National Library of Energy BETA

Sample records for applications design criteria

  1. Electronic Records Management Software Applications Design Criteria...

    Energy Savers [EERE]

    Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued under the authority of DoD Directive 5015.2, "Department of DefenseRecords ...

  2. Electronic Records Management Software Applications Design Criteria

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

    Standard | Department of Energy Electronic Records Management Software Applications Design Criteria Standard Electronic Records Management Software Applications Design Criteria Standard This Standard is reissued under the authority of DoD Directive 5015.2, "Department of DefenseRecords Management Program," March 6, 2000, (Reference (a)) which provides implementing and procedural guidance on the management of records in the Department of Defense. Electronic Records Management

  3. Fire protection design criteria

    SciTech Connect (OSTI)

    1997-03-01

    This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, national Fire Protection Association Codes and Standards, and any other applicable DOE construction criteria. This Standard, along with other delineated criteria, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  4. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, George F; Holcomb, David Eugene; Cetiner, Sacit M

    2012-06-01

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  5. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, G.F.; Holcomb, D.E.; Cetiner, S.M.

    2012-06-15

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC)–based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  6. Nuclear Reactor Safety Design Criteria

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

    1993-01-19

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Supersedes DOE 5480.1, dated 1-19-93. Certified 11-18-10.

  7. Application of Combined Sustained and Cyclic Loading Test Results to Alloy 617 Elevated Temperature Design Criteria

    SciTech Connect (OSTI)

    Wang, Yanli; Jetter, Robert I; Sham, Sam

    2014-08-25

    Alloy 617 is a reference structural material for very high temperature components of advanced-gas cooled reactors with outlet temperatures in the range of 900-950°C . In order for designers to be able to use Alloy 617 for these high temperature components, Alloy 617 has to be approved for use in Section III (the nuclear section) of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. A plan has been developed to submit a draft code for Alloy 617 to ASME Section III by 2015. However, the current rules in Subsection NH for the evaluation of strain limits and creep-fatigue damage using simplified methods based on elastic analysis have been deemed inappropriate for Alloy 617 at temperatures above 1200°F (650°C). The rationale for this exclusion is that at higher temperatures it is not feasible to decouple plasticity and creep deformation, which is the basis for the current simplified rules. This temperature, 1200 °F, is well below the temperature range of interest for this material in High Temperature Gas Cooled Reactor (HTGR) applications. The only current alternative is, thus, a full inelastic analysis which requires sophisticated material models which have been formulated but not yet verified. To address this issue, proposed code rules have been developed which are based on the use of elastic-perfectly plastic (EPP) analysis methods and which are expected to be applicable to very high temperatures.

  8. DOE Standard: Fire protection design criteria

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

    The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ``Fire Protection``, and DOE 6430.1A, ``General Design Criteria``. It also contains the fire protection guidelines from two (now canceled) draft standards: ``Glove Box Fire Protection`` and ``Filter Plenum Fire Protection``. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities.

  9. Aseismic design criteria for uranium enrichment plants

    SciTech Connect (OSTI)

    Beavers, J.E.

    1980-01-01

    In this paper technological, economical, and safety issues of aseismic design of uranium enrichment plants are presented. The role of management in the decision making process surrounding these issues is also discussed. The resolution of the issues and the decisions made by management are controlling factors in developing aseismic design criteria for any facility. Based on past experience in developing aseismic design criteria for the GCEP various recommendations are made for future enrichment facilities, and since uranium enrichment plants are members of the nuclear fuel cycle the discussion and recommendations presented herein are applicable to other nonreactor nuclear facilities.

  10. Application of biological design criteria and computational fluid dynamics to investigate fish survival in Kaplan turbines

    SciTech Connect (OSTI)

    Garrison, Laura A.; Fisher, Jr., Richard K.; Sale, Michael J.; Cada, Glenn

    2002-07-01

    One of the contributing factors to fish injury in a turbine environment is shear stress. This paper presents the use of computational fluid dynamics (CFD) to display and quantify areas of elevated shear stress in the Wanapum Kaplan turbine operating at four different flow conditions over its operating range. CFD observations will be compared to field test observations at the same four flow conditions. Methods developed here could be used to facilitate the design of turbines and related water passages with lower risks of fish injury.

  11. Range Design Criteria- June 4, 2012

    Broader source: Energy.gov [DOE]

    This document contains the currently-approved firearms "Range Design Criteria" referred to on DOE O 473.3, Protection Program Operations

  12. Understanding seismic design criteria for Japanese nuclear power...

    Office of Scientific and Technical Information (OSTI)

    Understanding seismic design criteria for Japanese nuclear power plants Citation Details In-Document Search Title: Understanding seismic design criteria for Japanese nuclear power ...

  13. Packaging design criteria for the MCO cask

    SciTech Connect (OSTI)

    Edwards, W.S.

    1996-04-29

    Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins (including possibly 700 additional elements from PUREX, N Reactor, and 327 Laboratory). The basin water, particularly in the K East Basin, contains significant quantities of dissolved nuclear isotopes and radioactive fuel corrosion particles. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the 100 K Area to a Canister Storage Building (CSB) in the 200 East area. In order to initiate K Basin cleanup on schedule, the two-year fuel-shipping campaign must begin by December 1997. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multiple Canister Overpacks.

  14. Durability-Based Design Criteria for a Chopped-Glass-Fiber Automotive Structural Composite

    SciTech Connect (OSTI)

    Battiste, R.L.; Corum, J.M.; Ren, W.; Ruggles, M.B.

    1999-11-01

    This report provides recommended durability-based design criteria for a chopped-glass-fiber reinforced polymeric composite for automotive structural applications. The criteria closely follow the framework of an earlier criteria document for a continuous-strand-mat (CSM) glass-fiber reference composite. Together these design criteria demonstrate a framework that can be adapted for future random-glass-fiber composites for automotive structural applications.

  15. Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety

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

    2000-03-28

    This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

  16. Application Content and Evaluation Criteria/Process

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

    Evaluation Criteria/Process Reginald Tyler Golden Field Office Office of Hydrogen, Fuel Cells and Infrastructure Technologies Application Content o Separate Applications for Each Major Topic o Title Should Identify the Topic Area o Application - SF 424 o Budget File - SF 424A o Project Summary - 1 page, non-proprietary Project Narrative o Provide clear description of the technical concept and how you plan to accomplish the work. o Include a description of the relevance of and justification for

  17. Durability-based design criteria for an automotive structural composite

    SciTech Connect (OSTI)

    Corum, J.M.; Battiste, R.L.; Brinkman, C.R.; Ren, W.; Ruggles, M.B.; Yahr, G.T.

    1998-11-01

    Before composite structures can be widely used in automotive applications, their long-term durability must be assured. The Durability of Lightweight Composite Structures Project at Oak Ridge National Laboratory was established by the US Department of Energy to help provide that assurance. The project is closely coordinated with the Automotive Composites Consortium. The experimentally-based, durability-driven design criteria described in this paper are the result of the initial project thrust. The criteria address a single reference composite, which is an SRIM (Structural Reaction Injection Molded) polyurethane, reinforced with continuous strand, swirl-mat E-glass fibers. The durability issues addressed include the effects of cyclic and sustained loadings, temperature, automotive fluid environments, and low-energy impacts (e.g., tool drops and roadway kickups) on strength, stiffness, and deformation. The criteria provide design analysis guidance, a multiaxial strength criterion, time-independent and time-dependent allowable stresses, rules for cyclic loading, and damage tolerance design guidance. Environmental degradation factors and the degrading effects of prior loadings are included. Efforts are currently underway to validate the criteria by application to a second random-glass-fiber composite. Carbon-fiber composites are also being addressed.

  18. DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria

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

    for DOE Facilities | Department of Energy Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities Department of Energy (DOE) Standard (STD)-1020-2012, Natural Phenomena Hazards Analysis and Design Criteria for DOE Facilities, provides criteria and guidance for the analysis and design of facility structures, systems, and components (SSCs) that are necessary to

  19. Application Content and Evaluation Criteria/Process

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

    Evaluation Criteria/Process Jill Gruber Golden Field Office Department of Energy May 18, 2007 The information presented here is an outline of how the Funding Opportunity Announcement (FOA) may be structured. The final application requirements will be shown in the FOA when it is posted on Grants.gov. The schedule and awards are dependent on future appropriations and may change if future appropriations are lower than expected or in the event of a continuing resolution. DOE Points of Contact DOE

  20. Natural Phenomena Hazard Analysis and Design Criteria for Department...

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

    20-2012, Natural Phenomena Hazard Analysis and Design Criteria for Department of Energy Facilities by Diane Johnson This Department of Energy (DOE) Standard (STD)-1020-2012,...

  1. Design and application of a mobile ground-based observatory for continuous measurements of atmospheric trace-gas and criteria pollutant species

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

    Bush, S. E.; Hopkins, F. M.; Randerson, J. T.; Lai, C.-T.; Ehleringer, J. R.

    2015-01-06

    Ground-based measurements of atmospheric trace gas species and criteria pollutants are essential for understanding emissions dynamics across space and time. Gas composition in the surface 50 m has the greatest direct impacts on human health as well as ecosystem processes, hence data at this level is necessary for addressing carbon cycle and public health related questions. However, such surface data are generally associated with stationary measurement towers, where spatial representation is limited due to the high cost of establishing and maintaining an extensive network of measurement stations. We describe here a compact mobile laboratory equipped to provide high-precision, high-frequency, continuous,more » on-road synchronous measurements of CO2, CO, CH4, H2O, NOx, O3, aerosol, meteorological, and geospatial position data. The mobile laboratory has been deployed across the western USA. In addition to describing the vehicle and its capacity, we present data that illustrate the use of the laboratory as a powerful tool for investigating the spatial structure of urban trace gas emissions and criteria pollutants at spatial scales ranging from single streets to whole ecosystem and regional scales. We identify fugitive urban CH4 emissions and assess the magnitude of CH4 emissions from known point sources. We illustrate how such a mobile laboratory can be used to better understand emissions dynamics and quantify emissions ratios associated with trace gas emissions from wildfire incidents. Lastly, we discuss additional mobile laboratory applications in health and urban metabolism.« less

  2. Design and application of a mobile ground-based observatory for continuous measurements of atmospheric trace gas and criteria pollutant species

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

    Bush, S. E.; Hopkins, F. M.; Randerson, J. T.; Lai, C.-T.; Ehleringer, J. R.

    2015-08-26

    Ground-based measurements of atmospheric trace gas species and criteria pollutants are essential for understanding emissions dynamics across space and time. Gas composition in the lower 50 m of the atmosphere has the greatest direct impacts on human health as well as ecosystem processes; hence data at this level are necessary for addressing carbon-cycle- and public-health-related questions. However, such surface data are generally associated with stationary measurement towers, where spatial representation is limited due to the high cost of establishing and maintaining an extensive network of measurement stations. We describe here a compact mobile laboratory equipped to provide high-precision, high-frequency, continuous,more » on-road synchronous measurements of CO2, CO, CH4, H2O, NOx, O3, aerosol, meteorological, and geospatial position data. The mobile laboratory has been deployed across the western USA. In addition to describing the vehicle and its capacity, we present data that illustrate the use of the laboratory as a powerful tool for investigating the spatial structure of urban trace gas emissions and criteria pollutants at spatial scales ranging from single streets to whole ecosystem and regional scales. We assess the magnitude of known point sources of CH4 and also identify fugitive urban CH4 emissions. We illustrate how such a mobile laboratory can be used to better understand emissions dynamics and quantify emissions ratios associated with trace gas emissions from wildfire incidents. Lastly, we discuss additional mobile laboratory applications in health and urban metabolism.« less

  3. Understanding seismic design criteria for Japanese Nuclear Power Plants

    SciTech Connect (OSTI)

    Park, Y.J.; Hofmayer, C.H.; Costello, J.F.

    1995-04-01

    This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with U.S. criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

  4. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

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

  5. DOE-STD-1066-99; Fire Protection Design Criteria

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

    ... Safety Analysis Report (SAR). 7.3.2 In the design of sway bracing, the criteria of Section 4-14.4.3.5.3 (or current equivalent) of NFPA 13 (1996) should be revised as follows. ...

  6. Design Criteria for Bagless Transfer System (BTS) Packaging System

    SciTech Connect (OSTI)

    RISENMAY, H.R.

    2000-04-26

    This document provides the criteria for the design and installation of a Bagless Transfer System (BTS); Blend, Sieve and Balance Equipment; and Supercritical Fluid Extraction System (SFE). The project consists of 3 major modules: (1) Bagless Transfer System (BTS) Module; (2) Blend, Sieve and Balance Equipment; and (3) Supercritical Fluid Extraction (SFE) Module.

  7. Earthquake design criteria for small hydro projects in the Philippines

    SciTech Connect (OSTI)

    Martin, P.P.; McCandless, D.H.; Asce, M.

    1995-12-31

    The definition of the seismic environment and seismic design criteria of more than twenty small hydro projects in the northern part of the island of Luzon in the Philippines took a special urgency on the wake of the Magnitude 7.7 earthquake that shook the island on July 17, 1990. The paper describes the approach followed to determine design shaking level criteria at each hydro site consistent with the seismic environment estimated at that same site. The approach consisted of three steps: (1) Seismicity: understanding the mechanisms and tectonic features susceptible to generate seismicity and estimating the associated seismicity levels, (2) Seismic Hazard: in the absence of an accurate historical record, using statistics to determine the expected level of ground shaking at a site during the operational 100-year design life of each Project, and (3) Criteria Selection: finally and most importantly, exercising judgment in estimating the final proposed level of shaking at each site. The resulting characteristics of estimated seismicity and seismic hazard and the proposed final earthquake design criteria are provided.

  8. Application Content and Evaluation Criteria/Process | Department...

    Office of Environmental Management (EM)

    Presentation on Application Content and Evaluation CriteriaProcess presented at the PEM fuel cell pre-solicitation meeting held May 26, 2005 in Arlington, VA. fcwrkshpreg.pdf ...

  9. Licensed reactor nuclear safety criteria applicable to DOE reactors

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

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

  10. Functional design criteria 241-AP-102 Flexible Receiver System

    SciTech Connect (OSTI)

    Roblyer, S.P.

    1995-02-16

    A mixer pump was installed in the 1.07 m (42-in.) riser of the central pump pit of tank 241-AP-102 to mitigate potential fluid separation particle sedimentation by mixing the tank`s contents. The mixer pump performed this function until failure. Its removal is now necessary to meet possible tank content removal commitments or other corrective actions. The proposed removal procedure requires a flexible receiver that will provide a barrier to contamination during removal and transfer of the pump to the mixer pump storage container. This document describes the functional design criteria of the flexible receiver. These criteria include the functional and performance requirements of the flexible receiver as a barrier to contamination during normal conditions and contingencies and the instrumentation requirements.

  11. Summary of the Advanced Reactor Design Criteria (ARDC) Phase 2 Activities

    SciTech Connect (OSTI)

    Holbrook, Mark Raymond

    2015-09-01

    This report provides an end-of-year summary reflecting the progress and status of proposed regulatory design criteria for advanced non-LWR designs in accordance with the Level 3 milestone in M3AT-15IN2001017 in work package AT-15IN200101. These criteria have been designated as ARDC, and they provide guidance to future applicants for addressing the GDC that are currently applied specifically to LWR designs. The report provides a summary of Phase 2 activities related to the various tasks associated with ARDC development and the subsequent development of example adaptations of ARDC for Sodium Fast Reactor (SFR) and modular High Temperature Gas-cooled Reactor (HTGR) designs.

  12. Design criteria Drain Rerouting Project 93-OR-EW-2

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This document contains the design criteria to be used by the architect-engineer (A--E) in the performance of Title I and II design for the Drain Rerouting Project. The Drain Rerouting project at the US Department of Energy`s (DOE) Oak Ridge Reservation in Oak Ridge, Tennessee will provide the Y-12 Plant with the capability to reroute particular drains within buildings 9202, 9203 and 9995. Process drains that are presently connected to the storm sewer shall be routed to the sanitary sewer to ensure that any objectionable material inadvertently discharged into process drains will not discharge to East Fork Popular Creek (EFPC) without treatment. The project will also facilitate compliance with the Y-12 Plant`s National Pollutant Discharge Elimination System (NPDES) discharge permit and allow for future pretreatment of once-through coolant.

  13. Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria...

    Office of Environmental Management (EM)

    New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) ...

  14. SOIL VAPOR EXTRACTION SYSTEM DESIGN: A CASE STUDY COMPARING VACUUM AND POREGAS VELOCITY CUTOFF CRITERIA

    SciTech Connect (OSTI)

    Dixon, K; Ralph Nichols, R

    2006-07-24

    Soil vapor extraction (SVE) systems are typically designed based on the results of a vadose zone pumping test (transient or steady state) using a pressure criteria to establish the zone of influence (ZOI). A common problem associated with pressure based SVE design is overestimating the ZOI of the extraction well. The vacuum criteria commonly used to establish the boundary of the ZOI results in large areas with very low pore velocities and thus long cleanup times. As a result, design strategies based upon critical pore gas velocity (CPGV) have increased in popularity. The CPGV is used in an effort to loosely incorporate the effects of mass transfer limitations into the design of SVE systems. Critical pore gas velocity designs use a minimum pore gas velocity rather than minimum vacuum to identify the extent of the treatment zone of an SVE system. The CPGV is typically much larger than the pore gas velocity at the perimeter of vacuum based (ZOI) designs resulting in shorter cleanup times. In this paper, we report the results of testing performed at the Savannah River Site (SRS) to determine the influence of a vapor extraction well based upon both a pressure and pore gas velocity design criteria. Results from this testing show that a SVE system designed based upon a CPGV is more robust and will have shorter cleanup times due to increased flow throughout the treatment zone. Pressure based SVE design may be appropriate in applications where soil gas containment is the primary objective; however, in cases where the capture and removal of contaminated soil gas is the primary objective, CPGV is a better design criteria.

  15. Guidance for Developing Principal Design Criteria for Advanced (Non-Light Water) Reactors

    SciTech Connect (OSTI)

    Holbrook, Mark; Kinsey, Jim

    2015-03-01

    In July 2013, the US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) established a joint initiative to address a key portion of the licensing framework essential to advanced (non-light water) reactor technologies. The initiative addressed the “General Design Criteria for Nuclear Power Plants,” Appendix A to10 Code of Federal Regulations (CFR) 50, which were developed primarily for light water reactors (LWRs), specific to the needs of advanced reactor design and licensing. The need for General Design Criteria (GDC) clarifications in non-LWR applications has been consistently identified as a concern by the industry and varied stakeholders and was acknowledged by the NRC staff in their 2012 Report to Congress1 as an area for enhancement. The initiative to adapt GDC requirements for non-light water advanced reactor applications is being accomplished in two phases. Phase 1, managed by DOE, consisted of reviews, analyses and evaluations resulting in recommendations and deliverables to NRC as input for NRC staff development of regulatory guidance. Idaho National Laboratory (INL) developed this technical report using technical and reactor technology stakeholder inputs coupled with analysis and evaluations provided by a team of knowledgeable DOE national laboratory personnel with input from individual industry licensing consultants. The DOE national laboratory team reviewed six different classes of emerging commercial reactor technologies against 10 CFR 50 Appendix A GDC requirements and proposed guidance for their adapted use in non-LWR applications. The results of the Phase 1 analysis are contained in this report. A set of draft Advanced Reactor Design Criteria (ARDC) has been proposed for consideration by the NRC in the establishment of guidance for use by non-LWR designers and NRC staff. The proposed criteria were developed to preserve the underlying safety bases expressed by the original GDC, and recognizing that advanced reactors may take

  16. Durability-Based Design Criteria for a Quasi-Isotropic Carbon-Fiber Automotive Composite

    SciTech Connect (OSTI)

    Corum, J.M.

    2002-04-17

    This report provides recommended durability-based design properties and criteria for a quasi-isotropic carbon-fiber composite for possible automotive structural applications. The composite, which was made by a rapid molding process suitable for high-volume automotive applications, consisted of continuous Thornel T300 fibers (6K tow) in a Baydur 420 IMR urethane matrix. The reinforcement was in the form of four {+-}45{sup o} stitch-bonded mats in the following layup: [0/90{sup o}/{+-}45{sup o}]{sub S}. This material is the second in a progression of three candidate thermoset composites to be characterized and modeled as part of an Oak Ridge National Laboratory project entitled Durability of Carbon-Fiber Composites. The overall goal of the project, which is sponsored by the U.S. Department of Energy's Office of Advanced Automotive Technologies and is closely coordinated with the industry Automotive Composites Consortium, is to develop durability-driven design data and criteria to assure the long-term integrity of carbon-fiber-based composite systems for large automotive structural components. This document is in two parts. Part I provides the design criteria, and Part 2 provides the underlying experimental data and models. The durability issues addressed include the effects on deformation, strength, and stiffness of cyclic and sustained loads, operating temperature, automotive fluid environments, and low-energy impacts (e.g., tool drops and kickups of roadway debris). Guidance is provided for design analysis, time-dependent allowable stresses, rules for cyclic loadings, and damage tolerance design guidance, including the effects of holes. Chapter 6 provides a brief summary of the design criteria.

  17. Core Design Applications

    Energy Science and Technology Software Center (OSTI)

    1995-07-12

    CORD-2 is intended for core desigh applications of pressurized water reactors. The main objective was to assemble a core design system which could be used for simple calculations (such as frequently required for fuel management) as well as for accurate calculations (for example, core design after refueling).

  18. IMPLEMENTATION OF THE SEISMIC DESIGN CRITERIA OF DOE-STD-1189-2008 APPENDIX A [FULL PAPER

    SciTech Connect (OSTI)

    OMBERG SK

    2008-05-14

    This paper describes the approach taken by two Fluor Hanford projects for implementing of the seismic design criteria from DOE-STD-1189-2008, Appendix A. The existing seismic design criteria and the new seismic design criteria is described, and an assessment of the primary differences provided. The gaps within the new system of seismic design criteria, which necessitate conduct of portions of work to the existing technical standards pending availability of applicable industry standards, is discussed. Two Hanford Site projects currently in the Control Decision (CD)-1 phase of design have developed an approach to implementation of the new criteria. Calculations have been performed to determine the seismic design category for one project, based on information available in early CD-1. The potential effects of DOE-STD-1189-2008, Appendix A seismic design criteria on the process of project alternatives analysis is discussed. Present of this work is expected to benefit others in the DOE Complex that may be implementing DOE-STD-1189-2008.

  19. Criteria for Selection of Seed Motions to Envelop Design Response Spectra

    Broader source: Energy.gov [DOE]

    Criteria for Selection of Seed Motions to Envelop Design Response Spectra DOE Natural Phenomena Hazards Workshop October 25, 2011 Michael Costantino, Thomas Houston, Greg Mertz, Andrew Maham

  20. OVERVIEW OF PRESSURE VESSEL DESIGN CRITERIA FOR INTERNAL DETONATION (BLAST) LOADING

    SciTech Connect (OSTI)

    T. A. DUFFEY; E. A. RODRIGUEZ

    2001-05-01

    Spherical and cylindrical pressure vessels are often used to completely contain the effects of high explosions. These vessels generally fall into two categories. The first includes vessels designed for multiple use ([1]-[6]). Applications of such multiple-use vessels include testing of explosive components and bomb disposal. Because of the multiple-use requirement, response of the vessel is restricted to the elastic range. The second category consists of vessels designed for one-time use only ([7]-[9]). Vessels in this category are typically used to contain accidental explosions and are designed to efficiently utilize the significant plastic energy absorption capacity of ductile materials. Because these vessels may undergo large permanent plastic deformations, they may not be reusable. Ideally one would design a Containment Vessel according to some National or International Consensus Standard, such as the ASME Boiler and Pressure Vessel Code. Unfortunately, however, a number of issues preclude direct use of the ASME Code in its present form to the design of Containment Vessels. These issues are described in Section 2, along with a request for guidance from the PVRC as to a suitable path forward for developing appropriate ASME B&PV design guidance for Containment Vessels. Next, a discussion of the nature of impulsive loading as a result of an internal detonation of the high explosive within a Containment Vessel is described in Section 3. Ductile failure criteria utilized for LANL Containment Vessels are described in Section 4. Finally, brittle fracture criteria currently utilized by LANL are presented in Section 5. This memo is concluded with a brief summary of results and an appeal to PVRC to recommend and develop an appropriate path forward (Section 6). This path forward could be of a short-term specialized nature (e.g., Code Case) for specific guidance regarding design of the LANL Containment Vessels; a long-term development of a general design approach

  1. Functional design criteria for standard hydrogen monitoring system portable platform

    SciTech Connect (OSTI)

    Schneider, T.C.

    1997-01-17

    Functional design description for a Standard-E cabinet arrangement Standard Hydrogen Monitoring System Portable Platform.

  2. Design criteria for a self-actuated shutdown system to ensure limitation of core damage. [LMFBR

    SciTech Connect (OSTI)

    Deane, N.A.; Atcheson, D.B.

    1981-09-01

    Safety-based functional requirements and design criteria for a self-actuated shutdown system (SASS) are derived in accordance with LOA-2 success criteria and reliability goals. The design basis transients have been defined and evaluated for the CDS Phase II design, which is a 2550 MWt mixed oxide heterogeneous core reactor. A partial set of reactor responses for selected transients is provided as a function of SASS characteristics such as reactivity worth, trip points, and insertion times.

  3. Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE

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

    Facilities (Proposed) | Department of Energy Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities (Proposed) Quazi Hossain, LLNL Joe Hunt, BWXT/Y-12 Robert Kennedy, RPK Consulting Carl Mazzola, Shaw Environmental, Inc. Steve McDuffie, DOE Gerald Meyers, DOE DOE Natural

  4. Criteria for Selection of Seed Motions to Envelop Design Response...

    Office of Environmental Management (EM)

    - Define seismic input into system as 5% damped Design Response Spectrum (DRS) based on Uniform Hazard Spectrum (UHS) - Select a seed record to be used in fitting process to ...

  5. DOE Standard Fire Protection Design Criteria DOE-STD-1006-97

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

    ... and vertical seismic loads. 7.3.3 In the design of sway bracing, the criteria of Section 4-6.4.3.5.2 (or current equivalent) of NFPA 13 (1994) should be revised as follows. ...

  6. Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities

    SciTech Connect (OSTI)

    Not Available

    1994-04-01

    This DOE standard gives design and evaluation criteria for natural phenomena hazards (NPH) effects as guidance for implementing the NPH mitigation requirements of DOE 5480.28. Goal of the criteria is to assure that DOE facilities can withstand the effects of earthquakes, extreme winds, tornadoes, flooding, etc. They apply to the design of new facilities and the evaluation of existing facilities; they may also be used for modification and upgrading of the latter.

  7. Natural Phenomena Hazard Analysis and Design Criteria for Department of Energy Facilities

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

    2012-08-03

    This Department of Energy (DOE) Standard (STD)-1020-2012, Natural Phenomena Hazards Analysis and Design Criteria for DOE Facilities, provides criteria and guidance for the analysis and design of facility structures, systems, and components (SSCs) that are necessary to implement the requirements of DOE Order (O) 420.1C, Facility Safety, and to ensure that the SSCs will be able to effectively perform their intended safety functions under the effects of natural phenomena hazards (NPHs).

  8. Risk Informed Design and Analysis Criteria for Nuclear Structures

    SciTech Connect (OSTI)

    Salmon, Michael W.

    2015-06-17

    Target performance can be achieved by defining design basis ground motion from results of a probabilistic seismic hazards assessment, and introducing known levels of conservatism in the design above the DBE. ASCE 4, 43, DOE-STD-1020 defined the DBE at 4x10-4 and introduce only slight levels of conservatism in response. ASCE 4, 43, DOE-STD-1020 assume code capacities shoot for about 98% NEP. There is a need to have a uniform target (98% NEP) for code developers (ACI, AISC, etc.) to aim for. In considering strengthening options, one must also consider cost/risk reduction achieved.

  9. Functional Design Criteria plutonium stabilization and handling (PUSH) project W-460

    SciTech Connect (OSTI)

    NELSON, D.W.

    1999-09-02

    This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years.

  10. 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

  11. Impact of structural design criteria on first wall surface heat flux limit

    SciTech Connect (OSTI)

    Majumdar, S.

    1998-09-01

    The irradiation environment experienced by the in-vessel components of fusion reactors presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.

  12. Application of Negligible Creep Criteria to Candidate Materials for HTGR Pressure Vessels

    SciTech Connect (OSTI)

    Jetter, Robert I; Sham, Sam; Swindeman, Robert W

    2011-01-01

    Two of the proposed High Temperature Gas Reactors (HTGRs) under consideration for a demonstration plant have the design object of avoiding creep effects in the reactor pressure vessel (RPV) during normal operation. This work addresses the criteria for negligible creep in Subsection NH, Division 1 of the ASME B&PV (Boiler and Pressure Vessel) Code, Section III, other international design codes and some currently suggested criteria modifications and their impact on permissible operating temperatures for various reactor pressure vessel materials. The goal of negligible creep could have different interpretations depending upon what failure modes are considered and associated criteria for avoiding the effects of creep. It is shown that for the materials of this study, consideration of localized damage due to cycling of peak stresses results in a lower temperature for negligible creep than consideration of the temperature at which the allowable stress is governed by creep properties. In assessing the effect of localized cyclic stresses it is also shown that consideration of cyclic softening is an important effect that results in a higher estimated temperature for the onset of significant creep effects than would be the case if the material were cyclically hardening. There are other considerations for the selection of vessel material besides avoiding creep effects. Of interest for this review are (1) the material s allowable stress level and impact on wall thickness (the goal being to minimize required wall thickness) and (2) ASME Code approval (inclusion as a permitted material in the relevant Section and Subsection of interest) to expedite regulatory review and approval. The application of negligible creep criteria to two of the candidate materials, SA533 and Mod 9Cr-1Mo (also referred to as Grade 91), and to a potential alternate, normalized and tempered 2 Cr-1Mo, is illustrated and the relative advantages and disadvantages of the materials are discussed.

  13. Functional design criteria W-367, 222-S ancillary equipment addition

    SciTech Connect (OSTI)

    McVey, C.B.

    1995-02-21

    This paper reviews the designs and performance of tubular solid oxide fuel cells (SOFCs). A large number of tubular cells of the porous support tube type have been electrically tested, some to times over 50,000 hours; these cells have shown excellent performance and performance stability. Since 1984, successfully larger electrical generators utilizing these cells have been built and operated; a 20 kW integrated SOFC system operated for 7064 hours during 1993-1994. Results of development efforts to reduce cost and increase power output of tubular cells by eliminating porous support tube and increasing active length are described, and plans to utilize such air electrode supported cells in future SOFC systems are discussed.

  14. 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.

  15. Functional design criteria for Project W-252, Phase II Liquid Effluent Treatment and Disposal: Revision 1

    SciTech Connect (OSTI)

    Hatch, C.E.

    1994-11-10

    This document provides the functional design criteria required for the Phase 2 Liquid Effluent Treatment and Disposal Project, Project W-252. Project W-252 shall provide new facilities and existing facility modifications required to implement Best Available Technology/All Known, Available, and Reasonable Methods of Prevention, Control, and Treatment (BAT/AKART) for the 200 East Phase II Liquid Effluent Streams. The project will also provide a 200 East Area Phase II Effluent Collection System (PTECS) for connection to a disposal system for relevant effluent streams to which BAT/AKART has been applied. Liquid wastestreams generated in the 200 East Area are currently discharged to the soil column. Included in these wastestreams are cooling water, steam condensate, raw water, and sanitary wastewaters. It is the policy of the DOE that the use of soil columns to treat and retain radionuclides and nonradioactive contaminants be discontinued at the earliest practical time in favor of wastewater treatment and waste minimization. In 1989, the DOE entered into an interagency agreement with Ecology and EPA. This agreement is referred to as the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). Project W-252 is one of the projects required to achieve the milestones set forth in the Tri-Party Agreement. One of the milestones requires BAT/AKART implementation for Phase II streams by October 1997. This Functional Design Criteria (FDC) document provides the technical baseline required to initiate Project W-252 to meet the Tri-Party Agreement milestone for the application of BAT/AKART to the Phase II effluents.

  16. Criteria for design of the Yucca Mountain structures, systems and components for fault displacement

    SciTech Connect (OSTI)

    Stepp, C.; Hossain, Q.; Nesbit, S.; Hardy, M.

    1995-12-31

    The DOE intends to design the Yucca Mountain high-level waste facility structures, systems and components (SSCs) for fault displacements to provide reasonable assurance that they will meet the preclosure safety performance objectives established by 10 CFR Part 60. To the extent achievable, fault displacement design of the facility will follow guidance provided in the NRC Staff Technical Position. Fault avoidance will be the primary design criterion, especially for spatially compact or clustered SSCs. When fault avoidance is not reasonably achievable, expected to be the case for most spatially extended SSCs, engineering design procedures and criteria or repair and rehabilitation actions, depending on the SSC`s importance to safety, are provided. SSCs that have radiological safety importance will be designed for fault displacements that correspond to the hazard exceedance frequency equal to their established seismic safety performance goals. Fault displacement loads are generally localized and may cause local inelastic response of SSCs. For this reason, the DOE intends to use strain-based design acceptance criteria similar to the strain-based criteria used to design nuclear plant SSCs for impact and impulsive loads.

  17. Canister storage building compliance assessment DOE Order 6430.1A, General Design Criteria

    SciTech Connect (OSTI)

    BLACK, D.M.

    1999-08-12

    This document presents the Project's position on compliance with DOE Order 6430.1A ''General Design Criteria.'' No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.

  18. Radiological risk evaluation for risk-based design criteria of the multiple canister overpack packaging

    SciTech Connect (OSTI)

    Green, J.R., Westinghouse Hanford

    1996-07-18

    The Multiple Canister Overpack (MCO) cask will be used in the transportation of irradiated nuclear fuel from the K Basins to a Canister Storage Building. This report presents the radiological risk evaluation, which is used in the development of the design criteria for the MCO cask. The radiological risk evaluation ensures compliance with the onsite transportation safety program.

  19. Development of biological criteria for the design of advanced hydropower turbines

    SciTech Connect (OSTI)

    ?ada, Glenn F.; Coutant, Charles C.; Whitney, Richard R.

    1997-03-01

    A review of the literature related to turbine-passage injury mechanisms suggests the following biological criteria should be considered in the design of new turbines: (1) pressure; (2) cavitation; (3) shear and turbulence; and (4) mechanical injury. Based on the studys review of fish behavior in relation to hydropower facilities, it provides a number of recommendations to guide both turbine design and additional research.

  20. Design criteria for Waste Coolant Processing Facility and preliminary proposal 722 for Waste Coolant Processing Facility

    SciTech Connect (OSTI)

    Not Available

    1991-09-27

    This document contains the design criteria to be used by the architect-engineer (A-E) in the performance of Titles 1 and 2 design for the construction of a facility to treat the biodegradable, water soluble, waste machine coolant generated at the Y-12 plant. The purpose of this facility is to reduce the organic loading of coolants prior to final treatment at the proposed West Tank Farm Treatment Facility.

  1. Design criteria for the light duty utility arm system end effectors

    SciTech Connect (OSTI)

    Pardini, A.F.

    1995-01-03

    This document provides the criteria for the design of end effectors that will be used as part of the Light Duty Utility Arm (LDUA) System. The LDUA System consists of a deployment vehicle, a vertical positioning mast, a light duty multi-axis robotic arm, a tank riser interface and confinement, a tool interface plate, a control system, and an operations control trailer. The criteria specified in this document will apply to all end effector systems being developed for use on or with the LDUA system at the Hanford site. The requirement stipulated in this document are mandatory.

  2. LBB application in Swedish BWR design

    SciTech Connect (OSTI)

    Kornfeldt, H.; Bjoerk, K.O.; Ekstroem, P.

    1997-04-01

    The protection against dynamic effects in connection with potential pipe breaks has been implemented in different ways in the development of BWR reactor designs. First-generation plant designs reflect code requirements in effect at that time which means that no piping restraint systems were designed and built into those plants. Modern designs have, in contrast, implemented full protection against damage in connection with postulated pipe breaks, as required in current codes and regulations. Moderns standards and current regulatory demands can be met for the older plants by backfitting pipe whip restraint hardware. This could lead to several practical difficulties as these installations were not anticipated in the original plant design and layout. Meeting the new demands by analysis would in this situation have great advantages. Application of leak-before-break criteria gives an alternative opportunity of meeting modem standards in reactor safety design. Analysis takes into account data specific to BWR primary system operation, actual pipe material properties, piping loads and leak detection capability. Special attention must be given to ensure that the data used reflects actual plant conditions.

  3. Development of design criteria for a high pressure vessel construction code

    SciTech Connect (OSTI)

    Mraz, G.J.

    1987-05-01

    Out of concern for public safety, most legal jurisdictions now require unfired pressure vessel construction to comply with the ASME Boiler and Pressure Vessel Code. Because the present two divisions of Section VIII of that Code are not well suited for high pressure design, a new division is needed. The currently anticipated main design criteria of the proposed division are full plastic flow or full overstrain pressure, stress intensity in the bore, fatigue, and fracture mechanics. The rules are expected to allow better utilization of high strength steels already included in the present Section VIII. At the same time materials of even higher strength are introduced. The benefits of compressive prestress are recognized. Construction methods allowing it's achievement, such as autofrettage, shrink fitting and wire winding are included. Reasons for selection of the criteria are given.

  4. Functional design criteria for project W-252, phase II liquid effluent treatment and disposal. Revision 2

    SciTech Connect (OSTI)

    Hatch, C.E.

    1995-05-01

    This document is the Functional Design Criteria for Project W-252. Project W-252 provides the scope to provide BAT/AKART (best available technology...) to 200 Liquid Effluent Phase II streams (B-Plant). This revision (Rev. 2) incorporates a major descoping of the project. The descoping was done to reflect a combination of budget cutting measures allowed by a less stringent regulatory posture toward the Phase II streams

  5. Evaluation Criteria

    Broader source: Energy.gov [DOE]

    Applications must meet the basic eligibility criteria. Final decisions regarding eligibility and compliance will be made by the Office of Energy Efficiency and Renewable Energy (EERE).

  6. Development and implementation of seismic design and evaluation criteria for NIF

    SciTech Connect (OSTI)

    Sommer, S.C.; MacCalden, P.B.

    1998-03-17

    The National Ignition Facility (NIF) is being built at the Lawrence Livermore National Laboratory (LLNL) as an international research center for inertial confinement fusion (ICF). This paper will provide an overview of NIF, review NIF seismic criteria, and briefly discuss seismic analyses of NIF optical support structures that have been performed by LLNL and the Ralph M. Parsons Company, the Architect and Engineer (A&E) for NIF. The NIF seismic design and evaluation criteria is based on provisions in DOE Standard 1020 (DOE-STD-1020), the Uniform Building Code (UBC), and the LLNL Mechanical Engineering Design Safety Standards (MEDSS). Different levels of seismic requirements apply to NIF structures, systems, and components (SSCs) based on their function. The highest level of requirements are defined for optical support structures and SSCs which could influence the performance of optical support structures, while the minimum level of requirements are Performance Category 2 (PC2) requirements in DOE-STD-1020. To demonstrate that the NIF seismic criteria is satisfied, structural analyses have been performed by LLNL and Parsons to evaluate the responses of optical support structures and other SSCs to seismic-induced forces.

  7. STRUCTURAL DESIGN CRITERIA FOR TARGET/BLANKET SYSTEM COMPONENT MATERIALS FOR THE ACCELERATOR PRODUCTION OF TRITIUM PROJECT

    SciTech Connect (OSTI)

    W. JOHNSON; R. RYDER; P. RITTENHOUSE

    2001-01-01

    The design of target/blanket system components for the Accelerator Production of Tritium (APT) plant is dependent on the development of materials properties data specified by the designer. These data are needed to verify that component designs are adequate. The adequacy of the data will be related to safety, performance, and economic considerations, and to other requirements that may be deemed necessary by customers and regulatory bodies. The data required may already be in existence, as in the open technical literature, or may need to be generated, as is often the case for the design of new systems operating under relatively unique conditions. The designers' starting point for design data needs is generally some form of design criteria used in conjunction with a specified set of loading conditions and associated performance requirements. Most criteria are aimed at verifying the structural adequacy of the component, and often take the form of national or international standards such as the ASME Boiler and Pressure Vessel Code (ASME B and PV Code) or the French Nuclear Structural Requirements (RCC-MR). Whether or not there are specific design data needs associated with the use of these design criteria will largely depend on the uniqueness of the conditions of operation of the component. A component designed in accordance with the ASME B and PV Code, where no unusual environmental conditions exist, will utilize well-documented, statistically-evaluated developed in conjunction with the Code, and will not be likely to have any design data needs. On the other hand, a component to be designed to operate under unique APT conditions, is likely to have significant design data needs. Such a component is also likely to require special design criteria for verification of its structural adequacy, specifically accounting for changes in materials properties which may occur during exposure in the service environment. In such a situation it is common for the design criteria and

  8. Functional design criteria for FY 1993-2000 groundwater monitoring wells

    SciTech Connect (OSTI)

    Williams, B.A.

    1996-01-01

    The purpose of this revision is to update the Line Item Project, 93-L-GFW-152 Functional Design Criteria (FDC) to reflect changes approved in change control M-24-91-6, Engineering Change Notices (ECNs), and expand the scope to include subsurface investigations along with the borehole drilling. This revision improves the ability and effectiveness of maintaining RCRA and Operational groundwater compliance by combining borehole and well drilling with subsurface data gathering objectives. The total projected number of wells to be installed under this project has decreased from 200 and the scope has been broadened to include additional subsurface investigation activities that usually occur simultaneously with most traditional borehole drilling and monitoring well installations. This includes borehole hydrogeologic characterization activities, and vadose monitoring. These activities are required under RCRA 40 CFR 264 and 265 and WAC 173-303 for site characterization, groundwater and vadose assessment and well placement.

  9. 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.

  10. Wind load comparison for the ASCE standard 7 and the Hanford site design criteria

    SciTech Connect (OSTI)

    Giller, R.A., Westinghouse Hanford

    1996-07-16

    This document provides calculations and discussions to compare Hanford Site wind load criteria with the current national standard for wind loads (ASCE 7, 1995). Site criteria uses the 1988 edition ASCE 7.

  11. American National Standard: design criteria for an independent spent-fuel-storage installation (water pool type)

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    This standard provides design criteria for systems and equipment of a facility for the receipt and storage of spent fuel from light water reactors. It contains requirements for the design of major buildings and structures including the shipping cask unloading and spent fuel storage pools, cask decontamination, unloading and loading areas, and the surrounding buildings which contain radwaste treatment, heating, ventilation and air conditioning, and other auxiliary systems. It contains requirements and recommendations for spent fuel storage racks, special equipment and area layout configurations, the pool structure and its integrity, pool water cleanup, ventilation, residual heat removal, radiation monitoring, fuel handling equipment, cask handling equipment, prevention of criticality, radwaste control and monitoring systems, quality assurance requirements, materials accountability, and physical security. Such an installation may be independent of both a nuclear power station and a reprocessing facility or located adjacent to any of these facilities in order to share selected support systems. Support systems shall not include a direct means of transferring fuel assemblies from the nuclear facility to the installation.

  12. 340 Facility Secondary Containment and Leak Detection Project W-302 Functional Design Criteria

    SciTech Connect (OSTI)

    Stordeur, R.T.

    1995-03-01

    This functional design criteria for the upgrade to the 340 radioactive liquid waste storage facility (Project W-302) specifically addresses the secondary containment issues at the current vault facility of the 340 Complex. This vault serves as the terminus for the Radioactive Liquid Waste System (RLWS). Project W-302 is necessary in order to bring this portion of the Complex into full regulatory compliance. The project title, ``340 Facility Secondary Containment and Leak Detection``, illustrates preliminary thoughts of taking corrective action directly upon the existing vault (such as removing the tanks, lining the vault, and replacing tanks). However, based on the conclusion of the engineering study, ``Engineering Study of the 300 Area Process Wastewater Handling System``, WHC-SD-WM-ER-277 (as well as numerous follow-up meetings with cognizant staff), this FDC prescribes a complete replacement of the current tank/vault system. This offers a greater array of tanks, and provides greater operating flexibility and ease of maintenance. This approach also minimizes disruption to RLWS services during ``tie-in``, as compared to the alternative of trying to renovate the old vault. The proposed site is within the current Complex area, and maintains the receipt of RLWS solutions through gravity flow.

  13. 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.

  14. Criteria for Selection of Seed Motions to Envelop Design Response Spectra

    Office of Environmental Management (EM)

    Reaffirmed June 2013 DOE STANDARD CRITERIA FOR EVALUATION OF NUCLEAR FACILITY TRAINING PROGRAMS (Formerly Titled: Guidelines for Evaluation of Nuclear Facility Training Programs) U.S. Department of Energy FSC Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE HDBK-1070-94 Errata June 2013 Table of Changes Page/Section Change Cover Criteria for Evaluation of Nuclear Facility Training Programs Page ii This document is available on the

  15. Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV

    SciTech Connect (OSTI)

    William J. O’Donnell; Donald S. Griffin

    2007-05-07

    The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.

  16. Structural Design Criteria for Anion Hosts: Strategies for Achieving Anion Shape Recognition through the Complementary Placement of Urea Donor Groups

    SciTech Connect (OSTI)

    Hay, Benjamin P.; Firman, Timothy K.; Moyer, Bruce A.

    2005-02-16

    The arrangement of urea ligands about different shaped anions has been evaluated with electronic structure calculations. Geometries and binding energies are reported for urea complexes with Cl{sup -}, NO{sub 3}{sup -}, and ClO{sub 4}{sup -}. The results yield new insight into the nature of urea-anion interactions and provide structural criteria for the deliberate design of anion selective receptors containing two or more urea donor groups.

  17. Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

    SciTech Connect (OSTI)

    Mertz, G.

    1999-12-16

    This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

  18. Brittle Failure Design Criteria for Ductile Cast Iron Spent-Fuel

    Office of Scientific and Technical Information (OSTI)

    Am. SOC. of Mech. Engineers, (1980). 3. "Pressure Vessel Codes: Their Application to Nuclear Reactor Systems," Technical Reports Series No. 56, International Atomic Energy...

  19. Design criteria for an independent spent fuel storage installation (water pool type)

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    This standard is intended to be used by those involved in the ownership and operation of an Independent Spent Fuel Storage Installation (ISFSI) in specifying the design requirements and by the designer in meeting the minimum design requirements of such installations. This standard continues the set of American National Standards on spent fuel storage design. Similar standards are: Design Objectives for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Stations, N210-1976 (ANS-57.2); Design Objectives for Highly Radioactive Solid Material Handling and Storage Facilities in a Reprocessing Plant, ANSI N305-1975; and Guidelines for Evaluating Site-Related Parameters for an Independent Spent Fuel Storage Installation, ANSI/ANS-2.19-1981.

  20. Structural Design Challenges in Design Certification Applications for New Reactors

    SciTech Connect (OSTI)

    Miranda, M.; Braverman, J.; Wei, X.; Hofmayer, C.; Xu, J.

    2011-07-17

    The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are confined within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of structural design chal- lenges encountered in recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.

  1. Synthesis of economic criteria in the design of electric utility industrial conservation programs in Costa Rica

    SciTech Connect (OSTI)

    Fisher, S.C.

    1995-12-31

    This paper lays out a set of economic criteria to guide the development of electricity conservation programs for industrial customers of the Costa Rican utilities. It puts the problem of utility and other public policy formulation in the industrial conservation field into the context of ongoing economic and trade liberalization in Costa Rica, as well as the financial and political pressures with which the country`s utilities must contend. The need to bolster utility financial performance and the perennial political difficulty of adjusting power rates for inflation and devaluation, not to mention maintaining efficient real levels, puts a premium on controlling the costs of utility conservation programs and increasing the degree of cost recovery over time. Industrial conservation programs in Costa Rica must adopt a certain degree of activation to help overcome serious market failures and imperfections while at the same time avoiding significant distortion of the price signals guiding the ongoing industrial rationalization process and the reactivation of growth.

  2. Nuclear Safety Design Base for License Application (Technical...

    Office of Scientific and Technical Information (OSTI)

    Nuclear Safety Design Base for License Application Citation Details In-Document Search Title: Nuclear Safety Design Base for License Application You are accessing a document ...

  3. Building the Next Generation of Parallel Applications: Co-Design...

    Office of Scientific and Technical Information (OSTI)

    Applications: Co-Design Opportunities and Challenges. Citation Details In-Document Search Title: Building the Next Generation of Parallel Applications: Co-Design Opportunities and ...

  4. Design of slurry reactor for indirect liquefaction applications...

    Office of Scientific and Technical Information (OSTI)

    Design of slurry reactor for indirect liquefaction applications Citation Details In-Document Search Title: Design of slurry reactor for indirect liquefaction applications You ...

  5. Design criteria for prestressed concrete reactor vessels for high-temperature reactors

    SciTech Connect (OSTI)

    Elter, C.; Becker, G.

    1982-11-01

    For the design and construction of prestressed concrete reactor vessels, data on loading, construction materials, and safety factors are required. A description is given of the design conditions according to the current state of technology in the Federal Republic of Germany. Special consideration is given to the allowable stresses and an appropriate proposal for such stresses is suggested.

  6. Design criteria and mitigation options for thermal fatigue effects in ATW blankets.

    SciTech Connect (OSTI)

    Dunn, F. E.

    2000-12-07

    Thermal fatigue due to beam interruptions is an issue that must be addressed in the design of an ATW blanket. Two different approaches can be taken to address this issue. One approach is to analyze current ATW blanket designs in order to set interrupt frequency design limits for the accelerator. The other approach is to assume that accelerator reliability can not be guaranteed before design and construction of the blanket. In this approach the blanket must be designed so as to accommodate an accelerator with a beam interruption frequency significantly higher than current high power accelerators in order to provide a margin of error. Both approaches are considered in this paper. Both a sodium cooled blanket design and a lead-bismuth cooled blanket design are considered. Thermal hydraulic analysis of the blanket for beam interruption transients is carried out with the SASSYS-1 systems analysis code to obtain the time histories of the coolant temperatures in contact with structural components. These coolant temperatures are then used in a detailed structure temperature calculation to obtain structure surface and structure average temperatures. The difference between the average temperature and the surface temperature is used to obtain thermal strains. Low cycle fatigue curves from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code are used to determine the number of cycles that the structural components can endure, based on these strains. Calculations are made for base case designs and for a number of mitigation options. The mitigation options include using two separate accelerators to provide the beam, reducing the thickness of the above core load pads in the subassemblies, increasing the coolant flow rate or reducing power in order to reduce the core temperature rise, and reducing the superheat in the once-through steam generator.

  7. Natural Phenomena Hazards Design Criteria and Other Characterization Information for the MFFF at SRS

    SciTech Connect (OSTI)

    Wyatt, D.E.

    2000-12-01

    This report is a comprehensive complication applicable to the general Savannah River Site area, developed by both the original contractor, the DuPont Company, and by the current plant operator, Westinghouse Savannah River Company, over the full plant lifetime period (1950 - 2000).

  8. K Basin sludge packaging design criteria (PDC) and safety analysis report for packaging (SARP) approval plan

    SciTech Connect (OSTI)

    Brisbin, S.A.

    1996-03-06

    This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging.

  9. Aerodynamic Design Criteria for Class 8 Heavy Vehicles Trailer Base Devices to Attain Optimum Performance

    SciTech Connect (OSTI)

    Salari, K; Ortega, J

    2010-12-13

    Lawrence Livermore National Laboratory (LLNL) as part of its Department of Energy (DOE), Energy Efficiency and Renewable Energy (EERE), and Vehicle Technologies Program (VTP) effort has investigated class 8 tractor-trailer aerodynamics for many years. This effort has identified many drag producing flow structures around the heavy vehicles and also has designed and tested many new active and passive drag reduction techniques and concepts for significant on the road fuel economy improvements. As part of this effort a database of experimental, computational, and conceptual design for aerodynamic drag reduction devices has been established. The objective of this report is to provide design guidance for trailer base devices to improve their aerodynamic performance. These devices are commonly referred to as boattails, base flaps, tail devices, and etc. The information provided here is based on past research and our most recent full-scale experimental investigations in collaboration with Navistar Inc. Additional supporting data from LLNL/Navistar wind tunnel, track test, and on the road test will be published soon. The trailer base devices can be identified by 4 flat panels that are attached to the rear edges of the trailer base to form a closed cavity. These devices have been engineered in many different forms such as, inflatable and non-inflatable, 3 and 4-sided, closed and open cavity, and etc. The following is an in-depth discussion with some recommendations, based on existing data and current research activities, of changes that could be made to these devices to improve their aerodynamic performance. There are 6 primary factors that could influence the aerodynamic performance of trailer base devices: (1) Deflection angle; (2) Boattail length; (3) Sealing of edges and corners; (4) 3 versus 4-sided, Position of the 4th plate; (5) Boattail vertical extension, Skirt - boattail transition; and (6) Closed versus open cavity.

  10. Design criteria document, Fire Protection Task, K Basin Essential Systems Recovery, Project W-405

    SciTech Connect (OSTI)

    Johnson, B.H.

    1994-12-14

    The K Basin were constructed in the early 1950`s with a 20 year design life. The K Basins are currently in their third design life and are serving as a near term storage facility for irradiated N Reactor fuel until an interim fuel storage solution can be implemented. In April 1994, Project W-405, K Basin Essential Systems Recovery, was established to address (among other things) the immediate fire protection needs of the 100K Area. A Fire Barrier Evaluation was performed for the wall between the active and inactive areas of the 105KE and 105KW buildings. This evaluation concludes that the wall is capable of being upgraded to provide an equivalent level of fire resistance as a qualified barrier having a fire resistance rating of 2 hours. The Fire Protection Task is one of four separate Tasks included within the scope of Project W405, K Basin Essential systems Recovery. The other three Tasks are the Water Distribution System Task, the Electrical System Task, and the Maintenance Shop/Support Facility Task. The purpose of Project W-405`s Fire Protection Task is to correct Life Safety Code (NFPA 101) non-compliances and to provide fire protection features in Buildings 105KE, 105KW and 190KE that are essential for assuring the safe operation and storage of spent nuclear fuel at the 100K Area Facilities` Irradiated Fuel Storage Basins (K Basins).

  11. HEPA Filter Differential Pressure Fan Interlock System Functional Requirements and Technical Design Criteria

    SciTech Connect (OSTI)

    TUCK, J.A.

    2000-05-11

    Double-shell tanks (DSTs) and Double Contained Receiver Tanks (DCRTs) are actively ventilated, along with certain single-shell tanks (SSTs) and other RPP facilities. The exhaust air stream on a typical primary ventilation system is drawn through two stages of high-efficiency particulate air (HEPA) filtration to ensure confinement of airborne radioactive materials. Active ventilation exhaust stacks require a stack CAM interlock to detect releases from postulated accidents, and to shut down the exhaust fan when high radiation levels are detected in the stack airstream. The stack CAM interlock is credited as a mitigating control to stop continued unfiltered radiological and toxicological discharges from the stack, which may result from an accident involving failure of a HEPA filter. This document defines the initial technical design baseline for a HEPA filter AP fan interlock system.

  12. Structural Aspects of Hydrogen Bonding with Nitrate and Sulfate: Design Criteria for Polyalcohol Hosts

    SciTech Connect (OSTI)

    Hay, Benjamin P.; Dixon, David A.; Lumetta, Gregg J.; Vargas, Rubicelia; Garza, Jorge

    2004-01-01

    Organic hosts for oxyanion complexation can be constructed by combining two or more hydrogen bonding sites. The deliberate design of architectures for such hosts requires knowledge of the optimal geometry for the hydrogen bonds formed between the host and the guest. Important structural parameters include the O--H distance, the O--H-D angle, the X-O--H angle, and the X-O--H-D dihedral angle (H-D=hydrogen bond donor, X=any atom). This information can be obtained through the analysis of hydrogen bonding observed in crystal structures and electronic structure calculations on simple gas-phase complexes. In this chapter, we present an analysis of hydrogen bonding structural parameters for alcohol hydrogen donors and the oxygen atom acceptors in nitrate and sulfate.

  13. Challenging design objectives and criteria for future nuclear plants in Italy

    SciTech Connect (OSTI)

    Gadola, A.; Tripputi, I. )

    1992-01-01

    The National Energy Plan of August 1988, after the public poll of November 1987 and the decision to stop the plants in operation and construction, placed a 5-yr moratorium on construction of new plants and, at the same time, called for the study of new designs that would allow a return of nuclear power in Italy. In this context ENEL, the Italian national utility, has started a broad program of research and development on new reactors with enhanced safety characteristics in an international context. With the approaching end of the 5-yr moratorium, this paper summarizes the work under way and outlines the results that are expected to be included in the reactors that could be built before the end of the century in Italy.

  14. Designing of Metallic Photonic Structures and Applications

    SciTech Connect (OSTI)

    Yong-Sung Kim

    2006-08-09

    In this thesis our main interest has been to investigate metallic photonic crystal and its applications. We explained how to solve a periodic photonic structure with transfer matrix method and when and how to use modal expansion method. Two different coating methods were introduced, modifying a photonic structure's intrinsic optical properties and rigorous calculation results are presented. Two applications of metallic photonic structures are introduced. For thermal emitter, we showed how to design and find optimal structure. For conversion efficiency increasing filter, we calculated its efficiency and the way to design it. We presented the relation between emitting light spectrum and absorption and showed the material and structural dependency of the absorption spectrum. By choosing a proper base material and structural parameters, we can design a selective emitter at a certain region we are interested in. We have developed a theoretical model to analyze a blackbody filament enclosed by a metallic mesh which can increase the efficiency of converting a blackbody radiation to visible light. With this model we found that a square lattice metallic mesh enclosing a filament might increase the efficiency of incandescent lighting sources. Filling fraction and thickness dependency were examined and presented. Combining these two parameters is essential to achieve the maximum output result.

  15. Design Concept and Application of Small Nuclear Power Reactor

    SciTech Connect (OSTI)

    Minato, Akio; Sekimoto, Hiroshi

    2009-03-31

    The outline of the recent design concepts and those features of the small nuclear power rector are described, including specifications, present design status, application and so on.

  16. CRAD, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities

    Office of Energy Efficiency and Renewable Energy (EERE)

    These guidelines and criteria provide a consistent overall framework for assessment of the processes that are currently in place to ensure that the software being used in the safety analysis and design of the SSCs in defense nuclear facilities is adequate. These reviews will be conducted only on software that is currently in use, not on software that was previously used as part of a safety analysis and design process.

  17. Advanced system demonstration for utilization of biomass as an energy source. Volume I. Scope and design criteria and project summary

    SciTech Connect (OSTI)

    1980-10-01

    The information in this document is the result of an intensive engineering effort to demonstrate the feasibility of biomass-fueled boilers in cogeneration applications. This design package is based upon a specific site in the State of Maine. However, the design is generic in nature and could serve as a model for other biomass conversion facilities located anywhere biomass is abundant. The project's purpose and summary information are presented: the plant, its concept of operation; and other overall information are described. The capital cost estimate for the plant, and the basis upon which it was obtained are given; a schedule of key milestones and activities required to construct the plant and put it into operation is presented; and the general findings in areas that affect the viability of the project are discussed. The technical design, biomass study, environmental impact, commercialization, and economic factors are addressed. Each major plant area and the equipment and facilities that each includes are discussed in depth. Some overall plant requirements, including noise control, reliability, maintainability, and safety, are detailed. The results of each study relating to alternatives considered for optimizing plant operation parameters and specific system process schemes are briefly presented. All economic factors that affect the feasibility and viability of the biomass project are defined and evaluated.

  18. Web Application Design Using Server-Side JavaScript

    SciTech Connect (OSTI)

    Hampton, J.; Simons, R.

    1999-02-01

    This document describes the application design philosophy for the Comprehensive Nuclear Test Ban Treaty Research & Development Web Site. This design incorporates object-oriented techniques to produce a flexible and maintainable system of applications that support the web site. These techniques will be discussed at length along with the issues they address. The overall structure of the applications and their relationships with one another will also be described. The current problems and future design changes will be discussed as well.

  19. MURMoT. Design and Application of Microbial Uranium Reduction...

    Office of Scientific and Technical Information (OSTI)

    MURMoT. Design and Application of Microbial Uranium Reduction Monitoring Tools Citation ... Sponsoring Org: USDOE Office of Science (SC), Biological and Environmental Research (BER) ...

  20. MURMoT. Design and Application of Microbial Uranium Reduction...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: MURMoT. Design and Application of Microbial Uranium Reduction Monitoring ... Sponsoring Org: USDOE Office of Science (SC), Biological and Environmental Research (BER) ...

  1. Design tools for passive solar applications

    SciTech Connect (OSTI)

    Balcomb, J.D.

    1986-04-01

    Examples of passive solar design tools are given, categorized as either evaluation tools or guidance tools. A trend toward microcomputer-based tools is noted; however, these are usually developed for use by engineers rather than architects. The need for more instructive tools targeted specifically to designers is emphasized.

  2. Design of applicative 100 W Stirling engine

    SciTech Connect (OSTI)

    Kagawa, Noboru; Hirata, Koichi; Takeuchi, Makoto

    1995-12-31

    A small 100 W displacer type Stirling engine is being developed under a project of a JSME committee, RC127. The project consists of sixteen Japanese academic researchers of universities and governmental laboratories and eleven enterprise members related to the Stirling field. The engine has very unique features. Its expansion cylinder is heated by combustion gas or solar energy directly, and a simple cooling system rejects heat from the working fluid. A regenerator is built in the displacer piston with heating and cooling tubes in which the working fluid flows from/to outer tubes. The outer tubes for heating were located at the top of the expansion cylinder and the tubes for cooling are in the middle of the cylinder. The target performance is a 100 W output with 20% thermal efficiency at the operating conditions of 923 K expansion space temperature, 343 K compression space temperature, and 1,000 rpm. The 100 W displacer engine was designed based on a design manual established by a related JSME committee, RC110. It contains several guides to design for cycle, heat exchanger system, and mechanism of most Stirling cycle machines. The engine was designed by using the fundamental method, the second and third-order analyses accomplished with the newly arranged knowledge about each component. This paper presents the engine specifications and the theoretical analysis results. The design method is also introduced briefly.

  3. Accident analysis and DOE criteria

    SciTech Connect (OSTI)

    Graf, J.M.; Elder, J.C.

    1982-01-01

    In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied.

  4. Design of dynamic load-balancing tools for parallel applications

    SciTech Connect (OSTI)

    Devine, K.D.; Hendrickson, B.A.; Boman, E.G.; St. John, M.; Vaughan, C.T.

    2000-01-03

    The design of general-purpose dynamic load-balancing tools for parallel applications is more challenging than the design of static partitioning tools. Both algorithmic and software engineering issues arise. The authors have addressed many of these issues in the design of the Zoltan dynamic load-balancing library. Zoltan has an object-oriented interface that makes it easy to use and provides separation between the application and the load-balancing algorithms. It contains a suite of dynamic load-balancing algorithms, including both geometric and graph-based algorithms. Its design makes it valuable both as a partitioning tool for a variety of applications and as a research test-bed for new algorithmic development. In this paper, the authors describe Zoltan's design and demonstrate its use in an unstructured-mesh finite element application.

  5. Performance Criteria and Evaluation System

    Energy Science and Technology Software Center (OSTI)

    1992-06-18

    The Performance Criteria and Evaluation System (PCES) was developed in order to make a data base of criteria accessible to radiation safety staff. The criteria included in the package are applicable to occupational radiation safety at DOE reactor and nonreactor nuclear facilities, but any data base of criteria may be created using the Criterion Data Base Utiliity (CDU). PCES assists personnel in carrying out oversight, line, and support activities.

  6. Plant computer applications 'design and implementation tools' set

    SciTech Connect (OSTI)

    Anikanov, S. S.; Stolyetniy, I. V.; Tregubov, M. I.; Guslyakov, O. L.; Gladkov, Y. I.

    2006-07-01

    This paper describes functionality of the application programs' development tool, which is intended to support the full scope of the NPP plant computer applications' design process. The Application Development Tools' Set (ADTS), described in this paper, refers to a set of tools intended to capture functional requirements for applications and support design process from definition of design basis up to final testing of developed applications. There are several tools developed by Westinghouse that facilitate design of application software on different stages of design process. Those are: NAPDT - Nuclear Application Development Tool; SDODT - Simplified Display Object Development Tool; OPAL - Test case execution and documenting tool; The main idea of ADTS is to combine the aforementioned tools into one software environment with other Common out-of-shelf (COT) software to facilitate and expedite NPP plant computer applications. Combination of the software tools included into ADTS satisfies industry requirements for the application software intended for use in the Category B and C systems /2 - 4/. (authors)

  7. A criticism of applications with multi-criteria decision analysis that are used for the site selection for the disposal of municipal solid wastes

    SciTech Connect (OSTI)

    Kemal Korucu, M.; Erdagi, Bora

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer The existing structure of the multi-criteria decision analysis for site selection is criticized. Black-Right-Pointing-Pointer Fundamental problematic points based on the critics are defined. Black-Right-Pointing-Pointer Some modifications are suggested in order to provide solutions to these problematical points. Black-Right-Pointing-Pointer A new structure for the decision making mechanism is proposed. Black-Right-Pointing-Pointer The feasibility of the new method is subjected to an evaluation process. - Abstract: The main aim of this study is to criticize the process of selecting the most appropriate site for the disposal of municipal solid wastes which is one of the problematic issues of waste management operations. These kinds of problems are pathological symptoms of existing problematical human-nature relationship which is related to the syndrome called ecological crisis. In this regard, solving the site selection problem, which is just a small part of a larger entity, for the good of ecological rationality and social justice is only possible by founding a new and extensive type of human-nature relationship. In this study, as a problematic point regarding the discussions on ecological problems, the existing structure of the applications using multi-criteria decision analysis in the process of site selection with three main criteria is criticized. Based on this critique, fundamental problematic points (to which applications are insufficient to find solutions) will be defined. Later, some modifications will be suggested in order to provide solutions to these problematical points. Finally, the criticism addressed to the structure of the method with three main criteria and the feasibility of the new method with four main criteria is subjected to an evaluation process. As a result, it is emphasized that the new structure with four main criteria may be effective in solution of the fundamental problematic points.

  8. Application of multi-criteria decision-making on strategic municipal solid waste management in Dalmatia, Croatia

    SciTech Connect (OSTI)

    Vego, Goran Kucar-Dragicevic, Savka Koprivanac, Natalija

    2008-11-15

    The efficiency of providing a waste management system in the coastal part of Croatia consisting of four Dalmatian counties has been modelled. Two multi-criteria decision-making (MCDM) methods, PROMETHEE and GAIA, were applied to assist with the systematic analysis and evaluation of the alternatives. The analysis covered two levels; first, the potential number of waste management centres resulting from possible inter-county cooperation; and second, the relative merits of siting of waste management centres in the coastal or hinterland zone was evaluated. The problem was analysed according to several criteria; and ecological, economic, social and functional criteria sets were identified as relevant to the decision-making process. The PROMETHEE and GAIA methods were shown to be efficient tools for analysing the problem considered. Such an approach provided new insights to waste management planning at the strategic level, and gave a reason for rethinking some of the existing strategic waste management documents in Croatia.

  9. Advanced Electric Submersible Pump Design Tool for Geothermal Applications

    SciTech Connect (OSTI)

    Xuele Qi; Norman Turnquist; Farshad Ghasripoor

    2012-05-31

    Electrical Submersible Pumps (ESPs) present higher efficiency, larger production rate, and can be operated in deeper wells than the other geothermal artificial lifting systems. Enhanced Geothermal Systems (EGS) applications recommend lifting 300 C geothermal water at 80kg/s flow rate in a maximum 10-5/8-inch diameter wellbore to improve the cost-effectiveness. In this paper, an advanced ESP design tool comprising a 1D theoretical model and a 3D CFD analysis has been developed to design ESPs for geothermal applications. Design of Experiments was also performed to optimize the geometry and performance. The designed mixed-flow type centrifugal impeller and diffuser exhibit high efficiency and head rise under simulated EGS conditions. The design tool has been validated by comparing the prediction to experimental data of an existing ESP product.

  10. Summary of New DOE-STD-1020-2011 NPH Analysis and Design Criteria for DOE Facilities

    Office of Environmental Management (EM)

    Energy 5, 2015 - October 9, 2015 Summary of Decisions - October 5, 2015 - October 9, 2015 October 9, 2015 - 8:42am Addthis Personnel Security (10 CFR Part 710) On October 8, 2015, an OHA Administrative Judge issued a decision in which he concluded that an individual's request for a security clearance should not be granted. Processing of the individual's original application for access authorization was suspended in 2009 due to criminal charges pending against him for Aggravated DWI (which he

  11. FTCP Assessment Guidance and Criteria

    Broader source: Energy.gov [DOE]

    This document establishes the guidance and criteria for conducting internal and independent Federal Technical Capability Assessments within the Department. The requirements of this document are applicable to those organizations having safety responsibilities for defense nuclear facilities. This includes both headquarters and field organizations. Regardless of the type of assessment conducted, the objectives and criteria within this document are used as a basis for the assessment. Use of consistent objectives and criteria is necessary to establish baselines and to track and trend performance.

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

    SciTech Connect (OSTI)

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

    1992-01-01

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

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

    SciTech Connect (OSTI)

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

    1992-08-01

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

  14. Structural Criteria for the Rational Design of Selective Ligands: Convergent Hydrogen Bonding Sites for the Nitrate Anion

    SciTech Connect (OSTI)

    Hay, Benjamin P.; Gutowski, Maciej S.; Dixon, David A.; Garza , Jorge; Vargas, Rubicelia; Moyer, Bruce A.

    2004-06-30

    Molecular hosts for anion complexation are often constructed by combining two or more hydrogen bonding functional groups, DH. The deliberate design of complementary host architectures requires knowledge of the optimal geometry for the hydrogen bonds formed between the host and the guest. Herein, we present a detailed study of the structural aspects of hydrogen bonding interactions with the NO3 anion. A large number of crystal structures are analyzed to determine the number of hydrogen bond contacts per anion and to further characterize the structural aspects of these interactions. Electronic structure calculations are used to determine stable geometries and interaction energies for NO3 complexes with several simple molecules possessing DH groups, including water, methanol, N-methylformamide, and methane. Theoretical results are reported at several levels of density functional theory, including BP86/DN**, B3LYP/TZVP, and B3LYP/TZVP+, and at MP2/aug-cc-pVDZ. In addition, MP2 binding energies for these complexes were obtained at the complete basis set limit by extrapolating from single point energies obtained with larger correlation-consistent basis sets. The results establish that NO3 has an intrinsic hydrogen bonding topography in which there are six optimal sites for proton location. The structural features observed in crystal structures and in the optimized geometries of complexes are explained by a preference to locate the DH protons in these positions. For the strongest hydrogen bonding interactions, the NOH angle is bent at an angle of 115 10, and the hydrogen atom lies in the NO3 plane giving ONOH dihedral angles of 0 and 180. In addition, the D-H vector points towards the oxygen atom, giving DHO angles that are near linear, 170 10. Due to steric hindrance, simple alcohol OH and amide NH donors form 3:1 complexes with NO3, with HO distances of 1.85 0.5 . Thus, the optimal cavity radius for a tridentate host, defined as the

  15. Idaho National Laboratory Lead or Lead-Bismuth Eutectic (LBE) Test Facility - R&D Requirements, Design Criteria, Design Concept, and Concept Guidance

    SciTech Connect (OSTI)

    Eric P. Loewen; Paul Demkowicz

    2005-05-01

    The Idaho National Laboratory Lead-Bismuth Eutectic Test Facility will advance the state of nuclear technology relative to heavy-metal coolants (primarily Pb and Pb-Bi), thereby allowing the U.S. to maintain the pre-eminent position in overseas markets and a future domestic market. The end results will be a better qualitative understanding and quantitative measure of the thermal physics and chemistry conditions in the molten metal systems for varied flow conditions (single and multiphase), flow regime transitions, heat input methods, pumping requirements for varied conditions and geometries, and corrosion performance. Furthering INL knowledge in these areas is crucial to sustaining a competitive global position. This fundamental heavy-metal research supports the National Energy Policy Development Group’s stated need for energy systems to support electrical generation.1 The project will also assist the Department of Energy in achieving goals outlined in the Nuclear Energy Research Advisory Committee Long Term Nuclear Technology Research and Development Plan,2 the Generation IV Roadmap for Lead Fast Reactor development, and Advanced Fuel Cycle Initiative research and development. This multi-unit Lead-Bismuth Eutectic Test Facility with its flexible and reconfigurable apparatus will maintain and extend the U.S. nuclear knowledge base, while educating young scientists and engineers. The uniqueness of the Lead-Bismuth Eutectic Test Facility is its integrated Pool Unit and Storage Unit. This combination will support large-scale investigation of structural and fuel cladding material compatibility issues with heavy-metal coolants, oxygen chemistry control, and thermal hydraulic physics properties. Its ability to reconfigure flow conditions and piping configurations to more accurately approximate prototypical reactor designs will provide a key resource for Lead Fast Reactor research and development. The other principal elements of the Lead-Bismuth Eutectic Test Facility

  16. Seismic Analysis Issues in Design Certification Applications for New Reactors

    SciTech Connect (OSTI)

    Miranda, M.; Morante, R.; Xu, J.

    2011-07-17

    The licensing framework established by the U.S. Nuclear Regulatory Commission under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides requirements for standard design certifications (DCs) and combined license (COL) applications. The intent of this process is the early reso- lution of safety issues at the DC application stage. Subsequent COL applications may incorporate a DC by reference. Thus, the COL review will not reconsider safety issues resolved during the DC process. However, a COL application that incorporates a DC by reference must demonstrate that relevant site-specific de- sign parameters are within the bounds postulated by the DC, and any departures from the DC need to be justified. This paper provides an overview of several seismic analysis issues encountered during a review of recent DC applications under the 10 CFR Part 52 process, in which the authors have participated as part of the safety review effort.

  17. Strain-Based Acceptance Criteria for Energy-Limited Events

    SciTech Connect (OSTI)

    Spencer D. Snow; Dana K. Morton

    2009-07-01

    The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code was primarily written with stress-based acceptance criteria. These criteria are applicable to force, displacement, and energy-controlled loadings and ensure a factor of safety against failure. However, stress-based acceptance criteria are often quite conservative for one time energy-limited events such as accidental drops and impacts. For several years, the ASME Working Group on Design of Division 3 Containments has been developing the Design Articles for Section III, Division 3, “Containments for Transportation and Storage of Spent Nuclear Fuel and High-Level Radioactive Material and Waste,” and has wanted to establish strain-based acceptance criteria for accidental drops of containments. This Division 3 working group asked the Working Group on Design Methodology (WGDM) to assist in developing these strain-based acceptance criteria. This paper discusses the current proposed strain-based acceptance criteria, associated limitations of use, its background development, and the current status.

  18. Vermont Small Hydropower Assistance Program Screening Criteria...

    Open Energy Info (EERE)

    LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Vermont Small Hydropower Assistance Program Screening Criteria Summary and Application InstructionsPermitting...

  19. The Future Through the Past: The Use of Analog Sites for Design Criteria and Long Term Performance Assessment of Evapotranspiration Landfill Covers

    SciTech Connect (OSTI)

    Shafer, D. S.; Miller, J. J.; Young, M. H.; Edwards, S. C.; Rawlinson, S. E.

    2002-02-26

    There is growing support for using evapotranspiration (ET) covers for closure of low-level waste (LLW) and other types of waste disposal sites, particularly in the lower latitude arid regions of the western United States. At the Nevada Test Site (NTS), monolayer ET covers are the baseline technology for closure of LLW and mixed LLW cells. To better predict the long-term performance of monolayer ET covers, as well as to identify design criteria that will potentially improve their performance, the properties of, and processes occurring on, analog sites for ET covers on the NTS are being studied. The project is funded through the Subsurface Contaminants Focus Area of the U.S. Department of Energy. Four analog sites on the NTS have been selected to predict performance of ET covers over a 1,000-year compliance period. Two sites are relatively recently disturbed (within the last 50 years) and have been selected to evaluate processes and changes on ET covers for the early period after active cover maintenance is discontinued. Two other sites, late to mid-Holocene in age, are intended as analogs for the end of the compliance period (1,000 years or more); both surfaces are abandoned alluvial/colluvial deposits. The history of the early post-institutional control analog sites are being evaluated by an archaeologist to help determine when the sites were last disturbed or modified, and the mode of disturbance to help set baseline conditions. Similar to other ''landforms,'' ET covers will evolve over time because of pedogenic, biotic, and climatic processes. Properties of analog sites that could affect ET water balance performance will be evaluated to help understand ET cover performance over time.

  20. Conceptual design of a gas turbine for PFBC applications

    SciTech Connect (OSTI)

    Bannister, R.L.; McGuigan, A.W.; Risley, T.P.; Smith, O.J.

    1992-01-01

    First generation pressurized fluidized bed (PFBC) technology has potential advantages which include: lower capital cost, Unproved environmental performance, shorter lead times, higher efficiency and enhanced fuel flexibility. Coal firing with combustion turbines experiments have been conducted for over forty years. These efforts have evolved to the point where commercial demonstrations are now feasible. The PFBC is one of these technologies. It will be demonstrated as part of the Clean Coal III initiative. PFBC technology is applicable for new installations, replacement of existing equipment as well as repower and retrofit. Included with these options is the opportunity to reduce dependency on fuel oil and well as enhancing environmental performance and increasing efficiency. The turbo-machinery will require design changes to meet the requirements for PFBC application. The major change to the combustion turbine take place in the center section. This section will include provisions to supply compressed air to the PFBC as well as receive vitiated air from the PFBC. These efforts also have the objective of reducing the degree of change from a standard unit. Under a clean coal program a first generation PFBC demonstration win take place at the Des Moines Energy Center. For this demonstration it will be necessary to remove two stages from the 251B12 compressor. This will make the air supplied by the compressor suitable for the PFBC system. The results from this program will be applicable to the DMEC-1 program.

  1. Conceptual design of a gas turbine for PFBC applications

    SciTech Connect (OSTI)

    Bannister, R.L.; McGuigan, A.W.; Risley, T.P.; Smith, O.J.

    1992-12-31

    First generation pressurized fluidized bed (PFBC) technology has potential advantages which include: lower capital cost, Unproved environmental performance, shorter lead times, higher efficiency and enhanced fuel flexibility. Coal firing with combustion turbines experiments have been conducted for over forty years. These efforts have evolved to the point where commercial demonstrations are now feasible. The PFBC is one of these technologies. It will be demonstrated as part of the Clean Coal III initiative. PFBC technology is applicable for new installations, replacement of existing equipment as well as repower and retrofit. Included with these options is the opportunity to reduce dependency on fuel oil and well as enhancing environmental performance and increasing efficiency. The turbo-machinery will require design changes to meet the requirements for PFBC application. The major change to the combustion turbine take place in the center section. This section will include provisions to supply compressed air to the PFBC as well as receive vitiated air from the PFBC. These efforts also have the objective of reducing the degree of change from a standard unit. Under a clean coal program a first generation PFBC demonstration win take place at the Des Moines Energy Center. For this demonstration it will be necessary to remove two stages from the 251B12 compressor. This will make the air supplied by the compressor suitable for the PFBC system. The results from this program will be applicable to the DMEC-1 program.

  2. Acceptance Criteria Framework for Autonomous Biological Detectors

    SciTech Connect (OSTI)

    Dzenitis, J M

    2006-12-12

    The purpose of this study was to examine a set of user acceptance criteria for autonomous biological detection systems for application in high-traffic, public facilities. The test case for the acceptance criteria was the Autonomous Pathogen Detection System (APDS) operating in high-traffic facilities in New York City (NYC). However, the acceptance criteria were designed to be generally applicable to other biological detection systems in other locations. For such detection systems, ''users'' will include local authorities (e.g., facility operators, public health officials, and law enforcement personnel) and national authorities [including personnel from the Department of Homeland Security (DHS), the BioWatch Program, the Centers for Disease Control and Prevention (CDC), and the Federal Bureau of Investigation (FBI)]. The panel members brought expertise from a broad range of backgrounds to complete this picture. The goals of this document are: (1) To serve as informal guidance for users in considering the benefits and costs of these systems. (2) To serve as informal guidance for developers in understanding the needs of users. In follow-up work, this framework will be used to systematically document the APDS for appropriateness and readiness for use in NYC.

  3. Design of slurry reactor for indirect liquefaction applications. Final report

    SciTech Connect (OSTI)

    Prakash, A.; Bendale, P.G.

    1991-12-31

    The objective of this project is to design and model a conceptual slurry reactor for two indirect liquefaction applications; (1) production of methanol and (2) production of hydrocarbon fuels via Fischer-Tropsch route. A slurry reactor is defined here as a three-phase bubble column reactor using a fine catalyst particle suspension in a high molecular weight liquid. The feed gas is introduced through spargers. It then bubbles through the column providing the agitation necessary for catalyst suspension and mass transfer. The reactor models for the two processes have been formulated using computer simulation. Process data, kinetic and thermodynamic data, heat and mass transfer data and hydrodynamic data have been used in the mathematical models to describe the slurry reactor for each of the two processes. Available data from process development units and demonstration units were used to test and validate the models. Commercial size slurry reactors for methanol and Fischer-Tropsch synthesis were sized using reactor models developed in this report.

  4. 309 Facility deactivation and decommisioning Criteria Completion Check Lists

    SciTech Connect (OSTI)

    Cornwell, B.C.

    1996-02-01

    To facilitate and track completion of the 309 Facility turnover criteria completion an Applicability Matrix and Criteria Completion Check Lists were prepared. The applicability matrix documents the required turnover criteria for a given area in the facility or scope of work. The applicable criteria is selected for 16 different areas. For each area a completion checklist is provided to document completion of a requirement by WHC and the Environmental Restoration Contractor.

  5. Design and Development of e-Turbo for SUV and Light Truck Applications...

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

    Development of e-Turbo for SUV and Light Truck Applications Design and Development of ... More Documents & Publications Design & Development of e-TurboTM for SUV and Light Truck ...

  6. Design & Development of e-TurboTM for SUV and Light Truck Applications...

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

    Design & Development of e-TurboTM for SUV and Light Truck Applications 2003 DEER ... More Documents & Publications Design and Development of e-Turbo for SUV and Light Truck ...

  7. Machine plumbness criteria: Interim technology release

    SciTech Connect (OSTI)

    Not Available

    1987-06-01

    The objective of this technology release is to define the maximum allowable deviation from plumb of the centrifuge machine and to recommend machine installation techniques to achieve the specified criteria. The centrifuge feature used as a reference for plumbness is the casing centerline as defined by a line drawn between the theoretical centers of the top and bottom flange faces. In practice, this measurement is accomplished by using specified casing flange diameters or bolt patterns as the reference points. The criterion adopted for GCEP is that each machine shall be plumb within 0.5 in. over the length of the casing as initially installed. Over a long period of time the plumbness is allowed to degrade to 1.0 in. This standard should be achievable using the currently planned installation techniques and within a time limit consistent with GCEP operational objectives. For development testing, centrifuge machines are meticulously adjusted using a plumb bob to achieve a plumbness with 1/8 in. About one to two days are required to complete the installation. This level of effort is justified for a development machine especially where baseline data is being gathered. A more reasonable standard with a corresponding reduction in installation time is required for GCEP. The specified criteria of 0.5 in. maximum out-of-plumb at time of installation and 1.0 in., ultimate, are believed to be a reasonable compromise. Machine design features or operating modes that are dependent on vertical alignment were examined to assess the impact of the selected plumbness criteria. Machine performance and design requirements are defined in the applicable technology release documents.

  8. Design & Development of e-TurboTM for SUV and Light Truck Applications |

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

    Department of Energy & Development of e-TurboTM for SUV and Light Truck Applications Design & Development of e-TurboTM for SUV and Light Truck Applications 2003 DEER Conference Presentation: Garrett Engine Boosting Systems 2003_deer_shahed.pdf (477.34 KB) More Documents & Publications Design and Development of e-Turbo for SUV and Light Truck Applications The Potential of Elelcltric Exhaust Gas Turbocharging for HD DIesel Engines SuperTurbocharger

  9. Design and Development of e-Turbo for SUV and Light Truck Applications |

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

    Department of Energy Development of e-Turbo for SUV and Light Truck Applications Design and Development of e-Turbo for SUV and Light Truck Applications 2004 Diesel Engine Emissions Reduction (DEER) Conference Presentation: Honeywell Corporation 2004_deer_shahed.pdf (427.61 KB) More Documents & Publications Design & Development of e-TurboTM for SUV and Light Truck Applications SuperTurbocharger Electric Turbo Compounding...A Technology Who's Time Has Come

  10. ARM - Guidelines : Review Criteria

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

    Review Criteria Guidelines Overview Annual Facility Call Proposal Deadline Guidance Small Field Campaigns Review Criteria Expectations for Principal Investigators Forms Propose a Campaign Instrument Support Request (ISR) Form (Word, 89KB) Unmanned Aerial System (UAS) Mission Request Form (Word, 72KB) Documentation Submitting Field Campaign Data and Metadata Field Campaign Guidelines (PDF, 574KB) Unmanned Aerial System Operation Safety at ARM Sites (PDF, 639KB) Guidelines : Review Criteria

  11. Eco-Design of River Fishways for Upstream Passage: Application for Hanfeng Dam, Pengxi River, China

    SciTech Connect (OSTI)

    Johnson, Gary E.; Rainey, William S.

    2012-05-20

    This paper provides a scientific approach to eco-design of river fishways to allow upstream movement of fish past new and existing dams in China. This eco-design approach integrates principles of fish ecology/behavior and engineering, a scientific field also known as bio-engineering or eco-hydraulics. We define a fishway as a structure or mechanism to convey fish upstream past a dam. Man-made or natural stream beds can be part of the fishway mechanism. Fish include bony and non-bony fishes, and upstream passage is the concern here, not downstream passage. The problem is dams block access to upstream habitat used for spawning, rearing, and refuge, i.e., dams decrease habitat connectivity. A solution to alleviate this problem is to design fishways, preferably while the dam is being designed, but if necessary, as retrofits afterward to provide a route that fish can and will use to pass safely upstream without undue delay. Our eco-design approach for fishways involves eight steps: 1) identify the primary species of importance; 2) understand basic ecology and behavior of these fish; 3) characterize the environmental conditions where passage is or will be blocked; 4 identify fishway alternatives and select a preferred alternative; 5) establish eco-design criteria for the fishway, either from management agencies or, if necessary, developed specifically for the given site; 6) where needed, identify and perform research required to resolve critical uncertainties and finalize the eco-design criteria; 7) apply the eco-design criteria and site-specific considerations to design the fishway, involving peer-review by local stakeholders in the process; 8) build the fishway, monitor its effectiveness, and apply the lessons learned. Example fishways are described showing a range of eco-designs depending on the dam site and fish species of concern. We apply the eco-design principles to recommend an approach and next steps for a fishway to pass fish upstream at Hanfeng Dam, an

  12. Acceptance Criteria - Hanford Site

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

    G and I clarified requirements throughout the appendices. Appendix I, Table I-1 in the Waste Acceptance Criteria for the "Payload Container Description" removed "208-L (55 gal)...

  13. Application of Engineering and Technical Requirements for 30, 60, and 90% Design of DOE Nuclear Facilities

    Office of Energy Efficiency and Renewable Energy (EERE)

    This Standard Review Plan (SRP), Application of Engineering and Technical Requirements for 30, 60 and 90% Design of DOE Nuclear Facilities, was developed by the Office of Chief of Nuclear Safety (CNS), Office of the Environmental Management. The SRP is designed to help strengthen the technical rigor of line management oversight and federal monitoring of the design process of DOE nuclear facilities.

  14. Design and synthesis of mixed oxides nanoparticles for biofuel applications

    SciTech Connect (OSTI)

    Chen, Senniang

    2010-05-15

    The work in this dissertation presents the synthesis of two mixed metal oxides for biofuel applications and NMR characterization of silica materials. In the chapter 2, high catalytic efficiency of calcium silicate is synthesized for transesterfication of soybean oil to biodisels. Chapter 3 describes the synthesis of a new Rh based catalyst on mesoporous manganese oxides. The new catalyst is found to have higher activity and selectivity towards ethanol. Chapter 4 demonstrates the applications of solid-state Si NMR in the silica materials.

  15. Using Application Proxies for Co-design of Future HPC Computer Systems and

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

    Applications Proxy Application Tutorial Using Application Proxies for Co-design of Future HPC Computer Systems and Applications Sunday, Nov. 11 8:30-5:00 Michael A. Heroux - Sandia National Laboratory Alice Koniges - NERSC / Lawrence Berkeley National Laboratory David F. Richards - Lawrence Livermore National Laboratory Richard F. Barrett - Sandia National Laboratory Thomas Brunner - Lawrence Berkeley Livermore Laboratory ABSTRACT: The computing community is in the midst of disruptive

  16. Plutonium storage criteria

    SciTech Connect (OSTI)

    Chung, D.; Ascanio, X.

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  17. Conceptual design of pressure relief systems for cryogenic application

    SciTech Connect (OSTI)

    Grohmann, S.; Süßer, M.

    2014-01-29

    The conceptual design of pressure relief systems is an important aspect in the early phase of any cryogenic system design, because a prudent and responsible evaluation of relief systems involves much more than just relief devices. The conceptual design consists of various steps: At first, hazard scenarios must be considered and the worst-case scenario identified. Next, a staged interaction against pressure increase is to be defined. This is followed by the selection of the general type of pressure relief device for each stage, such as safety valve and rupture disc, respectively. Then, a decision concerning their locations, their capacities and specific features must be taken. Furthermore, it is mandatory to consider the inlet pressure drop and the back pressure in the exhaust line for sizing the safety devices. And last but not least, economic and environmental considerations must be made in case of releasing the medium to the atmosphere. The development of the system's safety concept calls for a risk management strategy based on identification and analysis of hazards, and consequent risk mitigation using a system-based approach in compliance with the standards.

  18. KrF amplifier design issues and application to ICF system design

    SciTech Connect (OSTI)

    Sullivan, J.A.; Allen, G.R.; Berggren, R.R.; Czuchlewski, S.J.; Harris, D.B.; Jones, M.E.; Krohn, B.J.; Kurnit, N.A.; Leland, W.T.; Mansfield, C.; McLeod, J.; McCown, A.W.; McLeod, J.; Pendergrass, J.H.; Rose, E.A.; Rosocha, L.A.; Thomas, V.A.

    1991-01-01

    Los Alamos National Laboratory has assembled an array of experimental and theoretical tools to optimize amplifier design for future KrF lasers. The next opportunity to exercise these tools is with the design of the second generation NIKE system under construction at the Naval Research Laboratory with the collaboration of Los Alamos National Laboratory. Major issues include laser physics (energy extraction in large modules with amplified spontaneous emission) and diode performance and efficiency. High efficiency and low cost are increasingly important for larger future KrF amplifiers. In this paper we present our approach to amplifier scaling and discuss the more important design considerations for large KrF amplifiers. We point out where improvements in the fundamental data base for KrF amplifiers could lead to increased confidence in performance predictions for large amplifiers, and we address the currently unresolved issues of anomalous absorption near line center and the possibility of diode instabilities for low impedance designs. Los Alamos has designed a 100-kJ KrF laser-fusion system for both direct- and indirect-drive target physics experiments using 60-kJ amplifier modules. The design of this system will be reviewed. 38 refs., 110 figs., 3 tabs.

  19. Designing robust unitary gates: Application to concatenated composite pulses

    SciTech Connect (OSTI)

    Ichikawa, Tsubasa; Bando, Masamitsu; Kondo, Yasushi; Nakahara, Mikio

    2011-12-15

    We propose a simple formalism to design unitary gates robust against given systematic errors. This formalism generalizes our previous observation [Y. Kondo and M. Bando, J. Phys. Soc. Jpn. 80, 054002 (2011)] that vanishing dynamical phase in some composite gates is essential to suppress pulse-length errors. By employing our formalism, we derive a composite unitary gate which can be seen as a concatenation of two known composite unitary operations. The obtained unitary gate has high fidelity over a wider range of error strengths compared to existing composite gates.

  20. A DOE-Funded Design Study for Pioneer Baseload Application Of...

    Open Energy Info (EERE)

    Of an Advanced Geothermal binary Cycle at a Utility Plant in Western Utah Citation W.E. Lewis, M. Ralph. 2002. A DOE-Funded Design Study for Pioneer Baseload Application Of an...

  1. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    SciTech Connect (OSTI)

    Coles, Garill A.; Hockert, John; Gitau, Ernest TN; Zentner, Michael D.

    2013-01-26

    FSA is a screening process intended to focus a facility designers attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  2. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    SciTech Connect (OSTI)

    Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

    2012-11-09

    FSA is a screening process intended to focus a facility designers attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  3. TRU-fueled VHTRs: design, performance, and applications

    SciTech Connect (OSTI)

    Tsvetkov, Pavel V.; Ames, David E. II; Pritchard, Megan L.; Alajo, Ayodeji B.; Lewis, Tom G. III

    2007-07-01

    The Very High Temperature Reactor (VHTR) is the nearest Generation IV concept. This paper presents results of the U.S. DOE NERI Project on utilization of higher actinides (TRUs and partitioned MAs) as a fuel component for extended-life VHTR configurations. The idea is to approach autonomous operation on a single fuel loading that would allow marketing power units with VHTRs as nuclear batteries for worldwide deployment. The research focus is on possible designs and their advantages and limitations. The project is currently within its third year of studies. Although indicating some technical limitations and challenges, studies of VHTRs with TRUs/MAs definitely suggest promising performance and possibility to utilize the core configurations with TRUs/MAs gaining prolonged operation and self-sustainability. (authors)

  4. The design of the AIE: An object-oriented application development system

    SciTech Connect (OSTI)

    Fuja, R.S.; Widing, M.A.

    1992-02-27

    Three years ago, in response to our challenging development context, the Advanced Modeling and Analysis Section designed and implemented an object-oriented environment -- the Application Interface Engine (AIE). Our prototyping requirements forced existing application development systems beyond their capabilities. Programmers at AMAS and its contractors have developed over twenty applications using AIE. Our initial experience has been very positive. AIE extends an object-oriented programming language with syntax and classes to support applications specification. This extended system improves all stages of the application engineering life cycle, from rapid prototyping to long term maintenance.

  5. Vermont Agency of Commerce and Community Development's Criteria...

    Open Energy Info (EERE)

    case-by-case basis and focus on direct and indirect impacts of a substantial nature. Use of these criteria further implements any applicable state and federal review...

  6. Mechanical Design of Hybrid Densitometer for Laboratory Applications

    SciTech Connect (OSTI)

    G. Walton; P. J. Polk; S. -T. Hsue

    1999-01-01

    The hybrid K-edge densitometry (KED) and x-ray fluorescence (XRF) densitometer is a unique nondestructive assay (NDA) technique to determine the concentrations of nuclear material (SNM) in solutions. The technique is ideally suited to assay the dissolver solutions as well as the uranium and plutonium product solutions from reprocessing It is an important instrument for safeguarding reprocessing; it is also a useful tool in analytical laboratories because of its capability of analyzing mixed solutions of SNM without chemical separation. Figure 1 shows the hardware of an hybrid system developed at Los Alamos. The hybrid densitometer employs a combination of two complimentary techniques: absorption KED and XRF. The KED technique measures the transmission of a tightly collimated photon beam through the sample; it is therefore quite insensitive to the radiation emitted by the sample material. Fission product level of {approximately}1 Ci/mL can be tolerated. The technique is insensitive to matrix variation. XRF measures the fluorescent x-rays from the same sample and can be used to determine the ratios of SNM. The technique can be applied to thorium, uranium, neptunium, plutonium, and americium concentration determination. The technique can also be applied to mixed solutions found in nuclear fuel cycle without separation: thorium-uranium, uranium-plutoniun neptunium-plutonium-americium. The design of the hybrid densitometer is shown schematically in Figs. 1 and 2; Fig. 1 shows the top view; Fig. 2 shows the side view. The heart of the design is the changer. The sample changer can accommodate a sample tray, which holds up to six samples. The samples can be a 2-cm path length cell, 4-cm path length cell, or a mixture of both sizes. The sample tray is controlled by a "Compumotor" which in turn is controlled by a computer. The absolute position of the sample cell can be reproduced to a standard deviation of 0.02 mm. The sample changer is housed inside square stainless steel

  7. Designs and applications for floating-hydro power systems in small streams

    SciTech Connect (OSTI)

    Rehder, J.B.

    1983-01-01

    The project focuses on an appropriate technology for small-scale hydro power: floating waterwheels and turbines. For background, relic and existing systems such as early floating mills, traditional Amish waterwheels, and micro-hydro systems are examined. In the design phase of the project, new designs for Floating Hydro Power Systems include: an analysis of floatation materials and systems; a floating undershot waterwheel design; a floating cylinder (fiberglass storage tank) design; a submerged tube design; and a design for a floating platform with submerged propellers. Finally, in the applications phase, stream flow data from East Tennessee streams are used in a discussion of the potential applications of floating hydro power systems in small streams.

  8. Electromechanical battery design suitable for back-up power applications

    DOE Patents [OSTI]

    Post, Richard F.

    2002-01-01

    The windings that couple energy into and out of the rotor of an electro-mechanical battery are modified. The normal stator windings of the generator/motor have been replaced by two orthogonal sets of windings. Because of their orthogonality, they are decoupled from each other electrically, though each can receive (or deliver) power flows from the rotating field produced by the array of permanent magnets. Due to the orthogonal design of the stator windings and the high mechanical inertia of the flywheel rotor, the resulting power delivered to the computer system is completely insensitive to any and all electrical transients and variabilities of the power from the main power source. This insensitivity includes complete failure for a period determined only by the amount of stored kinetic energy in the E-M battery modules that are supplied. Furthermore there is no need whatsoever for fast-acting, fractional-cycle switches, such as are employed in conventional systems, and which are complicated to implement.

  9. Knowledge representation and the application of case-based reasoning in engineering design

    SciTech Connect (OSTI)

    Bhangal, J.S.; Esat, I.

    1996-12-31

    This paper is an assessment of the requirements in the application of Case-based Reasoning to Engineering Design. The methods in which a CBR system will assist a designer when he/she is presented with a problem specification and the various methods which need to be understood before attempting to build an such expert system are discussed here. The problem is two fold, firstly the methods of utilizing CBR are varied and secondly the method of representing the knowledge in design also needs to be established. How a design represented basically differs for each application and this is a decision which needs to be made when setting up the case memory but the methods used are discussed here. CBR itself can also be utilized in various ways and it has been seen from previous applications that a hybrid approach can produce the best results.

  10. Applicability of GALE-86 Codes to Integral Pressurized Water Reactor designs

    SciTech Connect (OSTI)

    Geelhood, Kenneth J.; Rishel, Jeremy P.

    2012-06-01

    This report describes work that Pacific Northwest National Laboratory is doing to assist the U.S. Nuclear Regulatory Commission (NRC) Office of New Reactors (NRO) staff in their reviews of applications for nuclear power plants using new reactor core designs. These designs include small integral PWRs (IRIS, mPower, and NuScale reactor designs), HTGRs, (pebble-bed and prismatic-block modular reactor designs) and SFRs (4S and PRISM reactor designs). Under this specific task, PNNL will assist the NRC staff in reviewing the current versions of the GALE codes and identify features and limitations that would need to be modified to accommodate the technical review of iPWR and mPower® license applications and recommend specific changes to the code, NUREG-0017, and associated NRC guidance. This contract is necessary to support the licensing of iPWRs with a near-term focus on the B&W mPower® reactor design. While the focus of this review is on the mPower® reactor design, the review of the code and the scope of recommended changes consider a revision of the GALE codes that would make them universally applicable for other types of integral PWR designs. The results of a detailed comparison between PWR and iPWR designs are reported here. Also included is an investigation of the GALE code and its basis and a determination as to the applicability of each of the bases to an iPWR design. The issues investigated come from a list provided by NRC staff, the results of comparing the PWR and iPWR designs, the parameters identified as having a large impact on the code outputs from a recent sensitivity study and the main bases identified in NUREG-0017. This report will provide a summary of the gaps in the GALE codes as they relate to iPWR designs and for each gap will propose what work could be performed to fill that gap and create a version of GALE that is applicable to integral PWR designs.

  11. Compact superconducting rf-dipole cavity designs for deflecting and crabbing applications

    SciTech Connect (OSTI)

    De Silva, Subashini; Delayen, Jean R.; Castilla, Alejandro

    2013-06-01

    Over the years the superconducting parallel-bar design has evolved into an rf-dipole cavity with improved properties. The new rf-dipole design is considered for a number of deflecting and crabbing applications. Some of those applications are the 499 MHz rf separator system for the Jefferson Lab 12 GeV upgrade, the 400 MHz crabbing cavity system for the proposed LHC high luminosity upgrade, and the 750 MHz crabbing cavity for the medium energy electron-ion collider in Jefferson Lab. In this paper we present the optimized rf design in terms of rf performance including rf properties, higher order modes (HOM) properties, multipacting and multipole expansion for the above mentioned applications.

  12. Generalized Lawson Criteria for Inertial Confinement Fusion

    SciTech Connect (OSTI)

    Tipton, Robert E.

    2015-08-27

    The Lawson Criterion was proposed by John D. Lawson in 1955 as a general measure of the conditions necessary for a magnetic fusion device to reach thermonuclear ignition. Over the years, similar ignition criteria have been proposed which would be suitable for Inertial Confinement Fusion (ICF) designs. This paper will compare and contrast several ICF ignition criteria based on Lawson’s original ideas. Both analytical and numerical results will be presented which will demonstrate that although the various criteria differ in some details, they are closely related and perform similarly as ignition criteria. A simple approximation will also be presented which allows the inference of each ignition parameter directly from the measured data taken on most shots fired at the National Ignition Facility (NIF) with a minimum reliance on computer simulations. Evidence will be presented which indicates that the experimentally inferred ignition parameters on the best NIF shots are very close to the ignition threshold.

  13. Solar photovoltaic applications seminar: design, installation and operation of small, stand-alone photovoltaic power systems

    SciTech Connect (OSTI)

    Not Available

    1980-07-01

    This seminar material was developed primarily to provide solar photovoltaic (PV) applied engineering technology to the Federal community. An introduction to photoconductivity, semiconductors, and solar photovoltaic cells is included along with a demonstration of specific applications and application identification. The seminar details general systems design and incorporates most known information from industry, academia, and Government concerning small solar cell power system design engineering, presented in a practical and applied manner. Solar PV power system applications involve classical direct electrical energy conversion and electric power system analysis and synthesis. Presentations and examples involve a variety of disciplines including structural analysis, electric power and load analysis, reliability, sizing and optimization; and, installation, operation and maintenance. Four specific system designs are demonstrated: water pumping, domestic uses, navigational and aircraft aids, and telecommunications. All of the applications discussed are for small power requirement (under 2 kilowatts), stand-alone systems to be used in remote locations. Also presented are practical lessons gained from currently installed and operating systems, problems at sites and their resolution, a logical progression through each major phase of system acquisition, as well as thorough design reviews for each application.

  14. Characteristics, design implications, and applicability of passive solar heating systems for buildings

    SciTech Connect (OSTI)

    Givoni, B. )

    1991-01-01

    The paper reviews the performance characteristics of various passive solar heating systems for buildings, the main design factors affecting their performance, the relative advantages and main problems associated with them, and their applicability to different building types and climatic regions. Emphasis is placed on the architectural design issues associated with the different passive solar heating systems and to the problems that may be encountered when passive solar heating is applied in regions with hot summers.

  15. Maintenance Free Fluidic Transfer and Mixing Devices for Highly Radioactive Applications - Design, Development, Deployment and Operational Experience

    SciTech Connect (OSTI)

    Phillips, C.; Richardson, J. E.; Fallows, P.

    2006-07-01

    Power Fluidics is the generic name for a range of maintenance-free fluid transfer and mixing devices, capable of handling a wide range of highly radioactive fluids, jointly developed by British Nuclear Group, its US-based subsidiary BNG America, and AEA Technology. Power Fluidic devices include Reverse Flow Diverters (RFDs), Vacuum Operated Slug Lifts (VOSLs), and Air Lifts, all of which have an excellent proven record for pumping radioactive liquids and sludges. Variants of the RFD, termed Pulse Jet Mixers (PJMs) are used to agitate and mix tank contents, where maintenance-free equipment is desirable, and where a high degree of homogenization is necessary. The equipment is designed around the common principle of using compressed air to provide the motive force to transfer liquids and sludges. These devices have no moving parts in contact with the radioactive medium and therefore require no maintenance in radioactive areas of processing plants. Once commissioned, Power Fluidic equipment has been demonstrated to operate for the life of the facility. Over 800 fluidic devices continue to operate safely and reliably in British Nuclear Group's nuclear facilities at the Sellafield site in the United Kingdom, and some of these have done so for almost 40 years. More than 400 devices are being supplied by AEA Technology and BNG America for the Waste Treatment Plant (WTP) at the Hanford Site in southeastern Washington State, USA. This paper discusses: - Principles of operation of fluidic pumps and mixers. - Selection criteria and design of fluidic pumps and mixers. - Operational experience of fluidic pumps and mixers in the United Kingdom. - Applications of fluidic pumps and mixers at the U.S. Department of Energy nuclear sites. (authors)

  16. Guidelines for preparing and reviewing applications for the licensing of non-power reactors: Standard review plan and acceptance criteria. NUREG - 1537, Part 2

    SciTech Connect (OSTI)

    1996-02-01

    NUREG - 1537, Part 2 gives guidance on the conduct of licensing action reviews to NRC staff who review non-power reactor licensing applications. These licensing actions include construction permits and initial operating licenses, license renewals, amendments, conversions from highly enriched uranium to low-enriched uranium, decommissioning, and license termination.

  17. A comparison of vertical ground heat exchanger design software for commercial applications

    SciTech Connect (OSTI)

    Shonder, J.A.; Baxter, V.D.; Hughes, P.J.; Thornton, J.W.

    2000-07-01

    In previous work, the authors compared a number of commercially available programs for the design of vertical borehole heat exchangers (BHEx) in residential applications. The objective of this paper is to compare four BHEx design programs and a benchmark simulation for a commercial application. An energy use model of an elementary school served by geothermal heat pumps was calibrated with site-collected data to form the benchmark; the school's operation was then simulated for a typical meteorological year at the site, and the outputs from the simulation were used as inputs to the four design programs. Since loads at the school are dominated by heating, the programs were exercised to design borefields with minimum inlet water temperatures of 30 F ({minus}1.1 C), 35 F (1.7 C), and 40 F (4.4 C). On average, the depths predicted by the design programs agreed with the depths predicted by the benchmark program to within about {+-} 14%. Three of the programs were found to provide relatively consistent results: their design lengths varied from the benchmark lengths by {minus}7% to +12%, while designs from the other program varied by about 16% from the benchmark lengths. This is consistent with the results obtained for the residential comparison.

  18. Design and development of Stirling Engines for stationary power generation applications in the 500 to 3000 hp range. Subtask 1A report: state-of-the-art conceptual design

    SciTech Connect (OSTI)

    1980-03-01

    The first portion of the Conceptual Design Study of Stirling Engines for Stationary Power Application in the 500 to 3000 hp range which was aimed at state-of-the-art stationary Stirling engines for a 1985 hardware demonstration is summarized. The main goals of this effort were to obtain reliable cost data for a stationary Stirling engine capable of meeting future needs for total energy/cogeneration sysems and to establish a pragmatic and conservative base design for a first generation hardware. Starting with an extensive screening effort, 4 engine types, i.e., V-type crank engine, radial engine, swashplate engine, and rhombic drive engine, and 3 heat transport systems, i.e., heat pipe, pressurized gas heat transport loop, and direct gas fired system, were selected. After a preliminary layout cycle, the rhombic drive engine was eliminated due to intolerable maintenance difficulties on the push rod seals. V, radial and swashplate engines were taken through a detailed design/layout cycle, to establish all important design features and reliable engine weights. After comparing engine layouts and analyzing qualitative and quantitative evaluation criteria, the V-crank engine was chosen as the candidate for a 1985 hardware demonstration.

  19. Facility Energy Management Guidelines and Criteria for Energy and Water

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

    Evaluations in Covered Facilities | Department of Energy Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Facility Energy Management Guidelines and Criteria for Energy and Water Evaluations in Covered Facilities Guidelines and criteria describe meeting requirements within Section 432 of the Energy Independence and Security Act of 2007 (EISA 2007), including defining facilities covered by the provision, designating facility energy

  20. Application

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

    Application Searchable Application Supplemental Information

  1. Hanford Site solid waste acceptance criteria

    SciTech Connect (OSTI)

    Ellefson, M.D.

    1998-07-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities.

  2. Regulatory compliance in the design of packages used to transport radioactive materials

    SciTech Connect (OSTI)

    Raske, D.T.

    1993-06-01

    Shipments of radioactive materials within the regulatory jurisdiction of the US Department of Energy (DOE) must meet the package design requirements contained in Title 10 of the Code of Federal Regulations, Part 71, and DOE Order 5480.3. These regulations do not provide design criteria requirements, but only detail the approval standards, structural performance criteria, and package integrity requirements that must be met during transport. The DOE recommended design criterion for high-level Category I radioactive packagings is Section III, Division 1, of the ASME Boiler and Pressure Vessel Code. However, alternative design criteria may be used if all the design requirements are satisfied. The purpose of this paper is to review alternatives to the Code criteria and discuss their applicability to the design of containment vessels in packages for high-level radioactive materials. Issues such as design qualification by physical testing, the use of scale models, and problems encountered using a non-ASME design approach are addressed.

  3. The structural design of air and gas ducts for power stations and industrial boiler applications

    SciTech Connect (OSTI)

    Schneider, R.L.

    1996-10-01

    The purpose of this paper is to discuss the new American Society of Civil Engineers (ASCE) book entitled, The Structural Design of Air and Gas Ducts for Power Stations and Industrial Boiler Applications. This 312 page book was published by the ASCE in August of 1995. This ASCE publication was created to assist structural engineers in performing the structural analysis and design of air and flue-gas ducts. The structural behavior of steel ductwork can be difficult to understand for structural engineers inexperienced in ductwork analysis and design. Because of this needed expertise, the ASCE committee that created this document highly recommends that the structural analysis and design of ducts be performed by qualified structural engineers, not be technicians, designers or drafters. There is a history within the power industry of failures and major degradation of flue-gas ductwork. There are many reasons for these failures or degradation, but in many cases, the problems may have been voided by a better initial design. This book attempts to help the structural engineer with this task. This book is not intended to be used to size or configure ductwork for flow and pressure drop considerations. But it does recommend that the ductwork system arrangement consider the structural supports and the structural behavior of the duct system.

  4. A Novel Coupled Resonator Photonic Crystal Design in Lithium Niobate for Electrooptic Applications

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

    Ozturk, Birol; Yavuzcetin, Ozgur; Sridhar, Srinivas

    2015-01-01

    High-aspect-ratio photonic crystal air-hole fabrication on bulk Lithium Niobate (LN) substrates is extremely difficult due to its inherent resistance to etching, resulting in conical structures and high insertion losses. Here, we propose a novel coupled resonator photonic crystal (CRPC) design, combining a coupled resonator approach with that of Bragg gratings. CRPC design parameters were optimized by analytical calculations and FDTD simulations. CRPC structures with optimized parameters were fabricated and electrooptically tested on bulk LN annealed proton exchange waveguides. Low insertion loss and large electrooptic effect were observed with the fabricated devices, making the CRPC design a promising structure for electroopticmore » device applications.« less

  5. Assessment B - Program Criteria | Department of Energy

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

    B - Program Criteria Assessment B - Program Criteria Microsoft Word - Assessment-B-ProgramCriteria (218.66 KB) More Documents & Publications ATTACHMENT A - CHECKLIST FOR SELF ...

  6. Systems Engineering Applications to Wind Energy Research, Design, and Development (Poster)

    SciTech Connect (OSTI)

    Dykes, K.; Damiani, R.; Felker, F.; Graf, P.; Hand, M.; Meadows, R.; Musial, W.; Moriarty, P.; Ning, A.; Scott, G.; Sirnivas, S.; Veers, P.

    2012-06-01

    Over the last few decades, wind energy has evolved into a large international industry involving major players in the manufacturing, construction, and utility sectors. Coinciding with the industry's growth, significant innovation in the technology has resulted in larger turbines with lower associated costs of energy and more complex designs in all subsystems. However, as the deployment of the technology grows, and its role within the electricity sector becomes more prominent, so has the expectations of the technology in terms of performance, reliability, and cost. The industry currently partitions its efforts into separate paths for turbine design, plant design and development, grid interaction and operation, and mitigation of adverse community and environmental impacts. These activities must be integrated to meet a diverse set of goals while recognizing trade-offs between them. To address these challenges, the National Renewable Energy Laboratory (NREL) has embarked on the Wind Energy Systems Engineering (WESE) initiative to use methods of systems engineering in the research, design, and development of wind energy systems. Systems engineering is a field that has a long history of application to complex technical systems. The work completed to date represents a first step in understanding this potential. It reviews systems engineering methods as applied to related technical systems and illustrates how these methods can be combined in a WESE framework to meet the research, design, and development needs for the future of the industry.

  7. Conceptual design report for a Direct Hydrogen Proton Exchange Membrane Fuel Cell for transportation application

    SciTech Connect (OSTI)

    1995-09-05

    This report presents the conceptual design for a Direct-Hydrogen-Fueled Proton Exchange Membrane (PEM) Fuel Cell System for transportation applications. The design is based on the initial selection of the Chrysler LH sedan as the target vehicle with a 50 kW (gross) PEM Fuel Cell Stack (FCS) as the primary power source, a battery-powered Load Leveling Unit (LLU) for surge power requirements, an on-board hydrogen storage subsystem containing high pressure gaseous storage, a Gas Management Subsystem (GMS) to manage the hydrogen and air supplies for the FCS, and electronic controllers to control the electrical system. The design process has been dedicated to the use of Design-to-Cost (DTC) principles. The Direct Hydrogen-Powered PEM Fuel Cell Stack Hybrid Vehicle (DPHV) system is designed to operate on the Federal Urban Driving Schedule (FUDS) and Hiway Cycles. These cycles have been used to evaluate the vehicle performance with regard to range and hydrogen usage. The major constraints for the DPHV vehicle are vehicle and battery weight, transparency of the power system and drive train to the user, equivalence of fuel and life cycle costs to conventional vehicles, and vehicle range. The energy and power requirements are derived by the capability of the DPHV system to achieve an acceleration from 0 to 60 MPH within 12 seconds, and the capability to achieve and maintain a speed of 55 MPH on a grade of seven percent. The conceptual design for the DPHV vehicle is shown in a figure. A detailed description of the Hydrogen Storage Subsystem is given in section 4. A detailed description of the FCS Subsystem and GMS is given in section 3. A detailed description of the LLU, selection of the LLU energy source, and the power controller designs is given in section 5.

  8. Expansion solution of Laplace`s equation: Technique and application to hollow beam gun design

    SciTech Connect (OSTI)

    Jackson, R.H.; Taccetti, J.M.

    1996-12-31

    This paper presents a flexible algorithm for the general calculation of expansion solutions to Laplace`s equation. The limiting factor in application of the technique is shown to be series truncation error and not errors in calculating numerical derivatives. Application of the algorithm to the accurate computation of arbitrary magnetic fields in cylindrical geometry from on-axis or coil data will be presented. For an ideal current loop, magnetic field accuracies of better than 0.01% of the exact elliptic integral solution can be obtained out to approximately 70--80% of the loop radius. Accuracy improves dramatically for radii closer to the axis. Results also is shown for thin current disks, thin solenoids and thick coils. Other aspects of the technique is illustrated by application to the design of a coil system for a hollow beam electron gun. With some reasonable assumptions about the overlay of the electron trajectories and the magnetic flux contours, it is possible to generate an estimate for the on-axis profile of the gun magnetic field. The expansion technique can then be applied to calculate the off-axis field and its impact on the trajectories without assuming any particular coil system. The initial estimate can then be refined and retested. Finally, an optimization technique is used to develop a coil system which closely reproduces the refined field. The results of carrying out this set of calculations on a 150 kV, 20 A hollow electron gun design for an FEL experiment is reported.

  9. EXPO Award Criteria - Hanford Site

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

    Award Criteria About Us Hanford Cultural Resources Charging Your Time Committee Members Contact Us Electronic Registration Form Exhibitor and Vendor Information EXPO 2016 Sponsors EXPO Award Criteria How to Get to TRAC Special Events What is EXPO Why Should I Participate in EXPO EXPO Award Criteria Email Email Page | Print Print Page | Text Increase Font Size Decrease Font Size WRPS won the awards for Most Interactive and Best Overall booth! WRPS won the awards for Most Interactive and Best

  10. Microsoft Word - Assessment-B-ProgramCriteria

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

    ATTACHMENT B PROGRAM ASSESSMENT CRITERIA Identify the following for all sites: Program Management * Number FTE's devoted to Records Management o Full-time Federal and Contractor o Part-time Federal and Contractor Percent of time spent on Records Management duties * Percentage of time each Records Management employee is assigned to: o Program Management o Operations Training/Assistance Schedule Application Records Holding/Storage Area Activities EEOICPA Claims * Monthly Claim Volume Other,

  11. Application Content and Evaluation Criteria/Process

    Broader source: Energy.gov [DOE]

    This presentation by Jill Gruber of the DOE Golden Field Office was given at the Manufacturing Pre-Solicitation Workshop in Arlington, Va., on May 18, 2007.

  12. Coherent imaging with two-dimensional focal-plane arrays: design and applications

    SciTech Connect (OSTI)

    Simpson, M.L.; Bennett, C.A.; Emery, M.S.; Hutchinson, D.P.; Miller, G.H.; Richards, R.K.; Sitter, D.N.

    1997-09-01

    Scanned, single-channel optical heterodyne detection has been used in a variety of lidar applications from ranging and velocity measurements to differential absorption spectroscopy. We describe the design of a coherent camera system that is based on a two-dimensional staring array of heterodyne receivers for coherent imaging applications. Experimental results with a single HgCdTe detector translated in the image plane to form a synthetic two-dimensional array demonstrate the ability to obtain passive heterodyne images of chemical vapor plumes that are invisible to normal video infrared cameras. We describe active heterodyne imaging experiments with use of focal-plane arrays that yield hard-body Doppler lidar images and also demonstrate spatial averaging to reduce speckle effects in static coherent images. {copyright} 1997 Optical Society of America

  13. Engineering design for geothermal commerical and industrial direct heat applications in Salida, Colorado

    SciTech Connect (OSTI)

    Zocholl, J.R.; Meyer, R.T.

    1981-10-01

    The Salida Geothermal Prospect (Poncha Hot Springs) is being evaluated for commercial and industrial direct heat applications in Salida, Colorado, located approximately five miles east. The prospective energy use includes domestic space heating and hot water, commercial space heating and hot water for motels, restaurants, greenhouses, and swimming pools, and industrial space and process heat requirements for existing and future facilities. The objective of the engineering design is to use the full flow capacity of the resource and to provide for the future development of the commercial and industrial sectors of Salida. The engineering evaluation has included significant design features, including cascaded uses of the hot water, conversion of chicken waste, warm water fish hatching, pipeline crossing of a river, and geothermal fluid cooling and discharge to the Arkansas River. Engineering feasibility of the geothermal well supply and of selected user facility retrofits has been demonstrated.

  14. PM Motor Parametric Design Analyses for Hybrid Electric Vehicle Traction Drive Application: Interim Report

    SciTech Connect (OSTI)

    Staunton, R.H.

    2004-08-11

    The Department of Energy's (DOE) Office of FreedomCAR (Cooperative Automotive Research) and Vehicle Technologies has a strong interest in making rapid progress in permanent magnet (PM) machine development. The program is directing various technology development projects that will advance the technology and lead to request for proposals (RFP) for manufacturer prototypes. This aggressive approach is possible because the technology is clearly within reach and the approach is deemed essential, based on strong market demand, escalating fuel prices, and competitive considerations. In response, this study began parallel development paths that included a literature search/review, development and utilization of multiple parametric models to determine the effects of design parameters, verification of the modeling methodology, development of an interior PM (IPM) machine baseline design, development of alternative machine baseline designs, and cost analyses for several candidate machines. This interim progress report summarizes the results of these activities as of June 2004. This report provides background and summary information for recent machine parametric studies and testing programs that demonstrate both the potential capabilities and technical limitations of brushless PM machines (axial gap and radial gap), the IPM machine, the surface-mount PM machines (interior or exterior rotor), induction machines, and switched reluctance machines. The FreedomCAR program, while acknowledging the progress made by Oak Ridge National Laboratory, Delphi, Delco-Remy International, and others in these programs, has redirected efforts toward a ''short path'' to a marketable and competitive PM motor for hybrid electric vehicle traction applications. The program has developed a set of performance targets for the type of traction machine desired. The short-path approach entails a comprehensive design effort focusing on the IPM machine and meeting the performance targets. The selection of the

  15. Design Optimization of Vena Cava Filters: An application to dual filtration devices

    SciTech Connect (OSTI)

    Singer, M A; Wang, S L; Diachin, D P

    2009-12-03

    Pulmonary embolism (PE) is a significant medical problem that results in over 300,000 fatalities per year. A common preventative treatment for PE is the insertion of a metallic filter into the inferior vena cava that traps thrombi before they reach the lungs. The goal of this work is to use methods of mathematical modeling and design optimization to determine the configuration of trapped thrombi that minimizes the hemodynamic disruption. The resulting configuration has implications for constructing an optimally designed vena cava filter. Computational fluid dynamics is coupled with a nonlinear optimization algorithm to determine the optimal configuration of trapped model thrombus in the inferior vena cava. The location and shape of the thrombus are parameterized, and an objective function, based on wall shear stresses, determines the worthiness of a given configuration. The methods are fully automated and demonstrate the capabilities of a design optimization framework that is broadly applicable. Changes to thrombus location and shape alter the velocity contours and wall shear stress profiles significantly. For vena cava filters that trap two thrombi simultaneously, the undesirable flow dynamics past one thrombus can be mitigated by leveraging the flow past the other thrombus. Streamlining the shape of thrombus trapped along the cava wall reduces the disruption to the flow, but increases the area exposed to abnormal wall shear stress. Computer-based design optimization is a useful tool for developing vena cava filters. Characterizing and parameterizing the design requirements and constraints is essential for constructing devices that address clinical complications. In addition, formulating a well-defined objective function that quantifies clinical risks and benefits is needed for designing devices that are clinically viable.

  16. An Overview of Nuclear vs. Non-Nuclear Design Code Requirements for a Candidate Steam Supply System for Commercial Applications

    SciTech Connect (OSTI)

    Robert Jetter

    2011-04-01

    The objective is to identify (mostly for industrial end-users) the difference between a Section III nuclear steam generator (classified as Structures, Systems and Components (SSC)) and a Section VIII steam generator in the same general conditions, but used in a conventional application. Specifically, applicable temperature and pressure ranges and a more quantitative description of how materials change, design margins change and required design rigor changes are of interest. This overview focuses on the steam generator pressure boundary but the downstream piping will also be considered. Within the designations of Section III and Section VIII there are subcategories with their specific regions of applicability. Each of these subcategories has evolved their own unique features with respect to design rules and their implementation. A general overview of the various design codes will be provided in sufficient detail to illustrate the major differences; however, a detailed discussion of the various design requirements and their implementation is beyond the scope of this discussion. References (1) and (2) are sources of more detailed information. Also, example wall sizing calculations will be provided to illustrate the application of the relevant design codes under the candidate design conditions. The candidate steam supply Design Conditions are 600C (1112F) and 24MPa (3,480psi). The Operating Conditions or Service Levels will be somewhat lower and the difference shows up in some of the various design methodologies employed.

  17. Design of an Annular Linear Induction Pump for Nuclear Space Applications

    SciTech Connect (OSTI)

    Carloa O. Maidana; James E. Werner; Daniel M. Wachs

    2011-02-01

    Abstract. The United States Department of Energy's (DOE) Office of Nuclear Energy, Science, and Technology is supporting the National Aeronautics and Space Administration (NASA) in evaluating space mission power, propulsion systems and technologies to support the implementation of the Vision for Space Exploration (VSE). NASA will need increased power for propulsion and for surface power applications to support both robotic and human space exploration missions. As part of the Fission Surface Power Technology Project for the development of nuclear reactor technologies for multi-mission spacecrafts, an Annular Linear Induction Pump, a type of Electromagnetic Pump for liquid metals, able to operate in space has to be designed. Results of such design work are described as well as the fundamental ideas behind the development of an optimized design methodology. This project, which is a collaboration between Idaho National Laboratory (INL), Pacific Northwest National Laboratory (PNNL) and Marshall Space Flight Center (MSFC), involves the use of theoretical, computational and experimental tools for multi-physics analysis as well as advanced engineering design methods and techniques.

  18. Application of Best Industry Practices to the Design of Commercial Refrigerators

    SciTech Connect (OSTI)

    2002-06-30

    The substantial efficiency improvements which have been realized in residential refrigerators over the last twenty years due to implementation of the National Appliance Energy Conservation Act and changing consumer reactions to energy savings give an indication of the potential for improvement in the commercial sector, where few such efficiency improvements have been made to date. The purchase decision for commercial refrigerators is still focused primarily on first cost and product performance issues such as maximizing storage capacity, quick pulldown, durability, and reliability. The project applied techniques used extensively to reduce energy use in residential refrigeration to a commercial reach-in refrigerator. The results will also be applicable to other commercial refrigeration equipment, such as refrigerated vending machines, reach-in freezers, beverage merchandisers, etc. The project described in this paper was a collaboration involving the Appliance and Building Technology Sector of TIAX, the Delfield Company, and the U. S. Department of Energy's Office of Building Technologies. Funding was provided by DOE through Cooperative Agreement No. DE-FC26-00NT41000. The program plan and schedule were structured to assure successful integration of the TIAX work on development of efficient design concepts into Delfield's simultaneous development of the Vantage product line. The energy-saving design options evaluated as part of the development included brushless DC and PSC fan motors, high-efficiency compressors, variable-speed compressor technology, cabinet thermal improvement (particularly in the face frame area), increased insulation thickness, a trap for the condensate line, improved insulation, reduced-wattage antisweat heaters, non-electric antisweat heating, off-cycle defrost termination, rifled heat exchanger tubing, and system optimization (selection of heat exchangers, fans, and subcooling, superheat, and suction temperatures for efficient operation). The

  19. A design methodology for unattended monitoring systems

    SciTech Connect (OSTI)

    SMITH,JAMES D.; DELAND,SHARON M.

    2000-03-01

    The authors presented a high-level methodology for the design of unattended monitoring systems, focusing on a system to detect diversion of nuclear materials from a storage facility. The methodology is composed of seven, interrelated analyses: Facility Analysis, Vulnerability Analysis, Threat Assessment, Scenario Assessment, Design Analysis, Conceptual Design, and Performance Assessment. The design of the monitoring system is iteratively improved until it meets a set of pre-established performance criteria. The methodology presented here is based on other, well-established system analysis methodologies and hence they believe it can be adapted to other verification or compliance applications. In order to make this approach more generic, however, there needs to be more work on techniques for establishing evaluation criteria and associated performance metrics. They found that defining general-purpose evaluation criteria for verifying compliance with international agreements was a significant undertaking in itself. They finally focused on diversion of nuclear material in order to simplify the problem so that they could work out an overall approach for the design methodology. However, general guidelines for the development of evaluation criteria are critical for a general-purpose methodology. A poor choice in evaluation criteria could result in a monitoring system design that solves the wrong problem.

  20. Design Studies for a Multiple Application Thermal Reactor for Irradiation Experiments (MATRIX)

    SciTech Connect (OSTI)

    Pope, Michael A.; Gougar, Hans D.; Ryskamp, J. M.

    2015-03-01

    The Advanced Test Reactor (ATR) is a high power density test reactor specializing in fuel and materials irradiation. For more than 45 years, the ATR has provided irradiations of materials and fuels testing along with radioisotope production. Should unforeseen circumstances lead to the decommissioning of ATR, the U.S. Government would be left without a large-scale materials irradiation capability to meet the needs of its nuclear energy and naval reactor missions. In anticipation of this possibility, work was performed under the Laboratory Directed Research and Development (LDRD) program to investigate test reactor concepts that could satisfy the current missions of the ATR along with an expanded set of secondary missions. A survey was conducted in order to catalogue the anticipated needs of potential customers. Then, concepts were evaluated to fill the role for this reactor, dubbed the Multi-Application Thermal Reactor Irradiation eXperiments (MATRIX). The baseline MATRIX design is expected to be capable of longer cycle lengths than ATR given a particular batch scheme. The volume of test space in In-Pile-Tubes (IPTs) is larger in MATRIX than in ATR with comparable magnitude of neutron flux. Furthermore, MATRIX has more locations of greater volume having high fast neutron flux than ATR. From the analyses performed in this work, it appears that the lead MATRIX design can be designed to meet the anticipated needs of the ATR replacement reactor. However, this design is quite immature, and therefore any requirements currently met must be re-evaluated as the design is developed further.

  1. DOE Standard 1020 - Natural Phenomena Hazard analysis and Design...

    Office of Environmental Management (EM)

    DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE Facilities DOE Standard 1020 - Natural Phenomena Hazard analysis and Design Criteria for DOE ...

  2. APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.; Abramczyk, G.

    2012-07-11

    This paper reports on the development and testing performed to demonstrate the use of flow forming as an alternate method of manufacturing containment vessels for use in radioactive material shipping packaging designs. Additionally, ASME Boiler and Pressure Vessel Code, Section III, Subsection NB compliance along with the benefits compared to typical welding of containment vessels will be discussed. SRNL has completed fabrication development and the testing on flow formed containment vessels to demonstrate the use of flow forming as an alternate method of manufacturing a welded 6-inch diameter containment vessel currently used in the 9975 and 9977 radioactive material shipping packaging. Material testing and nondestructive evaluation of the flow formed parts demonstrate compliance to the minimum material requirements specified in applicable parts of ASME Boiler and Pressure Vessel Code, Section II. Destructive burst testing shows comparable results to that of a welded design. The benefits of flow forming as compared to typical welding of containment vessels are significant: dimensional control is improved due to no weld distortion; less final machining; weld fit-up issues associated with pipes and pipe caps are eliminated; post-weld non-destructive testing (i.e., radiography and die penetrant tests) is not necessary; and less fabrication steps are required. Results presented in this paper indicate some of the benefits in adapting flow forming to design of future radioactive material shipping packages containment vessels.

  3. Probing the molecular design of hyper-branched aryl polyesters towards lubricant applications

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

    Robinson, Joshua W.; Zhou, Yan; Bhattacharya, Priyanka; Erck, Robert; Qu, Jun; Bays, J. Timothy; Cosimbescu, Lelia

    2016-01-05

    We report novel polymeric materials that may be used as viscosity index improvers (VII) for lubricant applications. Our efforts included probing the comb-burst hyper-branched aryl polyester architecture for beneficial viscosity and friction behavior when utilized as an additive in a group I oil. The monomer was designed as to undergo polymerization via polycondensation within the architectural construct (AB2), typical of hyperbranched polymers. The monomer design was comprised of aliphatic arms (12 or 16 methylenes) to provide the necessary lipophilicity to achieve solubility in a non-polar medium. Once polymerized, via catalyst and heat, the surface alcohols were functionalized with fatty acidsmore » (lauric and palmitic). Controlling the aliphatic nature of the internal arms and peripheral end-groups provided four unique flexible polymer designs. Changing the reaction time and concentration provided opportunities to investigate the influence of molecular weight and branching density on oil-solubility, viscosity, and friction. Oil-solubility was found to decrease with fewer internal carbons, but the number of internal carbons appears to have little influence on the bulk solution viscosity. Increased branching and degree of polymerization, and thus molecular weight, were found to reduce the solubility of these systems in the base oil. At concentrations of 2 wt % in a group I base oil, these polymer additives demonstrated improved viscosity index and reduced friction coefficient, validating the basic approach.« less

  4. Innovative coke oven gas cleaning system for retrofit applications. Volume 1, Public design report

    SciTech Connect (OSTI)

    Not Available

    1994-05-24

    This Public Design Report provides, in a single document, available nonproprietary design -information for the ``Innovative Coke Oven Gas Cleaning System for Retrofit Applications`` Demonstration Project at Bethlehem Steel Corporation`s Sparrows Point, Maryland coke oven by-product facilities. This project demonstrates, for the first time in the United States, the feasibility of integrating four commercially available technologies (processes) for cleaning coke oven gas. The four technologies are: Secondary Gas Cooling, Hydrogen Sulfide and Ammonia Removal, Hydrogen Sulfide and Ammonia Recovery, and Ammonia Destruction and Sulfur Recovery. In addition to the design aspects, the history of the project and the role of the US Department of,Energy are briefly discussed. Actual plant capital and projected operating costs are also presented. An overview of the integration (retrofit) of the processes into the existing plant is presented and is followed by detailed non-proprietary descriptions of the four technologies and their overall effect on reducing the emissions of ammonia, sulfur, and other pollutants from coke oven gas. Narrative process descriptions, simplified process flow diagrams, input/output stream data, operating conditions, catalyst and chemical requirements, and utility requirements are given for each unit. Plant startup provisions, environmental considerations and control monitoring, and safety considerations are also addressed for each process.

  5. Direct-hydrogen-fueled proton-exchange-membrane fuel cell system for transportation applications: Conceptual vehicle design report pure fuel cell powertrain vehicle

    SciTech Connect (OSTI)

    Oei, D.; Kinnelly, A.; Sims, R.; Sulek, M.; Wernette, D.

    1997-02-01

    In partial fulfillment of the Department of Energy (DOE) Contract No. DE-AC02-94CE50389, {open_quotes}Direct-Hydrogen-Fueled Proton-Exchange-Membrane (PEM) Fuel Cell for Transportation Applications{close_quotes}, this preliminary report addresses the conceptual design and packaging of a fuel cell-only powered vehicle. Three classes of vehicles are considered in this design and packaging exercise, the Aspire representing the small vehicle class, the Taurus or Aluminum Intensive Vehicle (AIV) Sable representing the mid-size vehicle and the E-150 Econoline representing the van-size class. A fuel cell system spreadsheet model and Ford`s Corporate Vehicle Simulation Program (CVSP) were utilized to determine the size and the weight of the fuel cell required to power a particular size vehicle. The fuel cell power system must meet the required performance criteria for each vehicle. In this vehicle design and packaging exercise, the following assumptions were made: fuel cell power system density of 0.33 kW/kg and 0.33 kg/liter, platinum catalyst loading less than or equal to 0.25 mg/cm{sup 2} total and hydrogen tanks containing gaseous hydrogen under 340 atm (5000 psia) pressure. The fuel cell power system includes gas conditioning, thermal management, humidity control, and blowers or compressors, where appropriate. This conceptual design of a fuel cell-only powered vehicle will help in the determination of the propulsion system requirements for a vehicle powered by a PEMFC engine in lieu of the internal combustion (IC) engine. Only basic performance level requirements are considered for the three classes of vehicles in this report. Each vehicle will contain one or more hydrogen storage tanks and hydrogen fuel for 560 km (350 mi) driving range. Under these circumstances, the packaging of a fuel cell-only powered vehicle is increasingly difficult as the vehicle size diminishes.

  6. Applications of Systems Engineering to the Research, Design, and Development of Wind Energy Systems

    SciTech Connect (OSTI)

    Dykes, K.; Meadows, R.; Felker, F.; Graf, P.; Hand, M.; Lunacek, M.; Michalakes, J.; Moriarty, P.; Musial, W.; Veers, P.

    2011-12-01

    development. To address these challenges, NREL has embarked on an initiative to evaluate how methods of systems engineering can be applied to the research, design and development of wind energy systems. Systems engineering is a field within engineering with a long history of research and application to complex technical systems in domains such as aerospace, automotive, and naval architecture. As such, the field holds potential for addressing critical issues that face the wind industry today. This paper represents a first step for understanding this potential through a review of systems engineering methods as applied to related technical systems. It illustrates how this might inform a Wind Energy Systems Engineering (WESE) approach to the research, design, and development needs for the future of the industry. Section 1 provides a brief overview of systems engineering and wind as a complex system. Section 2 describes these system engineering methods in detail. Section 3 provides an overview of different types of design tools for wind energy with emphasis on NREL tools. Finally, Section 4 provides an overview of the role and importance of software architecture and computing to the use of systems engineering methods and the future development of any WESE programs. Section 5 provides a roadmap of potential research integrating systems engineering research methodologies and wind energy design tools for a WESE framework.

  7. DESIGN & DEVELOPMENT OF E-TURBO FOR SUV AND LIGHT TRUCK APPLICATIONS

    SciTech Connect (OSTI)

    Balis, C; Middlemass, C; Shahed, SM

    2003-08-24

    The purpose of the project is to develop an electronically controlled, electrically assisted turbocharging system, e-Turbo, for application to SUV and light truck class of passenger vehicles. Earlier simulation work had shown the benefits of e-Turbo system on increasing low-end torque and improving fuel economy. This paper will present further data from the literature to show that advanced turbocharging can enable diesel engine downsizing of 10-30% with 6-17% improvement in fuel economy. This is in addition to the fuel economy benefit that a turbocharged diesel engine offers over conventional gasoline engines. E-Turbo is necessary to get acceptable driving characteristics with downsized diesel engines. As a first step towards the development of this technology for SUV/light truck sized diesel engines (4-6 litre displacement), design concepts and hardware were evaluated for a smaller engine (2 litre displacement). It was felt that design and developments issues could be minimized, the concept proven progressively on the bench, on a small engine and then applied to a large Vee engine (one on each bank). After successful demonstration of the concept, large turbomachinery could be designed and built specifically for larger SUV sized diesel engines. This paper presents the results of development of e-Turbo for a 2 litre diesel engine. A detailed comparison of several electric assist technologies including permanent magnet, six-phase induction and conventional induction motor/generator technology was done. A comparison of switched reluctance motor technology was also done although detailed design was not carried out.

  8. PM Motor Parametric Design Analyses for a Hybrid Electric Vehicle Traction Drive Application

    SciTech Connect (OSTI)

    Staunton, R.H.

    2004-10-11

    The Department of Energy's (DOE) Office of FreedomCAR (Cooperative Automotive Research) and Vehicle Technologies office has a strong interest in making rapid progress in permanent magnet (PM) machine development. The DOE FreedomCAR program is directing various technology development projects that will advance the technology and hopefully lead to a near-term request for proposals (RFP) for a to-be-determined level of initial production. This aggressive approach is possible because the technology is clearly within reach and the approach is deemed essential, based on strong market demand, escalating fuel prices, and competitive considerations. In response, this study began parallel development paths that included a literature search/review, development and utilization of multiple parametric models, verification of the modeling methodology, development of an interior PM (IPM) machine baseline design, development of alternative machine baseline designs, and cost analyses for several candidate machines. This report summarizes the results of these activities as of September 2004. This report provides background and summary information for recent machine parametric studies and testing programs that demonstrate both the potential capabilities and technical limitations of brushless PM machines (axial gap and radial gap), the IPM machine, the surface-mount PM machines (interior or exterior rotor), induction machines, and switched-reluctance machines. The FreedomCAR program, while acknowledging the progress made by Oak Ridge National Laboratory (ORNL), Delphi, Delco-Remy International, and others in these programs, has redirected efforts toward a ''short path'' to a marketable and competitive PM motor for hybrid electric vehicle (HEV) traction applications. The program has developed a set of performance targets for the type of traction machine desired. The short-path approach entails a comprehensive design effort focusing on the IPM machine and meeting the performance targets

  9. Design, synthesis, and stability of organic glasses for advanced optical applications

    SciTech Connect (OSTI)

    Chen, S.H.; Shi, H.; Mastrangelo, J.C.; Blanton, T.N.

    1995-12-31

    Organic materials have been actively pursued in recent years for various advanced optical applications based on active and passive device concepts. Polymeric materials are unique in their ability to form glassy films or fibers with good morphological stability, whereas low molar mass counterparts are characterized by relative case of processing. To take advantage of the inherent merits of these two distinctive classes of materials, a novel molecular design concept is formulated in which functional moieties are chemically bonded to excluded-volume cores, resulting in amorphous or liquid crystalline glasses. A series of model compounds have been synthesized based on mesogenic and NLO moieties attached to cyclohexane and bicyclooctene rings. Morphological stability has also characterized in terms of crystallization velocity as a function of temperature. It is concluded that stereochemistry plays a critical role in the ability to vitrify and that low molar mass systems can be as morphologically stable as typical slowly crystallizing polymers, e.g. polystyrene.

  10. Evaluation Criteria for PDIL Proposal

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

    Criteria for PDIL Proposal The selection/decision criteria used by the NCPV Business Development Team are the following: 1. Quality and Relevance of the Proposed Technical Plan (30%) * Technology impact with industry and likelihood of success. Demonstrated benefits of success to both the proposer and NREL to meet the DOE SunShot goals. * Proposed task descriptions and time line. Clear demonstration of entrance and exit strategies in the PDIL. * Extent to which the Proposer and NREL can rapidly

  11. MURMoT. Design and Application of Microbial Uranium Reduction Monitoring Tools

    SciTech Connect (OSTI)

    Loeffler, Frank E.

    2014-12-31

    Uranium (U) contamination in the subsurface is a major remediation challenge at many DOE sites. Traditional site remedies present enormous costs to DOE; hence, enhanced bioremediation technologies (i.e., biostimulation and bioaugmentation) combined with monitoring efforts are being considered as cost-effective corrective actions to address subsurface contamination. This research effort improved understanding of the microbial U reduction process and developed new tools for monitoring microbial activities. Application of these tools will promote science-based site management decisions that achieve contaminant detoxification, plume control, and long-term stewardship in the most efficient manner. The overarching hypothesis was that the design, validation and application of a suite of new molecular and biogeochemical tools advance process understanding, and improve environmental monitoring regimes to assess and predict in situ U immobilization. Accomplishments: This project (i) advanced nucleic acid-based approaches to elucidate the presence, abundance, dynamics, spatial distribution, and activity of metal- and radionuclide-detoxifying bacteria; (ii) developed proteomics workflows for detection of metal reduction biomarker proteins in laboratory cultures and contaminated site groundwater; (iii) developed and demonstrated the utility of U isotopic fractionation using high precision mass spectrometry to quantify U(VI) reduction for a range of reduction mechanisms and environmental conditions; and (iv) validated the new tools using field samples from U-contaminated IFRC sites, and demonstrated their prognostic and diagnostic capabilities in guiding decision making for environmental remediation and long-term site stewardship.

  12. 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.

  13. NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft

    SciTech Connect (OSTI)

    1982-07-01

    This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

  14. Guidelines Establishing Criteria for Excluding Buildings from...

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

    by the Energy Policy Act of 2005 Guidelines Establishing Criteria for Excluding ... This document contains the Guidelines Establishing Criteria for Excluding Buildings from ...

  15. Membership Criteria: Better Buildings Residential Network | Department...

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

    Membership Criteria: Better Buildings Residential Network of the U.S. Department of Energy. Membership Criteria (126.27 KB) More Documents & Publications Better Buildings ...

  16. Performance of R-410A Alternative Refrigerants in a Reciprocating Compressor Designed for Air Conditioning Applications

    SciTech Connect (OSTI)

    Shrestha, Som S; Vineyard, Edward Allan; Mumpower, Kevin

    2016-01-01

    In response to environmental concerns raised by the use of refrigerants with high Global Warming Potential (GWP), the Air-Conditioning, Heating, and Refrigeration Institute (AHRI) has launched an industry-wide cooperative research program, referred to as the Low-GWP Alternative Refrigerants Evaluation Program (AREP), to identify and evaluate promising alternative refrigerants for major product categories. After successfully completing the first phase of the program in December 2013, AHRI launched a second phase of the Low-GWP AREP in 2014 to continue research in areas that were not previously addressed, including refrigerants in high ambient conditions, refrigerants in applications not tested in the first phase, and new refrigerants identified since testing for the program began. Although the Ozone Depletion Potential of R-410A is zero, this refrigerant is under scrutiny due to its high GWP. Several candidate alternative refrigerants have already demonstrated low global warming potential. Performance of these low-GWP alternative refrigerants is being evaluated for Air conditioning and heat pump applications to ensure acceptable system capacity and efficiency. This paper reports the results of a series of compressor calorimeter tests conducted for the second phase of the AREP to evaluate the performance of R-410A alternative refrigerants in a reciprocating compressor designed for air conditioning systems. It compares performance of alternative refrigerants ARM-71A, L41-1, DR-5A, D2Y-60, and R-32 to that of R-410A over a wide range of operating conditions. The tests showed that, in general, cooling capacities were slightly lower (except for the R-32), but energy efficiency ratios (EER) of the alternative refrigerants were comparable to that of R-410A.

  17. Labs21 Environmental Performance Criteria: Toward 'LEED (trademark) for Labs'

    SciTech Connect (OSTI)

    Mathew, Paul; Sartor, Dale; Lintner, William; Wirdzek, Phil

    2002-10-14

    Laboratory facilities present a unique challenge for energy efficient and sustainable design, with their inherent complexity of systems, health and safety requirements, long-term flexibility and adaptability needs, energy use intensity, and environmental impacts. The typical laboratory is about three to five times as energy intensive as a typical office building and costs about three times as much per unit area. In order to help laboratory stakeholders assess the environmental performance of their laboratories, the Labs21 program, sponsored by the US Environmental Protection Agency and the US Department of Energy, is developing the Environmental Performance Criteria (EPC), a point-based rating system that builds on the LEED(TM) rating system. Currently, LEED(TM) is the primary tool used to rate the sustainability of commercial buildings. However, it lacks some attributes essential to encouraging the application of sustainable design principles to laboratory buildings. Accordingly, the EPC has additions and modifications to the prerequisites and credits in each of the six sections of LEED(TM). It is being developed in a consensus-based approach by a diverse group of architects, engineers, consulting experts, health & safety personnel and facilities personnel. This report describes the EPC version 2.0, highlighting the underlying technical issues, and describes implications for the development of a LEED version for Laboratories.

  18. Orthogonal decomposition as a design tool: With application to a mixing impeller

    SciTech Connect (OSTI)

    Sloan, Benjamin

    2013-05-15

    Digital manufacturing eliminates the expense and time required to develop custom products. By utilizing this technology, designers can quickly create a customized product specifically for their performance needs. But the timescale and expense from the engineering design workflows used to develop these customized products have not been adapted from the workflows used in mass production. In many cases these customized designs build upon already successful mass-produced products that were developed using conventional engineering design workflows. Many times as part of this conventional design process significant time is spent creating and validating high fidelity models that accurately predict the performance of the final design. These existing validated high fidelity models used for the mass-produced design can be reused for analysis and design of unknown products. This thesis explores the integration of reduced order modeling and detailed analysis into the engineering design workflow developing a customized design using digital manufacturing. Specifically, detailed analysis is coupled with proper orthogonal decomposition to enable the exploration of the design space while simultaneously shaping the model representing the design. This revised workflow is examined using the design of a laboratory scale overhead mixer impeller. The case study presented here is compared with the design of the Kar Dynamic Mixer impeller developed by The Dow Chemical Company. The result of which is a customized design for a refined set of operating conditions with improved performance.

  19. Criteria Review and Approach Documents | Department of Energy

    Energy Savers [EERE]

    Criteria Review and Approach Documents Criteria Review and Approach Documents CRAD Type Criteria Review and Approach Document List...

  20. Criteria and Review Approach Documents | Department of Energy

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

    Criteria and Review Approach Documents Criteria and Review Approach Documents CRAD Type Criteria and Review Approach Document List

  1. Tornado missile simulation and design methodology. Volume 1: simulation methodology, design applications, and TORMIS computer code. Final report

    SciTech Connect (OSTI)

    Twisdale, L.A.; Dunn, W.L.

    1981-08-01

    A probabilistic methodology has been developed to predict the probabilities of tornado-propelled missiles impacting and damaging nuclear power plant structures. Mathematical models of each event in the tornado missile hazard have been developed and sequenced to form an integrated, time-history simulation methodology. The models are data based where feasible. The data include documented records of tornado occurrence, field observations of missile transport, results of wind tunnel experiments, and missile impact tests. Probabilistic Monte Carlo techniques are used to estimate the risk probabilities. The methodology has been encoded in the TORMIS computer code to facilitate numerical analysis and plant-specific tornado missile probability assessments. Sensitivity analyses have been performed on both the individual models and the integrated methodology, and risk has been assessed for a hypothetical nuclear power plant design case study.

  2. NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

    SciTech Connect (OSTI)

    1981-04-01

    At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

  3. Nuclear Safety Reporting Criteria | Department of Energy

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

    Reporting Criteria Nuclear Safety Reporting Criteria January 1, 2012 Nuclear Safety Noncompliances Associated With Occurrences (DOE Order 232.2) These tables provide the criteria for reporting nuclear safety noncompliances into the Department of Energy's Noncompliance Tracking System (NTS). A more detailed description of the NTS reporting criteria and expectations can be found in the Office of Health, Safety and Security's Enforcement Coordinator Handbook. Nuclear Safety Reporting Criteria

  4. Proposed new accelerator design for homeland security x-ray applications

    SciTech Connect (OSTI)

    Clayton, James; Shedlock, Daniel; Langeveld, Willem G.J.; Bharadwaj, Vinod; Nosochkov, Yuri

    2015-01-01

    Two goals for security scanning of cargo and freight are the ability to determine the type of material that is being imaged, and to do so at low radiation dose. One commonly used technique to determine the effective Z of the cargo is dual-energy imaging, i.e. imaging with different x-ray energy spectra. Another technique uses the fact that the transmitted x-ray spectrum itself also depends on the effective Z. Spectroscopy is difficult because the energy of individual x rays needs to be measured in a very high count-rate environment. Typical accelerators for security applications offer large but short bursts of x-rays, suitable for current-mode integrated imaging. In order to perform x-ray spectroscopy, a new accelerator design is desired that has the following features: 1) increased duty factor in order to spread out the arrival of x-rays at the detector array over time; 2) x-ray intensity modulation from one delivered pulse to the next by adjusting the accelerator electron beam instantaneous current so as to deliver adequate signal without saturating the spectroscopic detector; and 3) the capability to direct the (forward peaked) x-ray intensity towards high-attenuation areas in the cargo (fan-beam-steering). Current sources are capable of 0.1% duty factor, although usually they are operated at significantly lower duty factors (~0.04%), but duty factors in the range 0.4-1.0% are desired. The higher duty factor can be accomplished, e.g., by moving from 300 pulses per second (pps) to 1000 pps and/or increasing the pulse duration from a typical 4 ?s to 10 ?s. This paper describes initial R&D to examine cost effective modifications that could be performed on a typical accelerator for these purposes, as well as R&D for fan-beam steering.

  5. Computational and Experimental Design of Fe-Based Superalloys for Elevated-Temperature Applications

    SciTech Connect (OSTI)

    Liaw, Peter K.; Fine, Morris E.; Ghosh, Gautam; Asta, Mark D.; Liu, Chain T.; Sun, Zhiqian; Huang, Shenyan; Teng, Zhenke; Wang, Gongyao

    2012-04-13

    Analogous to nickel-based superalloys, Fe-based superalloys, which are strengthened by coherent B2- type precipitates are proposed for elevated-temperature applications. During the period of this project, a series of ferritic superalloys have been designed and fabricated by methods of vacuum-arc melting and vacuum-induction melting. Nano-scale precipitates were characterized by atom-probe tomography, ultrasmall- angle X-ray scattering, and transmission-electron microscopy. A duplex distribution of precipitates was found. It seems that ferritic superalloys are susceptible to brittle fracture. Systematic endeavors have been devoted to understanding and resolving the problem. Factors, such as hot rolling, precipitate volume fractions, alloy compositions, precipitate sizes and inter-particle spacings, and hyperfine cooling precipitates, have been investigated. In order to understand the underlying relationship between the microstructure and creep behavior of ferric alloys at elevated temperatures, in-situ neutron studies have been carried out. Based on the current result, it seems that the major role of β' with a 16%-volume fraction in strengthening ferritic alloys is not load sharing but interactions with dislocations. The oxidation behavior of one ferritic alloy, FBB8 (Fe-6.5Al-10Ni-10Cr-3.4Mo-0.25Zr-0.005B, weight percent), was studied in dry air. It is found that it possesses superior oxidation resistance at 1,023 and 1,123 K, compared with other creep-resistant ferritic steels [T91 (modified 9Cr-1Mo, weight percent) and P92 (9Cr-1.8W-0.5Mo, weight percent)]. At the same time, the calculation of the interfacial energies between the -iron and B2-type intermetallics (CoAl, FeAl, and NiAl) has been conducted.

  6. DESIGN ANALYSIS FOR THE NAVAL SNF WASTE PACKAGE

    SciTech Connect (OSTI)

    T.L. Mitchell

    2000-05-31

    The purpose of this analysis is to demonstrate the design of the naval spent nuclear fuel (SNF) waste package (WP) using the Waste Package Department's (WPD) design methodologies and processes described in the ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000b). The calculations that support the design of the naval SNF WP will be discussed; however, only a sub-set of such analyses will be presented and shall be limited to those identified in the ''Waste Package Design Sensitivity Report'' (CRWMS M&O 2000c). The objective of this analysis is to describe the naval SNF WP design method and to show that the design of the naval SNF WP complies with the ''Naval Spent Nuclear Fuel Disposal Container System Description Document'' (CRWMS M&O 1999a) and Interface Control Document (ICD) criteria for Site Recommendation. Additional criteria for the design of the naval SNF WP have been outlined in Section 6.2 of the ''Waste Package Design Sensitivity Report'' (CRWMS M&O 2000c). The scope of this analysis is restricted to the design of the naval long WP containing one naval long SNF canister. This WP is representative of the WPs that will contain both naval short SNF and naval long SNF canisters. The following items are included in the scope of this analysis: (1) Providing a general description of the applicable design criteria; (2) Describing the design methodology to be used; (3) Presenting the design of the naval SNF waste package; and (4) Showing compliance with all applicable design criteria. The intended use of this analysis is to support Site Recommendation reports and assist in the development of WPD drawings. Activities described in this analysis were conducted in accordance with the technical product development plan (TPDP) ''Design Analysis for the Naval SNF Waste Package (CRWMS M&O 2000a).

  7. Long period grating refractive-index sensor: optimal design for single wavelength interrogation

    SciTech Connect (OSTI)

    Kapoor, Amita; Sharma, Enakshi K.

    2009-11-01

    We report the design criteria for the use of long period gratings (LPGs) as refractive-index sensors with output power at a single interrogating wavelength as the measurement parameter. The design gives maximum sensitivity in a given refractive-index range when the interrogating wavelength is fixed. Use of the design criteria is illustrated by the design of refractive-index sensors for specific application to refractive-index variation of a sugar solution with a concentration and detection of mole fraction of xylene in heptane (paraffin).

  8. Proposed new accelerator design for homeland security x-ray applications

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

    Clayton, James; Shedlock, Daniel; Langeveld, Willem G.J.; Bharadwaj, Vinod; Nosochkov, Yuri

    2015-01-01

    Two goals for security scanning of cargo and freight are the ability to determine the type of material that is being imaged, and to do so at low radiation dose. One commonly used technique to determine the effective Z of the cargo is dual-energy imaging, i.e. imaging with different x-ray energy spectra. Another technique uses the fact that the transmitted x-ray spectrum itself also depends on the effective Z. Spectroscopy is difficult because the energy of individual x rays needs to be measured in a very high count-rate environment. Typical accelerators for security applications offer large but short bursts ofmore » x-rays, suitable for current-mode integrated imaging. In order to perform x-ray spectroscopy, a new accelerator design is desired that has the following features: 1) increased duty factor in order to spread out the arrival of x-rays at the detector array over time; 2) x-ray intensity modulation from one delivered pulse to the next by adjusting the accelerator electron beam instantaneous current so as to deliver adequate signal without saturating the spectroscopic detector; and 3) the capability to direct the (forward peaked) x-ray intensity towards high-attenuation areas in the cargo (“fan-beam-steering”). Current sources are capable of 0.1% duty factor, although usually they are operated at significantly lower duty factors (~0.04%), but duty factors in the range 0.4-1.0% are desired. The higher duty factor can be accomplished, e.g., by moving from 300 pulses per second (pps) to 1000 pps and/or increasing the pulse duration from a typical 4 μs to 10 μs. This paper describes initial R&D to examine cost effective modifications that could be performed on a typical accelerator for these purposes, as well as R&D for fan-beam steering.« less

  9. Integrated Design and Rapid Development of Refractory Metal Based Alloys for Fossil Energy Applications

    SciTech Connect (OSTI)

    Dogan, O.N.; King, P.E.; Gao, M.C.

    2008-07-01

    One common barrier in the development of new technologies for future energy generating systems is insufficiency of existing materials at high temperatures (>1150oC) and aggressive atmospheres (e.g., steam, oxygen, CO2). To overcome this barrier, integrated design methodology will be applied to the development of refractory metal based alloys. The integrated design utilizes the multi-scale computational methods to design materials for requirements of processing and performance. This report summarizes the integrated design approach to the alloy development and project accomplishments in FY 2008.

  10. Standard terminal panel and UPS (uninterruptible power supply) design for exterior intrusion detectors and data collection applications

    SciTech Connect (OSTI)

    Wolfenbarger, F.M.

    1989-01-01

    Need for standardization has been discussed for years by many government agencies. In the past, every perimeter site upgrade resulted in the design, specification, procurement, and fabrication of a unique power and signal junction box. To save design and specification cost, a standard terminal panel and uninterruptible power supply (UPS) design for an exterior intrusion sensor detection system was developed for a security system within the Sandia National Laboratories complex at Albuquerque, New Mexico. In facilitating this requirement a design was sought that could easily be modified for other government or commercial applications and one that could easily be fabricated in the shop. Also of primary importance was the need for lightning protection for both the communications and voltage sources. A 12V dc UPS with a current capacity of up to 4 amperes complements the standard terminal design and allows uninterrupted sensor operation for a number of hours should the primary ac source be interrupted. This report encompasses the features of the designs. The designs are also being used and continuously evaluated in Sandia's Area III exterior test field. 7 figs.

  11. Design and evaluation of hybrid wind/PV/diesel power systems for Brazilian applications

    SciTech Connect (OSTI)

    McGowan, J.G.; Manwell, J.F.; Avelar, C.; Warner, C.

    1996-12-31

    This paper presents a summary of a study centered on the design and evaluation of hybrid wind/PV/diesel systems for remote locations in Brazil. The objective of this work was to evaluate high reliability hybrid power systems that have been designed for the lowest life cycle costs. The technical and economic analysis of the hybrid wind/PV/diesel systems was carried out using HYBRID2, a computational code developed at the University of Massachusetts in conjunction with the National Renewable Energy Laboratory (NREL). After a summary of a generalized design procedure for such systems based on the use of this code, a systematic parametric evaluation of a representative design case for a village power system in Brazil is presented. As summarized in the paper, the performance and economic effects of key design parameters are illustrated. 8 refs., 10 figs.

  12. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    SciTech Connect (OSTI)

    Not Available

    1993-03-01

    The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

  13. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect (OSTI)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  14. Application of the ASME code in designing containment vessels for packages used to transport radioactive materials

    SciTech Connect (OSTI)

    Raske, D.T.; Wang, Z.

    1992-07-01

    The primary concern governing the design of shipping packages containing radioactive materials is public safety during transport. When these shipments are within the regulatory jurisdiction of the US Department of Energy, the recommended design criterion for the primary containment vessel is either Section III or Section VIII, Division 1, of the ASME Boiler and Pressure Vessel Code, depending on the activity of the contents. The objective of this paper is to discuss the design of a prototypic containment vessel representative of a packaging for the transport of high-level radioactive material.

  15. A handbook for solar central receiver design

    SciTech Connect (OSTI)

    Falcone, P.K.

    1986-12-01

    This Handbook describes central receiver technology for solar thermal power plants. It contains a description and assessment of the major components in a central receiver system configured for utility scale production of electricity using Rankine-cycle steam turbines. It also describes procedures to size and optimize a plant and discussed examples from recent system analyses. Information concerning site selection criteria, cost estimation, construction, and operation and maintenance is also included, which should enable readers to perform design analyses for specific applications.

  16. Evaluation of the three-phase, electric arc melting furnace for treatment of simulated, thermally oxidized radioactive and mixed wastes. Part 1: Design criteria and description of integrated waste treatment facility

    SciTech Connect (OSTI)

    Oden, L.L.; O`Connor, W.K.; Turner, P.C.; Hartman, A.D.

    1995-06-01

    The US Bureau of Mines and the Department of Energy (DOE), through its contractor EG and G Idaho Inc., are collaborating on a multiyear research project to evaluate the applicability of three-phase, electric-arc furnace melting technology to vitrify materials simulating low-level radioactive and mixed wastes buried or stored at the Idaho National Engineering Laboratory and other DOE sites. The melter is sealed, 1-t (1.1-st), three-phase, 800-kV {center_dot} A electric arc melting furnace with 10.2-cm- (4-in-) diameter graphite electrodes, water-cooled roof and sidewalls, and four water-cooled feed tubes. A water-cooled copper fixture provides for continuous tapping of slag. An instrumented air pollution control system (APCS) with access ports for analysis and a feeder based on screw conveyors and a bucket elevator are dedicated to the facility. Test data are provided by an arc furnace analyzer and by sensors indicating feed rate; slag temperature; and temperature, pressure, and velocity in the APCS. These data are received by a data logger, digitized, and transmitted to a personal computer for storage and display. This unique waste treatment facility is available for public and private use on a cost-sharing basis.

  17. Falcon: automated optimization method for arbitrary assessment criteria

    DOE Patents [OSTI]

    Yang, Tser-Yuan; Moses, Edward I.; Hartmann-Siantar, Christine

    2001-01-01

    FALCON is a method for automatic multivariable optimization for arbitrary assessment criteria that can be applied to numerous fields where outcome simulation is combined with optimization and assessment criteria. A specific implementation of FALCON is for automatic radiation therapy treatment planning. In this application, FALCON implements dose calculations into the planning process and optimizes available beam delivery modifier parameters to determine the treatment plan that best meets clinical decision-making criteria. FALCON is described in the context of the optimization of external-beam radiation therapy and intensity modulated radiation therapy (IMRT), but the concepts could also be applied to internal (brachytherapy) radiotherapy. The radiation beams could consist of photons or any charged or uncharged particles. The concept of optimizing source distributions can be applied to complex radiography (e.g. flash x-ray or proton) to improve the imaging capabilities of facilities proposed for science-based stockpile stewardship.

  18. Wind Turbine Design Guideline DG03: Yaw and Pitch Rolling Bearing Life

    SciTech Connect (OSTI)

    Harris, T.; Rumbarger, J. H.; Butterfield, C. P.

    2009-12-01

    This report describes the design criteria, calculation methods, and applicable standards recommended for use in performance and life analyses of ball and roller (rolling) bearings for yaw and pitch motion support in wind turbine applications. The formulae presented here for rolling bearing analytical methods and bearing-life ratings are consistent with methods in current use by wind turbine designers and rolling-bearing manufacturers.

  19. Development of thermal performance criteria for residential passive solar buildings

    SciTech Connect (OSTI)

    Sabatiuk, P.A.; Cassel, D.E.; McCabe, M.; Scarbrough, C.

    1980-01-01

    In support of the development of thermal performance criteria for residential passive solar buildings, thermal design characteristics and anticipated performance for 266 projects in the HUD Passive Residential Design Competition and the HUD Cycle 5 Demonstration Program were analyzed. These passive residences are located in all regions of the United States requiring space heating, and they represent a variety of passive solar system types including direct gain, indirect gain, and solarium (isolated gain) systems. The results of this statistical analysis are being used to develop proposed minimum acceptable levels of thermal performance for passive solar buildings for the residential performance criteria. A number of performance measures were examined, including net solar contribution, solar fraction, and auxiliary energy use. These and other design and climate-related parameters were statistically correlated using the DATAPLOT computer program and standard statistical analysis techniques.

  20. Investigation of conductor swinging by wind and its application for design of compact transmission line

    SciTech Connect (OSTI)

    Tsujimoto, K.; Fujii, K.; Kubokawa, H.; Okomura, T.; Simojima, K.; Yoshioka, V.

    1982-11-01

    In Japan it has recently become necessary to shorten the interphase spacing in overhead transmission lines because of land limitations and economical considerations. In this connection, the authors have attempted to analyze, in-depth, the possibilities of shortened interphase spacing via conductor swinging caused by wind effects: one of the important factors in the design of more compact overhead lines. This paper describes not only the investigative results of conductor swinging that were obtained both through computer simulation and in 3 years of full scale field line testing, but also design methodology for compact overhead lines based on these results.

  1. Design and first cold test of BNL superconducting 112 MHz QWR for electron gun applications

    SciTech Connect (OSTI)

    Belomestnykh, S.; Ben-Zvi, I.; Boulware, C.H.; Chang, X.; Grimm, T.L.; Siegel, B.; Than, R.; Winowski, M.

    2011-03-28

    Brookhaven National Laboratory and Niowave, Inc. have designed, fabricated, and performed the first cold test of a superconducting 112 MHz quarter-wave resonator (QWR) for electron gun experiments. The first cold test of the QWR cryomodule has been completed at Niowave. The paper discusses the cryomodule design, presents the cold test results, and outline plans to upgrade the cryomodule for future experiments. A quarter-wave resonator concept of superconducting RF (SRF) electron gun was proposed at BNL for electron cooling ion/proton beams at RHIC. QWRs can be made sufficiently compact even at low RF frequencies (long wavelengths). The long wavelength allows to produce long electron bunches, thus minimizing space charge effects and enabling high bunch charge. Also, such guns should be suitable for experiments requiring high average current electron beams. A 112 MHz QWR gun was designed, fabricated, and cold-tested in collaboration between BNL and Niowave. This is the lowest frequency SRF gun ever tested successfully. In this paper we describe the gun design and fabrication, present the cold test results, and outline plans for the cryomodule upgrade for future experiments.

  2. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

  3. Numerical design of SiC bulk crystal growth for electronic applications

    SciTech Connect (OSTI)

    Wejrzanowski, T.; Grybczuk, M.; Kurzydlowski, K. J.; Tymicki, E.

    2014-10-06

    Presented study concerns numerical simulation of Physical Vapor Transport (PVT) growth of bulk Silicon Carbide (SiC) crystals. Silicon Carbide is a wide band gap semiconductor, with numerous applications due to its unique properties. Wider application of SiC is limited by high price and insufficient quality of the product. Those problems can be overcame by optimizing SiC production methods. Experimental optimization of SiC production is expensive because it is time consuming and requires large amounts of energy. Numerical modeling allows to learn more about conditions inside the reactor and helps to optimize the process at much lower cost. In this study several simulations of processes with different reactor geometries were presented along with discussion of reactor geometry influence on obtained monocrystal shape and size.

  4. Protocol, Inspection Criteria - April 23, 2008 | Department of...

    Energy Savers [EERE]

    Protocol, Inspection Criteria - April 23, 2008 Protocol, Inspection Criteria - April 23, 2008 April 23, 2008 Inspection Criteria, Activities, and Lines of Inquiry, April 23, 2008...

  5. Proposed New Accelerator Design for Homeland Security X-Ray Applications

    SciTech Connect (OSTI)

    Clayton, James; Shedlock, Daniel; Langeveld, Willem G.J.; Bharadwaj, Vinod; Nosochkov, Yuri

    2015-08-07

    In the security and inspection market, there is a push towards highly mobile, reduced-dose active interrogation scanning and imaging systems to allow operation in urban environments. To achieve these goals, the accelerator system design needs to be smaller than existing systems. A smaller radiation exclusion zone may be accomplished through better beam collimation and an integrated, x-ray-source/detector-array assembly to allow feedback and control of an intensity-modulated x-ray source. A shaped low-Z target in the x-ray source can be used to generate a more forward peaked x-ray beam. Electron-beam steering can then be applied to direct the forward-peaked x rays toward areas in the cargo with high attenuation. This paper presents an exploratory study to identify components and upgrades that would be required to meet the desired specifications, as well as the best technical approach to design and build a prototype.

  6. Nuclear Safety Design Principles & the Concept of Independence: Insights from Nuclear Weapon Safety for Other High-Consequence Applications.

    SciTech Connect (OSTI)

    Brewer, Jeffrey D.

    2014-05-01

    Insights developed within the U.S. nuclear weapon system safety community may benefit system safety design, assessment, and management activities in other high consequence domains. The approach of assured nuclear weapon safety has been developed that uses the Nuclear Safety Design Principles (NSDPs) of incompatibility, isolation, and inoperability to design safety features, organized into subsystems such that each subsystem contributes to safe system responses in independent and predictable ways given a wide range of environmental contexts. The central aim of the approach is to provide a robust technical basis for asserting that a system can meet quantitative safety requirements in the widest context of possible adverse or accident environments, while using the most concise arrangement of safety design features and the fewest number of specific adverse or accident environment assumptions. Rigor in understanding and applying the concept of independence is crucial for the success of the approach. This paper provides a basic description of the assured nuclear weapon safety approach, in a manner that illustrates potential application to other domains. There is also a strong emphasis on describing the process for developing a defensible technical basis for the independence assertions between integrated safety subsystems.

  7. Analysis of the impact of safeguards criteria

    SciTech Connect (OSTI)

    Mullen, M.F.; Reardon, P.T.

    1981-01-01

    As part of the US Program of Technical Assistance to IAEA Safeguards, the Pacific Northwest Laboratory (PNL) was asked to assist in developing and demonstrating a model for assessing the impact of setting criteria for the application of IAEA safeguards. This report presents the results of PNL's work on the task. The report is in three parts. The first explains the technical approach and methodology. The second contains an example application of the methodology. The third presents the conclusions of the study. PNL used the model and computer programs developed as part of Task C.5 (Estimation of Inspection Efforts) of the Program of Technical Assistance. The example application of the methodology involves low-enriched uranium conversion and fuel fabrication facilities. The effects of variations in seven parameters are considered: false alarm probability, goal probability of detection, detection goal quantity, the plant operator's measurement capability, the inspector's variables measurement capability, the inspector's attributes measurement capability, and annual plant throughput. Among the key results and conclusions of the analysis are the following: the variables with the greatest impact on the probability of detection are the inspector's measurement capability, the goal quantity, and the throughput; the variables with the greatest impact on inspection costs are the throughput, the goal quantity, and the goal probability of detection; there are important interactions between variables. That is, the effects of a given variable often depends on the level or value of some other variable. With the methodology used in this study, these interactions can be quantitatively analyzed; reasonably good approximate prediction equations can be developed using the methodology described here.

  8. Technical Qualification Program Accreditation Objectives and Criteria |

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

    Department of Energy Objectives and Criteria Technical Qualification Program Accreditation Objectives and Criteria The program clearly identifies and documents the process used to demonstrate employee technical competence. TQP Accreditation Objectives and Criteria (40.57 KB) More Documents & Publications Technical Qualification Program Self-Assessment Report - Sandia Site Office - 2012 Technical Qualification Program Self-Assessment Report - Richland Operations Office - 2014 Technical

  9. Alloy Design and Thermomechanical Processing of a Beta Titanium Alloy for a Heavy Vehicle Application

    SciTech Connect (OSTI)

    Blue, C.A.; Peter, W.H.

    2010-07-02

    With the strength of steel, but at half the weight, titanium has the potential to offer significant benefits in the weight reduction of heavy vehicle components while possibly improving performance. However, the cost of conventional titanium fabrication is a major barrier in implementation. New reduction technologies are now available that have the potential to create a paradigm shift in the way the United States uses titanium, and the economics associated with fabrication of titanium components. This CRADA project evaluated the potential to develop a heavy vehicle component from titanium powders. The project included alloy design, development of manufacturing practices, and modeling the economics associated with the new component. New Beta alloys were designed for this project to provide the required mechanical specifications while utilizing the benefits of the new fabrication approach. Manufacturing procedures were developed specific to the heavy vehicle component. Ageing and thermal treatment optimization was performed to provide the desired microstructures. The CRADA partner established fabrication practices and targeted capital investment required for fabricating the component out of titanium. Though initial results were promising, the full project was not executed due to termination of the effort by the CRADA partner and economic trends observed in the heavy vehicle market.

  10. Security Enforcement Reporting Criteria | Department of Energy

    Office of Environmental Management (EM)

    Mandatory Security Incident Reporting This document provides information and criteria for reporting classified information security incidents and noncompliances to the Department ...

  11. Nevada National Security Site Waste Acceptance Criteria

    National Nuclear Security Administration (NNSA)

    Nevada National Security Site Waste Acceptance Criteria Prepared by U.S. Department of Energy National Nuclear Security Administration Nevada Field Office Environmental...

  12. Proposal Writing Guidelines and Scoring Criteria

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

    when the reasons for choosing a specific beamline are clearly stated, e.g., unique features, required resolution, higher flux, etc. Criteria for Evaluating the Scientific...

  13. WPN 99-7- WAP Eligibility Criteria

    Broader source: Energy.gov [DOE]

    To provide states with guidance on the interpretation of certain eligibility criteria for use in the low-income Weatherization Assistance Program.

  14. Application of Nuclear Energy for Seawater Desalination: Design Concepts of Nuclear Desalination Plants

    SciTech Connect (OSTI)

    Faibish, R.S.; Konishi, T.; Gasparini, M.

    2002-07-01

    Nuclear energy is playing an important role in electricity generation, producing 16% of the world's electricity. However, most of the world's energy consumption is in the form of heat, in which case nuclear energy could also play an important role. In particular, process heat for seawater desalination using nuclear energy has been of growing interest to some Member States of the International Atomic Energy Agency over the past two decades. This growing interest stems from increasingly acute freshwater shortages in many arid and semi-arid zones around the world. Indeed, several national and international nuclear desalination demonstration programs are already under way or being planned. Of particular interest are projects for seawater nuclear desalination plants in coastal regions, where saline feed water can serve the dual purpose of cooling water for the nuclear reactor and as feed water for the desalination plant. In principle any nuclear reactor can provide energy (low-grade heat and/or electricity), as required by desalination processes. However, there are some additional requirements to be met under specific conditions in order to introduce nuclear desalination. Technical issues include meeting more stringent safety requirements (nuclear reactors themselves and nuclear-desalination integrated complexes in particular), and performance improvement of the integrated systems. Economic competitiveness is another important factor to be considered for a broader deployment of nuclear desalination. For technical robustness and economic competitiveness a number of design variants of coupling configurations of nuclear desalination integrated plant concepts are being evaluated. This paper identifies and discusses various factors, which support the attractiveness of nuclear desalination. It further summarizes some of the key approaches recommended for nuclear desalination complex design and gives an overview of various design concepts of nuclear desalination plants, which

  15. Natural Phenomena Hazards Analysis and Design Criteria for DOE...

    Office of Environmental Management (EM)

    to existing hazard category 1, 2, and 3 nuclear facilities, and for 10-year NPH ... of Natural Phenomena Hazards for DOE Nuclear and Non-Nuclear Facilities; ...

  16. Natural Phenomena Hazards Analysis and Design Criteria for DOE...

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

    ... mitigating extreme wind hazards (i.e., extreme straight-line winds, rapid atmospheric pressure changes (APCs) from tornadoes, tornado missiles, hurricanes, and hurricane missiles). ...

  17. UNDERSTANDING SEISMIC DESIGN CRITERIA FOR JAPANESE NUCLEAR POWER...

    Office of Scientific and Technical Information (OSTI)

    FOR JAPANESE NUCLEAR POWER PLANTS Y.J. Park and C.H. Hofmayer Brookhaven National Laboratory Upton, Long Island, New York 11973 J.F. Costello U.S. Nuclear Regulatory ...

  18. Electrical and mechanical design criteria for EHV and UHV: overhead...

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

    Report Number(s): DOERA2133-01 DOE Contract Number: AC01-77ET29236 Resource Type: Technical Report Research Org: Main (Charles T.), Inc., Boston, MA (USA) Country of Publication: ...

  19. Natural Phenomena Hazards Analysis and Design Criteria for DOE...

    Energy Savers [EERE]

    ... winds, rapid atmospheric pressure changes (APCs) ... hurricane-induced water surges and ... that house emergency generators and fuel shall be ...

  20. Natural Phenomena Hazards Design and Evaluation Criteria for...

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

    ... for Nuclear Power Generating Stations NFPA 13-96 Installation of Sprinkler Systems ... O 420.1 and the associated Guides, and Executive Orders 12699 and 12941 for earthquakes. ...

  1. 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).

  2. Design Analysis Kit for Optimization and Terascale Applications 6.0

    Energy Science and Technology Software Center (OSTI)

    2015-10-19

    Sandia's Dakota software (available at http://dakota.sandia.gov) supports science and engineering transformation through advanced exploration of simulations. Specifically it manages and analyzes ensembles of simulations to provide broader and deeper perspective for analysts and decision makers. This enables them to: (1) enhance understanding of risk, (2) improve products, and (3) assess simulation credibility. In its simplest mode, Dakota can automate typical parameter variation studies through a generic interface to a computational model. However, Dakota also deliversmore » advanced parametric analysis techniques enabling design exploration, optimization, model calibration, risk analysis, and quantification of margins and uncertainty with such models. It directly supports verification and validation activities. The algorithms implemented in Dakota aim to address challenges in performing these analyses with complex science and engineering models from desktop to high performance computers.« less

  3. Design Analysis Kit for Optimization and Terascale Applications 6.0

    SciTech Connect (OSTI)

    2015-10-19

    Sandia's Dakota software (available at http://dakota.sandia.gov) supports science and engineering transformation through advanced exploration of simulations. Specifically it manages and analyzes ensembles of simulations to provide broader and deeper perspective for analysts and decision makers. This enables them to: (1) enhance understanding of risk, (2) improve products, and (3) assess simulation credibility. In its simplest mode, Dakota can automate typical parameter variation studies through a generic interface to a computational model. However, Dakota also delivers advanced parametric analysis techniques enabling design exploration, optimization, model calibration, risk analysis, and quantification of margins and uncertainty with such models. It directly supports verification and validation activities. The algorithms implemented in Dakota aim to address challenges in performing these analyses with complex science and engineering models from desktop to high performance computers.

  4. Resilient Monitoring Systems: Architecture, Design, and Application to Boiler/Turbine Plant

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

    Garcia, Humberto E.; Lin, Wen-Chiao; Meerkov, Semyon M.; Ravichandran, Maruthi T.

    2014-11-01

    Resilient monitoring systems, considered in this paper, are sensor networks that degrade gracefully under malicious attacks on their sensors, causing them to project misleading information. The goal of this work is to design, analyze, and evaluate the performance of a resilient monitoring system intended to monitor plant conditions (normal or anomalous). The architecture developed consists of four layers: data quality assessment, process variable assessment, plant condition assessment, and sensor network adaptation. Each of these layers is analyzed by either analytical or numerical tools. The performance of the overall system is evaluated using a simplified boiler/turbine plant. The measure of resiliencymore » is quantified using Kullback-Leibler divergence, and is shown to be sufficiently high in all scenarios considered.« less

  5. Resilient Monitoring Systems: Architecture, Design, and Application to Boiler/Turbine Plant

    SciTech Connect (OSTI)

    Garcia, Humberto E.; Lin, Wen-Chiao; Meerkov, Semyon M.; Ravichandran, Maruthi T.

    2014-11-01

    Resilient monitoring systems, considered in this paper, are sensor networks that degrade gracefully under malicious attacks on their sensors, causing them to project misleading information. The goal of this work is to design, analyze, and evaluate the performance of a resilient monitoring system intended to monitor plant conditions (normal or anomalous). The architecture developed consists of four layers: data quality assessment, process variable assessment, plant condition assessment, and sensor network adaptation. Each of these layers is analyzed by either analytical or numerical tools. The performance of the overall system is evaluated using a simplified boiler/turbine plant. The measure of resiliency is quantified using Kullback-Leibler divergence, and is shown to be sufficiently high in all scenarios considered.

  6. Application of finite element, global polynomial, and kriging response surfaces in Progressive Lattice Sampling designs

    SciTech Connect (OSTI)

    ROMERO,VICENTE J.; SWILER,LAURA PAINTON; GIUNTA,ANTHONY A.

    2000-04-25

    This paper examines the modeling accuracy of finite element interpolation, kriging, and polynomial regression used in conjunction with the Progressive Lattice Sampling (PLS) incremental design-of-experiments approach. PLS is a paradigm for sampling a deterministic hypercubic parameter space by placing and incrementally adding samples in a manner intended to maximally reduce lack of knowledge in the parameter space. When combined with suitable interpolation methods, PLS is a formulation for progressive construction of response surface approximations (RSA) in which the RSA are efficiently upgradable, and upon upgrading, offer convergence information essential in estimating error introduced by the use of RSA in the problem. The three interpolation methods tried here are examined for performance in replicating an analytic test function as measured by several different indicators. The process described here provides a framework for future studies using other interpolation schemes, test functions, and measures of approximation quality.

  7. Predicted performance of an Induction Linac Driven FEL amplifier designed for radar applications at 94 GHz

    SciTech Connect (OSTI)

    Caplan, M.

    1991-08-01

    The saturated performance of an Induction Linac Driven FEL operating at 94 GHz with peak microwave powers in excess of 2 GW is evaluated using a self-consistent 3D waveguide mode-particle interaction code. The code includes the effect of AC longitudinal space charge and DC transverse space charge with the resulting prediction that operation is not possible below 2.5 MeV with a 2 kA beam and 10 cm wiggler. A design based around a 4 MeV beam predicts peak power in excess of 2.4 GW over a 10% bandwidth with output phase varying linear with frequency. 2 refs., 5 figs., 1 tab.

  8. Design of experiments and data analysis challenges in calibration for forensics applications

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

    Anderson-Cook, Christine M.; Burr, Thomas L.; Hamada, Michael S.; Ruggiero, Christy E.; Thomas, Edward V.

    2015-07-15

    Forensic science aims to infer characteristics of source terms using measured observables. Our focus is on statistical design of experiments and data analysis challenges arising in nuclear forensics. More specifically, we focus on inferring aspects of experimental conditions (of a process to produce product Pu oxide powder), such as temperature, nitric acid concentration, and Pu concentration, using measured features of the product Pu oxide powder. The measured features, Y, include trace chemical concentrations and particle morphology such as particle size and shape of the produced Pu oxide power particles. Making inferences about the nature of inputs X that were usedmore » to create nuclear materials having particular characteristics, Y, is an inverse problem. Therefore, statistical analysis can be used to identify the best set (or sets) of Xs for a new set of observed responses Y. One can fit a model (or models) such as Υ = f(Χ) + error, for each of the responses, based on a calibration experiment and then “invert” to solve for the best set of Xs for a new set of Ys. This perspectives paper uses archived experimental data to consider aspects of data collection and experiment design for the calibration data to maximize the quality of the predicted Ys in the forward models; that is, we assume that well-estimated forward models are effective in the inverse problem. In addition, we consider how to identify a best solution for the inferred X, and evaluate the quality of the result and its robustness to a variety of initial assumptions, and different correlation structures between the responses. In addition, we also briefly review recent advances in metrology issues related to characterizing particle morphology measurements used in the response vector, Y.« less

  9. Design of experiments and data analysis challenges in calibration for forensics applications

    SciTech Connect (OSTI)

    Anderson-Cook, Christine M.; Burr, Thomas L.; Hamada, Michael S.; Ruggiero, Christy E.; Thomas, Edward V.

    2015-07-15

    Forensic science aims to infer characteristics of source terms using measured observables. Our focus is on statistical design of experiments and data analysis challenges arising in nuclear forensics. More specifically, we focus on inferring aspects of experimental conditions (of a process to produce product Pu oxide powder), such as temperature, nitric acid concentration, and Pu concentration, using measured features of the product Pu oxide powder. The measured features, Y, include trace chemical concentrations and particle morphology such as particle size and shape of the produced Pu oxide power particles. Making inferences about the nature of inputs X that were used to create nuclear materials having particular characteristics, Y, is an inverse problem. Therefore, statistical analysis can be used to identify the best set (or sets) of Xs for a new set of observed responses Y. One can fit a model (or models) such as ? = f(?) + error, for each of the responses, based on a calibration experiment and then invert to solve for the best set of Xs for a new set of Ys. This perspectives paper uses archived experimental data to consider aspects of data collection and experiment design for the calibration data to maximize the quality of the predicted Ys in the forward models; that is, we assume that well-estimated forward models are effective in the inverse problem. In addition, we consider how to identify a best solution for the inferred X, and evaluate the quality of the result and its robustness to a variety of initial assumptions, and different correlation structures between the responses. We also briefly review recent advances in metrology issues related to characterizing particle morphology measurements used in the response vector, Y.

  10. Design of experiments and data analysis challenges in calibration for forensics applications

    SciTech Connect (OSTI)

    Anderson-Cook, Christine M.; Burr, Thomas L.; Hamada, Michael S.; Ruggiero, Christy E.; Thomas, Edward V.

    2015-07-15

    Forensic science aims to infer characteristics of source terms using measured observables. Our focus is on statistical design of experiments and data analysis challenges arising in nuclear forensics. More specifically, we focus on inferring aspects of experimental conditions (of a process to produce product Pu oxide powder), such as temperature, nitric acid concentration, and Pu concentration, using measured features of the product Pu oxide powder. The measured features, Y, include trace chemical concentrations and particle morphology such as particle size and shape of the produced Pu oxide power particles. Making inferences about the nature of inputs X that were used to create nuclear materials having particular characteristics, Y, is an inverse problem. Therefore, statistical analysis can be used to identify the best set (or sets) of Xs for a new set of observed responses Y. One can fit a model (or models) such as Υ = f(Χ) + error, for each of the responses, based on a calibration experiment and then “invert” to solve for the best set of Xs for a new set of Ys. This perspectives paper uses archived experimental data to consider aspects of data collection and experiment design for the calibration data to maximize the quality of the predicted Ys in the forward models; that is, we assume that well-estimated forward models are effective in the inverse problem. In addition, we consider how to identify a best solution for the inferred X, and evaluate the quality of the result and its robustness to a variety of initial assumptions, and different correlation structures between the responses. In addition, we also briefly review recent advances in metrology issues related to characterizing particle morphology measurements used in the response vector, Y.