measurement Plan, according to the identified completion criteria. Evaluation Results: FY 2012 Base Period Fee Available Fee allocated to FY 2012* Performance Measures $10,399,033.60 Incremental Fee $4,490,000.00 Provisional Fee

  15. Award Fee Determination Summary

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

    1 CH2M Hill Plateau Remediation Company Contract Number: DE-AC06-08RL14788 Final Fee Determination for Base funded and American Recovery and Reinvestment Act (Recovery) funded Performance Measures Basis of Evaluation: Completion of Performance Measures contained in Section J, AttachmentJ.4, Performance Evaluation and Measurement Plan, according to the identified completion criteria. Evaluation Results: Fiscal Year 2011 (Oct 1, 2010 - Sept 30, 2011) Base Funded Fee Recovery Funded Fee Available

  16. Morphological basis of tolerance to ozone

    SciTech Connect (OSTI)

    Evans, M.J.; Dekker, N.P.; Cabral-Anderson, L.J.; Shami, S.G.

    1985-06-01

    The purpose of this research was to study Type 1 epithelial cells in the ozone (O/sub 3/)-tolerant lung epithelium. Rats were made tolerant by exposure to 0.5 ppm O/sub 3/ for 2 days and allowed to recover in air. Reexposure to a lethal concentration of O/sub 3/ (6 ppm) at 3, 7, and 15 days of recovery revealed that tolerance was present at 3 days but almost absent at 7 and 15 days of recovery. Using Type 2 cell proliferation as a means of quantitating Type 1 cell injury, it was observed that when the preexposed rats were reexposed to 0.5 ppm at 3, 7, and 15 days, very little Type 1 cell injury occurred at 3 days. However, at 7 and 15 days the amount of Type 1 cell injury was the same as that associated with the original exposure. To determine whether there was any change in the alveolar epithelial cell populations between the periods of tolerance (3 days) and its decline (7 and 15 days), the percentage of tritiated thymidine (( /sup 3/H)TdR-labeled Type 1 and 2 cells at these times were determined. There was a significant decrease in (/sup 3/H)TdR-labeled Type 1 and 2 cells between the third and fifteenth days of recovery as excess cells were sloughed off and the tissue returned to normal. Using electron microscopic morphometry, Type 1 and 2 cells were then studied during the decline of tolerance. No change was found in the morphology of Type 2 cells; however, the morphology of Type 1 cells revealed a 58% decrease in surface area and a 25% increase in the arithmetic mean thickness when tolerance was present at 3 days. As tolerance declined (7 and 15 days), Type 1 cell morphology returned to normal. It was concluded that tolerance exists when the surface area of a cell exposed to a particular concentration of ozone is small enough so that the existing antioxidant mechanism contained within that cell volume can protect it from damage.

  17. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz.

  18. Basis for Section 3116 Determination for Closure of F-Tank Farm...

    Office of Environmental Management (EM)

    ......... 2-58 2.3.3 Chemical Cleaning ......Waste Processing Facility ECC Enhanced Chemical Cleaning Eh Measure of reduction (or ...

  19. Draft Basis for Section 3116 Determination for Closure of F-Tank...

    Energy Savers [EERE]

    .........2-58 2.3.3 Chemical Cleaning ......Waste Processing Facility ECC Enhanced Chemical Cleaning E h Measure of reduction (or ...

  20. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

    SciTech Connect (OSTI)

    Not Available

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

  1. Enterprise Assessments Review of the Delegation of Safety Basis Approval

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

    Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 | Department of Energy Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear Facilities - April 2016 April 2016 Enterprise Assessments Review of the Delegation of Safety Basis Approval Authority for Hazard Category 1, 2, and 3 Nuclear

  2. Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting

    Energy Savers [EERE]

    Implementation of Operating Experience Report 2013-01 | Department of Energy Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 April, 2013 Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 To support the

  3. ORISE: The Medical Basis for Radiation-Accident Preparedness: Medical

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

    Management (Published by REAC/TS) The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness and the Biodosimetry Workshop As part of its mission to provide continuing education for personnel responsible for treating radiation injuries, REAC/TS hosted the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness symposium and

  4. Technical Planning Basis - DOE Directives, Delegations, and Requiremen...

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

    2, Technical Planning Basis by David Freshwater Functional areas: Defense Nuclear Facility Safety and Health Requirement, Safety and Security, The Guide assists DOENNSA field...

  5. Protocol for Enhanced Evaluations of Beyond Design Basis Events...

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

    Protocol for Enhanced Evaluations of Beyond Design Basis Events Supporting Implementation of Operating Experience Report 2013-01 Protocol for Enhanced Evaluations of Beyond Design...

  6. CRAD, Review of Safety Basis Development- January 31, 2013

    Broader source: Energy.gov [DOE]

    Review of Safety Basis Development for the Savannah River Site Salt Waste Processing Facility - Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-57, Rev. 0)

  7. Assessing Beyond Design Basis Seismic Events and Implications...

    Office of Environmental Management (EM)

    Defense Nuclear Facilities Safety Board Topics Covered: Department of Energy Approach to Natural Phenomena Hazards Analysis and Design (Seismic) Design Basis and Beyond Design...

  8. Structural and Functional Basis for Broad-spectrum Neutralization...

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

    Structural and Functional Basis for Broad-spectrum Neutralization of Avian and Human ... unsuccessful. figure 2 Fig 2A. Broad spectrum neutralizing antibody F10 in complex ...

  9. FY 14 Award Fee Determination Scorecard

    Office of Environmental Management (EM)

    14 Award Fee Determination Scorecard Contractor: Swift and Staley Inc. (SST) Contract: DE-AC30-10CC40021 Award Period: October 1,2013 - September 30,2014 Basis of Evaluation: FY 14 ...

  10. Structural basis for the antibody neutralization of Herpes simplex virus

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural basis for the antibody neutralization of Herpes simplex virus Citation Details In-Document Search Title: Structural basis for the antibody neutralization of Herpes simplex virus The gD-E317-Fab complex crystal revealed the conformational epitope of human mAb E317 on HSV gD, providing a molecular basis for understanding the viral neutralization mechanism. Glycoprotein D (gD) of Herpes simplex virus (HSV) binds to a host cell surface receptor,

  11. Technical Basis for U. S. Department of Energy Nuclear Safety Policy, DOE Policy 420.1

    Broader source: Energy.gov [DOE]

    This document provides the technical basis for the Department of Energy (DOE) Policy (P) 420.1, Nuclear Safety Policy, dated 2-8-2011. It includes an analysis of the revised Policy to determine whether it provides the necessary and sufficient high-level expectations that will lead DOE to establish and implement appropriate requirements to assure protection of the public, workers, and the environment from the hazards of DOE’s operation of nuclear facilities.

  12. Structural basis for ubiquitin-mediated antiviral signal activation...

    Office of Scientific and Technical Information (OSTI)

    Title: Structural basis for ubiquitin-mediated antiviral signal activation by RIG-I Authors: Peisley, Alys ; Wu, Bin ; Xu, Hui ; Chen, Zhijian J. ; Hur , Sun 1 ; HHMI) 2 ; ...

  13. The Three-Dimensional Structural Basis of Type II Hyperprolinemia...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: The Three-Dimensional Structural Basis of Type II Hyperprolinemia Citation Details In-Document Search ... Here, we report the first structure of human P5CDH (HsP5CDH) ...

  14. CRAD, Review of Safety Basis Development- October 11, 2012

    Broader source: Energy.gov [DOE]

    Review of Safety Basis Development for the Y-12 National Security Complex Uranium Processing Facility Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 45-55, Rev. 0)

  15. Enterprise Assessments Targeted Review of the Safety Basis at...

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

    ... in SAR 3.3.2.3.1 does not address the effect of an earthquake followed by a fire. ... Although the accident analysis is generally sound, the analysis of the design basis ...

  16. Structural basis for the antibody neutralization of Herpes simplex...

    Office of Scientific and Technical Information (OSTI)

    of Herpes simplex virus Citation Details In-Document Search Title: Structural basis for the antibody neutralization of Herpes simplex virus The gD-E317-Fab complex ...

  17. General Engineer/Physical Scientist (Safety Basis Engineer/Scientist)

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as an authority in the safety basis functional area. The incumbent is responsible for managing, coordinating, and authorizing work in the context...

  18. Structural and Functional Basis for Inhibition of Erythrocyte Invasion by

    Office of Scientific and Technical Information (OSTI)

    Antibodies that Target Plasmodium falciparum EBA-175 (Journal Article) | SciTech Connect Journal Article: Structural and Functional Basis for Inhibition of Erythrocyte Invasion by Antibodies that Target Plasmodium falciparum EBA-175 Citation Details In-Document Search Title: Structural and Functional Basis for Inhibition of Erythrocyte Invasion by Antibodies that Target Plasmodium falciparum EBA-175 Authors: Chen, Edwin ; Paing, May M. ; Salinas, Nichole ; Sim, B. Kim Lee ; Tolia, Niraj H.

  19. Structural basis for biomolecular recognition in overlapping binding sites

    Office of Scientific and Technical Information (OSTI)

    in a diiron enzyme system (Journal Article) | SciTech Connect Structural basis for biomolecular recognition in overlapping binding sites in a diiron enzyme system Citation Details In-Document Search Title: Structural basis for biomolecular recognition in overlapping binding sites in a diiron enzyme system Authors: Acheson, Justin F. ; Bailey, Lucas J. ; Elsen, Nathaniel L. ; Fox, Brian G. [1] + Show Author Affiliations UW Publication Date: 2016-01-22 OSTI Identifier: 1229904 Resource Type:

  20. Structural basis of JAZ repression of MYC transcription factors in

    Office of Scientific and Technical Information (OSTI)

    jasmonate signalling (Journal Article) | SciTech Connect Journal Article: Structural basis of JAZ repression of MYC transcription factors in jasmonate signalling Citation Details In-Document Search Title: Structural basis of JAZ repression of MYC transcription factors in jasmonate signalling Authors: Zhang, Feng ; Yao, Jian ; Ke, Jiyuan ; Zhang, Li ; Lam, Vinh Q. ; Xin, Xiu-Fang ; Zhou, X. Edward ; Chen, Jian ; Brunzelle, Joseph ; Griffin, Patrick R. ; Zhou, Mingguo ; Xu, H. Eric ; Melcher,

  1. Structural basis for Tetrahymena telomerase processivity factor Teb1

    Office of Scientific and Technical Information (OSTI)

    binding to single-stranded telomeric-repeat DNA (Journal Article) | SciTech Connect Journal Article: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Citation Details In-Document Search Title: Structural basis for Tetrahymena telomerase processivity factor Teb1 binding to single-stranded telomeric-repeat DNA Authors: Zeng, Zhixiong ; Min, Bosun ; Huang, Jing ; Hong, Kyungah ; Yang, Yuting ; Collins, Kathleen ; Lei, Ming [1]

  2. Structural basis for substrate specificity in the Escherichia coli maltose

    Office of Scientific and Technical Information (OSTI)

    transport system (Journal Article) | SciTech Connect Structural basis for substrate specificity in the Escherichia coli maltose transport system Citation Details In-Document Search Title: Structural basis for substrate specificity in the Escherichia coli maltose transport system Authors: Oldham, Michael L. ; Chen, Shanshuang ; Chen, Jue [1] ; HHMI) [2] + Show Author Affiliations (Purdue) [Purdue ( Publication Date: 2013-11-11 OSTI Identifier: 1105053 Resource Type: Journal Article Resource

  3. Atomic substitution reveals the structural basis for substrate adenine

    Office of Scientific and Technical Information (OSTI)

    recognition and removal by adenine DNA glycosylase (Journal Article) | SciTech Connect Atomic substitution reveals the structural basis for substrate adenine recognition and removal by adenine DNA glycosylase Citation Details In-Document Search Title: Atomic substitution reveals the structural basis for substrate adenine recognition and removal by adenine DNA glycosylase Adenine DNA glycosylase catalyzes the glycolytic removal of adenine from the promutagenic A {center_dot} oxoG base pair in

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

    SciTech Connect (OSTI)

    Beaulieu, R. A.

    2013-10-03

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

  5. A new paradigm for the molecular basis of rubber elasticity

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

    Hanson, David E.; Barber, John L.

    2015-02-19

    The molecular basis for rubber elasticity is arguably the oldest and one of the most important questions in the field of polymer physics. The theoretical investigation of rubber elasticity began in earnest almost a century ago with the development of analytic thermodynamic models, based on simple, highly-symmetric configurations of so-called Gaussian chains, i.e. polymer chains that obey Markov statistics. Numerous theories have been proposed over the past 90 years based on the ansatz that the elastic force for individual network chains arises from the entropy change associated with the distribution of end-to-end distances of a free polymer chain. There aremore » serious philosophical objections to this assumption and others, such as the assumption that all network nodes undergo affine motion and that all of the network chains have the same length. Recently, a new paradigm for elasticity in rubber networks has been proposed that is based on mechanisms that originate at the molecular level. Using conventional statistical mechanics analyses, quantum chemistry, and molecular dynamics simulations, the fundamental entropic and enthalpic chain extension forces for polyisoprene (natural rubber) have been determined, along with estimates for the basic force constants. Concurrently, the complex morphology of natural rubber networks (the joint probability density distributions that relate the chain end-to-end distance to its contour length) has also been captured in a numerical model. When molecular chain forces are merged with the network structure in this model, it is possible to study the mechanical response to tensile and compressive strains of a representative volume element of a polymer network. As strain is imposed on a network, pathways of connected taut chains, that completely span the network along strain axis, emerge. Although these chains represent only a few percent of the total, they account for nearly all of the elastic stress at high strain. Here we provide a brief review of previous elasticity theories and their deficiencies, and present a new paradigm with an emphasis on experimental comparisons.« less

  6. CRAD, Safety Basis- Idaho MF-628 Drum Treatment Facility

    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) used for a May 2007 readiness assessment of the Safety Basis at the Advanced Mixed Waste Treatment Project.

  7. CRAD, Safety Basis- Idaho Accelerated Retrieval Project Phase II

    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) used for a February 2006 Commencement of Operations assessment of the Safety Basis at the Idaho Accelerated Retrieval Project Phase II.

  8. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    PIEPHO, M.G.

    1999-10-20

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  9. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.; PIEPHO, M.G.

    2000-03-23

    This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  10. Canister storage building design basis accident analysis documentation

    SciTech Connect (OSTI)

    KOPELIC, S.D.

    1999-02-25

    This document provides the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  11. Canister Storage Building (CSB) Design Basis Accident Analysis Documentation

    SciTech Connect (OSTI)

    CROWE, R.D.

    1999-09-09

    This document provides the detailed accident analysis to support ''HNF-3553, Spent Nuclear Fuel Project Final Safety, Analysis Report, Annex A,'' ''Canister Storage Building Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

  12. Burbank Water & Power- Green Building Incentive Program

    Broader source: Energy.gov [DOE]

    Incentives are on a first come first serve basis. More information can be found on the web site listed above.

  13. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    SciTech Connect (OSTI)

    Petersen, C.A., Westinghouse Hanford

    1996-07-17

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  14. Technical basis for classification of low-activity waste fraction from Hanford site tanks

    SciTech Connect (OSTI)

    Petersen, C.A.

    1996-09-20

    The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

  15. Safety basis for the 241-AN-107 mixer pump installation and caustic addition

    SciTech Connect (OSTI)

    Van Vleet, R.J.

    1994-10-05

    This safety Basis was prepared to determine whether or not the proposed activities of installing a 76 HP jet mixer pump and the addition of approximately 50,000 gallons of 19 M (50:50 wt %) aqueous caustic are within the safety envelope as described by Tank Farms (chapter six of WHC-SD-WM-ISB-001, Rev. 0). The safety basis covers the components, structures and systems for the caustic addition and mixer pump installation. These include: installation of the mixer pump and monitoring equipment; operation of the mixer pump, process monitoring equipment and caustic addition; the pump stand, caustic addition skid, the electrical skid, the video camera system and the two densitometers. Also covered is the removal and decontamination of the mixer pump and process monitoring system. Authority for this safety basis is WHC-IP-0842 (Waste Tank Administration). Section 15.9, Rev. 2 (Unreviewed Safety Questions) of WHC-IP-0842 requires that an evaluation be performed for all physical modifications.

  16. Basis for NGNP Reactor Design Down-Selection

    SciTech Connect (OSTI)

    L.E. Demick

    2011-11-01

    The purpose of this paper is to identify the extent of technology development, design and licensing maturity anticipated to be required to credibly identify differences that could make a technical choice practical between the prismatic and pebble bed reactor designs. This paper does not address a business decision based on the economics, business model and resulting business case since these will vary based on the reactor application. The selection of the type of reactor, the module ratings, the number of modules, the configuration of the balance of plant and other design selections will be made on the basis of optimizing the Business Case for the application. These are not decisions that can be made on a generic basis.

  17. Resilient Control Systems Practical Metrics Basis for Defining Mission Impact

    SciTech Connect (OSTI)

    Craig G. Rieger

    2014-08-01

    "Resilience” describes how systems operate at an acceptable level of normalcy despite disturbances or threats. In this paper we first consider the cognitive, cyber-physical interdependencies inherent in critical infrastructure systems and how resilience differs from reliability to mitigate these risks. Terminology and metrics basis are provided to integrate the cognitive, cyber-physical aspects that should be considered when defining solutions for resilience. A practical approach is taken to roll this metrics basis up to system integrity and business case metrics that establish “proper operation” and “impact.” A notional chemical processing plant is the use case for demonstrating how the system integrity metrics can be applied to establish performance, and

  18. Design-Load Basis for LANL Structures, Systems, and Components

    SciTech Connect (OSTI)

    I. Cuesta

    2004-09-01

    This document supports the recommendations in the Los Alamos National Laboratory (LANL) Engineering Standard Manual (ESM), Chapter 5--Structural providing the basis for the loads, analysis procedures, and codes to be used in the ESM. It also provides the justification for eliminating the loads to be considered in design, and evidence that the design basis loads are appropriate and consistent with the graded approach required by the Department of Energy (DOE) Code of Federal Regulation Nuclear Safety Management, 10, Part 830. This document focuses on (1) the primary and secondary natural phenomena hazards listed in DOE-G-420.1-2, Appendix C, (2) additional loads not related to natural phenomena hazards, and (3) the design loads on structures during construction.

  19. Basis functions for electronic structure calculations on spheres

    SciTech Connect (OSTI)

    Gill, Peter M. W. Loos, Pierre-François Agboola, Davids

    2014-12-28

    We introduce a new basis function (the spherical Gaussian) for electronic structure calculations on spheres of any dimension D. We find general expressions for the one- and two-electron integrals and propose an efficient computational algorithm incorporating the Cauchy-Schwarz bound. Using numerical calculations for the D = 2 case, we show that spherical Gaussians are more efficient than spherical harmonics when the electrons are strongly localized.

  20. Online Monitoring Technical Basis and Analysis Framework for Emergency

    Energy Savers [EERE]

    Diesel Generators-Interim Report for FY 2013 | Department of Energy for Emergency Diesel Generators-Interim Report for FY 2013 Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators-Interim Report for FY 2013 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's

  1. Online Monitoring Technical Basis and Analysis Framework for Large Power

    Energy Savers [EERE]

    Transformers; Interim Report for FY 2012 | Department of Energy for Large Power Transformers; Interim Report for FY 2012 Online Monitoring Technical Basis and Analysis Framework for Large Power Transformers; Interim Report for FY 2012 The Light Water Reactor Sustainability Program is a research, development, and deployment program sponsored by the U.S. Department of Energy Office of Nuclear Energy. The program is operated in collaboration with the Electric Power Research Institute's (EPRI's)

  2. Interim Safety Basis for Fuel Supply Shutdown Facility

    SciTech Connect (OSTI)

    BENECKE, M.W.

    2000-09-07

    This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

  3. SRS FTF Section 3116 Determination signed by Secretary Chu | Department of

    Office of Environmental Management (EM)

    Basis for Determination SRS FTF Section 3116 Basis for Determination Basis for Section 3116 Determination for Closure of F-Tank Farm at the Savannah River Site. In accordance with NDAA Section 3116, certain waste from reprocessing of spent nuclear fuel is not high-level waste if the Secretary of Energy, in consultation with the NRC, determines that the criteria in NDAA Section 3116(a) are met. This FTF 3116 Basis Document shows that those criteria are satisfied, to support a determination that

  4. Waste Determination Equivalency - 12172

    SciTech Connect (OSTI)

    Freeman, Rebecca D.

    2012-07-01

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility encompassing approximately 800 square kilometers near Aiken, South Carolina which began operations in the 1950's with the mission to produce nuclear materials. The SRS contains fifty-one tanks (2 stabilized, 49 yet to be closed) distributed between two liquid radioactive waste storage facilities at SRS containing carbon steel underground tanks with storage capacities ranging from 2,800,000 to 4,900,000 liters. Treatment of the liquid waste from these tanks is essential both to closing older tanks and to maintaining space needed to treat the waste that is eventually vitrified or disposed of onsite. Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005 (NDAA) provides the Secretary of Energy, in consultation with the Nuclear Regulatory Commission (NRC), a methodology to determine that certain waste resulting from prior reprocessing of spent nuclear fuel are not high-level radioactive waste if it can be demonstrated that the waste meets the criteria set forth in Section 3116(a) of the NDAA. The Secretary of Energy, in consultation with the NRC, signed a determination in January 2006, pursuant to Section 3116(a) of the NDAA, for salt waste disposal at the SRS Saltstone Disposal Facility. This determination is based, in part, on the Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site and supporting references, a document that describes the planned methods of liquid waste treatment and the resulting waste streams. The document provides descriptions of the proposed methods for processing salt waste, dividing them into 'Interim Salt Processing' and later processing through the Salt Waste Processing Facility (SWPF). Interim Salt Processing is separated into Deliquification, Dissolution, and Adjustment (DDA) and Actinide Removal Process/Caustic Side Solvent Extraction Unit (ARP/MCU). The Waste Determination was signed by the Secretary of Energy in January of 2006 based on proposed processing techniques with the expectation that it could be revised as new processing capabilities became viable. Once signed, however, it became evident that any changes would require lengthy review and another determination signed by the Secretary of Energy. With the maturation of additional salt removal technologies and the extension of the SWPF start-up date, it becomes necessary to define 'equivalency' to the processes laid out in the original determination. For the purposes of SRS, any waste not processed through Interim Salt Processing must be processed through SWPF or an equivalent process, and therefore a clear statement of the requirements for a process to be equivalent to SWPF becomes necessary. (authors)

  5. 5th International REAC/TS Symposium: The Medical Basis for Radiation...

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

    The Medical Basis for Radiation Accident Preparedness Skip site navigation and ... The Medical Basis for Radiation Accident Preparedness Sept. 27-29, 2011 | Miami, ...

  6. CRAD, Safety Basis Upgrade Review (DOE-STD-3009-2014) - May 15...

    Office of Environmental Management (EM)

    1) provides objectives, criteria, and approaches for establishing and maintaining the safety basis at nuclear facilities. CRAD, Safety Basis Upgrade Review (DOE-STD-3009-2014)...

  7. Guidance For Preparatioon of Basis For Interim Operation (BIO) Documents

    Energy Savers [EERE]

    3011-2002 December 2002 Superceding DOE-STD-3011-94 November 1994 DOE STANDARD GUIDANCE FOR PREPARATION OF BASIS FOR INTERIM OPERATION (BIO) DOCUMENTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-3011-2002 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S.

  8. The Bender-Dunne basis operators as Hilbert space operators

    SciTech Connect (OSTI)

    Bunao, Joseph; Galapon, Eric A. E-mail: eric.galapon@upd.edu.ph

    2014-02-15

    The Bender-Dunne basis operators, T{sub ?m,n}=2{sup ?n}?{sub k=0}{sup n}(n/k )q{sup k}p{sup ?m}q{sup n?k} where q and p are the position and momentum operators, respectively, are formal integral operators in position representation in the entire real line R for positive integers n and m. We show, by explicit construction of a dense domain, that the operators T{sub ?m,n}'s are densely defined operators in the Hilbert space L{sup 2}(R)

  9. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2005-02-25

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.

  10. Electronic structure basis for the extraordinary magnetoresistance in WTe2

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

    Pletikosić, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. As a result, a change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior ofmore » the magnetoresistance in WTe₂ was identified.« less

  11. Electronic structure basis for the titanic magnetoresistance in WTe?

    SciTech Connect (OSTI)

    Pletikosic, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. A change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance in WTe? was identified.

  12. Electronic structure basis for the titanic magnetoresistance in WTe?

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

    Pletikosic, I.; Ali, Mazhar N.; Fedorov, A. V.; Cava, R. J.; Valla, T.

    2014-11-19

    The electronic structure basis of the extremely large magnetoresistance in layered non-magnetic tungsten ditelluride has been investigated by angle-resolved photoelectron spectroscopy. Hole and electron pockets of approximately the same size were found at the Fermi level, suggesting that carrier compensation should be considered the primary source of the effect. The material exhibits a highly anisotropic, quasi one-dimensional Fermi surface from which the pronounced anisotropy of the magnetoresistance follows. A change in the Fermi surface with temperature was found and a high-density-of-states band that may take over conduction at higher temperatures and cause the observed turn-on behavior of the magnetoresistance inmoreWTe? was identified.less

  13. Draft Geologic Disposal Requirements Basis for STAD Specification

    SciTech Connect (OSTI)

    Ilgen, Anastasia G.; Bryan, Charles R.; Hardin, Ernest

    2015-03-25

    This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.

  14. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2009-08-28

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

  15. Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site

    SciTech Connect (OSTI)

    Simecka, W.B.; Grant, T.A.; Voegele, M.D.; Cline, K.M.

    1992-12-31

    A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation`s first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities.

  16. Engineering Basis Document Review Supporting the Double Shell Tank (DST) System Specification Development

    SciTech Connect (OSTI)

    LEONARD, M.W.

    2000-03-14

    The Double-Shell Tank (DST) System is required to transition from its current storage mission to a storage and retrieval mission supporting the River Protection Project Phase 1 privatization, defined in HNF-SD-WM-MAR-008, Tank Waste Remediation System Mission Analysis Report. Requirements for the DST subsystems are being developed using the top-down systems engineering process outlined in HNF-SD-WM-SEMP-002, Tank Waste Remediation System Systems Engineering Management Plan. This top-down process considers existing designs to the extent that these designs impose unavoidable constraints on the Phase 1 mission. Existing engineering-basis documents were screened, and the unavoidable constraints were identified. The constraints identified herein will be added to the DST System specification (HNF-SD-WM-TRD-007, System Specification for the Double-Shell Tank System). While the letter revisions of the DST System specification were constructed with a less rigorous review of the existing engineering-basis documents, the Revision 0 release of the specification must incorporate the results of the review documented herein. The purpose of this document is to describe the screening process and criteria used to determine which constraints are unavoidable and to document the screening results.

  17. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 2, Technical basis

    SciTech Connect (OSTI)

    Not Available

    1992-12-01

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume, Volume 2, contains the technical basis for the 1992 PA. Specifically, it describes the conceptual basis for consequence modeling and the PA methodology, including the selection of scenarios for analysis, the determination of scenario probabilities, and the estimation of scenario consequences using a Monte Carlo technique and a linked system of computational models. Additional information about the 1992 PA is provided in other volumes. Volume I contains an overview of WIPP PA and results of a preliminary comparison with the long-term requirements of the EPA`s Environmental Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses related to the preliminary comparison with 40 CFR 191B. Volume 5 contains uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance. Finally, guidance derived from the entire 1992 PA is presented in Volume 6.

  18. Micrometer-scale fabrication of complex three dimensional lattice + basis structures in silicon

    SciTech Connect (OSTI)

    Burckel, D. Bruce; Resnick, Paul J.; Finnegan, Patrick S.; Sinclair, Michael B.; Davids, Paul S.

    2015-01-01

    A complementary metal oxide semiconductor (CMOS) compatible version of membrane projection lithography (MPL) for fabrication of micrometer-scale three-dimensional structures is presented. The approach uses all inorganic materials and standard CMOS processing equipment. In a single layer, MPL is capable of creating all 5 2D-Bravais lattices. Furthermore, standard semiconductor processing steps can be used in a layer-by-layer approach to create fully three dimensional structures with any of the 14 3D-Bravais lattices. The unit cell basis is determined by the projection of the membrane pattern, with many degrees of freedom for defining functional inclusions. Here we demonstrate several unique structural motifs, and characterize 2D arrays of unit cells with split ring resonators in a silicon matrix. The structures exhibit strong polarization dependent resonances and, for properly oriented split ring resonators (SRRs), coupling to the magnetic field of a normally incident transverse electromagnetic wave, a response unique to 3D inclusions.

  19. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2011-04-04

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

  20. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2007-03-12

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor revision. Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, 9.2.

  1. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2010-04-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2.

  2. Development of engineering technology basis for industrialization of pyrometallurgical reprocessing

    SciTech Connect (OSTI)

    Koyama, Tadafumi; Hijikata, Takatoshi; Yokoo, Takeshi; Inoue, Tadashi

    2007-07-01

    Development of the engineering technology basis of pyrometallurgical reprocessing is a key issue for industrialization. For development of the transport technologies of molten salt and liquid cadmium at around 500 deg. C, a salt transport test rig and a metal transport test rig were installed in Ar glove box. Function of centrifugal pump and 1/2' declined tubing were confirmed with LiCl- KCl molten salt. The transport behavior of molten salt was found to follow that of water. Function of centrifugal pump, vacuum sucking and 1/2' declined tubing were confirmed with liquid Cd. With employing the transport technologies, industrialization applicable electro-refiner was newly designed and engineering-scale model was fabricated in Ar glove box. The electro-refiner has semi-continuous liquid Cd cathode instead of conventional one used in small-scale tests. With using actinide-simulating elements, demonstration of industrial-scale throughput will be carried out in this electro-refiner for more precise evaluation of industrialization potential of pyrometallurgical reprocessing. (authors)

  3. Hanford Technical Basis for Multiple Dosimetry Effective Dose Methodology

    SciTech Connect (OSTI)

    Hill, Robin L.; Rathbone, Bruce A.

    2010-08-01

    The current method at Hanford for dealing with the results from multiple dosimeters worn during non-uniform irradiation is to use a compartmentalization method to calculate the effective dose (E). The method, as documented in the current version of Section 6.9.3 in the 'Hanford External Dosimetry Technical Basis Manual, PNL-MA-842,' is based on the compartmentalization method presented in the 1997 ANSI/HPS N13.41 standard, 'Criteria for Performing Multiple Dosimetry.' With the adoption of the ICRP 60 methodology in the 2007 revision to 10 CFR 835 came changes that have a direct affect on the compartmentalization method described in the 1997 ANSI/HPS N13.41 standard, and, thus, to the method used at Hanford. The ANSI/HPS N13.41 standard committee is in the process of updating the standard, but the changes to the standard have not yet been approved. And, the drafts of the revision of the standard tend to align more with ICRP 60 than with the changes specified in the 2007 revision to 10 CFR 835. Therefore, a revised method for calculating effective dose from non-uniform external irradiation using a compartmental method was developed using the tissue weighting factors and remainder organs specified in 10 CFR 835 (2007).

  4. Climate Change: The Physical Basis and Latest Results

    ScienceCinema (OSTI)

    None

    2011-10-06

    The 2007 Assessment Report of the Intergovernmental Panel on Climate Change (IPCC) concludes: "Warming in the climate system is unequivocal." Without the contribution of Physics to climate science over many decades, such a statement would not have been possible. Experimental physics enables us to read climate archives such as polar ice cores and so provides the context for the current changes. For example, today the concentration of CO2 in the atmosphere, the second most important greenhouse gas, is 28% higher than any time during the last 800,000 years. Classical fluid mechanics and numerical mathematics are the basis of climate models from which estimates of future climate change are obtained. But major instabilities and surprises in the Earth System are still unknown. These are also to be considered when the climatic consequences of proposals for geo-engineering are estimated. Only Physics will permit us to further improve our understanding in order to provide the foundation for policy decisions facing the global climate change challenge.

  5. Hanford External Dosimetry Technical Basis Manual PNL-MA-842

    SciTech Connect (OSTI)

    Rathbone, Bruce A.

    2010-01-01

    The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the manual by PNNL was discontinued beginning with Revision 0.2. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Updated Chapters 5, 6 and 9 to reflect change in default ring calibration factor used in HEDP dose calculation software. Factor changed from 1.5 to 2.0 beginning January 1, 2007. Pages on which changes were made are as follows: 5.23, 5.69, 5.78, 5.80, 5.82, 6.3, 6.5, 6.29, and 9.2. Rev 0.2 (8/28/2009) Updated Chapters 3, 5, 6, 8 and 9. Chapters 6 and 8 were significantly expanded. References in the Preface and Chapters 1, 2, 4, and 7 were updated to reflect updates to DOE documents. Approved by HPDAC on 6/2/2009. Rev 1.0 (1/1/2010) Major revision. Updated all chapters to reflect the Hanford site wide implementation on January 1, 2010 of new DOE requirements for occupational radiation protection. The new requirements are given in the June 8, 2007 amendment to 10 CFR 835 Occupational Radiation Protection (Federal Register, June 8, 2007. Title 10 Part 835. U.S., Code of Federal Regulations, Vol. 72, No. 110, 31904-31941). Revision 1.0 to the manual replaces ICRP 26 dosimetry concepts and terminology with ICRP 60 dosimetry concepts and terminology and replaces external dose conversion factors from ICRP 51 with those from ICRP 74 for use in measurement of operational quantities with dosimeters. Descriptions of dose algorithms and dosimeter response characteristics, and field performance were updated to reflect changes in the neutron quality factors used in the measurement of operational quantities.

  6. The Structural Basis for Tight Control of PP2A Methylation and...

    Office of Scientific and Technical Information (OSTI)

    The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Citation Details In-Document Search Title: The Structural Basis for Tight Control of PP2A ...

  7. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

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

  8. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    SciTech Connect (OSTI)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  9. Establishing the Technical Basis for Disposal of Heat-generating Waste in

    Energy Savers [EERE]

    Salt | Department of Energy Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis. Though the basis for a salt

  10. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21

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

  11. Enterprise Assessments Targeted Review of the Safety Basis at the Savannah

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

    River Site F-Area Central Laboratory Facility - January 2016 | Department of Energy Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 Enterprise Assessments Targeted Review of the Safety Basis at the Savannah River Site F-Area Central Laboratory Facility - January 2016 January 2016 Review of the Safety Basis F-Area Central Laboratory Facility at the Savannah River Site The Office of Nuclear Safety and Environmental Assessments, within the U.S. Department of

  12. Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan

    Broader source: Energy.gov [DOE]

    This SRP, Nuclear Safety Basis Program Review, consists of five volumes. It provides information to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. It provides a primer on the safety basis development and documentation process used by the DOE. It also provides a set of LOIs for the review of safety basis programs and documents of nuclear facilities at various stages of the facility life cycle.

  13. Report to the Secretary of Energy on Beyond Design Basis Event...

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

    BDBEReportfinal.pdf More Documents & Publications Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements...

  14. Technical Basis and Considerations for DOE M 435.1-1 (Appendix A)

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

    1999-07-09

    This appendix establishes the technical basis of the order revision process and of each of the requirements included in the revised radioactive waste management order.

  15. Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events

    Broader source: Energy.gov [DOE]

    This is a level 1 operating experience document providing direction for Improving Department of Energy Capabilities for Mitigating Beyond Design Basis Events. [OE-1: 2013-01

  16. Structural basis for the prion-like MAVS filaments in antiviral...

    Office of Scientific and Technical Information (OSTI)

    in antiviral innate immunity Citation Details In-Document Search Title: Structural basis for the prion-like MAVS filaments in antiviral innate immunity Authors: Xu, Hui ; He, ...

  17. 2010 DOE National Science Bowl® Photos - Basis Charter School...

    Office of Science (SC) Website

    Basis Charter School National Science Bowl (NSB) NSB Home About National Science Bowl Contacts Regional Science Bowl Coordinators National Science Bowl FAQ's Alumni Past National ...

  18. CRAD, Review of Safety Basis Development - May 6, 2013 | Department of

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

    Energy Review of Safety Basis Development - May 6, 2013 CRAD, Review of Safety Basis Development - May 6, 2013 May 6, 2013 Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0) The review will consider selected aspects of the development of safety basis for the Transuranic Waste Facility (TWF) to assess the extent to which safety is integrated into the design of the TWF in accordance with DOE directives; in particular,

  19. Natural micropolymorphism in human leukocyte antigens provides a basis for genetic control of antigen recognition

    SciTech Connect (OSTI)

    Archbold, Julia K.; Macdonald, Whitney A.; Gras, Stephanie; Ely, Lauren K.; Miles, John J.; Bell, Melissa J.; Brennan, Rebekah M.; Beddoe, Travis; Wilce, Matthew C.J.; Clements, Craig S.; Purcell, Anthony W.; McCluskey, James; Burrows, Scott R.; Rossjohn, Jamie

    2009-07-10

    Human leukocyte antigen (HLA) gene polymorphism plays a critical role in protective immunity, disease susceptibility, autoimmunity, and drug hypersensitivity, yet the basis of how HLA polymorphism influences T cell receptor (TCR) recognition is unclear. We examined how a natural micropolymorphism in HLA-B44, an important and large HLA allelic family, affected antigen recognition. T cell-mediated immunity to an Epstein-Barr virus determinant (EENLLDFVRF) is enhanced when HLA-B*4405 was the presenting allotype compared with HLA-B*4402 or HLA-B*4403, each of which differ by just one amino acid. The micropolymorphism in these HLA-B44 allotypes altered the mode of binding and dynamics of the bound viral epitope. The structure of the TCR-HLA-B*4405EENLLDFVRF complex revealed that peptide flexibility was a critical parameter in enabling preferential engagement with HLA-B*4405 in comparison to HLA-B*4402/03. Accordingly, major histocompatibility complex (MHC) polymorphism can alter the dynamics of the peptide-MHC landscape, resulting in fine-tuning of T cell responses between closely related allotypes.

  20. Micrometer-scale fabrication of complex three dimensional lattice + basis structures in silicon

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

    Burckel, D. Bruce; Resnick, Paul J.; Finnegan, Patrick S.; Sinclair, Michael B.; Davids, Paul S.

    2015-01-01

    A complementary metal oxide semiconductor (CMOS) compatible version of membrane projection lithography (MPL) for fabrication of micrometer-scale three-dimensional structures is presented. The approach uses all inorganic materials and standard CMOS processing equipment. In a single layer, MPL is capable of creating all 5 2D-Bravais lattices. Furthermore, standard semiconductor processing steps can be used in a layer-by-layer approach to create fully three dimensional structures with any of the 14 3D-Bravais lattices. The unit cell basis is determined by the projection of the membrane pattern, with many degrees of freedom for defining functional inclusions. Here we demonstrate several unique structural motifs, andmorecharacterize 2D arrays of unit cells with split ring resonators in a silicon matrix. The structures exhibit strong polarization dependent resonances and, for properly oriented split ring resonators (SRRs), coupling to the magnetic field of a normally incident transverse electromagnetic wave, a response unique to 3D inclusions.less

  1. Human System Simulation in Support of Human Performance Technical Basis at NPPs

    SciTech Connect (OSTI)

    David Gertman; Katya Le Blanc; alan mecham; william phoenix; Magdy Tawfik; Jeffrey Joe

    2010-06-01

    This paper focuses on strategies and progress toward establishing the Idaho National Laboratorys (INLs) Human Systems Simulator Laboratory at the Center for Advanced Energy Studies (CAES), a consortium of Idaho State Universities. The INL is one of the National Laboratories of the US Department of Energy. One of the first planned applications for the Human Systems Simulator Laboratory is implementation of a dynamic nuclear power plant simulation (NPP) where studies of operator workload, situation awareness, performance and preference will be carried out in simulated control rooms including nuclear power plant control rooms. Simulation offers a means by which to review operational concepts, improve design practices and provide a technical basis for licensing decisions. In preparation for the next generation power plant and current government and industry efforts in support of light water reactor sustainability, human operators will be attached to a suite of physiological measurement instruments and, in combination with traditional Human Factors Measurement techniques, carry out control room tasks in simulated advanced digital and hybrid analog/digital control rooms. The current focus of the Human Systems Simulator Laboratory is building core competence in quantitative and qualitative measurements of situation awareness and workload. Of particular interest is whether introduction of digital systems including automated procedures has the potential to reduce workload and enhance safety while improving situation awareness or whether workload is merely shifted and situation awareness is modified in yet to be determined ways. Data analysis is carried out by engineers and scientists and includes measures of the physical and neurological correlates of human performance. The current approach supports a user-centered design philosophy (see ISO 13407 Human Centered Design Process for Interactive Systems, 1999) wherein the context for task performance along with the requirements of the end-user are taken into account during the design process and the validity of design is determined through testing of real end users

  2. Criteria Document for B-plant Surveillance and Maintenance Phase Safety Basis Document

    SciTech Connect (OSTI)

    SCHWEHR, B.A.

    1999-08-31

    This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S&M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S&M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S&M Phase safety basis document.

  3. Safety basis academy summary of project implementation from 2007-2009

    SciTech Connect (OSTI)

    Johnston, Julie A

    2009-01-01

    During fiscal years 2007 through 2009, in accordance with Performance Based Incentives with DOE/NNSA Los Alamos Site Office, Los Alamos National Security (LANS) implemented and operated a Safety Basis Academy (SBA) to facilitate uniformity in technical qualifications of safety basis professionals across the nuclear weapons complex. The implementation phase of the Safety Basis Academy required development, delivery, and finalizing a set of 23 courses. The courses developed are capable of supporting qualification efforts for both federal and contractor personnel throughout the DOE/NNSA Complex. The LANS Associate Director for Nuclear and High Hazard Operations (AD-NHHO) delegated project responsibillity to the Safety Basis Division. The project was assigned to the Safety Basis Technical Services (SB-TS) Group at Los Alamos National Laboratory (LANL). The main tasks were project needs analysis, design, development, implementation of instructional delivery, and evaluation of SBA courses. DOE/NNSA responsibility for oversight of the SBA project was assigned to the Chief of Defense for Nuclear Safety, and delegated to the Authorization Basis Senior Advisor, Continuous Learning Chair (CDNS-ABSA/CLC). NNSA developed a memorandum of agreement with LANS AD-NHHO. Through a memorandum of agreement initiated by NNSA, the DOE National Training Center (NTC) will maintain the set of Safety Basis Academy courses and is able to facilitate course delivery throughout the DOE Complex.

  4. Structural basis for Notch1 engagement of Delta-like 4 (Journal...

    Office of Scientific and Technical Information (OSTI)

    Title: Structural basis for Notch1 engagement of Delta-like 4 Authors: Luca, Vincent C. ; Jude, Kevin M. ; Pierce, Nathan W. ; Nachury, Maxence V. ; Fischer, Suzanne ; Garcia, K. ...

  5. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2...

    Office of Scientific and Technical Information (OSTI)

    Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) ...

  6. Structure of P-Glycoprotein Reveals a Molecular Basis for Poly...

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

    Structure of P-Glycoprotein Reveals a Molecular Basis for Poly-Specific Drug Binding figure 1 Figure 1. Structure of P-gp. Many forms of cancer fail to respond to chemotherapy by ...

  7. Reducing Uncertainty in the Seismic Design Basis for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Reidel, Steve; Gardner, Martin G.

    2007-02-27

    The seismic design basis for the Waste Treatment Plant (WTP) at the Department of Energys (DOE) Hanford Site near Richland was re-evaluated in 2005, resulting in an increase by up to 40% in the seismic design basis. The original seismic design basis for the WTP was established in 1999 based on a probabilistic seismic hazard analysis completed in 1996. The 2005 analysis was performed to address questions raised by the Defense Nuclear Facilities Safety Board (DNFSB) about the assumptions used in developing the original seismic criteria and adequacy of the site geotechnical surveys. The updated seismic response analysis used existing and newly acquired seismic velocity data, statistical analysis, expert elicitation, and ground motion simulation to develop interim design ground motion response spectra which enveloped the remaining uncertainties. The uncertainties in these response spectra were enveloped at approximately the 84th percentile to produce conservative design spectra, which contributed significantly to the increase in the seismic design basis.

  8. NSS 18.3 Verification of Authorization Basis Documentation 12/8/03

    Broader source: Energy.gov [DOE]

    The objective of this surveillance is for the Facility Representative to verify that the facility's configuration and operations remain consistent with the authorization basis.  As defined in DOE...

  9. Determination of Dusty Particle Charge Taking into Account Ion Drag

    SciTech Connect (OSTI)

    Ramazanov, T. S.; Dosbolayev, M. K.; Jumabekov, A. N.; Amangaliyeva, R. Zh.; Orazbayev, S. A.; Petrov, O. F.; Antipov, S. N.

    2008-09-07

    This work is devoted to the experimental estimation of charge of dust particle that levitates in the stratum of dc glow discharge. Particle charge is determined on the basis of the balance between ion drag force, gravitational and electric forces. Electric force is obtained from the axial distribution of the light intensity of strata.

  10. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) light-induced pyrimidine photodimers are repaired by the nucleotide excision repair pathway. Photolesions have biophysical parameters closely resembling undamaged DNA, impeding discovery through damage surveillance proteins. The DDB1DDB2 complex serves in

  11. Los Alamos National Laboratory fission basis (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    National Laboratory fission basis Citation Details In-Document Search Title: Los Alamos National Laboratory fission basis Authors: Keksis, August L [1] ; Chadwick, Mark B [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2011-05-06 OSTI Identifier: 1063939 Report Number(s): LA-UR-11-02744; LA-UR-11-2744 DOE Contract Number: AC52-06NA25396 Resource Type: Conference Resource Relation: Conference: 14th International Symposium on Reactor Dosimetry ; May 22, 2011 ;

  12. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    KURTZ, J.E.

    2000-05-10

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, and radiation surveys of the Cold Vacuum Drying Facility (CVD) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  13. Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | DOE PAGES Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Title: Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Authors: Zeng, Zhixiong ; Wang, Wei ; Yang, Yuting ; Chen, Yong ; Yang, Xiaomei ; Diehl, J. Alan ; Liu, Xuedong ; Lei, Ming Publication Date: 2010-02-01 OSTI Identifier: 1198117 Grant/Contract Number: AC02-06CH11357 Type: Published Article Journal Name: Developmental Cell Additional Journal Information: Journal Volume: 18; Journal Issue:

  14. Structural basis for the prion-like MAVS filaments in antiviral innate

    Office of Scientific and Technical Information (OSTI)

    immunity (Journal Article) | SciTech Connect Structural basis for the prion-like MAVS filaments in antiviral innate immunity Citation Details In-Document Search Title: Structural basis for the prion-like MAVS filaments in antiviral innate immunity Authors: Xu, Hui ; He, Xiaojing ; Zheng, Hui ; Huang, Lily J ; Hou, Fajian ; Yu, Zhiheng ; de la Cruz, Michael Jason ; Borkowski, Brian ; Zhang, Xuewu ; Chen, Zhijian J ; Jiang, Qiu-Xing [1] ; HHMI) [2] + Show Author Affiliations (UTSMC) (

  15. Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA

    Office of Scientific and Technical Information (OSTI)

    Ligase (Journal Article) | SciTech Connect Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA Ligase Citation Details In-Document Search Title: Structural Basis for Specificity and Flexibility in a Plant 4-Coumarate:CoA Ligase Authors: Li, Zhi ; Nair, Satish K. [1] + Show Author Affiliations UIUC Publication Date: 2015-12-04 OSTI Identifier: 1227510 Resource Type: Journal Article Resource Relation: Journal Name: Structure; Journal Volume: 23; Journal Issue: (11) ;

  16. Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Citation Details In-Document Search Title: Structural Basis of Selective Ubiquitination of TRF1 by SCFFbx4 Authors: Zeng, Zhixiong ; Wang, Wei ; Yang, Yuting ; Chen, Yong ; Yang, Xiaomei ; Diehl, J. Alan ; Liu, Xuedong ; Lei, Ming Publication Date: 2010-02-01 OSTI Identifier: 1198117 Grant/Contract Number: AC02-06CH11357 Type: Published Article Journal Name: Developmental Cell Additional Journal

  17. Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Citation Details In-Document Search Title: Structural Basis of UV DNA-Damage Recognition by the DDB1-DDB2 Complex Ultraviolet (UV) light-induced pyrimidine photodimers are repaired by the nucleotide excision repair pathway. Photolesions have biophysical parameters closely resembling undamaged DNA, impeding discovery through damage surveillance proteins. The DDB1DDB2 complex serves in

  18. Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the

    Office of Scientific and Technical Information (OSTI)

    Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics (Journal Article) | SciTech Connect Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics Citation Details In-Document Search Title: Crystal Structures of mPGES-1 Inhibitor Complexes Form a Basis for the Rational Design of Potent Analgesic and Anti-Inflammatory Therapeutics Authors: Luz, John Gately ; Antonysamy, Stephen ; Kuklish,

  19. Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for

    Office of Scientific and Technical Information (OSTI)

    allosteric regulation (Journal Article) | SciTech Connect Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for allosteric regulation Citation Details In-Document Search Title: Crystal structure of a ;#8203;BRAF kinase domain monomer explains basis for allosteric regulation Authors: Thevakumaran, Neroshan ; Lavoie, Hugo ; Critton, David A. ; Tebben, Andrew ; Marinier, Anne ; Sicheri, Frank ; Therrien , Marc [1] ; Montreal) [2] ; BMS) [2] + Show Author Affiliations

  20. The Three-Dimensional Structural Basis of Type II Hyperprolinemia (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | SciTech Connect The Three-Dimensional Structural Basis of Type II Hyperprolinemia Citation Details In-Document Search Title: The Three-Dimensional Structural Basis of Type II Hyperprolinemia Type II hyperprolinemia is an autosomal recessive disorder caused by a deficiency in {Delta}{sup 1}-pyrroline-5-carboxylate dehydrogenase (P5CDH; also known as ALDH4A1), the aldehyde dehydrogenase that catalyzes the oxidation of glutamate semialdehyde to glutamate. Here, we report the first

  1. Non-homogeneous solutions of a Coulomb Schrdinger equation as basis set for scattering problems

    SciTech Connect (OSTI)

    Del Punta, J. A.; Ambrosio, M. J.; Gasaneo, G.; Zaytsev, S. A.; Ancarani, L. U.

    2014-05-15

    We introduce and study two-body Quasi Sturmian functions which are proposed as basis functions for applications in three-body scattering problems. They are solutions of a two-body non-homogeneous Schrdinger equation. We present different analytic expressions, including asymptotic behaviors, for the pure Coulomb potential with a driven term involving either Slater-type or Laguerre-type orbitals. The efficiency of Quasi Sturmian functions as basis set is numerically illustrated through a two-body scattering problem.

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

    SciTech Connect (OSTI)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01

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

  3. TECHNICAL BASIS FOR EVALUATING SURFACE BARRIERS TO PROTECT GROUNDWATER FROM DEEP VADOSE ZONE CONTAMINATION

    SciTech Connect (OSTI)

    FAYER JM; FREEDMAN VL; WARD AL; CHRONISTER GB

    2010-02-24

    The U.S. DOE and its predecessors released nearly 2 trillion liters (450 billion gallons) of contaminated liquid into the vadose zone at the Hanford Site. Some of the contaminants currently reside in the deeper parts of the vadose zone where they are much less accessible to characterization, monitoring, and typical remediation activities. The DOE Richland Operations Office (DOE-RL) prepared a treatability test plan in 2008 to examine remediation options for addressing contaminants in the deep vadose zone; one of the technologies identified was surface barriers (also known as engineered barriers, covers, and caps). In the typical configuration, the contaminants are located relatively close to the surface, generally within 15 m, and thus they are close to the base of the surface barrier. The proximity of the surface barrier under these conditions yielded few concerns about the effectiveness of the barrier at depth, particularly for cases in which the contaminants were in a lined facility. At Hanford, however, some unlined sites have contaminants located well below depths of 15 m. The issue raised about these sites is the degree of effectiveness of a surface barrier in isolating contaminants in the deep vadose zone. Previous studies by Hanford Site and PNNL researchers suggest that surface barriers have the potential to provide a significant degree of isolation of deep vadose zone contaminants. The studies show that the actual degree of isolation is site-specific and depends on many factors, including recharge rates, barrier size, depth of contaminants, geohydrologic properties ofthe sediments, and the geochemical interactions between the contaminants and the sediments. After the DOE-RL treatability test plan was published, Pacific Northwest National Laboratory was contracted to review the information available to support surface barrier evaluation for the deep vadose zone, identify gaps in the information and outcomes necessary to fill the data gaps, and outline tasks to achieve those outcomes. Full understanding of contaminant behavior in the deep vadose zone is constrained by four key data gaps: limited access; limited data; limited time; and the lack of an accepted predictive capability for determining whether surface barriers can effectively isolate deep vadose zone contaminants. Activities designed to fill these data gaps need to have these outcomes: (1) common evaluation methodology that provides a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination; (2) deep vadose zone data that characterize the lithology, the spatial distribution of moisture and contaminants, the physical, chemical, and biological process that affect the mobility of each contaminant, and the impacts to the contaminants following placement of a surface barrier; (3) subsurface monitoring to provide subsurface characterization of initial conditions and changes that occur during and following remediation activities; and (4) field observations that span years to decades to validate the evaluation methodology. A set of six proposed tasks was identified to provide information needed to address the above outcomes. The proposed tasks are: (1) Evaluation Methodology - Develop common evaluation methodology that will provide a clear, consistent, and defensible basis for evaluating groundwater impacts caused by placement of a surface barrier above deep vadose zone contamination. (2) Case Studies - Conduct case studies to demonstrate the applicability ofthe common evaluation methodology and provide templates for subsequent use elsewhere. Three sites expected to have conditions that would yield valuable information and experience pertinent to deep vadose zone contamination were chosen to cover a range of conditions. The sites are BC Cribs and Trenches, U Plant Cribs, and the T Farm Interim Cover. (3) Subsurface Monitoring Technologies - Evaluate minimally invasive geophysical approaches for delineating subsurface plumes and monitoring their migration in the deep

  4. Tax Credits, Rebates & Savings | Department of Energy

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

    Hydroelectric (Small) Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until...

  5. Tax Credits, Rebates & Savings | Department of Energy

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

    Thermal Electric, Solar Thermal Process Heat, Solar Photovoltaics Burbank Water & Power- Green Building Incentive Program Incentives are on a first come first serve basis. More...

  6. Tax Credits, Rebates & Savings | Department of Energy

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

    Hydroelectric (Small), Geothermal Direct-Use, Anaerobic Digestion Burbank Water & Power- Green Building Incentive Program Incentives are on a first come first serve basis. More...

  7. Tax Credits, Rebates & Savings | Department of Energy

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

    Air sealing, Building Insulation, Windows, Doors, Wind (Small) Burbank Water & Power- Green Building Incentive Program Incentives are on a first come first serve basis. More...

  8. Tax Credits, Rebates & Savings | Department of Energy

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

    Photovoltaics Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the...

  9. Alternative Fuels Data Center

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

    Commercial customers may also receive 500 for qualified commercial electric vehicle supply equipment. Funding is available on a first-come, first-served basis through 2015. ...

  10. Tax Credits, Rebates & Savings | Department of Energy

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

    Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the rated generating capacity...

  11. New Braunfels Utilities- Residential Solar Water Heater Rebate Program

    Broader source: Energy.gov [DOE]

    Funding is limited and is awarded on a first-come, first-served basis. Applications are located on the program web site.

  12. Tax Credits, Rebates & Savings | Department of Energy

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

    Burbank Water & Power- Green Building Incentive Program Incentives are on a first come first serve basis. More information can be found on the web site listed above. Eligibility:...

  13. Tax Credits, Rebates & Savings | Department of Energy

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

    Gas, Wind (Small), Hydroelectric (Small), Anaerobic Digestion, Fuel Cells using Renewable Fuels Net Metering Net metering is available on a first-come, first-served basis...

  14. Tax Credits, Rebates & Savings | Department of Energy

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

    Hydroelectric Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the...

  15. Tax Credits, Rebates & Savings | Department of Energy

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

    Multifamily Residential Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis...

  16. The power of simplification: Operator interface with the AP1000{sup R} during design-basis and beyond design-basis events

    SciTech Connect (OSTI)

    Williams, M. G.; Mouser, M. R.; Simon, J. B.

    2012-07-01

    The AP1000{sup R} plant is an 1100-MWe pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, safety and cost. The passive safety features are designed to function without safety-grade support systems such as component cooling water, service water, compressed air or HVAC. The AP1000 passive safety features achieve and maintain safe shutdown in case of a design-basis accident for 72 hours without need for operator action, meeting the expectations provided in the European Utility Requirements and the Utility Requirement Document for passive plants. Limited operator actions may be required to maintain safe conditions in the spent fuel pool (SFP) via passive means. This safety approach therefore minimizes the reliance on operator action for accident mitigation, and this paper examines the operator interaction with the Human-System Interface (HSI) as the severity of an accident increases from an anticipated transient to a design basis accident and finally, to a beyond-design-basis event. The AP1000 Control Room design provides an extremely effective environment for addressing the first 72 hours of design-basis events and transients, providing ease of information dissemination and minimal reliance upon operator actions. Symptom-based procedures including Emergency Operating Procedures (EOPs), Abnormal Operating Procedures (AOPs) and Alarm Response Procedures (ARPs) are used to mitigate design basis transients and accidents. Use of the Computerized Procedure System (CPS) aids the operators during mitigation of the event. The CPS provides cues and direction to the operators as the event progresses. If the event becomes progressively worse or lasts longer than 72 hours, and depending upon the nature of failures that may have occurred, minimal operator actions may be required outside of the control room in areas that have been designed to be accessible using components that have been designed to be reliable in these conditions. The primary goal of any such actions is to maintain or refill the passive inventory available to cool the core, containment and spent fuel pool in the safety-related and seismically qualified Passive Containment Cooling Water Storage Tank (PCCWST). The seismically-qualified, ground-mounted Passive Containment Cooling Ancillary Water Storage Tank (PCCAWST) is also available for this function as appropriate. The primary effect of these actions would be to increase the coping time for the AP1000 during design basis events, as well as events such as those described above, from 72 hours without operator intervention to 7 days with minimal operator actions. These Operator actions necessary to protect the health and safety of the public are addressed in the Post-72 Hour procedures, as well as some EOPs, AOPs, ARPs and the Severe Accident Management Guidelines (SAMGs). Should the event continue to become more severe and plant conditions degrade further with indications of inadequate core cooling, the SAMGs provide guidance for strategies to address these hypothetical severe accident conditions. The AP1000 SAMG diagnoses and actions are prioritized to first utilize the AP1000 features that are expected to retain a damaged core inside the reactor vessel. Only one strategy is undertaken at any time. This strategy will be followed and its effectiveness evaluated before other strategies are undertaken. This is a key feature of both the symptom-oriented AP1000 EOPs and the AP1000 SAMGs which maximizes the probability of retaining a damaged core inside the reactor vessel and containment while minimizing the chances for confusion and human errors during implementation. The AP1000 SAMGs are simple and straight-forward and have been developed with considerable input from human factors and plant operations experts. Most importantly, and different from severe accident management strategies for other plants, the AP1000 SAMGs do not require diagnosis of the location of the core (i.e., whether reactor vessel failure has occurred). This is a fun

  17. Time-dependent density functional theory quantum transport simulation in non-orthogonal basis

    SciTech Connect (OSTI)

    Kwok, Yan Ho; Xie, Hang; Yam, Chi Yung; Chen, Guan Hua; Zheng, Xiao

    2013-12-14

    Basing on the earlier works on the hierarchical equations of motion for quantum transport, we present in this paper a first principles scheme for time-dependent quantum transport by combining time-dependent density functional theory (TDDFT) and Keldysh's non-equilibrium Green's function formalism. This scheme is beyond the wide band limit approximation and is directly applicable to the case of non-orthogonal basis without the need of basis transformation. The overlap between the basis in the lead and the device region is treated properly by including it in the self-energy and it can be shown that this approach is equivalent to a lead-device orthogonalization. This scheme has been implemented at both TDDFT and density functional tight-binding level. Simulation results are presented to demonstrate our method and comparison with wide band limit approximation is made. Finally, the sparsity of the matrices and computational complexity of this method are analyzed.

  18. Hamiltonian Light-Front Ffield Theory in a Basis Function Approach

    SciTech Connect (OSTI)

    Vary, J.P.; Honkanen, H.; Li, Jun; Maris, P.; Brodsky, S.J.; Harindranath, A.; de Teramond, G.F.; Sternberg, P.; Ng, E.G.; Yang, C.

    2009-05-15

    Hamiltonian light-front quantum field theory constitutes a framework for the non-perturbative solution of invariant masses and correlated parton amplitudes of self-bound systems. By choosing the light-front gauge and adopting a basis function representation, we obtain a large, sparse, Hamiltonian matrix for mass eigenstates of gauge theories that is solvable by adapting the ab initio no-core methods of nuclear many-body theory. Full covariance is recovered in the continuum limit, the infinite matrix limit. There is considerable freedom in the choice of the orthonormal and complete set of basis functions with convenience and convergence rates providing key considerations. Here, we use a two-dimensional harmonic oscillator basis for transverse modes that corresponds with eigensolutions of the soft-wall AdS/QCD model obtained from light-front holography. We outline our approach, present illustrative features of some non-interacting systems in a cavity and discuss the computational challenges.

  19. JLab Will Begin Testing its Public Address System on a Monthly Basis |

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

    Jefferson Lab Will Begin Testing its Public Address System on a Monthly Basis On April 20, Jefferson Lab Will Begin Testing its Public Address System on a Monthly Basis On Wednesday, April 20, Jefferson Lab will begin conducting a monthly test of its Public Address (PA) System - the live audible announcement feature - available through the lab's Cisco phones. Starting on April 20, these tests will occur at 5:30 p.m. on the third Wednesday of each month. The Public Address System may be used

  20. Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6 Citation Details In-Document Search Title: Structural Basis of Wnt Signaling Inhibition by Dickkopf Binding to LRP5/6 Authors: Ahn, Victoria E. ; Chu, Matthew Ling-Hon ; Choi, Hee-Jung ; Tran, Denise ; Abo, Arie ; Weis, William I. Publication Date: 2011-11-01 OSTI Identifier: 1198118 Type: Published Article Journal Name: Developmental Cell Additional Journal Information: Journal Volume: 21;

  1. Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by

    Office of Scientific and Technical Information (OSTI)

    the Wnt receptor LRP6 (Journal Article) | SciTech Connect Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by the Wnt receptor LRP6 Citation Details In-Document Search Title: Structural basis of GSK-3 inhibition by N-terminal phosphorylation and by the Wnt receptor LRP6 Authors: Stamos, Jennifer L. ; Chu, Matthew Ling-Hon ; Enos, Michael D. ; Shah, Niket ; Weis, William I. [1] + Show Author Affiliations (Stanford) Publication Date: 2015-02-19 OSTI Identifier: 1168492

  2. Basis for Identification of Disposal Options for R and D for Spent Nuclear

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

    Fuel and High-Level Waste | Department of Energy Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered

  3. Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase Citation Details In-Document Search Title: Structural Basis for Microcin C7 Inactivation by the MccE Acetyltransferase The antibiotic microcin C7 (McC) acts as a bacteriocide by inhibiting aspartyl-tRNA synthetase and stalling the protein translation machinery. McC is synthesized as a heptapeptide-nucleotide conjugate, which is

  4. Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript

    Office of Scientific and Technical Information (OSTI)

    Fbx4] (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript Fbx4] Citation Details In-Document Search Title: Structural Basis of Selective Ubiquitination of TRF1 by SCF[superscript Fbx4] TRF1 is a critical regulator of telomere length. As such, TRF1 levels are regulated by ubiquitin-dependent proteolysis via an SCF E3 ligase where Fbx4 contributes to substrate specification. Here, we report

  5. The Structural Basis for Tight Control of PP2A Methylation and Function by

    Office of Scientific and Technical Information (OSTI)

    LCMT-1 (Journal Article) | SciTech Connect The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Citation Details In-Document Search Title: The Structural Basis for Tight Control of PP2A Methylation and Function by LCMT-1 Proper formation of protein phosphatase 2A (PP2A) holoenzymes is essential for the fitness of all eukaryotic cells. Carboxyl methylation of the PP2A catalytic subunit plays a critical role in regulating holoenzyme assembly; methylation is

  6. Universal basis of two-center functions. Test computations of certain diatomic molecules and ions

    SciTech Connect (OSTI)

    Kirnos, V.F.; Samsonov, B.F.; Cheglokov, E.I.

    1987-05-01

    It is shown that the basis of two-center functions is universal. The dependence of the nuclei of atoms comprising a molecule on charges and on the intranuclear spacing is separated explicitly in the integrals used in analyzing diatomic molecules. The basis integrals constructed once permitted rapid and effective execution of computations for the ground state potential curves for a number of electron systems: H/sub 2/, He/sub 2//sup 2 +/, HeH/sup +/, He/sub 2/, LiH, Li/sub 2/, HeB/sup +/, Be/sub 2/.

  7. Technical Basis Spent Nuclear Fuel (SNF) Project Radiation and Contamination Trending Program

    SciTech Connect (OSTI)

    ELGIN, J.C.

    2000-10-02

    This report documents the technical basis for the Spent Nuclear Fuel (SNF) Program radiation and contamination trending program. The program consists of standardized radiation and contamination surveys of the KE Basin, radiation surveys of the KW basin, radiation surveys of the Cold Vacuum Drying Facility (CVD), and radiation surveys of the Canister Storage Building (CSB) with the associated tracking. This report also discusses the remainder of radiological areas within the SNFP that do not have standardized trending programs and the basis for not having this program in those areas.

  8. Electron Anomalous Magnetic Moment in Basis Light-Front Quantization Approach

    SciTech Connect (OSTI)

    Zhao, Xingbo; Honkanen, Heli; Maris, Pieter; Vary, James P.; Brodsky, Stanley J.; /SLAC

    2012-02-17

    We apply the Basis Light-Front Quantization (BLFQ) approach to the Hamiltonian field theory of Quantum Electrodynamics (QED) in free space. We solve for the mass eigenstates corresponding to an electron interacting with a single photon in light-front gauge. Based on the resulting non-perturbative ground state light-front amplitude we evaluate the electron anomalous magnetic moment. The numerical results from extrapolating to the infinite basis limit reproduce the perturbative Schwinger result with relative deviation less than 1.2%. We report significant improvements over previous works including the development of analytic methods for evaluating the vertex matrix elements of QED.

  9. Analytic matrix elements for the two-electron atomic basis with logarithmic terms

    SciTech Connect (OSTI)

    Liverts, Evgeny Z.; Barnea, Nir

    2014-08-01

    The two-electron problem for the helium-like atoms in S-state is considered. The basis containing the integer powers of ln r, where r is a radial variable of the Fock expansion, is studied. In this basis, the analytic expressions for the matrix elements of the corresponding Hamiltonian are presented. These expressions include only elementary and special functions, what enables very fast and accurate computation of the matrix elements. The decisive contribution of the correct logarithmic terms to the behavior of the two-electron wave function in the vicinity of the triple-coalescence point is reaffirmed.

  10. Temperature determination using pyrometry

    DOE Patents [OSTI]

    Breiland, William G.; Gurary, Alexander I.; Boguslavskiy, Vadim

    2002-01-01

    A method for determining the temperature of a surface upon which a coating is grown using optical pyrometry by correcting Kirchhoff's law for errors in the emissivity or reflectance measurements associated with the growth of the coating and subsequent changes in the surface thermal emission and heat transfer characteristics. By a calibration process that can be carried out in situ in the chamber where the coating process occurs, an error calibration parameter can be determined that allows more precise determination of the temperature of the surface using optical pyrometry systems. The calibration process needs only to be carried out when the physical characteristics of the coating chamber change.

  11. NEPA Determination Complete

    Broader source: Energy.gov [DOE]

    DOE has determined that this proposed project is a major Federal action that may significantly affect the quality of the human environment. To comply with the National Environmental Policy Act ...

  12. Solids mass flow determination

    DOE Patents [OSTI]

    Macko, Joseph E.

    1981-01-01

    Method and apparatus for determining the mass flow rate of solids mixed with a transport fluid to form a flowing mixture. A temperature differential is established between the solids and fluid. The temperature of the transport fluid prior to mixing, the temperature of the solids prior to mixing, and the equilibrium temperature of the mixture are monitored and correlated in a heat balance with the heat capacities of the solids and fluid to determine the solids mass flow rate.

  13. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    SciTech Connect (OSTI)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  14. CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor

    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) used for a February 2007 assessment of the Safety Basis in preparation for restart of the Oak Ridge National Laboratory High Flux Isotope Reactor.

  15. CRAD, Safety Basis- Oak Ridge National Laboratory TRU ALPHA LLWT Project

    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) used for a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

  16. CRAD, Safety Basis- Los Alamos National Laboratory TA 55 SST Facility

    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) used for an assessment of the Safety Basis at the Los Alamos National Laboratory TA 55 SST Facility.

  17. CRAD, Safety Basis- Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility

    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) used for an assessment of the Safety Basis portion of an Operational Readiness Review at the Los Alamos National Laboratory Waste Characterization, Reduction, and Repackaging Facility.

  18. CRAD, Safety Basis- Oak Ridge National Laboratory High Flux Isotope Reactor Contractor ORR

    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) used for a February 2007 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory High Flux Isotope Reactor.

  19. CRAD, Safety Basis- Y-12 Enriched Uranium Operations Oxide Conversion Facility

    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) used for a January 2005 assessment of the Safety Basis at the Y-12 - Enriched Uranium Operations Oxide Conversion Facility.

  20. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    SciTech Connect (OSTI)

    HARRIS, J.P.

    1999-08-31

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

  1. Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

    SciTech Connect (OSTI)

    HARRIS, J.P.

    2000-03-27

    This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.

  2. Sensitivity of the Properties of Ruthenium Blue Dimer to Method, Basis Set, and Continuum Model

    SciTech Connect (OSTI)

    Ozkanlar, Abdullah; Clark, Aurora E.

    2012-05-23

    The ruthenium blue dimer [(bpy)2RuIIIOH2]2O4+ is best known as the first well-defined molecular catalyst for water oxidation. It has been subject to numerous computational studies primarily employing density functional theory. However, those studies have been limited in the functionals, basis sets, and continuum models employed. The controversy in the calculated electronic structure and the reaction energetics of this catalyst highlights the necessity of benchmark calculations that explore the role of density functionals, basis sets, and continuum models upon the essential features of blue-dimer reactivity. In this paper, we report Kohn-Sham complete basis set (KS-CBS) limit extrapolations of the electronic structure of blue dimer using GGA (BPW91 and BP86), hybrid-GGA (B3LYP), and meta-GGA (M06-L) density functionals. The dependence of solvation free energy corrections on the different cavity types (UFF, UA0, UAHF, UAKS, Bondi, and Pauling) within polarizable and conductor-like polarizable continuum model has also been investigated. The most common basis sets of double-zeta quality are shown to yield results close to the KS-CBS limit; however, large variations are observed in the reaction energetics as a function of density functional and continuum cavity model employed.

  3. Dynamical properties of non-ideal plasma on the basis of effective potentials

    SciTech Connect (OSTI)

    Ramazanov, T. S.; Kodanova, S. K.; Moldabekov, Zh. A.; Issanova, M. K.

    2013-11-15

    In this work, stopping power has been calculated on the basis of the Coulomb logarithm using the effective potentials. Calculations of the Coulomb logarithm and stopping power for different interaction potentials and degrees of ionization are compared. The comparison with the data of other theoretical and experimental works was carried out.

  4. Grid and basis adaptive polynomial chaos techniques for sensitivity and uncertainty analysis

    SciTech Connect (OSTI)

    Perk, Zoltn Gilli, Luca Lathouwers, Danny Kloosterman, Jan Leen

    2014-03-01

    The demand for accurate and computationally affordable sensitivity and uncertainty techniques is constantly on the rise and has become especially pressing in the nuclear field with the shift to Best Estimate Plus Uncertainty methodologies in the licensing of nuclear installations. Besides traditional, already well developed methods such as first order perturbation theory or Monte Carlo sampling Polynomial Chaos Expansion (PCE) has been given a growing emphasis in recent years due to its simple application and good performance. This paper presents new developments of the research done at TU Delft on such Polynomial Chaos (PC) techniques. Our work is focused on the Non-Intrusive Spectral Projection (NISP) approach and adaptive methods for building the PCE of responses of interest. Recent efforts resulted in a new adaptive sparse grid algorithm designed for estimating the PC coefficients. The algorithm is based on Gerstner's procedure for calculating multi-dimensional integrals but proves to be computationally significantly cheaper, while at the same it retains a similar accuracy as the original method. More importantly the issue of basis adaptivity has been investigated and two techniques have been implemented for constructing the sparse PCE of quantities of interest. Not using the traditional full PC basis set leads to further reduction in computational time since the high order grids necessary for accurately estimating the near zero expansion coefficients of polynomial basis vectors not needed in the PCE can be excluded from the calculation. Moreover the sparse PC representation of the response is easier to handle when used for sensitivity analysis or uncertainty propagation due to the smaller number of basis vectors. The developed grid and basis adaptive methods have been implemented in Matlab as the Fully Adaptive Non-Intrusive Spectral Projection (FANISP) algorithm and were tested on four analytical problems. These show consistent good performance both in terms of the accuracy of the resulting PC representation of quantities and the computational costs associated with constructing the sparse PCE. Basis adaptivity also seems to make the employment of PC techniques possible for problems with a higher number of input parameters (1520), alleviating a well known limitation of the traditional approach. The prospect of larger scale applicability and the simplicity of implementation makes such adaptive PC algorithms particularly appealing for the sensitivity and uncertainty analysis of complex systems and legacy codes.

  5. Correlation consistent basis sets for actinides. I. The Th and U atoms

    SciTech Connect (OSTI)

    Peterson, Kirk A.

    2015-02-21

    New correlation consistent basis sets based on both pseudopotential (PP) and all-electron Douglas-Kroll-Hess (DKH) Hamiltonians have been developed from double- to quadruple-zeta quality for the actinide atoms thorium and uranium. Sets for valence electron correlation (5f6s6p6d), cc − pV nZ − PP and cc − pV nZ − DK3, as well as outer-core correlation (valence + 5s5p5d), cc − pwCV nZ − PP and cc − pwCV nZ − DK3, are reported (n = D, T, Q). The -PP sets are constructed in conjunction with small-core, 60-electron PPs, while the -DK3 sets utilized the 3rd-order Douglas-Kroll-Hess scalar relativistic Hamiltonian. Both series of basis sets show systematic convergence towards the complete basis set limit, both at the Hartree-Fock and correlated levels of theory, making them amenable to standard basis set extrapolation techniques. To assess the utility of the new basis sets, extensive coupled cluster composite thermochemistry calculations of ThF{sub n} (n = 2 − 4), ThO{sub 2}, and UF{sub n} (n = 4 − 6) have been carried out. After accurately accounting for valence and outer-core correlation, spin-orbit coupling, and even Lamb shift effects, the final 298 K atomization enthalpies of ThF{sub 4}, ThF{sub 3}, ThF{sub 2}, and ThO{sub 2} are all within their experimental uncertainties. Bond dissociation energies of ThF{sub 4} and ThF{sub 3}, as well as UF{sub 6} and UF{sub 5}, were similarly accurate. The derived enthalpies of formation for these species also showed a very satisfactory agreement with experiment, demonstrating that the new basis sets allow for the use of accurate composite schemes just as in molecular systems composed only of lighter atoms. The differences between the PP and DK3 approaches were found to increase with the change in formal oxidation state on the actinide atom, approaching 5-6 kcal/mol for the atomization enthalpies of ThF{sub 4} and ThO{sub 2}. The DKH3 atomization energy of ThO{sub 2} was calculated to be smaller than the DKH2 value by ∼1 kcal/mol.

  6. Categorical Exclusion Determinations: Environmental Management...

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

    Consolidated Business Service Center Categorical Exclusion Determinations: Environmental Management Consolidated Business Service Center Categorical Exclusion Determinations issued ...

  7. Categorical Exclusion Determinations: Minnesota | Department...

    Office of Environmental Management (EM)

    Minnesota Categorical Exclusion Determinations: Minnesota Location Categorical Exclusion Determinations issued for actions in Minnesota. DOCUMENTS AVAILABLE FOR DOWNLOAD December ...

  8. Licensing topical report: application of probabilistic risk assessment in the selection of design basis accidents. [HTGR

    SciTech Connect (OSTI)

    Houghton, W.J.

    1980-06-01

    A probabilistic risk assessment (PRA) approach is proposed to be used to scrutinize selection of accident sequences. A technique is described in this Licensing Topical Report to identify candidates for Design Basis Accidents (DBAs) utilizing the risk assessment results. As a part of this technique, it is proposed that events with frequencies below a specified limit would not be candidates. The use of the methodology described is supplementary to the traditional, deterministic approach and may result, in some cases, in the selection of multiple failure sequences as DBAs; it may also provide a basis for not considering some traditionally postulated events as being DBAs. A process is then described for selecting a list of DBAs based on the candidates from PRA as supplementary to knowledge and judgments from past licensing practice. These DBAs would be the events considered in Chapter 15 of Safety Analysis Reports of high-temperature gas-cooled reactors (HTGRs).

  9. Comparison of CRBR design-basis events with those of foreign LMFBR plants

    SciTech Connect (OSTI)

    Agrawal, A.K.

    1983-04-01

    As part of the Construction Permit (CP) review of the Clinch River Breeder Reactor Plant (CRBR), the Brookhaven National Laboratory was asked to compare the Design Basis Accidents that are considered in CRBR Preliminary Safety Analysis Report with those of the foreign contemporary plants (PHENIX, SUPER-PHENIX, SNR-300, PFR, and MONJU). A brief introductory review of any special or unusual characteristics of these plants is given. This is followed by discussions of the design basis accidents and their acceptance criteria. In spite of some discrepancies due either to semantics or to licensing decisions, there appears to be a considerable degree of unanimity in the selection (definition) of DBAs in all of these plants.

  10. 105-K Basin material design basis feed description for spent nuclear fuel project facilities

    SciTech Connect (OSTI)

    Praga, A.N.

    1998-01-08

    Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.

  11. Kinetically balanced Gaussian basis-set approach to relativistic Compton profiles of atoms

    SciTech Connect (OSTI)

    Jaiswal, Prerit; Shukla, Alok

    2007-02-15

    Atomic Compton profiles (CPs) are a very important property which provide us information about the momentum distribution of atomic electrons. Therefore, for CPs of heavy atoms, relativistic effects are expected to be important, warranting a relativistic treatment of the problem. In this paper, we present an efficient approach aimed at ab initio calculations of atomic CPs within a Dirac-Hartree-Fock (DHF) formalism, employing kinetically balanced Gaussian basis functions. The approach is used to compute the CPs of noble gases ranging from He to Rn, and the results have been compared to the experimental and other theoretical data, wherever possible. The influence of the quality of the basis set on the calculated CPs has also been systematically investigated.

  12. Hamiltonian Light-front Field Theory Within an AdS/QCD Basis

    SciTech Connect (OSTI)

    Vary, J.P.; Honkanen, H.; Li, Jun; Maris, P.; Brodsky, S.J.; Harindranath, A.; de Teramond, G.F.; Sternberg, P.; Ng, E.G.; Yang, C.; /LBL, Berkeley

    2009-12-16

    Non-perturbative Hamiltonian light-front quantum field theory presents opportunities and challenges that bridge particle physics and nuclear physics. Fundamental theories, such as Quantum Chromodynamics (QCD) and Quantum Electrodynamics (QED) offer the promise of great predictive power spanning phenomena on all scales from the microscopic to cosmic scales, but new tools that do not rely exclusively on perturbation theory are required to make connection from one scale to the next. We outline recent theoretical and computational progress to build these bridges and provide illustrative results for nuclear structure and quantum field theory. As our framework we choose light-front gauge and a basis function representation with two-dimensional harmonic oscillator basis for transverse modes that corresponds with eigensolutions of the soft-wall AdS/QCD model obtained from light-front holography.

  13. Polychromatic sparse image reconstruction and mass attenuation spectrum estimation via B-spline basis function expansion

    SciTech Connect (OSTI)

    Gu, Renliang E-mail: ald@iastate.edu; Dogandžić, Aleksandar E-mail: ald@iastate.edu

    2015-03-31

    We develop a sparse image reconstruction method for polychromatic computed tomography (CT) measurements under the blind scenario where the material of the inspected object and the incident energy spectrum are unknown. To obtain a parsimonious measurement model parameterization, we first rewrite the measurement equation using our mass-attenuation parameterization, which has the Laplace integral form. The unknown mass-attenuation spectrum is expanded into basis functions using a B-spline basis of order one. We develop a block coordinate-descent algorithm for constrained minimization of a penalized negative log-likelihood function, where constraints and penalty terms ensure nonnegativity of the spline coefficients and sparsity of the density map image in the wavelet domain. This algorithm alternates between a Nesterov’s proximal-gradient step for estimating the density map image and an active-set step for estimating the incident spectrum parameters. Numerical simulations demonstrate the performance of the proposed scheme.

  14. Technical Basis for Work Place Air Monitoring for the Plutonium Finishing Plan (PFP)

    SciTech Connect (OSTI)

    JONES, R.A.

    1999-10-06

    This document establishes the basis for the Plutonium Finishing Plant's (PFP) work place air monitoring program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), Part 835 ''Occupational Radiation Protection''; Hanford Site Radiological Control Manual (HSRCM-1); HNF-PRO-33 1, Work Place Air Monitoring; WHC-SD-CP-SAR-021, Plutonium Finishing Plant Final Safety Analysis Report; and Applicable recognized national standards invoked by DOE Orders and Policies.

  15. Hydro-Kansas (HK) Research Project: Tests of a Physical Basis of

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

    Statistical Self-Similarity in Peak Flows in the Whitewater Basin, Kansas Hydro-Kansas (HK) Research Project: Tests of a Physical Basis of Statistical Self-Similarity in Peak Flows in the Whitewater Basin, Kansas Gupta, Vijay University of Colorado Furey, Peter Colorado Research Associates Mantila, Ricardo University of Colorado Krajewski, Witold University of Iowa Kruger, Anton The University of Iowa Clayton, Jordan US Geological Survey and University of Iowa Category: Atmospheric State and

  16. Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development

    Broader source: Energy.gov [DOE]

    Slide Presentation by Rich Davies, Kami Lowry, Mike Schlender, Pacific Northwest National Laboratory (PNNL) and Ted Pietrok, Pacific Northwest Site Office (PNSO). Integrated Safety Management System as the Basis for Work Planning and Control for Research and Development. Work Planning and Control (WP&C) is essential to assuring the safety of workers and the public regardless of the scope of work Research and Development (R&D) activities are no exception.

  17. Tank waste remediation system retrieval and disposal mission authorization basis amendment task plan

    SciTech Connect (OSTI)

    Goetz, T.G.

    1998-01-08

    This task plan is a documented agreement between Nuclear Safety and Licensing and the Process Development group within the Waste Feed Delivery organization. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Waste Delivery Program, Project W-211, and Project W-TBD.

  18. A probabilistic risk assessment of the LLNL Plutonium facility`s evaluation basis fire operational accident

    SciTech Connect (OSTI)

    Brumburgh, G.

    1994-08-31

    The Lawrence Livermore National Laboratory (LLNL) Plutonium Facility conducts numerous involving plutonium to include device fabrication, development of fabrication techniques, metallurgy research, and laser isotope separation. A Safety Analysis Report (SAR) for the building 332 Plutonium Facility was completed rational safety and acceptable risk to employees, the public, government property, and the environment. This paper outlines the PRA analysis of the Evaluation Basis Fire (EDF) operational accident. The EBF postulates the worst-case programmatic impact event for the Plutonium Facility.

  19. Award Fee Determination Scorecard Contractor: Centerra-Savannah River Site

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

    Award Fee Determination Scorecard Contractor: Centerra-Savannah River Site Contract: Protective Force Security Services Contract Number: DE-AC30-10CC60025 Award Period: October 1, 2014 - September 30, 2015 Basis of Evaluation: Award Fee Plan The contractor is required to provide, operate and maintain an armed and uniformed protective force for the physical protection of United States Department of Energy (DOE) security interests and other such related duties at the Savannah River Site (SRS). The

  20. Award Fee Determination Scorecard Contractor: Bechtel National, Inc. (BNI)

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

    Award Fee Determination Scorecard Contractor: Bechtel National, Inc. (BNI) Contract: Design, Construction, and Commissioning of the Hanford Tank Waste Treatment and Immobilization Plant Contract Number: DE-AC27-01RV14136 Award Fee Period: January 1, 2015, to December 31, 2015 Basis of Evaluation: 2015 Performance Evaluation and Measurement Plan Award Fee Available: $12,600,000 Award Fee Earned: $8,310,000 (66.0* percent) Incentive B.1 - Award Fee-Project Management - Good The fee for Project

  1. Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings

    SciTech Connect (OSTI)

    Braverman, J.I.; Morante, R.

    2010-07-18

    ABSTRACT Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 and US NRC Standard Review Plan, Section 3.8) ; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 and 10 CFR 50); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 as well as SECY 90-016, SECY 93-087, and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

  2. Interim Action Determination

    Energy Savers [EERE]

    Interim Action Determination Processing of Plutonium Materials from the DOE Standard 3013 Surveillance Program in H-Canyon at the Savannah River Site The Department of Energy (DOE) is preparing the Surplus Plutonium Disposition Supplemental Environmental Impact Statement (SPD SEIS, DOE/EIS-0283-S2). DOE is evaluating alternatives for disposition of non-pit plutonium that is surplus to the national security needs of the United States. Although the Deputy Secretary of Energy approved Critical

  3. NEPA Determination Form

    National Nuclear Security Administration (NNSA)

    LA NEPA COMPLIANCE DETERMINATION FORM PRID - 09P-0059 V2 Page 1 of 8 Project/Activity Title: TA-3 Substation Replacement Project PRID: 09P-0059 V2 Date: February 16, 2016 Purpose: The proposed demolition and replacement of the Los Alamos National Laboratory's (LANL) Technical Area (TA)-3 electrical power substation is needed to provide reliable and efficient electrical distribution systems with sufficient electrical capacity to support the national security missions. The electrical distribution

  4. Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  5. Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Not Listed

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  6. Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    L. Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory Research and Education Campus facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  7. Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-09-01

    Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

  8. Structural basis of the heterodimerization of the MST and RASSF SARAH domains in the Hippo signalling pathway

    SciTech Connect (OSTI)

    Hwang, Eunha; Cheong, Hae-Kap; Mushtaq, Ameeq Ul; Kim, Hye-Yeon; Yeo, Kwon Joo; Kim, Eunhee; Lee, Woo Cheol; Hwang, Kwang Yeon; Cheong, Chaejoon; Jeon, Young Ho

    2014-07-01

    The heterodimeric structure of the MST1 and RASSF5 SARAH domains is presented. A comparison of homodimeric and heterodimeric interactions provides a structural basis for the preferential association of the SARAH heterodimer. Despite recent progress in research on the Hippo signalling pathway, the structural information available in this area is extremely limited. Intriguingly, the homodimeric and heterodimeric interactions of mammalian sterile 20-like (MST) kinases through the so-called ‘SARAH’ (SAV/RASSF/HPO) domains play a critical role in cellular homeostasis, dictating the fate of the cell regarding cell proliferation or apoptosis. To understand the mechanism of the heterodimerization of SARAH domains, the three-dimensional structures of an MST1–RASSF5 SARAH heterodimer and an MST2 SARAH homodimer were determined by X-ray crystallography and were analysed together with that previously determined for the MST1 SARAH homodimer. While the structure of the MST2 homodimer resembled that of the MST1 homodimer, the MST1–RASSF5 heterodimer showed distinct structural features. Firstly, the six N-terminal residues (Asp432–Lys437), which correspond to the short N-terminal 3{sub 10}-helix h1 kinked from the h2 helix in the MST1 homodimer, were disordered. Furthermore, the MST1 SARAH domain in the MST1–RASSF5 complex showed a longer helical structure (Ser438–Lys480) than that in the MST1 homodimer (Val441–Lys480). Moreover, extensive polar and nonpolar contacts in the MST1–RASSF5 SARAH domain were identified which strengthen the interactions in the heterodimer in comparison to the interactions in the homodimer. Denaturation experiments performed using urea also indicated that the MST–RASSF heterodimers are substantially more stable than the MST homodimers. These findings provide structural insights into the role of the MST1–RASSF5 SARAH domain in apoptosis signalling.

  9. Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee |

    Energy Savers [EERE]

    Department of Energy Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee I adopt and approve the attached annual determination of the Director, Office of Standard Contract Management, that there is no reasonable basis at this time to conclude that either excess or insufficient funds are being collected and thus will not propose an adjustment to the fee to Congress; the fee will, therefore, remain at

  10. Just in Time DSA-The Hanford Nuclear Safety Basis Strategy

    SciTech Connect (OSTI)

    Olinger, S. J.; Buhl, A. R.

    2002-02-26

    The U.S. Department of Energy, Richland Operations Office (RL) is responsible for 30 hazard category 2 and 3 nuclear facilities that are operated by its prime contractors, Fluor Hanford Incorporated (FHI), Bechtel Hanford, Incorporated (BHI) and Pacific Northwest National Laboratory (PNNL). The publication of Title 10, Code of Federal Regulations, Part 830, Subpart B, Safety Basis Requirements (the Rule) in January 2001 imposed the requirement that the Documented Safety Analyses (DSA) for these facilities be reviewed against the requirements of the Rule. Those DSA that do not meet the requirements must either be upgraded to satisfy the Rule, or an exemption must be obtained. RL and its prime contractors have developed a Nuclear Safety Strategy that provides a comprehensive approach for supporting RL's efforts to meet its long term objectives for hazard category 2 and 3 facilities while also meeting the requirements of the Rule. This approach will result in a reduction of the total number of safety basis documents that must be developed and maintained to support the remaining mission and closure of the Hanford Site and ensure that the documentation that must be developed will support: compliance with the Rule; a ''Just-In-Time'' approach to development of Rule-compliant safety bases supported by temporary exemptions; and consolidation of safety basis documents that support multiple facilities with a common mission (e.g. decontamination, decommissioning and demolition [DD&D], waste management, surveillance and maintenance). This strategy provides a clear path to transition the safety bases for the various Hanford facilities from support of operation and stabilization missions through DD&D to accelerate closure. This ''Just-In-Time'' Strategy can also be tailored for other DOE Sites, creating the potential for large cost savings and schedule reductions throughout the DOE complex.

  11. Technical basis for cases N-629 and N-631 as an alternative for RTNDT reference temperature

    SciTech Connect (OSTI)

    Merkle, John Graham; Server, W. L.

    2007-01-01

    ASME Code Cases N-629/N-631, published in 1999, provided an important new approach to allow material specific, measured fracture toughness curves for ferritic steels in the code applications. This has enabled some of the nuclear power plants whose reactor pressure vessel materials reached a certain threshold level based on overly conservative rules to use an alternative RTNDT to justify continued operation of their plants. These code cases have been approved by the US Nuclear Regulatory Commission and these have been proposed to be codified in Appendix A and Appendix G of the ASME Boiler and Pressure Vessel Code. This paper summarizes the basis of this approach for the record.

  12. Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic

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

    Influenza Virus Structural Basis of Pre-existing Immunity to the 2009 H1N1 Pandemic Influenza Virus The emergence of the 2009 H1N1 influenza pandemic, also known as the "swine flu", marks the first human flu pandemic in 40 years and has caused significant human infection and mortality globally (1). The emergence of the 2009 H1N1 flu marks the first time that an influenza pandemic was triggered by a virus carrying the same hemagglutinin (HA) subtype as circulating seasonal strains.

  13. Categorical Exclusion Determinations: California | Department...

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

    ... February 25, 2016 CX-100493 Categorical Exclusion Determination Integrated Glass Coating ... February 25, 2016 CX-100514 Categorical Exclusion Determination Crop Protection Utilizing ...

  14. Categorical Exclusion Determinations: Connecticut | Department...

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

    August 11, 2014 CX-100033: Categorical Exclusion Determination "Smart" Matrix Development ... May 22, 2014 CX-012145: Categorical Exclusion Determination Connecticut Clean Cities ...

  15. Categorical Exclusion Determinations: Louisiana | Department...

    Office of Environmental Management (EM)

    March 4, 2016 CX-100533 Categorical Exclusion Determination Pump Station Improvements ... February 18, 2015 CX-100185 Categorical Exclusion Determination Pump Station Improvements ...

  16. Categorical Exclusion Determinations: Mississippi | Department...

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

    March 30, 2015 CX-013741: Categorical Exclusion Determination Statistical Analysis of ... March 30, 2015 CX-013758: Categorical Exclusion Determination Statistical Analysis of ...

  17. Development of Probabilistic Design Basis Earthquake (DBE) Parameters for Moderate and High Hazard Facilities at INEEL

    SciTech Connect (OSTI)

    S. M. Payne; V. W. Gorman; S. A. Jensen; M. E. Nitzel; M. J. Russell; R. P. Smith

    2000-03-01

    Design Basis Earthquake (DBE) horizontal and vertical response spectra are developed for moderate and high hazard facilities or Performance Categories (PC) 3 and 4, respectively, at the Idaho National Engineering and Environmental Laboratory (INEEL). The probabilistic DBE response spectra will replace the deterministic DBE response spectra currently in the U.S. Department of Energy Idaho Operations Office (DOE-ID) Architectural Engineering Standards that govern seismic design criteria for several facility areas at the INEEL. Probabilistic DBE response spectra are recommended to DOE Naval Reactors for use at the Naval Reactor Facility at INEEL. The site-specific Uniform Hazard Spectra (UHS) developed by URS Greiner Woodward Clyde Federal Services are used as the basis for developing the DBE response spectra. In 1999, the UHS for all INEEL facility areas were recomputed using more appropriate attenuation relationships for the Basin and Range province. The revised UHS have lower ground motions than those produced in the 1996 INEEL site-wide probabilistic ground motion study. The DBE response spectra were developed by incorporating smoothed broadened regions of the peak accelerations, velocities, and displacements defined by the site-specific UHS. Portions of the DBE response spectra were adjusted to ensure conservatism for the structural design process.

  18. AP1000 Design Basis Event Simulation at the APEX-1000 Test Facility

    SciTech Connect (OSTI)

    Wright, Richard F.; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events are being simulated at APEX-1000 including a double-ended direct vessel injection (DEDVI) line break and a 2-inch cold leg break. These tests show that the core remains covered with ample margin until gravity injection is established regardless of the initiating event. The tests also show that liquid entrainment from the upper plenum which is proportional to the reactor power does not impact the ability of the passive core cooling system to keep the core covered. (authors)

  19. CX-004720: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Analyzing Genetic Basis of Mycobacterium Tuberculosis Latency/Reactivation (National Institute of Health Grant/University of New Mexico Health Sciences Center)CX(s) Applied: B3.12Date: 09/22/2010Location(s): New MexicoOffice(s): Sandia Site Office

  20. Determination of leakage areas in nuclear piping

    SciTech Connect (OSTI)

    Keim, E.

    1997-04-01

    For the design and operation of nuclear power plants the Leak-Before-Break (LBB) behavior of a piping component has to be shown. This means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safely detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. In the experience with the leak rate program is described while this paper deals with the computation of crack openings and leakage areas of longitudinal and circumferential cracks by means of fracture mechanics. The leakage areas are determined by the integration of the crack openings along the crack front, considering plasticity and geometrical effects. They are evaluated with respect to minimum values for the design of leak detection systems, and maximum values for controlling jet and reaction forces. By means of fracture mechanics LBB for subcritical cracks has to be shown and the calculation of leakage areas is the basis for quantitatively determining the discharge rate of leaking subcritical through-wall cracks. The analytical approach and its validation will be presented for two examples of complex structures. The first one is a pipe branch containing a circumferential crack and the second one is a pipe bend with a longitudinal crack.

  1. Analysis of main steam isolation valve leakage in design basis accidents using MELCOR 1.8.6 and RADTRAD.

    SciTech Connect (OSTI)

    Salay, Michael; Kalinich, Donald A.; Gauntt, Randall O.; Radel, Tracy E.

    2008-10-01

    Analyses were performed using MELCOR and RADTRAD to investigate main steam isolation valve (MSIV) leakage behavior under design basis accident (DBA) loss-of-coolant (LOCA) conditions that are presumed to have led to a significant core melt accident. Dose to the control room, site boundary and LPZ are examined using both approaches described in current regulatory guidelines as well as analyses based on best estimate source term and system response. At issue is the current practice of using containment airborne aerosol concentrations as a surrogate for the in-vessel aerosol concentration that exists in the near vicinity of the MSIVs. This study finds current practice using the AST-based containment aerosol concentrations for assessing MSIV leakage is non-conservative and conceptually in error. A methodology is proposed that scales the containment aerosol concentration to the expected vessel concentration in order to preserve the simplified use of the AST in assessing containment performance under assumed DBA conditions. This correction is required during the first two hours of the accident while the gap and early in-vessel source terms are present. It is general practice to assume that at {approx}2hrs, recovery actions to reflood the core will have been successful and that further core damage can be avoided. The analyses performed in this study determine that, after two hours, assuming vessel reflooding has taken place, the containment aerosol concentration can then conservatively be used as the effective source to the leaking MSIV's. Recommendations are provided concerning typical aerosol removal coefficients that can be used in the RADTRAD code to predict source attenuation in the steam lines, and on robust methods of predicting MSIV leakage flows based on measured MSIV leakage performance.

  2. U.S. Department of Energy, Oak Ridge Operations Office Nuclear Facility Safety Basis Fundamentals Self-Study Guide [Fulfills ORO Safety Basis Competency 1, 2 (Part 1), or 7 (Part 1)

    Broader source: Energy.gov [DOE]

    "This self-study guide provides an overview of safety basis terminology, requirements, and activities that are applicable to DOE and Oak Ridge Operations Office (ORO) nuclear facilities on the Oak...

  3. Structural basis of GDP release and gating in G protein coupled Fe[superscript 2+] transport

    SciTech Connect (OSTI)

    Guilfoyle, Amy; Maher, Megan J.; Rapp, Mikaela; Clarke, Ronald; Harrop, Stephen; Jormakka, Mika

    2009-09-29

    G proteins are key molecular switches in the regulation of membrane protein function and signal transduction. The prokaryotic membrane protein FeoB is involved in G protein coupled Fe{sup 2+} transport, and is unique in that the G protein is directly tethered to the membrane domain. Here, we report the structure of the soluble domain of FeoB, including the G protein domain, and its assembly into an unexpected trimer. Comparisons between nucleotide free and liganded structures reveal the closed and open state of a central cytoplasmic pore, respectively. In addition, these data provide the first observation of a conformational switch in the nucleotide-binding G5 motif, defining the structural basis for GDP release. From these results, structural parallels are drawn to eukaryotic G protein coupled membrane processes.

  4. Composition and Technical Basis for K Basin Settler Sludge Simulant for Inspection, Retrieval, and Pump Testing

    SciTech Connect (OSTI)

    Schmidt, Andrew J.; Zacher, Alan H.

    2007-06-25

    This report provides the formulation and technical basis for a K Basin Settler Tank Sludge simulant that will be used by the K Basin Closure Project (KBC) to test and develop equipment/approaches for Settler Tank sludge level measurement and retrieval in a mock-up test system of the actual Settler Tanks. The sludge simulant may also be used to demonstrate that the TOYO high pressure positive displacement pump design (reversing valves and hollow balls) is suitable for transfer of Settler Tank sludge from the K West (KW) Basin to the Cold Vacuum Drying Facility (CVDF) (~500 ft). As requested the by the K Basins Sludge Treatment Project (STP) the simulant is comprised of non-radioactive (and non-uranium) constituents.

  5. Scientific basis for risk assessment and management of uranium mill tailings

    SciTech Connect (OSTI)

    Not Available

    1986-01-01

    A National Research Council study panel, convened by the Board on Radioactive Waste Management, has examined the scientific basis for risk assessment and management of uranium mill tailings and issued this final report containing a number of recommendations. Chapter 1 provides a brief introduction to the problem. Chapter 2 examines the processes of uranium extraction and the mechanisms by which radionuclides and toxic chemicals contained in the ore can enter the environment. Chapter 3 is devoted to a review of the evidence on health risks associated with radon and its decay products. Chapter 4 provides a consideration of conventional and possible new technical alternatives for tailings management. Chapter 5 explores a number of issues of comparative risk, provides a brief history of uranium mill tailings regulation, and concludes with a discussion of choices that must be made in mill tailing risk management. 211 refs., 30 figs., 27 tabs.

  6. Breckinridge Project, initial effort. Report XI, Volume V. Critical review of the design basis. [Critical review

    SciTech Connect (OSTI)

    1982-01-01

    Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.

  7. Criteria for calculating the efficiency of HEPA filters during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1994-12-01

    We have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  8. Materials Data on BaSi23 (SG:223) by Materials Project

    SciTech Connect (OSTI)

    Kristin Persson

    2015-05-16

    Computed materials data using density functional theory calculations. These calculations determine the electronic structure of bulk materials by solving approximations to the Schrodinger equation. For more information, see https://materialsproject.org/docs/calculations

  9. Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables

    SciTech Connect (OSTI)

    Lisa Harvego; Brion Bennett

    2011-11-01

    U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. U.S. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool to develop the radioactive waste management basis.

  10. AUDIT REPORT Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National

    Energy Savers [EERE]

    Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory DOE/IG-0941 July 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report: "Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory" BACKGROUND A primary

  11. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, T.M.; Rohay, A.C. [Pacific Northwest National Laboratory, Richland, WA (United States); Youngs, R.R. [Geomatrix Consultants, Inc., Oakland, CA (United States); Costantino, C.J. [C.J. Costantino and Associates, Valley, NY (United States); Miller, L.F. [U.S. Department of Energy, Office of River Protection, Richland, WA (United States)

    2008-07-01

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energy's (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were reevaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretary's approval of the final seismic criteria in the summer of 2007, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities. The technical basis for the certification of seismic design criteria resulted from a two-year Seismic Boreholes Project that planned, collected, and analyzed geological data from four new boreholes drilled to depths of approximately 1400 feet below ground surface on the WTP site. A key uncertainty identified in the 2005 analyses was the velocity contrasts between the basalt flows and sedimentary interbeds below the WTP. The absence of directly-measured seismic shear wave velocities in the sedimentary interbeds resulted in the use of a wider and more conservative range of velocities in the 2005 analyses. The Seismic Boreholes Project was designed to directly measure the velocities and velocity contrasts in the basalts and sediments below the WTP, reanalyze the ground motion response, and assess the level of conservatism in the 2005 seismic design criteria. The characterization and analysis effort included 1) downhole measurements of the velocity properties (including uncertainties) of the basalt/interbed sequences, 2) confirmation of the geometry of the contact between the various basalt and interbedded sediments through examination of retrieved core from the core-hole and data collected through geophysical logging of each borehole, and 3) prediction of ground motion response to an earthquake using newly acquired and historic data. The data and analyses reflect a significant reduction in the uncertainty in shear wave velocities below the WTP and result in a significantly lower spectral acceleration (i.e., ground motion). The updated ground motion response analyses and corresponding design response spectra reflect a 25% lower peak horizontal acceleration than reflected in the 2005 design criteria. These results provide confidence that the WTP seismic design criteria are conservative. (authors)

  12. Beyond-Design-Basis-Accidents Passive Containment-Cooling Spray System

    SciTech Connect (OSTI)

    Karameldin, Aly; Temraz, Hassan M. Elsawy; Ibrahim, Nady Attia [Atomic Energy Authority (Egypt)

    2001-10-15

    The proposed safety feature considered in this study aims to increase the safety margins of nuclear power plants by proposed water tanks located inside or outside the upper zone of the containment to be utilized for (a) residual heat removal of the reactor in case of station blackout or in case of normal reactor shutdown and (b) beyond-design-basis accidents, in which core melt and debris-concrete interaction take place, associated with accumulative containment pressure increase and partial loss of the active systems. The proposed passive containment system can be implemented by a special mechanism, which can allow the pressurization of the water in the tanks and therefore can enable an additional spray system to start in case of increasing the containment pressure over a certain value just below the design pressure. A conservative case study is that of a Westinghouse 3411-MW(thermal) power station, where the proposed passive containment cooling spray system (PCCSS) will start at a pressure of 6 bars and terminate at a pressure of 3 bars. A one-dimensional lumped model is postulated to describe the thermal and hydraulic process behavior inside the containment after a beyond-design-basis accident. The considered parameters are the spray mass flow rate, the initial droplet diameters, fuel-cooling time, and the ultimate containment pressure. The overall heat and mass balance inside the containment are carried out, during both the containment depressurization (by the spraying system) and pressurization (by the residual energies). The results show that the design of the PCCSS is viable and has a capability to maintain the containment below the design pressure passively for the required grace period of 72 h. Design curves of the proposed PCCSS indicate the effect of the spray flow rate and cooling time on the total sprayed volume during the grace period of 72 h. From these curves it can be concluded that for the grace period of 72 h, the required tank volumes are 3800 and 4700 m{sup 3}, corresponding to fuel-cooling times (time after shutdown) of two weeks and one week, respectively. This large quantity of water serves as an ultimate heat sink available for the residual heat removal in the case of station blackout. The optimal spraying droplet diameter, travel, and mass flow rate are 3 mm, 30 m, and 100 to 125 kg/s, respectively.

  13. New method of determining the current carrier concentration in a substance in the state of superconductivity

    SciTech Connect (OSTI)

    Golotyuk, F.P.

    1985-08-02

    This report proposes a fundamentally new solution to the problem of determining the current carrier concentration in a substance. The basis of the corresponding experimental method is a theory that considers the electron drift energy when considering the oscillatory processes in certain circuits.

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

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

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

  15. Technical Basis for Radiological Emergency Plan Annex for WTD Emergency Response Plan: West Point Treatment Plant

    SciTech Connect (OSTI)

    Hickey, Eva E.; Strom, Daniel J.

    2005-08-01

    Staff of the King County Wastewater Treatment Division (WTD) have concern about the aftermath of a radiological dispersion event (RDE) leading to the introduction of significant quantities of radioactive material into the combined sanitary and storm sewer system in King County, Washington. Radioactive material could come from the use of a radiological dispersion device (RDD). RDDs include "dirty bombs" that are not nuclear detonations but are explosives designed to spread radioactive material (National Council on Radiation Protection and Measurements (NCRP) 2001). Radioactive material also could come from deliberate introduction or dispersion of radioactive material into the environment, including waterways and water supply systems. This document, Volume 3 of PNNL-15163 is the technical basis for the Annex to the West Point Treatment Plant (WPTP) Emergency Response Plan related to responding to a radiological emergency at the WPTP. The plan primarily considers response to radioactive material that has been introduced in the other combined sanitary and storm sewer system from a radiological dispersion device, but is applicable to any accidental or deliberate introduction of materials into the system.

  16. Solution to PDEs using radial basis function finite-differences (RBF-FD) on multiple GPUs

    SciTech Connect (OSTI)

    Bollig, Evan F.; Flyer, Natasha; Erlebacher, Gordon

    2012-08-30

    This paper presents parallelization strategies for the radial basis function-finite difference (RBF-FD) method. As a generalized finite differencing scheme, the RBF-FD method functions without the need for underlying meshes to structure nodes. It offers high-order accuracy approximation and scales as O(N) per time step, with N being with the total number of nodes. To our knowledge, this is the first implementation of the RBF-FD method to leverage GPU accelerators for the solution of PDEs. Additionally, this implementation is the first to span both multiple CPUs and multiple GPUs. OpenCL kernels target the GPUs and inter-processor communication and synchronization is managed by the Message Passing Interface (MPI). We verify our implementation of the RBF-FD method with two hyperbolic PDEs on the sphere, and demonstrate up to 9x speedup on a commodity GPU with unoptimized kernel implementations. On a high performance cluster, the method achieves up to 7x speedup for the maximum problem size of 27,556 nodes.

  17. APPARATUS FOR THE MASS ANALYSIS OF PLASMA ON A CONTINUOUS BASIS

    DOE Patents [OSTI]

    Neidigh, R.V.

    1963-07-01

    An apparatus for the mass analysis of plasmas on a continuous basis is described. The apparatus comprises a pair of parallel electrodes in a tubular member which serve as a velocity-selecting region for ions drawn by an accelerating potential through a tapered nose cone affixed to the tubular member. The magnetic force and electrostatic forces in the velocity-selecting region are made equal and opposite in direction to prevent the ionic species from striking either of the electrodes as they traverse the region. A pair of parallel plates is positioned within the tubular member and in alignment with the electrodes, but displaced slightly so as not to be seen by direct light coming through the entrance slit of the nose cone, and one of these plates serves as a collector plate. This collector plate is coupled to the vertical amplifier of an oscilloscope or other recorder to provide a continuous indication of the ionic coinposition of the plasma under analysis. ( DELTA EC)

  18. Technical Basis for Certification of Seismic Design Criteria for the Waste Treatment Plant, Hanford, Washington

    SciTech Connect (OSTI)

    Brouns, Thomas M.; Rohay, Alan C.; Youngs, Robert R.; Costantino, Carl J.; Miller, Lewis F.

    2008-02-28

    In August 2007, Secretary of Energy Samuel W. Bodman approved the final seismic and ground motion criteria for the Waste Treatment and Immobilization Plant (WTP) at the Department of Energys (DOE) Hanford Site. Construction of the WTP began in 2002 based on seismic design criteria established in 1999 and a probabilistic seismic hazard analysis completed in 1996. The design criteria were re-evaluated in 2005 to address questions from the Defense Nuclear Facilities Safety Board (DNFSB), resulting in an increase by up to 40% in the seismic design basis. DOE announced in 2006 the suspension of construction on the pretreatment and high-level waste vitrification facilities within the WTP to validate the design with more stringent seismic criteria. In 2007, the U.S. Congress mandated that the Secretary of Energy certify the final seismic and ground motion criteria prior to expenditure of funds on construction of these two facilities. With the Secretarys approval of the final seismic criteria this past summer, DOE authorized restart of construction of the pretreatment and high-level waste vitrification facilities.

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

    SciTech Connect (OSTI)

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

    2009-05-01

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

  20. Using compliance audits as the basis for developing an effective mechanical integrity program

    SciTech Connect (OSTI)

    Kiihne, E.J.; Mannan, M. [RMT/Jones and Neuse, Inc., Austin, TX (United States)

    1996-08-01

    The OSHA Process Safety Management (PSM) rule requires all covered facilities to conduct a compliance audit every three years. In addition, all the audit findings must be resolved within a reasonable time period. The process industry as a whole is lagging behind in compliance with mechanical integrity program requirements as demonstrated by the high number of OSHA citations issued to-date on mechanical integrity-related issues. This paper analyzes the findings of several PSM compliance audits and develops recommendations for developing effective mechanical integrity programs. The six explicit requirements of mechanical integrity, i.e. covered equipment, written procedures, training, inspection and testing, equipment deficiencies, and quality assurance are analyzed in the following manner: Number of OSHA citations in mechanical integrity and the distribution of these citations between the six specific requirements. Comparison of the OSHA citations with the audit findings from PSM compliance audits conducted by the authors. Using the conclusions from the OSHA citations and PSM compliance audits as a basis for developing effective mechanical integrity programs.

  1. Application of Radial Basis Functional Link Networks to Exploration for Proterozoic Mineral Deposits in Central Iran

    SciTech Connect (OSTI)

    Behnia, Pouran [Geological Survey of Iran, Geomatics Department (Iran, Islamic Republic of)], E-mail: pouranb@yahoo.com

    2007-06-15

    The metallogeny of Central Iran is characterized mainly by the presence of several iron, apatite, and uranium deposits of Proterozoic age. Radial Basis Function Link Networks (RBFLN) were used as a data-driven method for GIS-based predictive mapping of Proterozoic mineralization in this area. To generate the input data for RBFLN, the evidential maps comprising stratigraphic, structural, geophysical, and geochemical data were used. Fifty-eight deposits and 58 'nondeposits' were used to train the network. The operations for the application of neural networks employed in this study involve both multiclass and binary representation of evidential maps. Running RBFLN on different input data showed that an increase in the number of evidential maps and classes leads to a larger classification sum of squared error (SSE). As a whole, an increase in the number of iterations resulted in the improvement of training SSE. The results of applying RBFLN showed that a successful classification depends on the existence of spatially well distributed deposits and nondeposits throughout the study area.

  2. Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

    SciTech Connect (OSTI)

    OHara, J.M.; Higgins, J.C.

    2010-01-31

    Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and importance of automation in new and future plants, guidance is needed to enable the NRC staff to conduct safety reviews of the human factors engineering (HFE) aspects of modern automation. The objective of the research described in this report was to develop guidance for reviewing the operator's interface with automation. We first developed a characterization of the important HFE aspects of automation based on how it is implemented in current systems. The characterization included five dimensions: Level of automation, function of automation, modes of automation, flexibility of allocation, and reliability of automation. Next, we reviewed literature pertaining to the effects of these aspects of automation on human performance and the design of human-system interfaces (HSIs) for automation. Then, we used the technical basis established by the literature to develop design review guidance. The guidance is divided into the following seven topics: Automation displays, interaction and control, automation modes, automation levels, adaptive automation, error tolerance and failure management, and HSI integration. In addition, we identified insights into the automaton design process, operator training, and operations.

  3. Award Fee Determination Scorecard Contractor: Bechtel National, Inc. (BNI)

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

    Award Fee Determination Scorecard Contractor: Bechtel National, Inc. (BNI) Contract: Design, Construction, and Commissioning of the Hanford Tank Waste Treatment & Immobilization Plant Contract Number: DE-AC27-01RV14136 Award Fee Period: July 1, 2014 to December 31, 2014 Basis of Evaluation: 2014-B Performance Evaluation and Measurement Plan Award Fee Available: $6,300,000 Award Fee Earned: $4,095,000 (65.0%) Incentive B.1 - Award Fee-Project Management - Good The fee for Project Management

  4. AWARD FEE DETERMINATION SCORECARD Contractor: Restoration Services...

    Office of Environmental Management (EM)

    Basis of Evaluation: FY14 Award Fee Plan for Restoration Services, Inc.; Portsmouth Environmental Technical Services II Award Fee Available: 349,708.00 Award Fee Earned:...

  5. Alternative methods to determine headwater benefits

    SciTech Connect (OSTI)

    Bao, Y.S.; Perlack, R.D.; Sale, M.J.

    1997-11-10

    In 1992, the Federal Energy Regulatory Commission (FERC) began using a Flow Duration Analysis (FDA) methodology to assess headwater benefits in river basins where use of the Headwater Benefits Energy Gains (HWBEG) model may not result in significant improvements in modeling accuracy. The purpose of this study is to validate the accuracy and appropriateness of the FDA method for determining energy gains in less complex basins. This report presents the results of Oak Ridge National Laboratory`s (ORNL`s) validation of the FDA method. The validation is based on a comparison of energy gains using the FDA method with energy gains calculated using the MWBEG model. Comparisons of energy gains are made on a daily and monthly basis for a complex river basin (the Alabama River Basin) and a basin that is considered relatively simple hydrologically (the Stanislaus River Basin). In addition to validating the FDA method, ORNL was asked to suggest refinements and improvements to the FDA method. Refinements and improvements to the FDA method were carried out using the James River Basin as a test case.

  6. Structural basis for effectiveness of siderophore-conjugated monocarbams against clinically relevant strains of Pseudomonas aeruginosa

    SciTech Connect (OSTI)

    Han, Seungil; Zaniewski, Richard P.; Marr, Eric S.; Lacey, Brian M.; Tomaras, Andrew P.; Evdokimov, Artem; Miller, J. Richard; Shanmugasundaram, Veerabahu

    2012-02-08

    Pseudomonas aeruginosa is an opportunistic Gram-negative pathogen that causes nosocomial infections for which there are limited treatment options. Penicillin-binding protein PBP3, a key therapeutic target, is an essential enzyme responsible for the final steps of peptidoglycan synthesis and is covalently inactivated by {beta}-lactam antibiotics. Here we disclose the first high resolution cocrystal structures of the P. aeruginosa PBP3 with both novel and marketed {beta}-lactams. These structures reveal a conformational rearrangement of Tyr532 and Phe533 and a ligand-induced conformational change of Tyr409 and Arg489. The well-known affinity of the monobactam aztreonam for P. aeruginosa PBP3 is due to a distinct hydrophobic aromatic wall composed of Tyr503, Tyr532, and Phe533 interacting with the gem-dimethyl group. The structure of MC-1, a new siderophore-conjugated monocarbam complexed with PBP3 provides molecular insights for lead optimization. Importantly, we have identified a novel conformation that is distinct to the high-molecular-weight class B PBP subfamily, which is identifiable by common features such as a hydrophobic aromatic wall formed by Tyr503, Tyr532, and Phe533 and the structural flexibility of Tyr409 flanked by two glycine residues. This is also the first example of a siderophore-conjugated triazolone-linked monocarbam complexed with any PBP. Energetic analysis of tightly and loosely held computed hydration sites indicates protein desolvation effects contribute significantly to PBP3 binding, and analysis of hydration site energies allows rank ordering of the second-order acylation rate constants. Taken together, these structural, biochemical, and computational studies provide a molecular basis for recognition of P. aeruginosa PBP3 and open avenues for future design of inhibitors of this class of PBPs.

  7. NNSA?s Computing Strategy, Acquisition Plan, and Basis for Computing Time Allocation

    SciTech Connect (OSTI)

    Nikkel, D J

    2009-07-21

    This report is in response to the Omnibus Appropriations Act, 2009 (H.R. 1105; Public Law 111-8) in its funding of the National Nuclear Security Administration's (NNSA) Advanced Simulation and Computing (ASC) Program. This bill called for a report on ASC's plans for computing and platform acquisition strategy in support of stockpile stewardship. Computer simulation is essential to the stewardship of the nation's nuclear stockpile. Annual certification of the country's stockpile systems, Significant Finding Investigations (SFIs), and execution of Life Extension Programs (LEPs) are dependent on simulations employing the advanced ASC tools developed over the past decade plus; indeed, without these tools, certification would not be possible without a return to nuclear testing. ASC is an integrated program involving investments in computer hardware (platforms and computing centers), software environments, integrated design codes and physical models for these codes, and validation methodologies. The significant progress ASC has made in the past derives from its focus on mission and from its strategy of balancing support across the key investment areas necessary for success. All these investment areas must be sustained for ASC to adequately support current stockpile stewardship mission needs and to meet ever more difficult challenges as the weapons continue to age or undergo refurbishment. The appropriations bill called for this report to address three specific issues, which are responded to briefly here but are expanded upon in the subsequent document: (1) Identify how computing capability at each of the labs will specifically contribute to stockpile stewardship goals, and on what basis computing time will be allocated to achieve the goal of a balanced program among the labs. (2) Explain the NNSA's acquisition strategy for capacity and capability of machines at each of the labs and how it will fit within the existing budget constraints. (3) Identify the technical challenges facing the program and a strategy to resolve them.

  8. Physics Basis for the Advanced Tokamak Fusion Power Plant ARIES-AT

    SciTech Connect (OSTI)

    S.C. Jardin; C.E. Kessel; T.K. Mau; R.L. Miller; F. Najmabadi; V.S. Chan; M.S. Chu; R. LaHaye; L.L. Lao; T.W. Petrie; P. Politzer; H.E. St. John; P. Snyder; G.M. Staebler; A.D. Turnbull; W.P. West

    2003-10-07

    The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A always equal to R/a = 4.0, an elongation and triangularity of kappa = 2.20, delta = 0.90 (evaluated at the separatrix surface), a toroidal beta of beta = 9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta of bN * 100 x b/(I(sub)P(MA)/a(m)B(T)) = 5.4. These beta values are chosen to be 10% below the ideal-MHD stability limit. The bootstrap-current fraction is fBS * I(sub)BS/I(sub)P = 0.91. This leads to a design with total plasma current I(sub)P = 12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m, respectively. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current-drive system consists of ICRF/FW for on-axis current drive and a lower-hybrid system for off-axis. Tran sport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented.

  9. Nuclear-Renewable Hybrid System Economic Basis for Electricity, Fuel, and Hydrogen

    SciTech Connect (OSTI)

    Charles Forsberg; Steven Aumeier

    2014-04-01

    Concerns about climate change and altering the ocean chemistry are likely to limit the use of fossil fuels. That implies a transition to a low-carbon nuclear-renewable electricity grid. Historically variable electricity demand was met using fossil plants with low capital costs, high operating costs, and substantial greenhouse gas emissions. However, the most easily scalable very-low-emissions generating options, nuclear and non-dispatchable renewables (solar and wind), are capital-intensive technologies with low operating costs that should operate at full capacities to minimize costs. No combination of fully-utilized nuclear and renewables can meet the variable electricity demand. This implies large quantities of expensive excess generating capacity much of the time. In a free market this results in near-zero electricity prices at times of high nuclear renewables output and low electricity demand with electricity revenue collapse. Capital deployment efficiency—the economic benefit derived from energy systems capital investment at a societal level—strongly favors high utilization of these capital-intensive systems, especially if low-carbon nuclear renewables are to replace fossil fuels. Hybrid energy systems are one option for better utilization of these systems that consumes excess energy at times of low prices to make some useful product.The economic basis for development of hybrid energy systems is described for a low-carbon nuclear renewable world where much of the time there are massivequantities of excess energy available from the electric sector.Examples include (1) high-temperature electrolysis to generate hydrogen for non-fossil liquid fuels, direct use as a transport fuel, metal reduction, etc. and (2) biorefineries.Nuclear energy with its concentrated constant heat output may become the enabling technology for economically-viable low-carbon electricity grids because hybrid nuclear systems may provide an economic way to produce dispatachable variable electricity with economic base-load operation of the reactor.

  10. Categorical Exclusion Determinations: Tennessee | Department...

    Energy Savers [EERE]

    February 26, 2016 CX-100506 Categorical Exclusion Determination Biofuel Micro-Refineries ... Low-Viscosity Oils for Automotive Engine and Rear Axle Lubrication for 4% Improved ...

  11. CX-012200: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Determination of Excess Real Property CX(s) Applied: B1.36 Date: 05/01/2014 Location(s): Colorado Offices(s): Legacy Management

  12. CX-010689: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Generic CX Determination for Financial Assistance Awards CX(s) Applied: Unknown Date: 07/17/2013 Location(s): Illinois Offices(s): Chicago Office

  13. Categorical Exclusion Determinations: Environmental Management...

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

    ... September 13, 2011 CX-006990: Categorical Exclusion Determination Synthesis and Characterization of Coatings by Chemical Solution Deposition Methods CX(s) Applied: B3.6 Date: 09...

  14. Inferential determination of various properties of a gas mixture

    DOE Patents [OSTI]

    Morrow, Thomas B.; Behring, II, Kendricks A.

    2007-03-27

    Methods for inferentially determining various properties of a gas mixture, when the speed of sound in the gas is known at an arbitrary temperature and pressure. The method can be applied to natural gas mixtures, where the known parameters are the sound speed, temperature, pressure, and concentrations of any dilute components of the gas. The method uses a set of reference gases and their calculated density and speed of sound values to estimate the density of the subject gas. Additional calculations can be made to estimate the molecular weight of the subject gas, which can then be used as the basis for heating value calculations. The method may also be applied to inferentially determine density and molecular weight for gas mixtures other than natural gases.

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

    SciTech Connect (OSTI)

    Ferrada, Juan J

    2012-02-01

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

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

    SciTech Connect (OSTI)

    Ferrada, Juan J [ORNL

    2011-01-01

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

  17. Method of determining glass durability

    DOE Patents [OSTI]

    Jantzen, C.M.; Pickett, J.B.; Brown, K.G.; Edwards, T.B.

    1998-12-08

    A process is described for determining one or more leachate concentrations of one or more components of a glass composition in an aqueous solution of the glass composition by identifying the components of the glass composition, including associated oxides, determining a preliminary glass dissolution estimator, {Delta}G{sub p}, based upon the free energies of hydration for the component reactant species, determining an accelerated glass dissolution function, {Delta}G{sub a}, based upon the free energy associated with weak acid dissociation, {Delta}G{sub a}{sup WA}, and accelerated matrix dissolution at high pH, {Delta}G{sub a}{sup SB} associated with solution strong base formation, and determining a final hydration free energy, {Delta}G{sub f}. This final hydration free energy is then used to determine leachate concentrations for elements of interest using a regression analysis and the formula log{sub 10}(N C{sub i}(g/L))=a{sub i} + b{sub i}{Delta}G{sub f}. The present invention also includes a method to determine whether a particular glass to be produced will be homogeneous or phase separated. The present invention is also directed to methods of monitoring and controlling processes for making glass using these determinations to modify the feedstock materials until a desired glass durability and homogeneity is obtained. 4 figs.

  18. Method of determining glass durability

    DOE Patents [OSTI]

    Jantzen, Carol Maryanne; Pickett, John Butler; Brown, Kevin George; Edwards, Thomas Barry

    1998-01-01

    A process for determining one or more leachate concentrations of one or more components of a glass composition in an aqueous solution of the glass composition by identifying the components of the glass composition, including associated oxides, determining a preliminary glass dissolution estimator, .DELTA.G.sub.p, based upon the free energies of hydration for the component reactant species, determining an accelerated glass dissolution function, .DELTA.G.sub.a, based upon the free energy associated with weak acid dissociation, .DELTA.G.sub.a.sup.WA, and accelerated matrix dissolution at high pH, .DELTA.G.sub.a.sup.SB associated with solution strong base formation, and determining a final hydration free energy, .DELTA.G.sub.f. This final hydration free energy is then used to determine leachate concentrations for elements of interest using a regression analysis and the formula log.sub.10 (N C.sub.i (g/L))=a.sub.i +b.sub.i .DELTA.G.sub.f. The present invention also includes a method to determine whether a particular glass to be produced will be homogeneous or phase separated. The present invention is also directed to methods of monitoring and controlling processes for making glass using these determinations to modify the feedstock materials until a desired glass durability and homogeneity is obtained.

  19. Office of Enterprse Assessments Review of the West Valley Demonstration Project Emergency Management Program Technical Basis and Emergency Preparedness

    Energy Savers [EERE]

    Office of Enterprise Assessments Review of the West Valley Demonstration Project Emergency Management Program Technical Basis and Emergency Preparedness December 2014 Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy Table of Contents Acronyms ..................................................................................................................................................... ii 1.0 Purpose

  20. Categorical Exclusion Determinations: Pennsylvania | Department...

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

    August 3, 2015 CX-100321 Categorical Exclusion Determination VOLTTRON Compatible Whole Building root-Fault Detection and Diagnosis Award Number: DE-EE0007135 CX(s) Applied: A9, ...

  1. CX-100604 Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Final Determination of Coverage for Miscellaneous Refrigeration Products RIN 1904-AC66 CX(s) Applied: A6 EERE-Buildings Technology Program Date: 05/04/2016 Location(s): Nationwide Office(s): Golden Field Office

  2. CX-000768: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Determining the Variability of Continuous Mercury Monitors at Low Mercury LevelsCX(s) Applied: B3.6Date: 02/07/2010Location(s): Grand Forks, North DakotaOffice(s): Fossil Energy, National Energy Technology Laboratory

  3. CX-008905: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Optimizing Accuracy of Determinations of Carbon Dioxide Storage Capacity and Permanence CX(s) Applied: A1, A9, B3.6 Date: 08/29/2012 Location(s): Wyoming Offices(s): National Energy Technology Laboratory

  4. CX-010776: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Advanced Test Reactor (ATR) Primary Coolant Leak Rate Determination System Equipment Replacement CX(s) Applied: B2.2 Date: 07/24/2013 Location(s): Idaho Offices(s): Nuclear Energy

  5. CX-010493: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Determining Distribution Coefficients by Surface-Enhanced Raman Spectroscopy (SERS) CX(s) Applied: B3.6 Date: 05/14/2013 Location(s): South Carolina Offices(s): Savannah River Operations Office

  6. Categorical Exclusion Determinations: Wisconsin | Department...

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

    ... March 4, 2015 CX-100191 Categorical Exclusion Determination Cost-Optimized Modular Helical Rotors Turbine-Generator System for Small Hydro Power Plants Award Number: DE-EE0006927 ...

  7. Categorical Exclusion Determinations: Nationwide | Department...

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

    March 25, 2016 CX-100584 Categorical Exclusion Determination Data Collection and Comparison with Forecasted Sales of Five Lamp Types RIN NA CX(s) Applied: A6 EERE-Buildings ...

  8. Categorical Exclusion Determinations: Massachusetts | Department...

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

    December 3, 2015 CX-100413 Categorical Exclusion Determination The French Modular Impoundment Award Number: DE-FOA-0007244 CX(s) Applied: A9, B3.6 Wind and Water Power Technologies ...

  9. CX-012121: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Notice of Preliminary Determination of Energy Savings for ANSI/ASHRAE/IES Standard 90.1-2013 CX(s) Applied: A6 Date: 04/25/2014 Location(s): CX: none Offices(s): Golden Field Office

  10. CX-004264: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Phase II, Determination of Uranium in GroundwaterCX(s) Applied: B3.8Date: 09/27/2010Location(s): Richland, WashingtonOffice(s): Environmental Management, Office of River Protection-Richland Office

  11. Genetic basis of resistance to trauma in inbred strains of mice

    SciTech Connect (OSTI)

    Radojicic, C.; Andric, B.; Simovic, M.; Dujic, A.; Marinkovic, D. )

    1990-02-01

    In this study the resistance to mechanical, thermal, and radiation trauma in four inbred strains of mice (AKR, BALB/c, CBA, and C57Bl/6) was compared with the degree of genetic resemblance, by analyzing the allozyme variabilities of these strains. It was shown that the highest degree of genetic resemblance was among CBA and AKR strains, which correlated with a similar degree of resistance to trauma. On the other hand, BALB/c and C57Bl/6 strains expressed significant differences, both genetically and with respect to the responses to trauma. The hypothesis is introduced that the genetic determination of the resistance to trauma is based on: (a) a polygenic control of general physiological homeostasis, with the possibility that (b) some specific genes or single loci may contribute more than others to such adaptations of the strains tested.

  12. Technical Basis for Physical Fidelity of NRC Control Room Training Simulators for Advanced Reactors

    SciTech Connect (OSTI)

    Minsk, Brian S.; Branch, Kristi M.; Bates, Edward K.; Mitchell, Mark R.; Gore, Bryan F.; Faris, Drury K.

    2009-10-09

    The objective of this study is to determine how simulator physical fidelity influences the effectiveness of training the regulatory personnel responsible for examination and oversight of operating personnel and inspection of technical systems at nuclear power reactors. It seeks to contribute to the U.S. Nuclear Regulatory Commission’s (NRC’s) understanding of the physical fidelity requirements of training simulators. The goal of the study is to provide an analytic framework, data, and analyses that inform NRC decisions about the physical fidelity requirements of the simulators it will need to train its staff for assignment at advanced reactors. These staff are expected to come from increasingly diverse educational and experiential backgrounds.

  13. Technical Basis for Evaluating Surface Barriers to Protect Groundwater from Deep Vadose Zone Contamination

    SciTech Connect (OSTI)

    Fayer, Michael J.; Ward, Anderson L.; Freedman, Vicky L.

    2010-02-03

    This document presents a strategy for evaluating the effectiveness of surface barriers for site-specific deep vadose zone remediation. The strategy provides a technically defensible approach to determine the depth to which a surface barrier can effectively isolate contaminants in the vadose at a specific site as a function of subsurface properties, contaminant distribution, barrier design, and infiltration control performance. The strategy also provides an assessment of additional data and information needs with respect to surface barrier performance for deep vadose zone applications. The strategy addresses the linkage between surface barriers and deep vadose zone in situ remediation activities, monitoring issues, and emerging science, technology, and regulatory objectives. In short, the report documents the existing knowledge base, identifies knowledge needs (based on data gaps), and suggests tasks whose outcomes will address those knowledge needs. More important, the report serves as a starting point to engage the regulator and stakeholder community on the viability of deploying surface barriers for deep vadose zone contamination. As that engagement unfolds, a systematic methodology can be formalized and instituted. The strategy is focused on deep vadose zone contamination and the methods needed to determine the impact to groundwater from those deep vadose zone contaminants. Processes that affect surface barrier performance, recharge in the areas surrounding the surface barrier, and the near-surface vadose zone beneath the barrier are acknowledged but are not addressed by this strategy. In addition, the collection of site-specific data on contaminant distribution and geologic structure and properties are programmatic responsibilities and are not provided by this strategy.

  14. Gender determination of avian embryo

    DOE Patents [OSTI]

    Daum, Keith A.; Atkinson, David A.

    2002-01-01

    Disclosed is a method for gender determination of avian embryos. During the embryo incubation process, the outer hard shells of eggs are drilled and samples of allantoic fluid are removed. The allantoic fluids are directly introduced into an ion mobility spectrometer (IMS) for analysis. The resulting spectra contain the relevant marker peaks in the positive or negative mode which correlate with unique mobilities which are sex-specific. This way, the gender of the embryo can be determined.

  15. Structural basis for allosteric regulation of human ribonucleotide reductase by nucleotide-induced oligomerization

    SciTech Connect (OSTI)

    Fairman, James Wesley; Wijerathna, Sanath Ranjan; Ahmad, Md Faiz; Xu, Hai; Nakano, Ryo; Jha, Shalini; Prendergast, Jay; Welin, R. Martin; Flodin, Susanne; Roos, Annette; Nordlund, Pr; Li, Zongli; Walz, Thomas; Dealwis, Chris Godfrey

    2011-07-25

    Ribonucleotide reductase (RR) is an {alpha}{sub n}{beta}{sub n} (RR1-RR2) complex that maintains balanced dNTP pools by reducing NDPs to dNDPs. RR1 is the catalytic subunit, and RR2 houses the free radical required for catalysis. RR is allosterically regulated by its activator ATP and its inhibitor dATP, which regulate RR activity by inducing oligomerization of RR1. Here, we report the first X-ray structures of human RR1 bound to TTP alone, dATP alone, TTP-GDP, TTP-ATP, and TTP-dATP. These structures provide insights into regulation of RR by ATP or dATP. At physiological dATP concentrations, RR1 forms inactive hexamers. We determined the first X-ray structure of the RR1-dATP hexamer and used single-particle electron microscopy to visualize the {alpha}{sub 6}-{beta}{beta}'-dATP holocomplex. Site-directed mutagenesis and functional assays confirm that hexamerization is a prerequisite for inhibition by dATP. Our data indicate a mechanism for regulating RR activity by dATP-induced oligomerization.

  16. Structural Basis for Allosteric Regulation of Human Ribonucleotide Reductase by Nucleotide-induced Oligomerization

    SciTech Connect (OSTI)

    J Fairman; S Wijerathna; M Ahmad; H Xu; R nakano; S jha; J Prendergast; R Welin; S Flodin; et al.

    2011-12-31

    Ribonucleotide reductase (RR) is an {alpha}{sub n}{beta}{sub n} (RR1-RR2) complex that maintains balanced dNTP pools by reducing NDPs to dNDPs. RR1 is the catalytic subunit, and RR2 houses the free radical required for catalysis. RR is allosterically regulated by its activator ATP and its inhibitor dATP, which regulate RR activity by inducing oligomerization of RR1. Here, we report the first X-ray structures of human RR1 bound to TTP alone, dATP alone, TTP-GDP, TTP-ATP, and TTP-dATP. These structures provide insights into regulation of RR by ATP or dATP. At physiological dATP concentrations, RR1 forms inactive hexamers. We determined the first X-ray structure of the RR1-dATP hexamer and used single-particle electron microscopy to visualize the {alpha}{sub 6}-{beta}{beta}'-dATP holocomplex. Site-directed mutagenesis and functional assays confirm that hexamerization is a prerequisite for inhibition by dATP. Our data indicate a mechanism for regulating RR activity by dATP-induced oligomerization.

  17. Draft Function Allocation Framework and Preliminary Technical Basis for Advanced SMR Concepts of Operations

    SciTech Connect (OSTI)

    Jacques Hugo; John Forester; David Gertman; Jeffrey Joe; Heather Medema; Julius Persensky; April Whaley

    2013-04-01

    This report presents preliminary research results from the investigation in to the development of new models and guidance for concepts of operations (ConOps) in advanced small modular reactor (aSMR) designs. In support of this objective, three important research areas were included: operating principles of multi-modular plants, functional allocation models and strategies that would affect the development of new, non-traditional concept of operations, and the requiremetns for human performance, based upon work domain analysis and current regulatory requirements. As part of the approach for this report, we outline potential functions, including the theoretical and operational foundations for the development of a new functional allocation model and the identification of specific regulatory requirements that will influence the development of future concept of operations. The report also highlights changes in research strategy prompted by confirmationof the importance of applying the work domain analysis methodology to a reference aSMR design. It is described how this methodology will enrich the findings from this phase of the project in the subsequent phases and help in identification of metrics and focused studies for the determination of human performance criteria that can be used to support the design process.

  18. Structural basis of cargo membrane protein discrimination by the human COPII coat machinery

    SciTech Connect (OSTI)

    Mancias, Joseph D.; Goldberg, Jonathan

    2008-11-18

    Genomic analysis shows that the increased complexity of trafficking pathways in mammalian cells involves an expansion of the number of SNARE, Rab and COP proteins. Thus, the human genome encodes four forms of Sec24, the cargo selection subunit of the COPII vesicular coat, and this is proposed to increase the range of cargo accommodated by human COPII-coated vesicles. In this study, we combined X-ray crystallographic and biochemical analysis with functional assays of cargo packaging into COPII vesicles to establish molecular mechanisms for cargo discrimination by human Sec24 subunits. A conserved IxM packaging signal binds in a surface groove of Sec24c and Sec24d, but the groove is occluded in the Sec24a and Sec24b subunits. Conversely, LxxLE class transport signals and the DxE signal of VSV glycoprotein are selectively bound by Sec24a and Sec24b subunits. A comparative analysis of crystal structures of the four human Sec24 isoforms establishes the structural determinants for discrimination among these transport signals, and provides a framework to understand how an expansion of coat subunits extends the range of cargo proteins packaged into COPII-coated vesicles.

  19. Structural Basis of Cargo Membrane Protein Discrimination by the Human COPll Coat Machinery

    SciTech Connect (OSTI)

    Mancias, J.; Goldberg, J

    2008-01-01

    Genomic analysis shows that the increased complexity of trafficking pathways in mammalian cells involves an expansion of the number of SNARE, Rab and COP proteins. Thus, the human genome encodes four forms of Sec24, the cargo selection subunit of the COPII vesicular coat, and this is proposed to increase the range of cargo accommodated by human COPII-coated vesicles. In this study, we combined X-ray crystallographic and biochemical analysis with functional assays of cargo packaging into COPII vesicles to establish molecular mechanisms for cargo discrimination by human Sec24 subunits. A conserved IxM packaging signal binds in a surface groove of Sec24c and Sec24d, but the groove is occluded in the Sec24a and Sec24b subunits. Conversely, LxxLE class transport signals and the DxE signal of VSV glycoprotein are selectively bound by Sec24a and Sec24b subunits. A comparative analysis of crystal structures of the four human Sec24 isoforms establishes the structural determinants for discrimination among these transport signals, and provides a framework to understand how an expansion of coat subunits extends the range of cargo proteins packaged into COPII-coated vesicles.

  20. MEANS FOR DETERMINING CENTRIFUGE ALIGNMENT

    DOE Patents [OSTI]

    Smith, W.Q.

    1958-08-26

    An apparatus is presented for remotely determining the alignment of a centrifuge. The centrifage shaft is provided with a shoulder, upon which two followers ride, one for detecting radial movements, and one upon the shoulder face for determining the axial motion. The followers are attached to separate liquid filled bellows, and a tube connects each bellows to its respective indicating gage at a remote location. Vibrations produced by misalignment of the centrifuge shaft are transmitted to the bellows, and tbence through the tubing to the indicator gage. This apparatus is particularly useful for operation in a hot cell where the materials handled are dangerous to the operating personnel.

  1. Structural Basis for Ligand Recognition and Discrimination of a Quorum-quenching Antibody

    SciTech Connect (OSTI)

    Kirchdoerfer, Robert N.; Garner, Amanda L.; Flack, Caralyn E.; Mee, Jenny M.; Horswill, Alexander R.; Janda, Kim D.; Kaufmann, Gunnar F.; Wilson, Ian A.

    2011-09-16

    In the postantibiotic era, available treatment options for severe bacterial infections caused by methicillin-resistant Staphylococcus aureus have become limited. Therefore, new and innovative approaches are needed to combat such life-threatening infections. Virulence factor expression in S. aureus is regulated in a cell density-dependent manner using 'quorum sensing,' which involves generation and secretion of autoinducing peptides (AIPs) into the surrounding environment to activate a bacterial sensor kinase at a particular threshold concentration. Mouse monoclonal antibody AP4-24H11 was shown previously to blunt quorum sensing-mediated changes in gene expression in vitro and protect mice from a lethal dose of S. aureus by sequestering the AIP signal. We have elucidated the crystal structure of the AP4-24H11 Fab in complex with AIP-4 at 2.5 {angstrom} resolution to determine its mechanism of ligand recognition. A key GluH95 provides much of the binding specificity through formation of hydrogen bonds with each of the four amide nitrogens in the AIP-4 macrocyclic ring. Importantly, these structural data give clues as to the interactions between the cognate staphylococcal AIP receptors AgrC and the AIPs, as AP4-24H11 {center_dot} AIP-4 binding recapitulates features that have been proposed for AgrC-AIP recognition. Additionally, these structural insights may enable the engineering of AIP cross-reactive antibodies or quorum quenching vaccines for use in active or passive immunotherapy for prevention or treatment of S. aureus infections.

  2. Categorical Exclusion Determinations: Health, Safety, and Security...

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

    Health, Safety, and Security Categorical Exclusion Determinations: Health, Safety, and Security Categorical Exclusion Determinations issued by Health, Safety, and Security. ...

  3. Categorical Exclusion Determinations: Civilian Radioactive Waste...

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

    Civilian Radioactive Waste Management Categorical Exclusion Determinations: Civilian Radioactive Waste Management Categorical Exclusion Determinations issued by Civilian ...

  4. CX-100267 Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-100267 Categorical Exclusion Determination Next Generation Logistics Systems for Delivering Optimal Biomass Feedstocks to Biorefining Industries in...

  5. Categorical Exclusion Determinations: Strategic Petroleum Reserve...

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

    Strategic Petroleum Reserve Field Office Categorical Exclusion Determinations: Strategic Petroleum Reserve Field Office Categorical Exclusion Determinations issued by Strategic ...

  6. CX-100144 Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-100144 Categorical Exclusion Determination Solar and Distributed Generation as Key Elements in Meeting Vermont's Comprehensive Energy Plan...

  7. Categorical Exclusion Determinations: Office of Electricity Delivery...

    Office of Environmental Management (EM)

    Electricity Delivery and Energy Reliability Categorical Exclusion Determinations: Office of Electricity Delivery and Energy Reliability Categorical Exclusion Determinations issued ...

  8. CX-100363 Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-100363 Categorical Exclusion Determination Marine Algae Industrialization Consortium (MAGIC): Combining biofuel and high-value bioproducts to...

  9. Categorical Exclusion Determinations: Natural Gas Regulation...

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

    Natural Gas Regulation Categorical Exclusion Determinations: Natural Gas Regulation Categorical Exclusion Determinations issued by Natural Gas Regulation. DOCUMENTS AVAILABLE FOR ...

  10. Adjudicative Guidelines for Determining Eligibility for Access...

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

    Adjudicative Guidelines for Determining Eligibility for Access to Classified Information Adjudicative Guidelines for Determining Eligibility for Access to Classified Information ...

  11. Categorical Exclusion Determinations: Carlsbad Field Office ...

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

    Carlsbad Field Office Categorical Exclusion Determinations: Carlsbad Field Office Categorical Exclusion Determinations issued by Carlsbad Field Office. DOCUMENTS AVAILABLE FOR ...

  12. Categorical Exclusion Determinations: Energy Technology Engineering...

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

    Energy Technology Engineering Center Categorical Exclusion Determinations: Energy Technology Engineering Center Categorical Exclusion Determinations issued by Energy Technology ...

  13. Plasma digital density determining device

    DOE Patents [OSTI]

    Sprott, Julien C.; Lovell, Thomas W.; Holly, Donald J.

    1976-01-01

    The density of a decaying plasma in an electrically conducting enclosure is determined by applying an excitation to the cavity formed by the enclosure and counting digitally the number of resonant frequencies traversed by the combination of the cavity and the decaying plasma.

  14. CX-002602: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Determining Optimal Fuel Performance in Adapting Onsite Electrical Generation Platforms to Operate on Producer Gas from Fuels of OpportunityCX(s) Applied: A9, A11Date: 12/11/2009Location(s): Minneapolis, MinnesotaOffice(s): Energy Efficiency and Renewable Energy, National Energy Technology Laboratory

  15. CX-002600: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Determining Optimal Fuel Performance in Adapting Onsite Electrical Generation Platforms to Operate on Producer Gas from Fuels of OpportunityCX(s) Applied: B3.6Date: 12/11/2009Location(s): Minneapolis, MinnesotaOffice(s): Energy Efficiency and Renewable Energy, National Energy Technology Laboratory

  16. CX-002599: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Determining Optimal Fuel Performance in Adapting Onsite Electrical Generation Platforms to Operate on Producer Gas from Fuels of OpportunityCX(s) Applied: B3.6Date: 12/11/2009Location(s): Berkeley, CaliforniaOffice(s): Energy Efficiency and Renewable Energy, National Energy Technology Laboratory

  17. CX-002598: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Determining Optimal Fuel Performance in Adapting Onsite Electrical Generation Platforms to Operate on Producer Gas from Fuels of OpportunityCX(s) Applied: B3.6Date: 12/11/2009Location(s): Morris, MinnesotaOffice(s): Energy Efficiency and Renewable Energy, National Energy Technology Laboratory

  18. CX-002601: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Determining Optimal Fuel Performance in Adapting Onsite Electrical Generation Platforms to Operate on Producer Gas from Fuels of OpportunityCX(s) Applied: B3.6Date: 12/11/2009Location(s): Fridley, MinnesotaOffice(s): Energy Efficiency and Renewable Energy, National Energy Technology Laboratory

  19. CX-011193: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Categorical Exclusion Determination for Indoor, Small- and Pilot-Scale Research and Development CX(s) Applied: A9, B1.7, B3.6, B3.10, B3.12, B3.15, B5.1, B5.15 Date: 08/05/2013 Location(s): California Offices(s): Berkeley Site Office

  20. CX-008738: Categorical Exclusion Determination

    Office of Energy Efficiency and Renewable Energy (EERE)

    Determination of Microstructure and Chemical State Changes in Ion-Irradiated Fuels and Structural Components with a High Kinetic Energy Electron Detector – Illinois Institute of Technology CX(s) Applied: B3.6 Date: 05/22/2012 Location(s): Idaho Offices(s): Idaho Operations Office

  1. CX-013440: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Record of Categorical Exclusion Determination to Replace Piping Header at Bryan Mound RWIS and RWIP (BM-MM-1027) CX(s) Applied: B1.3Date: 02/18/2015 Location(s): TexasOffices(s): Strategic Petroleum Reserve Field Office

  2. CX-000373: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Measurements of 222 Radon, 220 Radon, and Carbon Dioxide Emissions in Natural Carbon Dioxide Fields in Wyoming: Monitoring, Verification, and Analysis Techniques for Determining Gas Transport and Caprock IntegrityCX(s) Applied: A1, A9, B3.6, B3.8Date: 11/20/2009Location(s): Laramie, WyomingOffice(s): Fossil Energy, National Energy Technology Laboratory

  3. CX-100312 Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Withdrawal of Proposed Determination Regarding Energy Conservation Program: Natural Draft Commercial Boilers RIN: 1904-AD01 CX(s) Applied: A5 EERE- Buildings Technology Program Date: 07/20/2015 Location(s): Nationwide Office(s): Golden Field Office

  4. CX-012693: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Experimental Determination and Mechanistic Modeling of Used Fuel Drying by Vacuum and Gas Circulation for Dry Cask Storage University of South Carolina CX(s) Applied: B3.6Date: 41869 Location(s): South CarolinaOffices(s): Nuclear Energy

  5. CX-100019: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Determination of Rare Earths in Geothermal Brines and Evaluation of Potential Extraction Techniques CX(s) Applied: A9, B3.1, B3.6 Date: 08/18/2014 Location(s): California Offices(s): Golden Field Office Technology Office: Geothermal Technologies Award Number: DE-EE0006750

  6. CX-100558 Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Final Determination of Coverage for Portable Air Conditioners (1904-AD02) RIN 1904-AD02 CX(s) Applied: A6 EERE-Buildings Technology Program Date: 03/03/2016 Location(s): Nationwide Office(s): Golden Field Office

  7. Long-Baseline Neutrino Experiment (LBNE)Water Cherenkov Detector Basis of Estimate Forms and Backup Documentation LBNE Far Site Internal Review (December 6-9, 2011)

    SciTech Connect (OSTI)

    Stewart J.; Diwan, M.; Dolph, J.; Novakova, P.; Sharma, R.; Stewart, J.; Viren, B.; Russo, T.; Kaducak, M.; Mantsch, P.; Paulos, B.; Feyzi, F.; Sullivan, G.; Bionta, R.; Fowler, J.; Warner, D.; Bahowick, S.; Van Berg, R.; Kearns, E.; Hazen, E.; Sinnis, G.; Sanchez, M.

    2011-12-09

    Basis of Estimate (BOE) forms and backup documentation developed for the Water Cherenkov Detector (WCD) option for the far detector of the Long Baseline Neutrino Experiment (LBNE)

  8. Award Fee Determination Scorecard Contractor: G4S Government Solutions, Inc. - Wackenhut Services

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

    Award Fee Determination Scorecard Contractor: G4S Government Solutions, Inc. - Wackenhut Services Incorporated (WSI) Contract: Protective Force Security Services Contract Number: DE-AC30-10CC60025 Award Period: October 1, 2013 - September 30, 2014 Basis of Evaluation: Award Fee Plan The contractor is required to provide, operate, and maintain an armed and uniformed protective force for the physical protection of U.S. Department of Energy (DOE) security interests and other such related duties at

  9. Range determination for scannerless imaging

    DOE Patents [OSTI]

    Muguira, Maritza Rosa; Sackos, John Theodore; Bradley, Bart Davis; Nellums, Robert

    2000-01-01

    A new method of operating a scannerless range imaging system (e.g., a scannerless laser radar) has been developed. This method is designed to compensate for nonlinear effects which appear in many real-world components. The system operates by determining the phase shift of the laser modulation, which is a physical quantity related physically to the path length between the laser source and the detector, for each pixel of an image.

  10. Method for determining gene knockouts

    DOE Patents [OSTI]

    Maranas, Costa D; Burgard, Anthony R; Pharkya, Priti

    2013-06-04

    A method for determining candidates for gene deletions and additions using a model of a metabolic network associated with an organism, the model includes a plurality of metabolic reactions defining metabolite relationships, the method includes selecting a bioengineering objective for the organism, selecting at least one cellular objective, forming an optimization problem that couples the at least one cellular objective with the bioengineering objective, and solving the optimization problem to yield at least one candidate.

  11. Method for determining gene knockouts

    DOE Patents [OSTI]

    Maranas, Costas D.; Burgard, Anthony R.; Pharkya, Priti

    2011-09-27

    A method for determining candidates for gene deletions and additions using a model of a metabolic network associated with an organism, the model includes a plurality of metabolic reactions defining metabolite relationships, the method includes selecting a bioengineering objective for the organism, selecting at least one cellular objective, forming an optimization problem that couples the at least one cellular objective with the bioengineering objective, and solving the optimization problem to yield at least one candidate.

  12. Tax Credits, Rebates & Savings | Department of Energy

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

    Tidal Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the rated...

  13. Search for: All records | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Water demands in excess of supplies have long been the norm in the west, and for more than a century water has been apportioned on a first-come, first-served basis. Unconventional ...

  14. Policy Analysis of Water Availability and Use Issues for Domestic...

    Office of Scientific and Technical Information (OSTI)

    Water demands in excess of supplies have long been the norm in the west, and for more than a century water has been apportioned on a first-come, first-served basis. Unconventional ...

  15. Alternative Fuels Data Center

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

    All conversion systems must be certified by the U.S. Environmental Protection Agency or the California Air Resources Board. Funds are available on a first-come, first-served basis. ...

  16. Tax Credits, Rebates & Savings | Department of Energy

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

    Digestion, Fuel Cells using Renewable Fuels Net Metering Net metering is available on a first-come, first-served basis until the cumulative generating capacity of net-metered...

  17. Tax Credits, Rebates & Savings | Department of Energy

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

    Cells using Renewable Fuels Net Metering Net metering in Virginia is available on a first-come, first-served basis until the rated generating capacity owned and operated by...

  18. Noble REMC- Buisness Energy Efficiency Rebate Incentives

    Broader source: Energy.gov [DOE]

    Noble REMC, with the Wabash Vally Power Association offers business rebate incentives through its POWER MOVES program.  Incentives are available on a first-come, first-served basis. View the...

  19. Puerto Rico- Green Energy Fund Tier I Incentive Program

    Broader source: Energy.gov [DOE]

    With funding from Puerto Rico's Green Energy Fund, Tier I rebates are available for photovoltaic (PV) and wind systems up to and including 100 kW in capacity on a first-come, first-served basis. ...

  20. Tax Credits, Rebates & Savings | Department of Energy

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

    Agricultural Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the rated...

  1. New Hampshire Electric Co-op- Solar Hot Water Rebate Program

    Broader source: Energy.gov [DOE]

    Systems must be pre-approved to receive a rebate. Program funds are available on a first-come, first-served basis. See the program website listed above for more information and an application for...

  2. Tax Credits, Rebates & Savings | Department of Energy

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

    State Government Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the...

  3. Middle School Science Bowl Registration | Argonne National Laboratory

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

    one team. A team is made up of 4-5 middle school students. All teams should have a coach mentoring and managing the team. Teams are selected on a first come first serve basis....

  4. Agenda: INFRASTRUCTURE CONSTRAINTS

    Broader source: Energy.gov [DOE]

    People who whish to make a pubic comment for the Quadrennial Energy Review record may sign up to speak at the meeting on a first-come-first-served basis, for up to five minutes.

  5. Dakota Electric Association- Residential Energy Efficiency Rebate Program

    Broader source: Energy.gov [DOE]

    Limited rebate funds are available, and rebates are awarded on a first-come, first-served basis. Some incentives vary by the efficiency of the purchased equipment. Detailed program requirements a...

  6. Tax Credits, Rebates & Savings | Department of Energy

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

    Fuel Cells using Non-Renewable Fuels Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering is available on a first-come, first-served basis...

  7. Tax Credits, Rebates & Savings | Department of Energy

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

    Industrial Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until the rated...

  8. Tax Credits, Rebates & Savings | Department of Energy

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

    Municipal Solid Waste Tax Credits, Rebates & Savings Tax Credits, Rebates & Savings Net Metering Net metering in Virginia is available on a first-come, first-served basis until...

  9. Net Metering

    Broader source: Energy.gov [DOE]

    Net metering in Virginia is available on a first-come, first-served basis until the rated generating capacity owned and operated by customer-generators reaches 1% of an electric distribution...

  10. Evaluation of the Scaling of the APEX-1000 Test Facility to AP1000 for Design Basis Events

    SciTech Connect (OSTI)

    Wright, Richard F.; Gagnon, Andre; Skinner, Jesse; Groome, John

    2004-07-01

    The AP1000 is a 1000 MWe advanced nuclear power plant that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs. The AP1000 relies heavily on the 600 MWe AP600 which received design certification in 1999. A critical part of the AP600 design certification process involved the testing of the passive safety systems. A one-fourth height, one-fourth pressure test facility, APEX-600, was constructed at the Oregon State University to study design basis events, and to provide a body of data to be used to validate the computer models used to analyze the AP600. This facility was extensively modified to reflect the design changes for AP1000 including higher power in the electrically heated rods representing the reactor core, and changes in the size of the pressurizer, core makeup tanks and automatic depressurization system. Several design basis events have been simulated at APEX-1000 including double-ended direct vessel injection (DEDVI) line break, 2-inch cold leg break, and inadvertent actuation of the automatic depressurization system. These events were analyzed as part of the AP1000 safety analysis using the NOTRUMP computer code. Applying the scaling factors that were used to size the APEX-1000 facility, the test results can be compared to the NOTRUMP plant simulations. These comparisons indicate the similarity between the design basis events in AP1000 and APEX-1000, the adequacy of the scaling of APEX-1000, and the applicability of the NOTRUMP code. (authors)

  11. Basis to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for the Stand-off Experiments Range

    SciTech Connect (OSTI)

    Michael Sandvig

    2011-01-01

    The purpose of this report is to provide the basis and the documentation to demonstrate general compliance with the National Emission Standard for Hazardous Air Pollutants (NESHAPS) 40 CFR 61 Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities, (the Standard) for outdoor linear accelerator operations at the Idaho National Laboratory (INL) Stand-off Experiments Range (SOX). The intent of this report is to inform and gain acceptance of this methodology from the governmental bodies regulating the INL.

  12. Liquid chromatographic determination of water

    DOE Patents [OSTI]

    Fortier, Nancy E.; Fritz, James S.

    1990-11-13

    A sensitive method for the determination of water in the presence of common interferences is presented. The detection system is based on the effect of water on the equilibrium which results from the reaction aryl aldehydes, such as cinnamaldehyde and methanol in the eluent to form cinnamaldehyde dimethylacetal, plus water. This equilibrium is shifted in a catalytic atmosphere of a hydrogen ion form past column reactor. The extent of the shift and the resulting change in absorbance are proportional to the amount of water present.

  13. Liquid chromatographic determination of water

    DOE Patents [OSTI]

    Fortier, N.E.; Fritz, J.S.

    1990-11-13

    A sensitive method for the determination of water in the presence of common interferences is presented. The detection system is based on the effect of water on the equilibrium which results from the reaction aryl aldehydes, such as cinnamaldehyde and methanol in the eluent to form cinnamaldehyde dimethylacetal, plus water. This equilibrium is shifted in a catalytic atmosphere of a hydrogen ion form past column reactor. The extent of the shift and the resulting change in absorbance are proportional to the amount of water present. 1 fig.

  14. RECORD OF CATEGORICAL EXCLUSION DETERMINATION

    Energy Savers [EERE]

    geological boring near 9 structure locations along the existing ED2-ED5 230-kV transmission line located in Pinal County, Arizona RECORD OF CATEGORICAL EXCLUSION DETERMINATION A, Proposed Action: Western proposes to do geologic borings within our right-of-way near structures 21/5,22/5,23/6,25/4,26/5,27/6,28/5,29/5 & 30/4 along the existing ED2-ED5 230-kV transmission line. This project involves accessing each bore hole location with a auger/drill rig and light crew trucks, setting up the

  15. Crystal face temperature determination means

    DOE Patents [OSTI]

    Nason, D.O.; Burger, A.

    1994-11-22

    An optically transparent furnace having a detection apparatus with a pedestal enclosed in an evacuated ampule for growing a crystal thereon is disclosed. Temperature differential is provided by a source heater, a base heater and a cold finger such that material migrates from a polycrystalline source material to grow the crystal. A quartz halogen lamp projects a collimated beam onto the crystal and a reflected beam is analyzed by a double monochromator and photomultiplier detection spectrometer and the detected peak position in the reflected energy spectrum of the reflected beam is interpreted to determine surface temperature of the crystal. 3 figs.

  16. Determination of a mutational spectrum

    DOE Patents [OSTI]

    Thilly, William G.; Keohavong, Phouthone

    1991-01-01

    A method of resolving (physically separating) mutant DNA from nonmutant DNA and a method of defining or establishing a mutational spectrum or profile of alterations present in nucleic acid sequences from a sample to be analyzed, such as a tissue or body fluid. The present method is based on the fact that it is possible, through the use of DGGE, to separate nucleic acid sequences which differ by only a single base change and on the ability to detect the separate mutant molecules. The present invention, in another aspect, relates to a method for determining a mutational spectrum in a DNA sequence of interest present in a population of cells. The method of the present invention is useful as a diagnostic or analytical tool in forensic science in assessing environmental and/or occupational exposures to potentially genetically toxic materials (also referred to as potential mutagens); in biotechnology, particularly in the study of the relationship between the amino acid sequence of enzymes and other biologically-active proteins or protein-containing substances and their respective functions; and in determining the effects of drugs, cosmetics and other chemicals for which toxicity data must be obtained.

  17. NREL: Climate Neutral Research Campuses - Determine Baseline...

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

    Determine Baseline Energy Consumption To create a climate action plan for your research campus, begin by determining current energy consumption and the resulting greenhouse gas ...

  18. Categorical Exclusion Determinations: Pantex Site Office | Department...

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

    March 18, 2015 CX-013480: Categorical Exclusion Determination Lightning Mapping Array ... December 27, 2013 CX-011714: Categorical Exclusion Determination Lightning Mapping Array ...

  19. Categorical Exclusion Determinations: West Valley Demonstration...

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

    September 8, 2011 CX-009529: Categorical Exclusion Determination WVDP-2011-01 Erdman Brook ... September 8, 2011 CX-006811: Categorical Exclusion Determination Erdman Brook Erosion ...

  20. Categorical Exclusion Determinations: Office of Energy Efficiency...

    Office of Environmental Management (EM)

    Energy Efficiency and Renewable Energy Categorical Exclusion Determinations: Office of Energy Efficiency and Renewable Energy Categorical Exclusion Determinations issued by Energy ...

  1. Determinations and Coverage Rulemakings | Department of Energy

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

    Determinations and Coverage Rulemakings Determinations and Coverage Rulemakings The Energy Policy and Conservation Act (EPCA) (42 U.S.C. 6292(a)) contains a list of 19 consumer ...

  2. CX-011104: Categorical Exclusion Determination | Department of...

    Energy Savers [EERE]

    Coupled Thermo-Mechanical and Photo-Chemical Degradation Mechanisms that Determine ... coupled thermo-mechanical and photo-chemical degradation mechanisms that determine ...

  3. CX-007095: Categorical Exclusion Determination | Department of...

    Office of Environmental Management (EM)

    Determination CX-007095: Categorical Exclusion Determination Paving the Way with Propane: The AutoGas Corridor Development Program CX(s) Applied: B5.1 Date: 10132011...

  4. CX-007096: Categorical Exclusion Determination | Department of...

    Office of Environmental Management (EM)

    Determination CX-007096: Categorical Exclusion Determination Paving the Way with Propane: The AutoGas Corridor Development Program CX(s) Applied: B5.1 Date: 10132011...

  5. CX-011970: Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-011970: Categorical Exclusion Determination Tuscarora Phase II Geothermal Observation Wells CX(s) Applied: B3.7 Date: 02222013 Location(s):...

  6. CX-001087: Categorical Exclusion Determination | Department of...

    Office of Environmental Management (EM)

    87: Categorical Exclusion Determination CX-001087: Categorical Exclusion Determination State of Nevada Energy Efficiency and Conservation Block Grant - American Recovery and...

  7. CX-006491: Categorical Exclusion Determination | Department of...

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

    Categorical Exclusion Determination CX-006491: Categorical Exclusion Determination Photovoltaic Manufacturing Consortium CX(s) Applied: B3.6 Date: 09012011 Location(s): Florida...

  8. CX-007867: Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-007867: Categorical Exclusion Determination Northeast Photovoltaic Regional Training Provider CX(s) Applied: A9, A11, B5.16 Date: 01272012...

  9. Categorical Exclusion Determinations: Florida | Department of...

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

    September 16, 2015 CX-100377 Categorical Exclusion Determination US-INDIA CONSORTIUM FOR ... September 8, 2015 CX-100367 Categorical Exclusion Determination US-India Consortium for ...

  10. CX-003164: Categorical Exclusion Determination | Department of...

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

    Categorical Exclusion Determination CX-003164: Categorical Exclusion Determination Optimization of Biomass Production Across a Landscape CX(s) Applied: A9 Date: 07262010...

  11. CX-004247: Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-004247: Categorical Exclusion Determination Carolina Blue Skies Initiative CX(s) Applied: A1, B5.1 Date: 10142010 Location(s): Indian Trail,...

  12. CX-008810: Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-008810: Categorical Exclusion Determination One Nevada Optimization of Microwave Telecommunication System CX(s) Applied: B1.19, B4.6 Date: 05292012...

  13. Categorical Exclusion Determinations: Kentucky | Department of...

    Office of Environmental Management (EM)

    ... May 14, 2013 CX-010281: Categorical Exclusion Determination Low Temperature Nitrous Oxide ... Determination Cost-Effective Treatment of Flowback and Produced Water via an ...

  14. Crystal face temperature determination means

    DOE Patents [OSTI]

    Nason, Donald O.; Burger, Arnold

    1994-01-01

    An optically transparent furnace (10) having a detection apparatus (29) with a pedestal (12) enclosed in an evacuated ampule (16) for growing a crystal (14) thereon. Temperature differential is provided by a source heater (20), a base heater (24) and a cold finger (26) such that material migrates from a polycrystalline source material (18) to grow the crystal (14). A quartz halogen lamp (32) projects a collimated beam (30) onto the crystal (14) and a reflected beam (34) is analyzed by a double monochromator and photomultiplier detection spectrometer (40) and the detected peak position (48) in the reflected energy spectrum (44) of the reflected beam (34) is interpreted to determine surface temperature of the crystal (14).

  15. Geochemistry Technical Basis Document

    SciTech Connect (OSTI)

    Benedict, Jr, F Christopher; Rose, Timothy P; Thomas, James M; Waddell, Richard; Jacobson, Roger

    2004-03-18

    This document presents a methodology whereby geochemical data can more effectively contribute to the development , calibration, and verification of groundwater flow and slute transport models for the Underground Test Area (UGTA) Project.

  16. design basis threat

    National Nuclear Security Administration (NNSA)

    training courses, and additional full-time instructors.

    • The shift to an "Elite Forces," or Tactical Response Force (TRF) model, to transform NNSA's protective forces...

    • Development of Site-Specific Soil Design Basis Earthquake (DBE) Parameters for the Integrated Waste Treatment Unit (IWTU)

      SciTech Connect (OSTI)

      Payne, Suzette

      2008-08-01

      Horizontal and vertical PC 3 (2,500 yr) Soil Design Basis Earthquake (DBE) 5% damped spectra, corresponding time histories, and strain-compatible soil properties were developed for the Integrated Waste Treatment Unit (IWTU). The IWTU is located at the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Laboratory (INL). Mean and 84th percentile horizontal DBE spectra derived from site-specific site response analyses were evaluated for the IWTU. The horizontal and vertical PC 3 (2,500 yr) Soil DBE 5% damped spectra at the 84th percentile were selected for Soil Structure Interaction (SSI) analyses at IWTU. The site response analyses were performed consistent with applicable Department of Energy (DOE) Standards, recommended guidance of the Nuclear Regulatory Commission (NRC), American Society of Civil Engineers (ASCE) Standards, and recommendations of the Blue Ribbon Panel (BRP) and Defense Nuclear Facilities Safety Board (DNFSB).

    • After Action Report:Idaho National Laboratory (INL) 2014 Multiple Facility Beyond Design Basis (BDBE) Evaluated Drill October 21, 2014

      SciTech Connect (OSTI)

      V. Scott Barnes

      2014-12-01

      On October 21, 2014, Idaho National Laboratory (INL), in coordination with local jurisdictions, and Department of Energy (DOE) Idaho Operations Office (DOE ID) conducted an evaluated drill to demonstrate the ability to implement the requirements of DOE O 151.1C, “Comprehensive Emergency Management System” when responding to a beyond design basis event (BDBE) scenario as outlined in the Office of Health, Safety, and Security Operating Experience Level 1 letter (OE-1: 2013-01). The INL contractor, Battelle Energy Alliance, LLC (BEA), in coordination with CH2M-WG Idaho, LLC (CWI), and Idaho Treatment Group LLC (ITG), successfully demonstrated appropriate response measures to mitigate a BDBE event that would impact multiple facilities across the INL while protecting the health and safety of personnel, the environment, and property. Offsite response organizations participated to demonstrate appropriate response measures.

    • Representation of a complex Green function on a real basis: Generalization to a three-body system

      SciTech Connect (OSTI)

      Li Tieniu; Shakeshaft, Robin; Piraux, Bernard

      2003-05-01

      We develop further a new method for employing a set of real basis functions to represent the Green function at energies in the continuum, without regard for the asymptotic boundary conditions. The method is based on the analyticity of the Green function with respect to its underlying time scale. The diagonalization of large matrices is unnecessary. Although a large complex symmetric linear system of equations must be solved, this can be done with high stability and efficiency by using a generalization of the Cholesky decomposition of real positive definite symmetric matrices. We present results of test applications to {sup 1}S-wave electron scattering from a hydrogen atom and photodetachment of the negative hydrogen ion. The extension from two- to three-body collisions entails the use of projection operators to distinguish different groups of asymptotic channels.

    • 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

      SciTech Connect (OSTI)

      PACKER, M.J.

      1999-11-04

      Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  1. Ballistic projectile trajectory determining system

    DOE Patents [OSTI]

    Karr, T.J.

    1997-05-20

    A computer controlled system determines the three-dimensional trajectory of a ballistic projectile. To initialize the system, predictions of state parameters for a ballistic projectile are received at an estimator. The estimator uses the predictions of the state parameters to estimate first trajectory characteristics of the ballistic projectile. A single stationary monocular sensor then observes the actual first trajectory characteristics of the ballistic projectile. A comparator generates an error value related to the predicted state parameters by comparing the estimated first trajectory characteristics of the ballistic projectile with the observed first trajectory characteristics of the ballistic projectile. If the error value is equal to or greater than a selected limit, the predictions of the state parameters are adjusted. New estimates for the trajectory characteristics of the ballistic projectile are made and are then compared with actual observed trajectory characteristics. This process is repeated until the error value is less than the selected limit. Once the error value is less than the selected limit, a calculator calculates trajectory characteristics such a the origin and destination of the ballistic projectile. 8 figs.

  2. Ballistic projectile trajectory determining system

    DOE Patents [OSTI]

    Karr, Thomas J.

    1997-01-01

    A computer controlled system determines the three-dimensional trajectory of a ballistic projectile. To initialize the system, predictions of state parameters for a ballistic projectile are received at an estimator. The estimator uses the predictions of the state parameters to estimate first trajectory characteristics of the ballistic projectile. A single stationary monocular sensor then observes the actual first trajectory characteristics of the ballistic projectile. A comparator generates an error value related to the predicted state parameters by comparing the estimated first trajectory characteristics of the ballistic projectile with the observed first trajectory characteristics of the ballistic projectile. If the error value is equal to or greater than a selected limit, the predictions of the state parameters are adjusted. New estimates for the trajectory characteristics of the ballistic projectile are made and are then compared with actual observed trajectory characteristics. This process is repeated until the error value is less than the selected limit. Once the error value is less than the selected limit, a calculator calculates trajectory characteristics such a the origin and destination of the ballistic projectile.

  3. 2015 Secretarial Determination | Department of Energy

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

    Secretarial Determination 2015 Secretarial Determination On May 1, 2015, the Secretary of Energy determined that continued uranium transfers for cleanup services at the Portsmouth Gaseous Diffusion Plant and for down-blending of highly-enriched uranium to low-enriched uranium will not have an adverse material impact on the domestic uranium mining, conversion, or enrichment industry ("2015 Secretarial Determination"). This Determination covers continued transfers at the rates specified

  4. Comment on “Rethinking first-principles electron transport theories with projection operators: The problems caused by partitioning the basis set” [J. Chem. Phys. 139, 114104 (2013)

    SciTech Connect (OSTI)

    Brandbyge, Mads

    2014-05-07

    In a recent paper Reuter and Harrison [J. Chem. Phys. 139, 114104 (2013)] question the widely used mean-field electron transport theories, which employ nonorthogonal localized basis sets. They claim these can violate an “implicit decoupling assumption,” leading to wrong results for the current, different from what would be obtained by using an orthogonal basis, and dividing surfaces defined in real-space. We argue that this assumption is not required to be fulfilled to get exact results. We show how the current/transmission calculated by the standard Greens function method is independent of whether or not the chosen basis set is nonorthogonal, and that the current for a given basis set is consistent with divisions in real space. The ambiguity known from charge population analysis for nonorthogonal bases does not carry over to calculations of charge flux.

  5. Device For Determining Therophysical Properties Of A Multi-Component Gas At Arbitrary Temperature And Pressure

    DOE Patents [OSTI]

    Morrow, Thomas B.; Behring, II, Kendricks A.

    2005-02-01

    A computer product for determining thermodynamic properties of a natural gas hydrocarbon, when the speed of sound in the gas is known at an arbitrary temperature and pressure. Thus, the known parameters are the sound speed, temperature, pressure, and concentrations of any dilute components of the gas. The method uses a set of reference gases and their calculated density and speed of sound values to estimate the density of the subject gas. Additional calculations can be made to estimate the molecular weight of the subject gas, which can then be used as the basis for mass flow calculations, to determine the speed of sound at standard pressure and temperature, and to determine various thermophysical characteristics of the gas.

  6. Liquid Effluent Retention Facility (LERF) Final Hazard Category Determination

    SciTech Connect (OSTI)

    HUTH, L.L.

    2001-06-06

    The Liquid Effluent Retention Facility was designed to store 242-A Evaporator process condensate and other liquid waste streams for treatment at the 200 East Area Effluent Treatment Facility. The Liquid Effluent Retention Facility has been previously classified as a Category 3 Nonreactor Nuclear Facility. As defined in Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports (DOE 1992, DOE 1997), Category 3 Nuclear Facilities have the potential for significant localized (radiological) consequences. However, based on current facility design, operations, and radioactive constituent concentrations, the Liquid Effluent Retention Facility does not have the potential for significant localized (radiological) consequences and is categorized as a Radiological Facility. This report documents the final hazard categorization process performed in accordance with DOE Order 5480.23, Nuclear Safety Analysis Reports. This report describes the current configuration and operations of the Liquid Effluent Retention Facility. Also included is a preliminary hazard categorization, which is based on current and proposed radioactive and hazardous material inventories, a preliminary hazards and accident analysis, and a final hazard category determination. The results of the hazards and accident analysis, based on the current configuration and operations of the Liquid Effluent Retention Facility and the current and proposed radioactive and hazardous material inventories, demonstrate that the Liquid Effluent Retention Facility does not have the potential for significant localized (radiological) consequences. Based on the final hazard category analysis, the Liquid Effluent Retention Facility is a Radiological Facility. The final hazard category determination is based on a comparative evaluation of the consequence basis for the Category 3 threshold quantities to the calculated consequences for credible releases The basis for the Category 3 threshold quantities is 10 rem-equivalent man at 30 meters (98 feet) (DOE 1992, DOE 1997). The calculated 12 hour consequences to an individual located at 30 meters (98 feet) for two credible scenarios, spray release and a pool release, are 3.50 rem and 1.32 rem, respectively, which based upon the original hazard categorization criteria (DOE 1992) classified the Liquid Effluent Retention Facility as a Radiological Facility. Comparison of the calculated 24 hour consequences to an individual located at 30 meters (98 feet) for two credible scenarios, spray release and a pool release, 7.00 rem and 2.64 rem respectively, confirmed the Liquid Effluent Retention Facility classification as a Radiological Facility under the current hazard categorization criteria (DOE 1997). Both result in dose consequence values less than the allowable, 10 rem, meeting the requirements for categorizing the Liquid Effluent Retention Facility as a Radiological Facility.

  7. Categorical Exclusion Determinations: B1.36

    Broader source: Energy.gov [DOE]

    B1.36: Determinations of excess real propertyDeterminations that real property is excess to the needs of DOE and, in the case of acquired real property, the subsequent reporting of such...

  8. CX-004531: Categorical Exclusion Determination | Department of...

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

    Determination CX-004531: Categorical Exclusion Determination Surprise Valley Multiple Use Geothermal Development CX(s) Applied: A9, B3.1, B5.12 Date: 11242010 Location(s):...

  9. CX-100322 Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-100322 Categorical Exclusion Determination Plug and Play Photovoltaics for American Homes Award Number: DE-EE0006035 CX(s) Applied: A9, B3.6, B5.15...

  10. CX-100193 Categorical Exclusion Determination | Department of...

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

    Exclusion Determination CX-100193 Categorical Exclusion Determination Installation of Solar Panels at Municipal Owned Facilities Award Number: DE-EE0003195 CX(s) Applied: B5.1...

  11. Categorical Exclusion Determinations: Intelligence and Counterintelligence

    Energy Savers [EERE]

    | Department of Energy Intelligence and Counterintelligence Categorical Exclusion Determinations: Intelligence and Counterintelligence Categorical Exclusion Determinations issued by Intelligence and Counterintelligence. DOCUMENTS AVAILABLE FOR DOWNLOAD No downloads found for this office.

  12. Categorical Exclusion Determinations: Western Area Power Administration |

    Energy Savers [EERE]

    Department of Energy Administration Categorical Exclusion Determinations: Western Area Power Administration Categorical Exclusion Determinations issued by Western Area Power Administration. DOCUMENTS AVAILABLE FOR DOWNLOAD No downloads found for this office.

  13. CX-100317 Categorical Exclusion Determination | Department of...

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

    7 Categorical Exclusion Determination CX-100317 Categorical Exclusion Determination Solar Hot Water Project in Greenburgh, NY Award Number: DE-EE0003193 CX(s) Applied: B5.16...

  14. Establishing a Cost Basis for Converting the High Flux Isotope Reactor from High Enriched to Low Enriched Uranium Fuel

    SciTech Connect (OSTI)

    Primm, Trent; Guida, Tracey

    2010-02-01

    Under the auspices of the Global Threat Reduction Initiative Reduced Enrichment for Research and Test Reactors Program, the National Nuclear Security Administration /Department of Energy (NNSA/DOE) has, as a goal, to convert research reactors worldwide from weapons grade to non-weapons grade uranium. The High Flux Isotope Reactor (HFIR) at Oak Ridge National Lab (ORNL) is one of the candidates for conversion of fuel from high enriched uranium (HEU) to low enriched uranium (LEU). A well documented business model, including tasks, costs, and schedules was developed to plan the conversion of HFIR. Using Microsoft Project, a detailed outline of the conversion program was established and consists of LEU fuel design activities, a fresh fuel shipping cask, improvements to the HFIR reactor building, and spent fuel operations. Current-value costs total $76 million dollars, include over 100 subtasks, and will take over 10 years to complete. The model and schedule follows the path of the fuel from receipt from fuel fabricator to delivery to spent fuel storage and illustrates the duration, start, and completion dates of each subtask to be completed. Assumptions that form the basis of the cost estimate have significant impact on cost and schedule.

  15. Structural Basis for a Switch in Receptor Binding Specificity of Two H5N1 Hemagglutinin Mutants

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

    Zhu, Xueyong; Viswanathan, Karthik; Raman, Rahul; Yu, Wenli; Sasisekharan, Ram; Wilson, Ian A.

    2015-11-01

    Avian H5N1 influenza viruses continue to spread in wild birds and domestic poultry with sporadic infection in humans. Receptor binding specificity changes are a prerequisite for H5N1 viruses and other zoonotic viruses to be transmitted among humans. Previous reported hemagglutinin (HA) mutants from ferret-transmissible H5N1 viruses of A/Viet Nam/1203/04 and A/Indonesia/5/05 showed slightly increased, but still very weak, binding to human receptors. From mutagenesis and glycan array studies, we previously identified two H5N1 HA mutants that could more effectively switch receptor specificity to human-like α2-6 linked sialosides with avidity comparable to wild-type H5 HA binding to avian-like α2-3 linked sialosides.more »Here, crystal structures of these two H5 HA mutants free and in complex with human and avian glycan receptor analogues reveal the structural basis for their preferential binding to human receptors. These findings suggest continuous surveillance should be maintained to monitor and assess human-to-human transmission potential of H5N1 viruses.« less

  16. Criteria for calculating the efficiency of deep-pleated HEPA filters with aluminum separators during and after design basis accidents

    SciTech Connect (OSTI)

    Bergman, W.; First, M.W.; Anderson, W.L.; Gilbert, H.; Jacox, J.W.

    1995-02-01

    The authors have reviewed the literature on the performance of high efficiency particulate air (HEPA) filters under normal and abnormal conditions to establish criteria for calculating the efficiency of HEPA filters in a DOE nonreactor nuclear facility during and after a Design Basis Accident (DBA). This study is only applicable to the standard deep-pleated HEPA filter with aluminum separators as specified in ASME N509. The literature review included the performance of new filters and parameters that may cause deterioration in the filter performance such as filter age, radiation, corrosive chemicals, seismic and rough handling, high temperature, moisture, particle clogging, high air flow and pressure pulses. The deterioration of the filter efficiency depends on the exposure parameters; in severe exposure conditions the filter will be structurally damaged and have a residual efficiency of 0%. Despite the many studies on HEPA filter performance under adverse conditions, there are large gaps and limitations in the data that introduce significant error in the estimates of HEPA filter efficiencies under DBA conditions. Because of this limitation, conservative values of filter efficiency were chosen when there was insufficient data.

  17. Categorical Exclusion Determinations: Program and Field Offices |

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

    Department of Energy Determinations: Program and Field Offices Categorical Exclusion Determinations: Program and Field Offices This page contains links (below) to pages on DOE Program, Field, or Site Office websites containing the CX determinations required to be posted under this policy, and also some for which documentation and posting are optional, i.e., determinations involving classes of actions listed in Appendix A or made before the policy's effective date of November 2, 2009. You may

  18. NREL Programmatic NEPA Determinations | Department of Energy

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

    Programmatic NEPA Determinations NREL Programmatic NEPA Determinations The U.S. Department of Energy's (DOE) Office of Energy Efficiency and Renewable Energy has developed five Programmatic NEPA Determinations (PND) to address routine activities and ongoing research conducted at National Renewable Energy Laboratory (NREL) facilities. These determinations were conducted as part of a joint DOE and NREL NEPA Enhancement Project that was developed to help streamline the NEPA process for activities

  19. POLICY GUIDANCE MEMORANDUM #26 Official Worksite Determinations |

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

    Department of Energy 6 Official Worksite Determinations POLICY GUIDANCE MEMORANDUM #26 Official Worksite Determinations The following information is provided to assist in determinations of official worksites for remote workers. This guidance applies to Federal employees and employees hired under the Intergovernmental Personnel Act (IPA). PDF icon POLICY GUIDANCE MEMORANDUM #26 Official Worksite Determinations Responsible Contacts Ahtora Brooks Human Resource Specialists E-mail

  20. Categorical Exclusion Determinations: Oregon | Department of...

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

    Recovery Act: Crump Geyser - High Precision Geophysics & ... Novel Hybrid Microbial Electrochemical System for Efficient ... Determination Microchannel Solar Receiver Development Award ...

  1. Categorical Exclusion Determinations: Advanced Technology Vehicles

    Energy Savers [EERE]

    Manufacturing Loan Program | Department of Energy Technology Vehicles Manufacturing Loan Program Categorical Exclusion Determinations: Advanced Technology Vehicles Manufacturing Loan Program Categorical Exclusion Determinations issued by Advanced Technology Vehicles Manufacturing Loan Program. DOCUMENTS AVAILABLE FOR DOWNLOAD September 6, 2011 CX-006488: Categorical Exclusion Determination Chrysler Group LLC, Revised Specific Project Application 2, Retooling, Reequipping and Engineering

  2. Categorical Exclusion Determinations: NNSA-Proliferation Detection |

    Energy Savers [EERE]

    Department of Energy Proliferation Detection Categorical Exclusion Determinations: NNSA-Proliferation Detection Categorical Exclusion Determinations issued by NNSA-Proliferation Detection. DOCUMENTS AVAILABLE FOR DOWNLOAD September 17, 2010 CX-004080: Categorical Exclusion Determination Fisk University Nonproliferation Grant CX(s) Applied: B3.6 Date: 09/17/2010 Location(s): Tennessee Office(s): NNSA-Proliferation Detection

  3. Excitation of helium Rydberg states and doubly excited resonances in strong extreme ultraviolet fields: Full-dimensional quantum dynamics using exponentially tempered Gaussian basis sets

    SciTech Connect (OSTI)

    Kaprlov-?nsk, Petra Ruth; mydke, Jan; Department of Radiation and Chemical Physics, Institute of Physics, Academy of Sciences of the Czech Republic, Na Slovance 2, 182 21 Prague 8 ; Civi, Svatopluk

    2013-09-14

    Recently optimized exponentially tempered Gaussian basis sets [P. R. Kapralova-Zdanska and J. Smydke, J. Chem. Phys. 138, 024105 (2013)] are employed in quantitative simulations of helium absorption cross-sections and two-photon excitation yields of doubly excited resonances. Linearly polarized half-infinite and Gaussian laser pulses at wavelengths 3858 nm and large intensities up to 100 TW/cm{sup 2} are considered. The emphasis is laid on convergence of the results with respect to the quality of the Gaussian basis sets (typically limited by a number of partial waves, density, and spatial extent of the basis functions) as well as to the quality of the basis set of field-free states (typically limited by the maximum rotational quantum number and maximum excitation of the lower electron). Particular attention is paid to stability of the results with respect to varying complex scaling parameter. Moreover, the study of the dynamics is preceded by a thorough check of helium energies and oscillator strengths as they are obtained with the exponentially tempered Gaussian basis sets, being also compared with yet unpublished emission wavelengths measured in electric discharge experiments.

  4. Possible Methods to Estimate Core Location in a Beyond-Design-Basis Accident at a GE BWR with a Mark I Containment Stucture

    SciTech Connect (OSTI)

    Walston, S; Rowland, M; Campbell, K

    2011-07-27

    It is difficult to track to the location of a melted core in a GE BWR with Mark I containment during a beyond-design-basis accident. The Cooper Nuclear Station provided a baseline of normal material distributions and shielding configurations for the GE BWR with Mark I containment. Starting with source terms for a design-basis accident, methods and remote observation points were investigated to allow tracking of a melted core during a beyond-design-basis accident. The design of the GE BWR with Mark-I containment highlights an amazing poverty of expectations regarding a common mode failure of all reactor core cooling systems resulting in a beyond-design-basis accident from the simple loss of electric power. This design is shown in Figure 1. The station blackout accident scenario has been consistently identified as the leading contributor to calculated probabilities for core damage. While NRC-approved models and calculations provide guidance for indirect methods to assess core damage during a beyond-design-basis loss-of-coolant accident (LOCA), there appears to be no established method to track the location of the core directly should the LOCA include a degree of fuel melt. We came to the conclusion that - starting with detailed calculations which estimate the release and movement of gaseous and soluble fission products from the fuel - selected dose readings in specific rooms of the reactor building should allow the location of the core to be verified.

  5. Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high-strength steel cylinder

    SciTech Connect (OSTI)

    Rana, M.D.; Smith, J.H.; Tribolet, R.O.

    1997-11-01

    High-pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high-pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3 to 10 mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6 (o.d. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) x Design Pressure.

  6. Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high strength steel cylinder

    SciTech Connect (OSTI)

    Rana, M.D.; Smith, J.H.; Tribolet, R.O.

    1996-12-01

    High pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-Notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3mm to 10mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6(O.D. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) {times} Design Pressure.

  7. CX-000567: Categorical Exclusion Determination | Department of Energy

    Office of Environmental Management (EM)

    Energy Review of Safety Basis Development - May 6, 2013 CRAD, Review of Safety Basis Development - May 6, 2013 May 6, 2013 Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility (HSS CRAD 45-59, Rev. 0) The review will consider selected aspects of the development of safety basis for the Transuranic Waste Facility (TWF) to assess the extent to which safety is integrated into the design of the TWF in accordance with DOE directives; in particular,

  8. Evaluation of kinetic phosphorescence analysis for the determination of uranium

    SciTech Connect (OSTI)

    Croatto, P.V.; Frank, I.W.; Johnson, K.D.; Mason, P.B.; Smith, M.M.

    1997-12-01

    In the past, New Brunswick Laboratory (NBL) has used a fluorometric method for the determination of sub-microgram quantities of uranium. In its continuing effort to upgrade and improve measurement technology, NBL has evaluated the commercially-available KPA-11 kinetic phosphorescence analyzer (Chemchek, Richland, WA). The Chemchek KPA-11 is a bench-top instrument which performs single-measurement, quench-corrected analyses for trace uranium. It incorporates patented kinetic phosphorimetry techniques to measure and analyze sample phosphorescence as a function of time. With laser excitation and time-corrected photon counting, the KPA-11 has a lower detection limit than conventional fluorometric methods. Operated with a personal computer, the state-of-the-art KPA-11 offers extensive time resolution and phosphorescence lifetime capabilities for additional specificity. Interferences are thereby avoided while obtaining precise measurements. Routine analyses can be easily and effectively accomplished, with the accuracy and precision equivalent to the pulsed-laser fluorometric method presently performed at NBL, without the need for internal standards. Applications of kinetic phosphorimetry at NBL include the measurement of trace level uranium in retention tank, waste samples, and low-level samples. It has also been used to support other experimental activities at NBL by the measuring of nanogram amounts of uranium contamination (in blanks) in isotopic sample preparations, and the determining of elution curves of different ion exchange resins used for uranium purification. In many cases, no pretreatment of samples was necessary except to fume them with nitric acid, and then to redissolve and dilute them to an appropriate concentration with 1 M HNO{sub 3} before measurement. Concentrations were determined on a mass basis ({micro}g U/g of solution), but no density corrections were needed since all the samples (including the samples used for calibration) were in the same density matrix (1 M HNO{sub 3}). A statistical evaluation of the determination of uranium using kinetic phosphorimetry is described in this report, along with a discussion of the method, and an evaluation of the use of plastic versus quartz cuvettes. Measurement with a precision of {+-} 3--4% relative standard deviation (RSD) and an accuracy of better than {+-} 2% relative difference (RD) are obtained in the 0.0006 to 5 {micro}g U/g-solution range. The instrument detection limit is 0.04 ppb (4 x 10{sup {minus}5} {micro}g U/g solution) using quartz cells, and 0.11 ppb (11 x 10{sup {minus}5} {micro}g U/g solution) using disposable methacrylate cuvettes.

  9. Categorical Exclusion Determinations: Southeastern Power Administration |

    Energy Savers [EERE]

    Department of Energy Southeastern Power Administration Categorical Exclusion Determinations: Southeastern Power Administration Categorical Exclusion Determinations issued by Southeastern Power Administration. DOCUMENTS AVAILABLE FOR DOWNLOAD August 3, 2009 CX-000478: Categorical Exclusion Determination Proposed rate adjustment for the Jim Woodruff System CX(s) Applied: B4.3 Date: 08/03/2009 Location(s): Panhandle, Florida Office(s): Southeastern Power Administration

  10. CX-100327 Categorical Exclusion Determination | Department of...

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

    CX-100327 Categorical Exclusion Determination Proposed Rulemaking for Energy Conservation Standards for Commercial Water Heating Equipment RIN: 1904-AD34 CX(s)...

  11. CX-009019: Categorical Exclusion Determination | Department of...

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

    DEVELOPMENT AND FULL-SCALE TESTING CX-009001: Categorical Exclusion Determination Ammonia Sensors Based on Doped-Sol-Gel-Tipped Optical Fibers for Catalyst System Diagnostics

  12. Perlick: Noncompliance Determination (2013-SE-14001)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Perlick Corporation finding that freezer basic model HP24F does not comport with the energy conservation standards.

  13. Perlick: Noncompliance Determination (2013-SE-14002)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Perlick Corporation finding that refrigerator basic model HP48RR does not comport with the energy conservation standards.

  14. Hydac: Noncompliance Determination (2012-SE-4107)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Hydac Technology Corporation finding that a variety of electric motor basic models do not comport with the energy conservation standards.

  15. Mueller Streamline: Noncompliance Determination (2011-SW-2802)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Mueller Streamline Co. finding that faucet model 120-003NL does not comport with the water conservation standards.

  16. Whirlpool: Noncompliance Determination (2013-SE-1420)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Whirlpool Corporation finding that refrigerator-freezer basic model 8TAR81 does not comport with the energy conservation standards.

  17. CX-010763: Categorical Exclusion Determination | Department of...

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

    CX-010763: Categorical Exclusion Determination Nevada Desert Research Institute- Photovoltaic Installation CX(s) Applied: B5.16 Date: 07172013 Location(s): Nevada Offices(s):...

  18. CX-003980: Categorical Exclusion Determination | Department of...

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

    CX-003980: Categorical Exclusion Determination Integration of Advanced Logistical Systems ... a comprehensive biomass supply chain system through collecting and deliver of ...

  19. Categorical Exclusion Determinations: Golden Field Office | Department...

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

    Categorical Exclusion Determination U.S. Department of Energy Collegiate Entrepreneurship Prize Award Number: TBD FOA CX(s) Applied: A9 Date: 12222014 Location(s): CO...

  20. CX-006520: Categorical Exclusion Determination | Department of...

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

    CX-006520: Categorical Exclusion Determination High Energy Density Distributed Hydrostatic Direct Drive for Large Wind Turbine and Marine Hydro-Kinetic Device Applications CX(s) ...

  1. CX-003608: Categorical Exclusion Determination | Department of...

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

    CX-003608: Categorical Exclusion Determination Sustainable Algal Energy Production and Environmental Remediation CX(s) Applied: A9, B3.6 Date: 08252010 Location(s): Virginia ...

  2. CX-006863: Categorical Exclusion Determination | Department of...

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

    CX-006863: Categorical Exclusion Determination Production ... Minnesota Office(s): Energy Efficiency and Renewable ... aims to establish a sustainable supply of ...

  3. CX-001627: Categorical Exclusion Determination | Department of...

    Office of Environmental Management (EM)

    CX-001627: Categorical Exclusion Determination Test Reactor Cask Implementation CX(s) ... This proposed action is a process and facility modification. The Advanced Test Reactor ...

  4. Methods for threshold determination in multiplexed assays

    DOE Patents [OSTI]

    Tammero, Lance F. Bentley; Dzenitis, John M; Hindson, Benjamin J

    2014-06-24

    Methods for determination of threshold values of signatures comprised in an assay are described. Each signature enables detection of a target. The methods determine a probability density function of negative samples and a corresponding false positive rate curve. A false positive criterion is established and a threshold for that signature is determined as a point at which the false positive rate curve intersects the false positive criterion. A method for quantitative analysis and interpretation of assay results together with a method for determination of a desired limit of detection of a signature in an assay are also described.

  5. Categorical Exclusion Determinations: Idaho | Department of Energy

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

    ... June 18, 2015 CX-013839: Categorical Exclusion Determination Materials and Fuels Complex (MFC)-752 Analytical Laboratory Casting Laboratory Glovebox Heat Detection CX(s) Applied: ...

  6. CX-008761: Categorical Exclusion Determination | Department of...

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

    CX-008761: Categorical Exclusion Determination Surface Water and Groundwater Sampling Near the Naturita, Colorado Title I Uranium Mill Tailings Radiation Control Act (UMTRCA) ...

  7. CX-100596 Categorical Exclusion Determination | Department of...

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

    by DOE under the Assisting Federal Facilities with Energy Conservation ... This conditional NEPA determination applies solely to preliminary design and project planning ...

  8. CX-100343 Categorical Exclusion Determination | Department of...

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

    CX-100343 Categorical Exclusion Determination RPM Solar Asset Management Software Award ... Management to develop a cloud based software platform that manages the financial and ...

  9. CX-000321: Categorical Exclusion Determination | Department of...

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

    CX-000321: Categorical Exclusion Determination Kentucky Revision 2 - Green and Healthy ...232009 Location(s): Kentucky Office(s): Energy Efficiency and Renewable Energy, National ...

  10. CX-000322: Categorical Exclusion Determination | Department of...

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

    CX-000322: Categorical Exclusion Determination Kentucky Revision 2 - Green Bank of Kentucky Date: 11232009 Location(s): Kentucky Office(s): Energy Efficiency and Renewable ...

  11. Categorical Exclusion Determinations: National Energy Technology...

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

    Laboratory September 9, 2014 CX-012155: Categorical Exclusion Determination Subsea High Voltage Direct Current Connectors for Environmentally Safe and Reliable Powering of UDW... ...

  12. CX-004649: Categorical Exclusion Determination | Department of...

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

    The Painesville Municipal Power Vanadium Redox Battery Demonstration Program CX(s) ... CX-006145: Categorical Exclusion Determination Fact Sheet: Vanadium Redox Battery ...

  13. Categorical Exclusion Determinations: Oklahoma | Department of...

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

    ... June 17, 2013 CX-010520: Categorical Exclusion Determination Silica Polymer Initiator ... PetrophysicsTight Rock Characterization for Improved Stimulation and Production ...

  14. Felix Storch: Noncompliance Determination (2010-SCE-0111)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Felix Storch finding that basic model FS62, a compact upright freezer, does not comport with the energy conservation standards.

  15. Morris: Noncompliance Determination (2013-SE-5403)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Morris Products, Inc. finding that various models of metal halide lamp fixtures do not comport with the energy conservation standards.

  16. CX-006211: Categorical Exclusion Determination | Department of...

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

    Exclusion Determination Missouri Independent Energy Efficiency Program: Henniges Automotive - Process Air Compressor Upgrades CX(s) Applied: B5.1 Date: 07182011 Location(s):...

  17. CX-013404: Categorical Exclusion Determination | Department of...

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

    CX-013404: Categorical Exclusion Determination NARUCDOE Natural Gas Infrastructure and Liquefied Natural Gas Partnership CX(s) Applied: A9, A11 Date: 02092015 Location(s): ...

  18. CX-000294: Categorical Exclusion Determination | Department of...

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

    CX-000294: Categorical Exclusion Determination A Novel Biogas Desulphurization Sorbent ... gas, providing an essentially sulfur-free biogas for Direct Fuel Cell? power plants. ...

  19. CX-000293: Categorical Exclusion Determination | Department of...

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

    CX-000293: Categorical Exclusion Determination A Novel Biogas Desulphurization Sorbent ... gas, providing an essentially sulfur-free biogas for Direct Fuel Cell? power plants. ...

  20. CX-001856: Categorical Exclusion Determination | Department of...

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

    Exclusion Determination Rural Cooperative Geothermal Development Electric and Agriculture CX(s) Applied: B3.1 Date: 04282010 Location(s): Paisley, Oregon Office(s): Energy...

  1. Categorical Exclusion Determinations: Bonneville Power Administration...

    Energy Savers [EERE]

    Power Administration July 9, 2015 CX-013781: Categorical Exclusion Determination Acquisition of Multiple Access Road Easements for the Holcomb-Naselle No. 1 Transmission Line ...

  2. DNA Sequence Determinants Controlling Affinity, Stability and...

    Office of Scientific and Technical Information (OSTI)

    the Nucleoid Protein Fis Citation Details In-Document Search Title: DNA Sequence Determinants Controlling Affinity, Stability and Shape of DNA Complexes Bound by the Nucleoid ...

  3. CX-003703: Categorical Exclusion Determination | Department of...

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

    Determination Florida Hydrogen Initiative - Florida Institute of Technology (Interdisciplinary Hydrogen and Fuel Cell Technology Academic Program) CX(s) Applied: A9 Date: 09...

  4. CX-011250: Categorical Exclusion Determination | Department of...

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

    Determination Transforming Photovoltaic Installations Toward Dispatchable, Schedulable Energy Solutions CX(s) Applied: B3.6, B5.15 Date: 10172013 Location(s): Oregon...

  5. CX-100138 Categorical Exclusion Determination | Department of...

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

    CX-100138 Categorical Exclusion Determination Sacrificial Protective Coating Materials ... a chemically resistant and anti-fouling coating for low-cost Weak Black Liquor (WBL) ...

  6. Categorical Exclusion Determinations: North Carolina | Department...

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

    ... Texas, Massachusetts Offices(s): Golden Field Office November 27, 2013 CX-011733: Categorical Exclusion Determination Research Triangle Institute - High Operating Temperature ...

  7. Zoe Industries: Noncompliance Determination (2011-SW-2912)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Zoe Industries, Inc. finding that Giessdorf 150043 model, a showerhead, does not comport with the water conservation standards.

  8. Arelik A.?: Compliance Determination (2010-SE-0105)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Compliance Determination after test results revealed that Arelik's Blomberg BRFB1450 refrigerator-freezer complies with the applicable energy conservation standards.

  9. Categorical Exclusion Determinations: Nuclear Energy | Department...

    Energy Savers [EERE]

    ... June 17, 2015 CX-013826: Categorical Exclusion Determination Assessment of Aging Degradation Mechanisms of Alloy 709 for Sodium Fast Reactors - Colorado School of Mines CX(s) ...

  10. CX-005301: Categorical Exclusion Determination | Department of...

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

    wind turbine(s); conducting business and organizational planning to determine whether a wind-diesel plant is feasible; developing and conducting educational and informational...

  11. CX-006215: Categorical Exclusion Determination | Department of...

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

    CX-006215: Categorical Exclusion Determination Oklahoma State Energy Program American Recovery and Reinvestment Act - Oklahoma Department of Commerce Large System Application ...

  12. CX-006216: Categorical Exclusion Determination | Department of...

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

    CX-006216: Categorical Exclusion Determination Oklahoma State Energy Program American Recovery and Reinvestment Act - Oklahoma Municipal Power Authority Large System Request R ...

  13. CX-005432: Categorical Exclusion Determination | Department of...

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

    CX-005432: Categorical Exclusion Determination Oklahoma State Energy Program American Recovery and Reinvestment Act - Oklahoma Municipal Power Authority Large System Rebate Request ...

  14. CX-003838: Categorical Exclusion Determination | Department of...

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

    CX-003838: Categorical Exclusion Determination Demolition of the X-605 H Booster Pump ... The proposed action involves the demolition of the X-605 H Booster Pump House Building, ...

  15. ET Industries: Noncompliance Determination (2012-SE-2902)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to ET Industries, Inc. finding that showerhead basic model TH-1 does not comport with the water conservation standards.

  16. CX-009166: Categorical Exclusion Determination | Department of...

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

    CX-009166: Categorical Exclusion Determination Bioelectrochemical Integration of Waste Heat Recovery, Waste-to-Energy Conversion, and Waste-to-Chemical Conversion with Industrial ...

  17. Categorical Exclusion Determinations: New Jersey | Department...

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

    August 1, 2014 CX-012497: Categorical Exclusion Determination Geophysical and Mineralogical Controls on the Rheology of Fracture Slip... CX(s) Applied: B3.6 Date: 41852 ...

  18. CX-002452: Categorical Exclusion Determination | Department of...

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

    Assessment of the Environmental Effects of Hydrokinetic Turbines on Fish CX(s) Applied: ... to determine injury and survival rates for fish passing through hydrokinetic turbines. ...

  19. CX-002506: Categorical Exclusion Determination | Department of...

    Energy Savers [EERE]

    CX-002506: Categorical Exclusion Determination Rhode Island Commercial and Industrial Energy Efficiency Initiative CX(s) Applied: A9, A11, B5.1 Date: 06012010...

  20. CX-010272: Categorical Exclusion Determination | Department of...

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

    CX-010272: Categorical Exclusion Determination Chesapeake Light Tower Survey, ... The U.S. Department of Energy's (DOE) National Renewable Energy Laboratory is proposing to ...

  1. CX-001068: Categorical Exclusion Determination | Department of...

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

    CX-001068: Categorical Exclusion Determination Analysis of Energy, Environmental, and Life Cycle Cost Reduction Potential of Ground Source Heat Pumps in Hot and Humid Climate CX(s) ...

  2. CX-010269: Categorical Exclusion Determination | Department of...

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

    CX-010269: Categorical Exclusion Determination Renewable Energy Initiatives for Clark ... The U.S. Department of Energy (DOE) is proposing to provide federal funding to the Clark ...

  3. CX-005846: Categorical Exclusion Determination | Department of...

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

    CX-005846: Categorical Exclusion Determination Wood Pole Replacement and Minor Access Road Maintenance Along Various Transmission Line Rights-Of-Way in the Wenatchee District CX(s) ...

  4. CX-100229 Categorical Exclusion Determination | Department of...

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

    CX-100229 Categorical Exclusion Determination Center for Ocean Renewable Energy (CORE) ... of New Hampshire (UNH) Center for Ocean Renewable Energy (CORE) to develop a tidal ...

  5. Categorical Exclusion Determinations: Missouri | Department of...

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

    March 7, 2016 CX-100535 Categorical Exclusion Determination Large Scale GSHP as Alternative Energy for American Farmers: Technical Demonstration & Business Approach Award Number: ...

  6. CX-004656: Categorical Exclusion Determination | Department of...

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

    CX-004656: Categorical Exclusion Determination Small Wind Turbine Regional Test Center - Otisco, New York; National Renewable Energy Laboratory Tracking Number 10-028 CX(s) ...

  7. Electrolux: Compliance Determination (2010-SE-0108)

    Broader source: Energy.gov [DOE]

    After conducting testing of Electrolux's Frigidaire chest freezer model FFN09M5HWC, DOE determined that the model met the applicable energy conservation standard.

  8. Vitrification Melter Waste Incidental to Reprocessing Determination...

    Office of Environmental Management (EM)

    Reprocessing Determination For The West Valley Demonstration Project Concentrator Feed Makeup Tank and Melter Feed Hold Tank Responses to Public Comments on Draft Vitrification...

  9. CX-007901: Categorical Exclusion Determination | Department of...

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

    CX-007901: Categorical Exclusion Determination Improving Atmospheric Models for Offshore Wind Resource Mapping and Prediction Using LIDAR, Aircraft, and In-Ocean...

  10. Categorical Exclusion Determinations: Alabama | Department of...

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

    ... September 17, 2013 CX-010944: Categorical Exclusion Determination Daikin Advanced Lithium Ion Battery Technology - High Voltage Electrolyte CX(s) Applied: B3.6 Date: 09172013 ...

  11. Categorical Exclusion Determinations: Illinois | Department of...

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

    ... March 9, 2015 CX-013445: Categorical Exclusion Determination Scale Up of Lithium Ion Battery Material Recycling, Building 369 CX(s) Applied: B3.6 Date: 03092015 ...

  12. Watermark: Noncompliance Determination (2011-SW-2908)

    Broader source: Energy.gov [DOE]

    DOE issued a Notice of Noncompliance Determination to Watermark Designs, Ltd. finding that model SH-FAL-90, a showerhead, does not comport with the water conservation standards.

  13. Categorical Exclusion Determinations: Savannah River Operations...

    Office of Environmental Management (EM)

    Savannah River Operations Office Categorical Exclusion Determinations: Savannah River ... Install Concrete Block Bins for Additional Rock Storage at MOX Batch Plant CX(s) Applied: ...

  14. Caldicellulosiruptor Core and Pangenomes Reveal Determinants...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Caldicellulosiruptor Core and Pangenomes Reveal Determinants for Citation Details In-Document Search Title: Caldicellulosiruptor Core and Pangenomes Reveal ...

  15. Determining Memory Use | Argonne Leadership Computing Facility

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

    Allinea DDT Core File Settings Determining Memory Use Using VNC with a Debugger bgqstack gdb Coreprocessor Runjob termination TotalView Performance Tools & APIs Software &...

  16. Categorical Exclusion Determinations: Maryland | Department of...

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

    ... May 27, 2014 CX-012134: Categorical Exclusion Determination Development of Advanced CFD Tools for Enhanced Prediction of Explosion Pressure Development and ... CX(s) Applied: A9, ...

  17. Categorical Exclusion Determinations: Ohio | Department of Energy

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

    ... August 12, 2014 CX-012681: Categorical Exclusion Determination Experimental Investigation and CFD Analysis of Steam Ingress Accidents in HTGRs - Ohio State University CX(s) ...

  18. CX-001207: Categorical Exclusion Determination | Department of...

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

    CX-001207: Categorical Exclusion Determination Grid-Scale Energy Storage Demonstration for ... of UltraBattery modules, integrated in a turnkey battery energy storage system (BESS). ...

  19. CX-009199: Categorical Exclusion Determination | Department of...

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

    CX-009199: Categorical Exclusion Determination Access Road Improvement For the ... Bonneville Power Administration proposes to perform access road maintenance on several ...

  20. Categorical Exclusion Determinations: Idaho Operations Office...

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

    May 5, 2015 CX-013679: Categorical Exclusion Determination In situ Raman Spectroscopy to Enhance Nuclear Materials Research and Education- University of Nevada Reno CX(s) Applied: ...