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Sample records for asme section viii

  1. Overview of new rules and recent changes in ASME code, Section VIII, pressure vessels

    SciTech Connect (OSTI)

    Farr, J.R.

    1995-12-01

    In this presentation, some of the new rules and recent changes to the ASME Boiler and Pressure Vessel Code, Section 8, Divisions 1 and 2, are reviewed. On July 1, 1995, the 1995 Edition of the ASME Code was issued. This 1995 Edition incorporates those items which were added of changed in the 1992, 1993, and 1994 Addenda to the 1992 Edition of the Code. The 1995 Edition contains no new items which were not included in the previous edition and three addenda. With the possibility of an extended time before some of the new rules are able to appear in the addenda, the recent trend is to put the rules in Code Cases which are approved earlier. Consequently, it is necessary to review new Code Cases as well as Code changes. Updates continue for impact requirements for standard components as well as for materials other than UCS, carbon steel and low alloys. Extensive changes have been made for UHA, high-alloy, materials regarding impact requirements. Example problems have been revised to include these effects. Significant changes are reviewed.

  2. Economic advantages of Division 2 design for vessels per ASME Code Section VIII

    SciTech Connect (OSTI)

    Lengsfeld, M.; Holman, R.; Lengsfeld, P.F.

    1995-12-01

    ASME Boiler and Pressure Vessel Code Section 8, Division 2 has been available since 1968 for the design of pressure equipment. Industry has generally accepted this code for the design of high pressure vessels, high pressure being relative. Some consider high pressure above 3,000 PSIG, others look at high pressure above 1,000 or 1,500 PSIG. There are organizations who tie the use of Division 2 to thickness, meaning vessels in a thickness range above 3 to 4 inches as worthwhile to design to Division 2. In this paper the authors discuss the use of Division 2 strictly as an economic issue. Independent of thickness, if say a 3/4 in. thick vessel is lower in cost designed to Division 2 vs Division 1 why would one not build this vessel using Division 2 as the design basis?

  3. TECHNICAL BASIS AND APPLICATION OF NEW RULES ON FRACTURE CONTROL OF HIGH PRESSURE HYDROGEN VESSEL IN ASME SECTION VIII, DIVISION 3 CODE

    SciTech Connect (OSTI)

    Rawls, G

    2007-04-30

    As a part of an ongoing activity to develop ASME Code rules for the hydrogen infrastructure, the ASME Boiler and Pressure Vessel Code Committee approved new fracture control rules for Section VIII, Division 3 vessels in 2006. These rules have been incorporated into new Article KD-10 in Division 3. The new rules require determining fatigue crack growth rate and fracture resistance properties of materials in high pressure hydrogen gas. Test methods have been specified to measure these fracture properties, which are required to be used in establishing the vessel fatigue life. An example has been given to demonstrate the application of these new rules.

  4. A Review & Assessment of Current Operating Conditions Allowable Stresses in ASME Section III Subsection NH

    SciTech Connect (OSTI)

    R. W. Swindeman

    2009-12-14

    The current operating condition allowable stresses provided in ASME Section III, Subsection NH were reviewed for consistency with the criteria used to establish the stress allowables and with the allowable stresses provided in ASME Section II, Part D. It was found that the S{sub o} values in ASME III-NH were consistent with the S values in ASME IID for the five materials of interest. However, it was found that 0.80 S{sub r} was less than S{sub o} for some temperatures for four of the materials. Only values for alloy 800H appeared to be consistent with the criteria on which S{sub o} values are established. With the intent of undertaking a more detailed evaluation of issues related to the allowable stresses in ASME III-NH, the availabilities of databases for the five materials were reviewed and augmented databases were assembled.

  5. Design practices in Japan for the super high pressure vessels and comparison with the ASME Code Sect. VIII Div. 3 (under preparation)

    SciTech Connect (OSTI)

    Onozawa, Tsutomu; Tahara, Takayasu

    1995-12-01

    Recently, super high pressure facilities have been increasing in the industrial area so that to establish the regulatory standard to regulate the super high pressure vessels is a matter of great urgency world widely to keep the industrial safety. Under such a situation, the author shows respect to the ASME Code Committee for their efforts to publish the super high pressure vessel code. Mr. Leslie P. Antalffy, Fluor Daniel, Incorporated, Houston, Texas presented a paper during the 1993 and 1994 ASME PVP Conferences that ASME Code Committee has been preparing the rules of Division 3 of Section 8 of the Boiler and Pressure Vessel Code and explained its outline. In this paper, the authors shows the current super high pressure vessel design practices in Japan and explain the merit and problem area of these formulas comparing with the ASME formula and necessary conditions for the fatigue analysis.

  6. Status of ASME Section III Task Group on Graphite Support Core Structures

    SciTech Connect (OSTI)

    Robert L. Bratton; Tim D. Burchell

    2005-08-01

    This report outlines the roadmap that the ASME Project Team on Graphite Core Supports is pursuing to establish design codes for unirradiated and irradiated graphite core components during its first year of operation. It discusses the deficiencies in the proposed Section III, Division 2, Subsection CE graphite design code and the different approaches the Project Team has taken to address those deficiencies.

  7. Welding and brazing qualifications (supplement to ASME Boiler and Pressure Vessel Code, Section IX)

    SciTech Connect (OSTI)

    Not Available

    1981-11-01

    This standard supplements the requirements of the 1980 edition of the ASME Boiler and Pressure Vessel Code (the Code), Section IX. When this standard is invoked or referenced, the applicable subsections of Section IX of the Code are also invoked or referenced. The paragraph numbers in this standard apply only to the 1980 edition of Section IX and its addenda. The user of this standard is responsible for obtaining and applying the edition and revision of this standard that supplement the edition and addenda of Section IX that are in legal effect at the time of use.

  8. Welding and brazing qualifications (supplement to ASME boiler and pressure vessel code, Section IX)

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    This standard supplements the requirements of the 1977 edition of the ASME Boiler and Pressure Vessel Code (the Code), Section IX. When this standard is invoked or referenced, the applicable subsections of Section IX of the Code are also invoked or referenced. The paragraph numbers apply only to the 1977 edition of Section IX and its addenda. The user of this standard is responsible for obtaining and applying the edition and revision of this standard that supplement the edition and Addenda of Section IX that are in legal effect at the time of use.

  9. Reviews of ASME Section 11 pump and valve relief requests: Post Generic Letter 89-04

    SciTech Connect (OSTI)

    DiBiasio, A.

    1992-07-01

    This paper presents a discussion of ASME Section 11 Pump and Valve Inservice Testing relief request reviews by the NRC and their contractors. Topics that will be discussed include the scope of USNRC reviews in Technical Evaluation Reports (TERs) (and Safety Evaluation, SEs); including the basis for granting relief requests, the status of relief requests in IST Program updates, and the Generic Letter 89-04 approval process; and the level of technical detail required in submitted programs. This presentation is based on the experiences of Brookhaven National Laboratory in reviewing IST Programs for the Mechanical Engineering Branch of the US Nuclear Regulatory Commission.

  10. Reviews of ASME Section 11 pump and valve relief requests: Post Generic Letter 89-04

    SciTech Connect (OSTI)

    DiBiasio, A.

    1992-01-01

    This paper presents a discussion of ASME Section 11 Pump and Valve Inservice Testing relief request reviews by the NRC and their contractors. Topics that will be discussed include the scope of USNRC reviews in Technical Evaluation Reports (TERs) (and Safety Evaluation, SEs); including the basis for granting relief requests, the status of relief requests in IST Program updates, and the Generic Letter 89-04 approval process; and the level of technical detail required in submitted programs. This presentation is based on the experiences of Brookhaven National Laboratory in reviewing IST Programs for the Mechanical Engineering Branch of the US Nuclear Regulatory Commission.

  11. REVIEW OF PROPOSED METHODOLOGY FOR A RISK- INFORMED RELAXATION TO ASME SECTION XI APPENDIX G

    SciTech Connect (OSTI)

    Dickson, Terry L; Kirk, Mark

    2010-01-01

    The current regulations, as set forth by the United States Nuclear Regulatory Commission (NRC), to insure that light-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to planned normal reactor startup (heat-up) and shut-down (cool-down) transients are specified in Appendix G to 10 CFR Part 50, which incorporates by reference Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Code. The technical basis for these regulations are now recognized by the technical community as being conservative and some plants are finding it increasingly difficult to comply with the current regulations. Consequently, the nuclear industry has developed, and submitted to the ASME Code for approval, an alternative risk-informed methodology that reduces the conservatism and is consistent with the methods previously used to develop a risk-informed revision to the regulations for accidental transients such as pressurized thermal shock (PTS). The objective of the alternative methodology is to provide a relaxation to the current regulations which will provide more operational flexibility, particularly for reactor pressure vessels with relatively high irradiation levels and radiation sensitive materials, while continuing to provide reasonable assurance of adequate protection to public health and safety. The NRC and its contractor at Oak Ridge National Laboratory (ORNL) have recently performed an independent review of the industry proposed methodology. The NRC / ORNL review consisted of performing probabilistic fracture mechanics (PFM) analyses for a matrix of cool-down and heat-up rates, permutated over various reactor geometries and characteristics, each at multiple levels of embrittlement, including 60 effective full power years (EFPY) and beyond, for various postulated flaw characterizations. The objective of this review is to quantify the risk of a reactor vessel experiencing non-ductile fracture, and possible

  12. ASME Material Challenges for Advanced Reactor Concepts

    SciTech Connect (OSTI)

    Piyush Sabharwall; Ali Siahpush

    2013-07-01

    This study presents the material Challenges associated with Advanced Reactor Concept (ARC) such as the Advanced High Temperature Reactor (AHTR). ACR are the next generation concepts focusing on power production and providing thermal energy for industrial applications. The efficient transfer of energy for industrial applications depends on the ability to incorporate cost-effective heat exchangers between the nuclear heat transport system and industrial process heat transport system. The heat exchanger required for AHTR is subjected to a unique set of conditions that bring with them several design challenges not encountered in standard heat exchangers. The corrosive molten salts, especially at higher temperatures, require materials throughout the system to avoid corrosion, and adverse high-temperature effects such as creep. Given the very high steam generator pressure of the supercritical steam cycle, it is anticipated that water tube and molten salt shell steam generators heat exchanger will be used. In this paper, the ASME Section III and the American Society of Mechanical Engineers (ASME) Section VIII requirements (acceptance criteria) are discussed. Also, the ASME material acceptance criteria (ASME Section II, Part D) for high temperature environment are presented. Finally, lack of ASME acceptance criteria for thermal design and analysis are discussed.

  13. Creep Effects on Design below the Temperature Limits of ASME Section III Subsection NB

    SciTech Connect (OSTI)

    Sham, Sam; Jetter, Robert I; Eno, D.R.

    2010-01-01

    Some recent studies of material response have identified an issue that crosses over and blurs the boundary between ASME Boiler and Pressure Vessel Code Section III Subsection NB and Subsection NH. For very long design lives, the effects of creep show up at lower and lower temperature as the design life increases. Although true for the temperature at which the allowable stress is governed by creep properties, the effect is more apparent, e.g. creep effects show up sooner, at local structural discontinuities and peak thermal stress locations. This is because creep is a function of time, temperature and stress and the higher the localized stress, the lower in temperature creep begins to cause damage. If the threshold is below the Subsection NB to NH temperature boundary, 700 F for ferritic steels and 800 F for austenitic materials, then this potential failure mode will not be considered. Unfortunately, there is no experience base with very long lives at temperatures close to but under the Subsection NB to NH boundary to draw upon. This issue is of particular interest in the application of Subsection NB rules of construction to some High Temperature Gas Reactor (HTGR) concepts. The purpose of this paper is, thus, twofold; one part is about statistical treatment and extrapolation of sparse data for a specific material of interest, A533B; the other part is about how these results could impact current design procedures in Subsection NB.

  14. Verification of Allowable Stresses In ASME Section III Subsection NH For Grade 91 Steel & Alloy 800H

    SciTech Connect (OSTI)

    R. W. Swindeman; M. J. Swindeman; B. W. Roberts; B. E. Thurgood; D. L. Marriott

    2007-11-30

    The database for the creep-rupture of 9Cr-1Mo-V (Grade 91) steel was collected and reviewed to determine if it met the needs for recommending time-dependent strength values, S{sub t}, for coverage in ASME Section III Subsection NH (ASME III-NH) to 650 C (1200 F) and 600,000 hours. The accumulated database included over 300 tests for 1% total strain, nearly 400 tests for tertiary creep, and nearly 1700 tests to rupture. Procedures for analyzing creep and rupture data for ASME III-NH were reviewed and compared to the procedures used to develop the current allowable stress values for Gr 91 for ASME II-D. The criteria in ASME III-NH for estimating S{sub t} included the average strength for 1% total strain for times to 600,000 hours, 80% of the minimum strength for tertiary creep for times to 600,000 hours, and 67% of the minimum rupture strength values for times to 600,000 hours. Time-temperature-stress parametric formulations were selected to correlate the data and make predictions of the long-time strength. It was found that the stress corresponding to 1% total strain and the initiation of tertiary creep were not the controlling criteria over the temperature-time range of concern. It was found that small adjustments to the current values in III-NH could be introduced but that the existing values were conservative and could be retained. The existing database was found to be adequate to extend the coverage to 600,000 hours for temperatures below 650 C (1200 F).

  15. ASME Code requirements for multi-canister overpack design and fabrication

    SciTech Connect (OSTI)

    SMITH, K.E.

    1998-11-03

    The baseline requirements for the design and fabrication of the MCO include the application of the technical requirements of the ASME Code, Section III, Subsection NB for containment and Section III, Subsection NG for criticality control. ASME Code administrative requirements, which have not historically been applied at the Hanford site and which have not been required by the US Nuclear Regulatory Commission (NRC) for licensed spent fuel casks/canisters, were not invoked for the MCO. As a result of recommendations made from an ASME Code consultant in response to DNFSB staff concerns regarding ASME Code application, the SNF Project will be making the following modifications: issue an ASME Code Design Specification and Design Report, certified by a Registered Professional Engineer; Require the MCO fabricator to hold ASME Section III or Section VIII, Division 2 accreditation; and Use ASME Authorized Inspectors for MCO fabrication. Incorporation of these modifications will ensure that the MCO is designed and fabricated in accordance with the ASME Code. Code Stamping has not been a requirement at the Hanford site, nor for NRC licensed spent fuel casks/canisters, but will be considered if determined to be economically justified.

  16. QSO ABSORPTION SYSTEMS DETECTED IN Ne VIII: HIGH-METALLICITY CLOUDS WITH A LARGE EFFECTIVE CROSS SECTION

    SciTech Connect (OSTI)

    Meiring, J. D.; Tripp, T. M. [Department of Astronomy, University of Massachusetts, Amherst, MA 01003 (United States)] [Department of Astronomy, University of Massachusetts, Amherst, MA 01003 (United States); Werk, J. K.; Prochaska, J. X. [University of California Observatories-Lick Observatory, UC Santa Cruz, CA 95064 (United States)] [University of California Observatories-Lick Observatory, UC Santa Cruz, CA 95064 (United States); Howk, J. C. [Department of Physics, University of Notre Dame, 225 Nieuwland Science Hall, Notre Dame, IN 46556 (United States)] [Department of Physics, University of Notre Dame, 225 Nieuwland Science Hall, Notre Dame, IN 46556 (United States); Jenkins, E. B. [Princeton University Observatory, Peyton Hall, Ivy Lane, Princeton, NJ 08544 (United States)] [Princeton University Observatory, Peyton Hall, Ivy Lane, Princeton, NJ 08544 (United States); Lehner, N.; Sembach, K. R. [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States)] [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States)

    2013-04-10

    Using high-resolution, high signal-to-noise ultraviolet spectra of the z{sub em} = 0.9754 quasar PG1148+549 obtained with the Cosmic Origins Spectrograph (COS) on the Hubble Space Telescope, we study the physical conditions and abundances of Ne VIII+O VI absorption line systems at z{sub abs} = 0.68381, 0.70152, 0.72478. In addition to Ne VIII and O VI, absorption lines from multiple ionization stages of oxygen (O II, O III, O IV) are detected and are well aligned with the more highly ionized species. We show that these absorbers are multiphase systems including hot gas (T Almost-Equal-To 10{sup 5.7} K) that produces Ne VIII and O VI, and the gas metallicity of the cool phase ranges from Z = 0.3 Z{sub Sun} to supersolar. The cool ( Almost-Equal-To 10{sup 4} K) phases have densities n{sub H} Almost-Equal-To 10{sup -4} cm{sup -3} and small sizes (<4 kpc); these cool clouds are likely to expand and dissipate, and the Ne VIII may be within a transition layer between the cool gas and a surrounding, much hotter medium. The Ne VIII redshift density, dN/dz{approx}7{sup +7}{sub -3}, requires a large number of these clouds for every L > 0.1 L* galaxy and a large effective absorption cross section ({approx}> 100 kpc), and indeed, we find a star-forming {approx}L {sup *} galaxy at the redshift of the z{sub abs} = 0.72478 system, at an impact parameter of 217 kpc. Multiphase absorbers like these Ne VIII systems are likely to be an important reservoir of baryons and metals in the circumgalactic media of galaxies.

  17. ASME95

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

    D. P. Burwinkle, "The Spectral Content of the Torque Loads on a Turbine Gear Tooth," Wind Energy - 1995, Musial, Hock and Berg (eds), SED-Vol. 16, ASME, January-February 1995, pp....

  18. DEVELOPMENT OF ASME SECTION X CODE RULES FOR HIGH PRESSURE COMPOSITE HYDROGEN PRESSURE VESSELS WITH NON-LOAD SHARING LINERS

    SciTech Connect (OSTI)

    Rawls, G.; Newhouse, N.; Rana, M.; Shelley, B.; Gorman, M.

    2010-04-13

    The Boiler and Pressure Vessel Project Team on Hydrogen Tanks was formed in 2004 to develop Code rules to address the various needs that had been identified for the design and construction of up to 15000 psi hydrogen storage vessel. One of these needs was the development of Code rules for high pressure composite vessels with non-load sharing liners for stationary applications. In 2009, ASME approved new Appendix 8, for Section X Code which contains the rules for these vessels. These vessels are designated as Class III vessels with design pressure ranging from 20.7 MPa (3,000 ps)i to 103.4 MPa (15,000 psi) and maximum allowable outside liner diameter of 2.54 m (100 inches). The maximum design life of these vessels is limited to 20 years. Design, fabrication, and examination requirements have been specified, included Acoustic Emission testing at time of manufacture. The Code rules include the design qualification testing of prototype vessels. Qualification includes proof, expansion, burst, cyclic fatigue, creep, flaw, permeability, torque, penetration, and environmental testing.

  19. 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.

  20. Implementation of ASME Code, Section XI, Code Case N-770, on Alternative Examination Requirements for Class 1 Butt Welds Fabricated with Alloy 82/182

    SciTech Connect (OSTI)

    Sullivan, Edmund J.; Anderson, Michael T.

    2012-09-17

    In May 2010, the NRC issued a proposed notice of rulemaking that includes a provision to add a new section to its rules to require licensees to implement ASME Code Case N-770, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without the Application of Listed Mitigation Activities, Section XI, Division 1, with 15 conditions. Code Case N-770 contains baseline and inservice inspection (ISI) requirements for unmitigated butt welds fabricated with Alloy 82/182 material and preservice and ISI requirements for mitigated butt welds. The NRC stated that application of ASME Code Case N-770 is necessary because the inspections currently required by the ASME Code, Section XI, were not written to address stress corrosion cracking Alloy 82/182 butt welds, and the safety consequences of inadequate inspections can be significant. The NRC expects to issue the final rule incorporating this code case into its regulations in the spring 2011 time frame. This paper discusses the new examination requirements, the conditions that NRC is imposing , and the major concerns with implementation of the new Code Case.

  1. 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.

  2. Foley elected ASM International Fellow

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

    Foley elected ASM International Fellow Foley elected ASM International Fellow James Foley is the 10th ASM Fellow from LANL. July 8, 2014 James Foley James Foley The Society...

  3. ASME89p125.PDF

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

    and H.J. Sutherland, "Fatigue Characterization of a VAWT Blade material," Eight ASME Wind Energy Symposium, D.E. Berg and P.C. Klimas (eds), SED-Vol. 7, ASME, January 1989, pp....

  4. The First ASME Code Stamped Cryomodule at SNS

    SciTech Connect (OSTI)

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

    2012-07-01

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

  5. Foley elected ASM International Fellow

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

    to microscopy sample preparation, the team provides microstructure characterization using optical and electron microscopy. Foley serves on the board of trustees for ASM...

  6. Aikin and Cerreta named as ASM Fellows

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

    Aikin and Cerreta named as ASM Fellows Aikin and Cerreta named as ASM Fellows ASM International named Beverly Aikin and Ellen Cerreta to the 2016 class of Fellows. August 1, 2016 Beverly Aikin, left, and Ellen Cerreta Beverly Aikin, left, and Ellen Cerreta Communications Office (505) 667-7000 ASM Fellows are technical and professional leaders who have been recognized by their colleagues and serve as advisors to the Society. ASM International named Beverly Aikin of Sigma Division (SIGMA) and

  7. ASME Code Efforts Supporting HTGRs

    SciTech Connect (OSTI)

    D.K. Morton

    2012-09-01

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

  8. ASME Code Efforts Supporting HTGRs

    SciTech Connect (OSTI)

    D.K. Morton

    2011-09-01

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

  9. ASME Code Efforts Supporting HTGRs

    SciTech Connect (OSTI)

    D.K. Morton

    2010-09-01

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

  10. ASM International NV | Open Energy Information

    Open Energy Info (EERE)

    back-end markets, including production technology for wafer processing, assembly and packaging of semiconductor devices. References: ASM International NV1 This article is a...

  11. ASME1-98A.PDF

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

    "Aeroelastic Behaviou of Twisted-Coupled HAWT Blades," Proceedings of the 1998 ASME Wind Energy Symposium, January 1998. AEROELASTIC BEHAVIOR OF TWIST-COUPLED HAWT BLADES Don W....

  12. Understanding DOE Quality Assurance Requirements and ASME NQA...

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

    DOE Quality Assurance Requirements and ASME NQA-1 For Application in DOE Nuclear Projects Training Agenda Understanding DOE Quality Assurance Requirements and ASME NQA-1 For ...

  13. Sandia Energy - 2015 VIII MECHANICAL BEHAVIOR OF SALT

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

    VIII MECHANICAL BEHAVIOR OF SALT Home Stationary Power Nuclear Fuel Cycle Nuclear Energy Workshops 2015 VIII MECHANICAL BEHAVIOR OF SALT 2015 VIII MECHANICAL BEHAVIOR OF...

  14. ASME95_CurveFit.PDF

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

    Veers, "Effects of Cyclic Stress Distribution Models on Fatigue Life Predictions," Wind Energy - 1995, Musial, Hock and Berg (eds), SED-Vol. 16, ASME, January-February 1995, pp....

  15. American Society of Mechanical Engineers (ASME) Power & Energy Conference

    Broader source: Energy.gov [DOE]

    Location: San Diego Convention CenterWebsite: https://www.asme.org/events/power-energyDescription: In 2015, four of ASME's major conferences come together to create an event of major impact for the...

  16. Alexander and Lienert selected as ASM International Fellows

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

    Alexander and Lienert selected as ASM International Fellows Alexander and Lienert selected as ASM International Fellows David Alexander and Thomas Lienert are among ASM International's 2013 Class of Fellows, who are honored for their distinguished contributions to materials science and engineering. November 6, 2013 Thomas Lienert, left, and David Alexander Thomas Lienert, left, and David Alexander A total of nine ASM fellows have come from Los Alamos over the years, according to the society,

  17. ASM Materials Camp 2015 | Y-12 National Security Complex

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

    ASM Materials Camp 2015 ASM Materials Camp 2015 The mp4 video format is not supported by this browser. Download video Captions: On Time: 3:17 min. Twenty students participated in the ASM Materials camp where they analyzed pieces of the Columbia space shuttle

  18. Understanding DOE Quality Assurance Requirements and ASME NQA-1 For

    Office of Environmental Management (EM)

    Application in DOE Nuclear Projects Training Agenda | Department of Energy Agenda Understanding DOE Quality Assurance Requirements and ASME NQA-1 For Application in DOE Nuclear Projects Training Agenda Agenda for the Understanding DOE Quality Assurance Requirements and ASME NQA-1 For Application in DOE Nuclear Projects Training Workshop held on May 14, 2015. Agenda (36.02 KB) More Documents & Publications Understanding DOE Quality Assurance Requirements and ASME NQA-1 For Application in

  19. Singh receives ASM International fellowship | Argonne National Laboratory

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

    Singh receives ASM International fellowship By Kate Thackrey * June 27, 2016 Tweet EmailPrint Dileep Singh of the Energy Systems Division at Argonne National Laboratory has been named a fellow of ASM International, formerly known as the American Society for Metals. Singh is the leader of Argonne's Energy Systems Thermal-Mechanical Technologies Group. He will be honored at the ASM awards dinner on October 25, 2016, in Salt Lake City, Utah. Singh was chosen "for pioneering contributions and

  20. Understanding DOE Quality Assurance Requirements and ASME NQA...

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

    Materials for the Understanding DOE Quality Assurance Requirements and ASME NQA-1 For Application in DOE Nuclear ... DOE Nuclear Projects, A Management Overview and ...

  1. Understanding and Implementing DOE Quality Requirements and ASME...

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

    Requirements and ASME NQA-1 in DOE Nuclear Projects, A Management Overview and Introduction, May 14, ... The class will be held May 14, 2015. Agenda Training Materials Training ...

  2. Students analyze artificial implants at ASM Materials Camp |...

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

    Students analyze artificial ... Students analyze artificial implants at ASM Materials Camp Posted: June 10, 2013 - 8:37am Student Hunter Stombaugh loads a material sample into the...

  3. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    SciTech Connect (OSTI)

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the {open_quotes}construction{close_quotes} of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc.

  4. Dow Chemical Company-Oyster Creek VIII | Open Energy Information

    Open Energy Info (EERE)

    Dow Chemical Company-Oyster Creek VIII Jump to: navigation, search Name: Dow Chemical Company-Oyster Creek VIII Place: Texas Phone Number: 1 989-636-1000; 1 800-331-6451 Website:...

  5. Tracking the Sun VIII (Technical Report) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Tracking the Sun VIII Citation Details In-Document Search Title: Tracking the Sun VIII Funded by the SunShot Initiative, this report summarizes trends in the ...

  6. ASM Asset Management DTVM SA | Open Energy Information

    Open Energy Info (EERE)

    Asset Management DTVM SA Jump to: navigation, search Name: ASM Asset Management DTVM SA Place: Rio de Janeiro, Rio de Janeiro, Brazil Zip: 22640-100 Sector: Carbon, Services...

  7. NREL's National Wind Technology Center Director Named ASME Fellow

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

    National Wind Technology Center Director Named ASME Fellow For more information contact: Terry Monrad, (303) 275-4096 Golden, Colo., January 25, 1996 -- Dr. Robert W. Thresher, director of the National Wind Technology Center (NWTC), will receive the grade of Fellow from the American Society of Mechanical Engineers (ASME) in ceremonies Jan. 29, 1996, in Houston, Texas. The NWTC, part of the Department of Energy's National Renewable Energy Laboratory (NREL), conducts research on advanced wind

  8. Understanding DOE Quality Assurance Requirements and ASME NQA-1 For

    Office of Environmental Management (EM)

    Application in DOE Nuclear Projects Training Materials | Department of Energy Materials Understanding DOE Quality Assurance Requirements and ASME NQA-1 For Application in DOE Nuclear Projects Training Materials Training Materials for the Understanding DOE Quality Assurance Requirements and ASME NQA-1 For Application in DOE Nuclear Projects Training Workshop held on May 14, 2015. Training Materials (4.27 MB) More Documents & Publications Understanding DOE Quality Assurance Requirements

  9. Chapter VIII: Enhancing Employment and Workforce Training

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

    -14 QER Report: Energy Transmission, Storage, and Distribution Infrastructure | April 2015 Chapter VIII: Enhancing Employment and Workforce Training QER Report: Energy Transmission, Storage, and Distribution Infrastructure | April 2015 9-1 Chapter IX This chapter is devoted to issues surrounding the siting and permitting of transmission, storage, and distribution (TS&D) infrastructure, building on the general identification of those issues in Chapter VII (Addressing Environmental Aspects of

  10. Tracking the Sun VIII: The Installed Price of Residential and...

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

    and Non-Residential Photovoltaic Systems in the United States Tracking the Sun VIII: The Installed Price of Residential and Non-Residential Photovoltaic Systems in the United ...

  11. Hydrogen peroxide propulsion for smaller satellites (SSC98-VIII...

    Office of Scientific and Technical Information (OSTI)

    Conference: Hydrogen peroxide propulsion for smaller satellites (SSC98-VIII-1) Citation Details In-Document Search Title: Hydrogen peroxide propulsion for smaller satellites ...

  12. Recent changes to ASME B31.3

    SciTech Connect (OSTI)

    Becht, C. IV; Frikken, D.R.; Bane, E.J.

    1996-07-01

    The code for process piping, ASME B31.3 Chemical Plant and Petroleum Refinery Piping, has undergone significant changes and additions in recent years. This includes many aspects of design, materials, and fabrication. Included are substantial changes to material impact testing requirements, qualification procedures for unlisted components, coverage of bellows expansion joints, and safety relief set pressure requirements. This paper provides an update on some of these recent changes to the Code together with some background on reasons for the changes.

  13. Tracking the Sun VIII. The Installed Price of Residential and...

    Office of Scientific and Technical Information (OSTI)

    Tracking the Sun VIII. The Installed Price of Residential and Non-Residential Photovoltaic Systems in the United States Citation Details In-Document Search Title: Tracking the Sun ...

  14. Tracking the Sun VIII: The Installed Price of Residential and

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

    Non-Residential Photovoltaic Systems in the United States | Department of Energy Tracking the Sun VIII: The Installed Price of Residential and Non-Residential Photovoltaic Systems in the United States Tracking the Sun VIII: The Installed Price of Residential and Non-Residential Photovoltaic Systems in the United States Now in its eighth edition, Lawrence Berkeley National Laboratory (LBNL)'s Tracking the Sun report series is dedicated to summarizing trends in the installed price of

  15. Understanding and Implementing DOE Quality Requirements and ASME NQA-1 in

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

    DOE Nuclear Projects, A Management Overview and Introduction, May 14, 2015 | Department of Energy Understanding and Implementing DOE Quality Requirements and ASME NQA-1 in DOE Nuclear Projects, A Management Overview and Introduction, May 14, 2015 Understanding and Implementing DOE Quality Requirements and ASME NQA-1 in DOE Nuclear Projects, A Management Overview and Introduction, May 14, 2015 Understanding and Implementing DOE Quality Requirements and ASME NQA-1 in DOE Nuclear Projects, A

  16. Team of NETL Scientists Honored By ASM International for Their Work on

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

    Team of NETL Scientists Honored By ASM International for Their Work on Platinum-Chromium Alloy for Coronary Stents Albany, Ore. - Scientists at the National Energy Technology Laboratory (NETL), and their colleagues, were recently honored with a 2015 ASM Engineering Materials Achievement Award from the materials science and engineering society ASM International. The NETL team received the prestigious award for their work on the development, transfer, and successful commercialization of a novel

  17. DOE Hydrogen and Fuel Cell Overview: ASME 2011 5th International Conference

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

    on Energy Sustainability | Department of Energy ASME 2011 5th International Conference on Energy Sustainability DOE Hydrogen and Fuel Cell Overview: ASME 2011 5th International Conference on Energy Sustainability Plenary presentation by Sunita Satyapal at the ASME 2011 5th International Conference on Energy Sustainability on August 8, 2011, in Washington, D.C. DOE Hydrogen and Fuel Cell Overview (6.81 MB) More Documents & Publications Hydrogen and Fuel Cell Activities: 5th International

  18. Significant issues and changes for ANSI/ASME OM-1 1981, part 1, ASME OMc code-1994, and ASME OM Code-1995, Appendix I, inservice testing of pressure relief devices in light water reactor power plants

    SciTech Connect (OSTI)

    Seniuk, P.J.

    1996-12-01

    This paper identifies significant changes to the ANSI/ASME OM-1 1981, Part 1, and ASME Omc Code-1994 and ASME OM Code-1995, Appendix I, {open_quotes}Inservice Testing of Pressure Relief Devices in Light-Water Reactor Power Plants{close_quotes}. The paper describes changes to different Code editions and presents insights into the direction of the code committee and selected topics to be considered by the ASME O&M Working Group on pressure relief devices. These topics include scope issues, thermal relief valve issues, as-found and as-left set-pressure determinations, exclusions from testing, and cold setpoint bench testing. The purpose of this paper is to describe some significant issues being addressed by the O&M Working Group on Pressure Relief Devices (OM-1). The writer is currently the chair of OM-1 and the statements expressed herein represents his personal opinion.

  19. Students try out high-tech equipment at ASM Materials Camp |...

    National Nuclear Security Administration (NNSA)

    try out high-tech equipment at ASM Materials Camp | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  20. Sandia Energy - Sandians Won Best Poster Award at the ASME 12th...

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

    Won Best Poster Award at the ASME 12th Fuel Cell Science, Engineering, and Technology Conference Home Energy Transportation Energy Facilities News News & Events Research &...

  1. Measurement and Modeling of the n=2-3 Emission of O VIII near...

    Office of Scientific and Technical Information (OSTI)

    Conference: Measurement and Modeling of the n2-3 Emission of O VIII near 102 Citation Details In-Document Search Title: Measurement and Modeling of the n2-3 Emission of O VIII ...

  2. Zwitterionic Group VIII transition metal initiators supported by olefin ligands

    DOE Patents [OSTI]

    Bazan, Guillermo C.; Chen, Yaofeng

    2011-10-25

    A zwitterionic Group VIII transition metal complex containing the simple and relatively small 3-(arylimino)-but-1-en-2-olato ligand that catalyzes the formation of polypropylene and high molecular weight polyethylene. A novel feature of this catalyst is that the active species is stabilized by a chelated olefin adduct. The present invention also provides methods of polymerizing olefin monomers using zwitterionic catalysts, particularly polypropylene and high molecular weight polyethylene.

  3. ASME code considerations for the compact heat exchanger

    SciTech Connect (OSTI)

    Nestell, James; Sham, Sam

    2015-08-31

    . Classic shell and tube designs will be large and costly, and may only be appropriate in steam generator service in the SHX where boiling inside the tubes occurs. For other energy conversion systems, all of these features can be met in a compact heat exchanger design. This report will examine some of the ASME Code issues that will need to be addressed to allow use of a Code-qualified compact heat exchanger in IHX or SHX nuclear service. Most effort will focus on the IHX, since the safety-related (Class A) design rules are more extensive than those for important-to-safety (Class B) or commercial rules that are relevant to the SHX.

  4. A guide for the ASME code for austenitic stainless steel containment vessels for high-level radioactive materials

    SciTech Connect (OSTI)

    Raske, D.T.

    1995-06-01

    The design and fabrication criteria recommended by the US Department of Energy (DOE) for high-level radioactive materials containment vessels used in packaging is found in Section III, Division 1, Subsection NB of the ASME Boiler and Pressure Vessel Code. This Code provides material, design, fabrication, examination, and testing specifications for nuclear power plant components. However, many of the requirements listed in the Code are not applicable to containment vessels made from austenitic stainless steel with austenitic or ferritic steel bolting. Most packaging designers, engineers, and fabricators are intimidated by the sheer volume of requirements contained in the Code; consequently, the Code is not always followed and many requirements that do apply are often overlooked during preparation of the Safety Analysis Report for Packaging (SARP) that constitutes the basis to evaluate the packaging for certification.

  5. Materials Research Project to Support Code Changes for GEN IV: A DOE/ASME Cooperative Effort

    SciTech Connect (OSTI)

    Ramirez, James; Erler, Bryan A.; Jetter, Robert

    2006-07-01

    For the last four years as reported in ICONE 13 Paper 13-50638, the ASME Board of Nuclear Codes and Standards (BNCS) has been leading an effort to identify code changes necessary to support the future nuclear plants of the world. In that paper the authors identified the results of meetings with NSSS suppliers, government regulators, engineers/constructors, and owner operators to ascertain the status of their future designs and what modifications are necessary so the right rules and materials are in ASME Nuclear Codes and Standards. (authors)

  6. The 1997 NRC IST workshops and the status of questions and issues directed to the ASME O and M committee

    SciTech Connect (OSTI)

    DiBiasio, A.M.

    1998-05-01

    This paper describes the results of the four NRC Inservice Testing (IST) Workshops which were held in early 1997 pertaining to NRC Inspection Procedure P 73756, Inservice Testing of Pumps and Valves. It also presents the status of the ASME code committees` resolution of certain questions forwarded to the ASME by the NRC. These questions relate to code interpretations, inconsistencies in the code, and industry concerns that are most appropriately resolved through the ASME consensus process. The ASME committees reviewed the questions at their December 1997 and March 1998 code meetings. Of particular interest are those questions for which the ASME code committees did not agree with the NRC response. These questions, as well as those which the committees provided some additional insight or input, are presented in this paper.

  7. PHASE I MATERIALS PROPERTY DATABASE DEVELOPMENT FOR ASME CODES AND STANDARDS

    SciTech Connect (OSTI)

    Ren, Weiju; Lin, Lianshan

    2013-01-01

    To support the ASME Boiler and Pressure Vessel Codes and Standard (BPVC) in modern information era, development of a web-based materials property database is initiated under the supervision of ASME Committee on Materials. To achieve efficiency, the project heavily draws upon experience from development of the Gen IV Materials Handbook and the Nuclear System Materials Handbook. The effort is divided into two phases. Phase I is planned to deliver a materials data file warehouse that offers a depository for various files containing raw data and background information, and Phase II will provide a relational digital database that provides advanced features facilitating digital data processing and management. Population of the database will start with materials property data for nuclear applications and expand to data covering the entire ASME Code and Standards including the piping codes as the database structure is continuously optimized. The ultimate goal of the effort is to establish a sound cyber infrastructure that support ASME Codes and Standards development and maintenance.

  8. TechLine: NETL Scientists Honored by ASM International for Work on Platinum

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

    Chromium Alloy for Coronary Stents | Department of Energy NETL Scientists Honored by ASM International for Work on Platinum Chromium Alloy for Coronary Stents Left to Right: NETL's Paul Jablonski, Paul Turner, Ed Argetsinger, and Jeffrey Hansen For their work on the development, transfer, and successful commercialization of a novel platinum-chromium alloy used in next-generation coronary stents, scientists at the National Energy Technology Laboratory (NETL), and their colleagues, were

  9. Section III, Division 5 - Development and Future Directions

    SciTech Connect (OSTI)

    D. K. Morton; R I Jetter; James E Nestell; T. D. Burchell; T L Sham

    2012-07-01

    This paper provides commentary on a new division under Section III of the ASME Boiler and Pressure Vessel (BPV) Code. This new Division 5 has an issuance date of November 1, 2011 and is part of the 2011 Addenda to the 2010 Edition of the BPV Code. The new Division covers the rules for the design, fabrication, inspection and testing of components for high temperature nuclear reactors. Information is provided on the scope and need for Division 5, the structure of Division 5, where the rules originated, the various changes made in finalizing Division 5, and the future near-term and long-term expectations for Division 5 development. Portions of this paper were based on Chapter 17 of the Companion Guide to the ASME Boiler & Pressure Vessel Code, Fourth Edition, © ASME, 2012, Reference.

  10. 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.

  11. 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.

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

    SciTech Connect (OSTI)

    Rowley, C.W.

    1996-12-01

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

  13. 3D automatic anatomy segmentation based on iterative graph-cut-ASM

    SciTech Connect (OSTI)

    Chen, Xinjian; Bagci, Ulas

    2011-08-15

    Purpose: This paper studies the feasibility of developing an automatic anatomy segmentation (AAS) system in clinical radiology and demonstrates its operation on clinical 3D images. Methods: The AAS system, the authors are developing consists of two main parts: object recognition and object delineation. As for recognition, a hierarchical 3D scale-based multiobject method is used for the multiobject recognition task, which incorporates intensity weighted ball-scale (b-scale) information into the active shape model (ASM). For object delineation, an iterative graph-cut-ASM (IGCASM) algorithm is proposed, which effectively combines the rich statistical shape information embodied in ASM with the globally optimal delineation capability of the GC method. The presented IGCASM algorithm is a 3D generalization of the 2D GC-ASM method that they proposed previously in Chen et al.[Proc. SPIE, 7259, 72590C1-72590C-8 (2009)]. The proposed methods are tested on two datasets comprised of images obtained from 20 patients (10 male and 10 female) of clinical abdominal CT scans, and 11 foot magnetic resonance imaging (MRI) scans. The test is for four organs (liver, left and right kidneys, and spleen) segmentation, five foot bones (calcaneus, tibia, cuboid, talus, and navicular). The recognition and delineation accuracies were evaluated separately. The recognition accuracy was evaluated in terms of translation, rotation, and scale (size) error. The delineation accuracy was evaluated in terms of true and false positive volume fractions (TPVF, FPVF). The efficiency of the delineation method was also evaluated on an Intel Pentium IV PC with a 3.4 GHZ CPU machine. Results: The recognition accuracies in terms of translation, rotation, and scale error over all organs are about 8 mm, 10 deg. and 0.03, and over all foot bones are about 3.5709 mm, 0.35 deg. and 0.025, respectively. The accuracy of delineation over all organs for all subjects as expressed in TPVF and FPVF is 93.01% and 0.22%, and

  14. Review of the margins for ASME code fatigue design curve - effects of surface roughness and material variability.

    SciTech Connect (OSTI)

    Chopra, O. K.; Shack, W. J.; Energy Technology

    2003-10-03

    The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. The Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of the existing fatigue {var_epsilon}-N data for carbon and low-alloy steels and wrought and cast austenitic SSs to define the effects of key material, loading, and environmental parameters on the fatigue lives of the steels. Experimental data are presented on the effects of surface roughness on the fatigue life of these steels in air and LWR environments. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are discussed. Data available in the literature have been reviewed to evaluate the conservatism in the existing ASME Code fatigue evaluations. A critical review of the margins for ASME Code fatigue design curves is presented.

  15. Structure and electrical characterization of gallium arsenide nanowires with different V/III ratio growth parameters

    SciTech Connect (OSTI)

    Muhammad, R.; Ahamad, R.; Ibrahim, Z.; Othaman, Z.

    2014-03-05

    Gallium arsenide (GaAs) nanowires were grown vertically on GaAs(111)B substrate by gold-assisted using metal-organic chemical vapour deposition. Field-emission scanning electron microscopy (FE-SEM), transmission electron microscopy (TEM) and conductivity atomic force microscopy (CAFM) analysis were carried out to investigate the effects of V/III ratio on structural properties and current-voltage changes in the wires. Results show that GaAs NWs grow preferably in the wurtzite crystal structure than zinc blende crystal structure with increasing V/III ratio. Additionally, CAFM studies have revealed that zincblende nanowires indicate ohmic characteristic compared to oscillation current occurred for wurtzite structures. The GaAs NWs with high quality structures are needed in solar cells technology for trapping energy that directly converts of sunlight into electricity with maximum capacity.

  16. Draft ASME Boiler and Pressure Vessel Code Section III, Division 5, Section HB, Subsection B, Code Case for Alloy 617 and Background Documentation

    SciTech Connect (OSTI)

    Wright, Julie Knibloe

    2015-08-01

    Alloy 617 is the leading candidate material for an intermediate heat exchanger for the very high temperature reactor. To evaluate the behavior of this material in the expected service conditions, strain controlled cyclic tests that include long hold times up to 240 minutes at maximum tensile strain were conducted at 850°C. In terms of the total number of cycles to failure, the fatigue resistance decreased when a hold time was added at peak tensile strain. Increases in the tensile hold duration degraded the creep fatigue resistance, at least to the investigated strain controlled hold time of up to 60 minutes at the 0.3% strain range and 240 minutes at the 1.0% strain range. The creep fatigue deformation mode is considered relative to the lack of saturation, or continually decreasing number of cycles to failure with increasing hold times. Additionally, preliminary values from the 850°C creep fatigue data are calculated for the creep fatigue damage diagram and have higher values of creep damage than those from tests at 950°C.

  17. EFFECTIVE COLLISION STRENGTHS FOR ELECTRON-IMPACT EXCITATION OF Fe VIII

    SciTech Connect (OSTI)

    Tayal, S. S.; Zatsarinny, O. E-mail: oleg.zatsarinny@drake.edu

    2011-12-20

    New extensive calculations are reported for electron collision strengths, rate coefficients, and transition probabilities for the astrophysically important lines of Fe VIII. The collision strengths have been calculated in the close-coupling approximation using the B-spline Breit-Pauli R-matrix method. The multiconfiguration Hartree-Fock method with term-dependent non-orthogonal orbitals is employed for an accurate representation of the target wave functions. The close-coupling expansion includes 102 fine-structure levels of Fe VIII covering all possible terms of the ground 3p {sup 6}3d and singly excited 3p {sup 5}3d{sup 2}, 3p {sup 6}4l, 3p {sup 5}3d4s, 3s3p {sup 6}3d{sup 2}, and 3p {sup 6}5l configurations. The present calculations are more extensive than the previous ones, leading to a total 5151 transitions between fine-structure levels. The effective collision strengths are obtained by averaging the electron collision strengths over a Maxwellian distribution of velocities and these are tabulated for all fine-structure transitions at electron temperatures in the range from 5 Multiplication-Sign 10{sup 3} to 5 Multiplication-Sign 10{sup 6} K. There is an overall good agreement with the previous 77-state calculations by Griffin, Pindzola, and Badnell, but significant differences are also noted for some transitions.

  18. Structure of the human factor VIII C2 domain in complex with the 3E6 inhibitory antibody

    SciTech Connect (OSTI)

    Wuerth, Michelle E.; Cragerud, Rebecca K.; Spiegel, P. Clint

    2015-11-24

    Blood coagulation factor VIII is a glycoprotein cofactor that is essential for the intrinsic pathway of the blood coagulation cascade. Inhibitory antibodies arise either spontaneously or in response to therapeutic infusion of functional factor VIII into hemophilia A patients, many of which are specific to the factor VIII C2 domain. The immune response is largely parsed into “classical” and “non-classical” inhibitory antibodies, which bind to opposing faces cooperatively. In this study, the 2.61 Å resolution structure of the C2 domain in complex with the antigen-binding fragment of the 3E6 classical inhibitory antibody is reported. The binding interface is largely conserved when aligned with the previously determined structure of the C2 domain in complex with two antibodies simultaneously. Further inspection of the B factors for the C2 domain in various X-ray crystal structures indicates that 3E6 antibody binding decreases the thermal motion behavior of surface loops in the C2 domain on the opposing face, thereby suggesting that cooperative antibody binding is a dynamic effect. Furthermore, understanding the structural nature of the immune response to factor VIII following hemophilia A treatment will help lead to the development of better therapeutic reagents.

  19. Structure of the human factor VIII C2 domain in complex with the 3E6 inhibitory antibody

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

    Wuerth, Michelle E.; Cragerud, Rebecca K.; Spiegel, P. Clint

    2015-11-24

    Blood coagulation factor VIII is a glycoprotein cofactor that is essential for the intrinsic pathway of the blood coagulation cascade. Inhibitory antibodies arise either spontaneously or in response to therapeutic infusion of functional factor VIII into hemophilia A patients, many of which are specific to the factor VIII C2 domain. The immune response is largely parsed into “classical” and “non-classical” inhibitory antibodies, which bind to opposing faces cooperatively. In this study, the 2.61 Å resolution structure of the C2 domain in complex with the antigen-binding fragment of the 3E6 classical inhibitory antibody is reported. The binding interface is largely conservedmore » when aligned with the previously determined structure of the C2 domain in complex with two antibodies simultaneously. Further inspection of the B factors for the C2 domain in various X-ray crystal structures indicates that 3E6 antibody binding decreases the thermal motion behavior of surface loops in the C2 domain on the opposing face, thereby suggesting that cooperative antibody binding is a dynamic effect. Furthermore, understanding the structural nature of the immune response to factor VIII following hemophilia A treatment will help lead to the development of better therapeutic reagents.« less

  20. SECTION H

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

    Operations Contract Section H Contract No. DE-AC27-08RV14800 Modification No. 360 H-i PART I - THE SCHEDULE SECTION H SPECIAL CONTRACT REQUIREMENTS TABLE OF CONTENTS H.1 WORKFORCE ...

  1. SECTION E

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

    E Contract No. DE-AC27-01RV14136 Conformed Thru Modification No. A143 E - i SECTION E INSPECTION AND ACCEPTANCE WTP Contract Section E Contract No. DE-AC27-01RV14136 Conformed Thru...

  2. Section III, Division 5 - Development And Future Directions

    SciTech Connect (OSTI)

    Morton, Dana K.; Jetter, Robert I; Nestell, James E.; Burchell, Timothy D; Sham, Sam

    2012-01-01

    This paper provides commentary on a new division under Section III of the ASME Boiler and Pressure Vessel (BPV) Code. This new Division 5 has an issuance date of November 1, 2011 and is part of the 2011 Addenda to the 2010 Edition of the BPV Code. The new Division covers the rules for the design, fabrication, inspection and testing of components for high temperature nuclear reactors. Information is provided on the scope and need for Division 5, the structure of Division 5, where the rules originated, the various changes made in finalizing Division 5, and the future near-term and long-term expectations for Division 5 development.

  3. Comparisons of ANS, ASME, AWS, and NFPA standards cited in the NRC standard review plan, NUREG-0800, and related documents

    SciTech Connect (OSTI)

    Ankrum, A.R.; Bohlander, K.L.; Gilbert, E.R.; Spiesman, J.B.

    1995-11-01

    This report provides the results of comparisons of the cited and latest versions of ANS, ASME, AWS and NFPA standards cited in the NRC Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG 0800) and related documents. The comparisons were performed by Battelle Pacific Northwest Laboratories in support of the NRC`s Standard Review Plan Update and Development Program. Significant changes to the standards, from the cited version to the latest version, are described and discussed in a tabular format for each standard. Recommendations for updating each citation in the Standard Review Plan are presented. Technical considerations and suggested changes are included for related regulatory documents (i.e., Regulatory Guides and the Code of Federal Regulations) citing the standard. The results and recommendations presented in this document have not been subjected to NRC staff review.

  4. SECTION J

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

    K-1 SECTION J APPENDIX K CONTRACTOR'S TRANSITION PLAN (RESERVED) Contract No.: DE-RW0000005 QA:QA J-K-2

  5. Section J

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

    L-1 Section J Appendix L MEMORANDUM FROM DAVID R. HILL, GENERAL COUNSEL, DATED NOVEMBER 30, 2006, SUBJECT: ONGOING LICENSING SUPPORT NETWORK ("LSN") OBLIGATIONS Contract No.: ...

  6. SECTION I

    National Nuclear Security Administration (NNSA)

    to Mod 0108 DE-NA0000622 Section I, Page i PART II - CONTRACT CLAUSES SECTION I CONTRACT CLAUSES TABLE OF CONTENTS I-1 FAR 52.202-1 DEFINITIONS (NOV 2013) (AS MODIFIED BY DEAR 952.202-1) (REPLACED MODS 020, 029, 0084) ................................................................................................................................ 1 I-2 FAR 52.203-3 GRATUITIES (APR 1984) ................................................................................................. 1 I-3 FAR

  7. SECTION B

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

    phases of the fee determination process consistent with Section B.2 of the subject contract. ... At the end of the rating period, after the determination of the award fee, the CBFO ...

  8. Section I

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

    Projectile and Target Z-scaling of Target K-vacancy Production Cross Sections at 10A MeV R. L. Watson, V. Horvat and K. E. Zaharakis Molecular Orbital Effects in Near-symmetric ...

  9. SECTION J

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

    J-1 SECTION J APPENDIX J PERFORMANCE EVALUATION AND MEASUREMENT PLAN (TO BE NEGOTIATED AFTER CONTRACT AWARD) Contract No.: DE-RW0000005 QA:QA J-J-2 Page Blank

  10. American Society of Mechanical Engineers/Savannah River National Laboratory (ASME/SRNL) Materials and Components for Hydrogen Infrastructure Codes and Standards Workshop and the DOE Hydrogen Pipeline Working Group Workshop Agenda

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

    ASME/SRNL Materials and Components for Hydrogen Infrastructure Codes and Standards Workshop and the DOE Hydrogen Pipeline Working Group Workshop Sponsored by SRNL, ASME, and DOE Center for Hydrogen Research, Aiken, SC Garden Conference Center September 23-26, 2007 1 AGENDA Sunday, September 23, 2007 6:00 - 7:30 pm Registration 6:15 - 7:30 pm Opening Reception Sponsored by ASME Monday, September 24, 2007 Joint Materials and Components for Hydrogen Infrastructure Codes and Standards Workshop 8:00

  11. SECTION J

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

    A-1 SECTION J APPENDIX A ADVANCE UNDERSTANDING ON HUMAN RESOURCES (TO BE NEGOTIATED DURING CONTRACT TRANSITION) The personnel appendix required by DEAR Subpart 970.31 entitled "Contract Cost Principles and Procedures" as referenced in Section I Clause, DEAR 970.5232-2, "Payments and Advances" will be Appendix A of the contract. The personnel appendix will be negotiated between DOE OCRWM and the selected offeror during the contract transition period. Contract No.: DE-RW0000005

  12. Section 66

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

    CFCl 3 ) (CF 2 Cl 2 ) (CHFCl 2 ) CF 4 CCl 4 (CFCl 3 ) (CF 2 Cl 2 ) (CHFCl 2 ) SF 6 CF 4 CCl 4 Session Papers 277 Figure 1. Spectral absorption cross-sections of CF 4 between 1281 and 1284 cm . The experimental -1 conditions correspond to the surface, 5-km, and 19-km levels of the U.S. Standard Atmosphere. Figure 2. Spectral absorption cross-sections of CCl 4 between 755 and 810 cm . The experimental conditions -1 correspond to the surface, 5-km, and 19-km levels of the U.S. Standard Atmosphere.

  13. Section CC

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

    30 J-12-1 ATTACHMENT J-12 GOVERNMENT FURNISHED SERVICES AND INFORMATION TABLE J-12.1 GFS/I LIST FROM SECTION C (SOW) ID GFS/I GFS/I Due Contract Section GF0001 DOE will administer MOUs with other law enforcement agencies or other Federal agencies (e.g., U.S. Department of Defense [Yakima Training Center]). DOE will provide copies of MOUs and/or contracts to the MSC. As required C.2.1.1.1 GF0002 DOE will provide Federal Commissions for Hanford Patrol personnel. As required C.2.1.1.1 GF0003 DOE

  14. Section CC

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

    Contract No. DE-AC06-09RL14728 Modification 464 J-11-1 ATTACHMENT J-11 CONTRACT DELIVERABLES TABLE J-11.1 DELIVERABLE LIST FROM SECTION C (SOW) ID Deliverable DOE Contract Deliverable Due Contract Section Action Response Time a CD0001 Hanford Site Services and Interface Requirements Matrix Approve 30 days July 24, 2009; thereafter by request as applicable C.1.3 CD0002 Annual Forecast of Services and Infrastructure Review NA November 21, 2009; annually thereafter by November 31 C.1.3 CD0003

  15. Section I

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

    Contract Modification No.0200 Section I I-1 PART II SECTION I CONTRACT CLAUSES TABLE OF CONTENTS CLAUSE I.1 - FAR 52.202-1 DEFINITIONS (NOV 2013); MODIFIED BY DEAR 952.202-1 9 CLAUSE I.2 - FAR 52.203-3 GRATUITIES (APR 1984) 9 CLAUSE I.3 - FAR 52.203-5 COVENANT AGAINST CONTINGENT FEES (MAY 2014) 10 CLAUSE I.4 - FAR 52.203-6 RESTRICTIONS ON SUBCONTRACTOR SALES TO THE GOVERNMENT (SEP 2006) 11 CLAUSE I.5 - FAR 52.203-7 ANTI-KICKBACK PROCEDURES (MAY 2014) 11 CLAUSE I.6 - FAR 52.203-8 CANCELLATION,

  16. Section J

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

    M-1 Section J Appendix M Key Design, Licensing and Site Management M&O Milestone Chart Activity Planned Date Develop and Submit CD-2 (25%-30%) 08/2009 Submission of Construction Performance Specifications - Balance of Plant Support Facilities (OCRWM Start of Construction 3/2012) TBD Submission of Construction Performance Specifications - Initial Handling Facility (IHF) (OCRWM Start of Construction for IHF: 9/2013) TBD Submission of Construction Performance Specifications - Wet Handling

  17. Section L

    National Nuclear Security Administration (NNSA)

    Section L - Attachment F - Past Performance Cover Letter and Questionnaire Date: ________________ Dear _________________: Our firm is submitting a proposal for a Department of Energy (DOE)/National Nuclear Security Administration (NNSA) Contract for the management and operation of the Nevada National Security Site with an estimated value of approximately $550M per year. Our firm is seeking your assistance. We are asking you to complete the attached questionnaire evaluating our performance on

  18. SECTION J

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

    D-1 SECTION J APPENDIX D KEY PERSONNEL Name Position Doug Cooper General Manager John Donnell Repository Licensing Lead Al Ebner, PE, PhD Repository Design Lead Steve Piccolo Deputy General Manager Steve White Quality & Performance Assurance Lead George Clare Project Management & Integration Lead Mike Hitchler Preclosure Safety Analysis Lead Contract No.: DE-RW0000005 QA:QA J-D-2 POSITION DESCRIPTIONS OCRWM SPECIFIED KEY PERSONNEL 1. General Manager: Requires 10 years experience as a

  19. SECTION J

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

    H-1 SECTION J APPENDIX H CONTRACT GUIDANCE FOR PREPARATION OF DIVERSITY PLAN This Guidance is to assist the Contractor in understanding the information being sought by the Department for each of the Diversity elements and where these issues may already be addressed in the contract. To the extent these issues are already addressed in the contract, the Contractor need only cross reference the location. Contractor's Workforce The Department's contracts contain clauses on Equal Employment

  20. Section 89

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

    Sensitivity Tests on the Microphysical Parameters of a 2-Dimensional Cirrus Model R.-F. Lin Department of Meteorology, Pennsylvania State University University Park, Pennsylvania Introduction Radiatively induced convection may serve a key role in the evolution of cirrus. A 2-dimensional cirrus model with a spatial resolution of 100 m is developed to investigate dynam- ical-radiative-microphysical interactions. It is assumed that the model domain represents part of a cross-section of cirrus

  1. Proceedings of the 1998 ASME energy sources technology conference (ETCE`98)

    SciTech Connect (OSTI)

    1998-12-31

    The approximately 160 papers in these proceedings have been arranged under the following topical sections: (1) Computers in engineering -- Technical databases and applied computing; Workgroup computing; Software process models; Internet computing; (2) Drilling technology -- Coiled tubing technology; Drilling dynamics and drilling systems; Advances in drill bits; Advances in percussion drilling; Testing field and laboratory; Novel/scientific drilling; Advances in drilling fluids; (3) Emerging energy technology -- Spray and combustion; Fuel cells; Flammability and flames; Fuels and engines; Miscellaneous combustion topics; (4) Composite materials design and analysis -- Interaction of cracks, notched strength, and free edge effects in laminated composites; Stress analysis of composites; Material response identification, property alteration, damage detection, and environmental effects; Wave propagation in elastic medium, numerical methods for composites; Process and property characterization of advanced materials; Fatigue degradation, viscoplasticity in composites, and numerical simulation of reinforced concrete structures; Aging, creep, plastic anisotropy, joining of different materials, and time history analysis; Shock fronts in compressible medium; Numerical simulation of propagating fronts and shocks in compressible medium; Computational methods and numerical simulation; Analysis and modeling techniques; (5) Manufacturing and services -- Drilling equipment; Process equipment; Patents and intellectual property; Computational methods in manufacturing; (6) Non-destructive evaluation engineering -- NDE applications: Visual inspections; Material property determination/flaw sizing; (7) Offshore engineering and operations -- Environmental and safety issues in offshore operations; Floating production system; Offshore topside facilities; Offshore facility infrastructure; Offshore structures and pipelines; (8) Pipeline engineering and operations -- Pipeline risk management

  2. Resistance Weld Qualification Analysis for Radioactive Waste Canisters

    SciTech Connect (OSTI)

    Gupta, N.K.; Gong, C.

    1995-01-10

    High level radioactive waste canisters are sealed by resistance upset welding to ensure leak tight closures. Resistance welding is fast, uniform, and can be performed remotely to minimize radiation exposure to the operators. Canisters are constructed in accordance with ASME Band PV Code, Section VIII, Division 1, however, the resistance welds are not used in Section VIII. The resistance welds are qualified by analysis using material properties obtained from the test coupons. Burst tests are performed on canister welds to meet ASME Section IX welder qualification requirements. Since burst tests are not used in Section IX for resistance weld qualification, finite element results of canister resistance welds are compared with the finite element analysis results of resistance weld tests in ASME Section IX, QW-196 to establish similarity between the two weld tests. Detailed analyses show that the primary mode of failure in both the tests is shear and, therefore, the use of burst test in place of shear test is acceptable. It is believed that the detailed analyses and results could help in establishing acceptance criteria for resistance upset welding in ASME B&PV Code, Sections VIII, and IX.

  3. ASME.Reno.paper

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

    for calculating airfoil aerodynamic charac- teristics range from coupled potential-flowboundary- layer methods (e.g., VSAERO, 1994) to full-blown com- putational fluid...

  4. Report on the activities of the ASME-NQA Committee Working Group on Quality Assurance Requirements for Research and Development, April 1990 to August 1991

    SciTech Connect (OSTI)

    Dronkers, J.J.

    1991-09-01

    This report transmits to the public eye the activities of the American Society of Mechanical Engineers-Nuclear Quality Assurance (ASME-NQA) Committee Working Group on Quality Assurance Requirements for Research and Development. The appendix lists the members of this group as of August 1991. The report covers a period of 17 months. The working group met eight times in this period, and much intellectual ground was traversed. There was seldom agreement on the nature of the task, but there was no doubt as to its urgency. The task was how to adapt the nuclear quality assurance standard, the NQA-1, to research and development work. 1 fig., 7 tabs.

  5. Microsoft Word - Errata for the Pressure and Vacuum Systems Safety Supplement 3-15

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

    SYSTEM PROJECT COVER SHEET FORM PS-1 GENERAL Pressure System Number: Pressure System Name: P&ID Number: Overall Installation/Assembly Drawing Number: Design Authority: System Owner: APPLICABLE CODES (Add Code Edition to all that apply) ASME BPVC VIII Div1 ASME BPVC VIII Div2 ASME B31.1 ASME B31.3 ASME B31.5 ASME B31.9 ASME B31.12 Other (Specify) Are there pressure components with no directly applicable Codes? YES NO (If YES then these components require a Peer Review) Briefly describe and

  6. American Society of Mechanical Engineers/Savannah River National Laboratory (ASME/SRNL) Materials and Components for Hydrogen Infrastructure Codes and Standards Workshop and the DOE Hydrogen Pipeline Working Group Meeting Attendee List

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

    PWG_regform First Name Last Name Organization Phone Email Thad Adams Savannah River National Lab 803-725-5510 thad.adams@srnl.doe.gov Anthony Amato ASME 212-591-7003 amatoa@asme.org Lawrence Anovitz Oak Ridge National Lab 865-574-5034 anovitzlm@ornl.gov Timothy Armstrong Oak Ridge National Lab 865-574-7996 armstrongt@ornl.gov James Blencoe Hydrogen Discoveries, Inc. 865-384-2251 jblencoe@hydrogendiscoveries.com Kyle Brinkman Savannah River National Lab 803-507-7955 kyle.brinkman@srs.gov Rod

  7. U.S. Environmental Protection Agency Region VIII Hazardous Waste Management Division

    Office of Legacy Management (LM)

    Ia) Monticello Mill Tailings Site (San Juan County, Utah) I. Introduction Authority Statement. Purpose. This review was conducted pursuant to Comprehensive Environmental Response, Compensation, and Liability (CERCLA) section 121(c), National Contingency Plan (NCP) section 300.430(f)(4)(ii), and Office of Solid Waste and Emergency Response (OSWER) Directives 9355.7-02 (May 23, 1991) and 9355.7-02A (July 26, 1994). The U.S. Department of Energy (DOE) Grand Junction Office (GJO) conducted the

  8. Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

    SciTech Connect (OSTI)

    Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P.

    1996-12-01

    This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising.

  9. Probing the mysteries of the X-ray binary 4U 1210-64 with ASM, PCA, MAXI, BAT, and Suzaku

    SciTech Connect (OSTI)

    Coley, Joel B.; Corbet, Robin H. D.; Mukai, Koji; Pottschmidt, Katja

    2014-10-01

    4U 1210-64 has been postulated to be a high-mass X-ray binary powered by the Be mechanism. X-ray observations with Suzaku, the ISS Monitor of All-sky X-ray Image (MAXI), and the Rossi X-ray Timing Explorer Proportional Counter Array (PCA) and All Sky Monitor (ASM) provide detailed temporal and spectral information on this poorly understood source. Long-term ASM and MAXI observations show distinct high and low states and the presence of a 6.7101 ± 0.0005 day modulation, interpreted as the orbital period. Folded light curves reveal a sharp dip, interpreted as an eclipse. To determine the nature of the mass donor, the predicted eclipse half-angle was calculated as a function of inclination angle for several stellar spectral types. The eclipse half-angle is not consistent with a mass donor of spectral type B5 V; however, stars with spectral types B0 V or B0-5 III are possible. The best-fit spectral model consists of a power law with index Γ = 1.85{sub −0.05}{sup +0.04} and a high-energy cutoff at 5.5 ± 0.2 keV modified by an absorber that fully covers the source as well as partially covering absorption. Emission lines from S XVI Kα, Fe Kα, Fe XXV Kα, and Fe XXVI Kα were observed in the Suzaku spectra. Out of eclipse, the Fe Kα line flux was strongly correlated with unabsorbed continuum flux, indicating that the Fe I emission is the result of fluorescence of cold dense material near the compact object. The Fe I feature is not detected during eclipse, further supporting an origin close to the compact object.

  10. In pursuit of clean air: a data book of problems and strategies at the state level. Volume 5. Federal Regions VIII, IX, and X

    SciTech Connect (OSTI)

    Garvey, D.B.; Streets, D.G.

    1980-02-01

    The following material is provided for each state in Federal Regions VIII, IX, and X: state title page (lists nonattainment areas for each pollutant, the number of monitors with valid readings for a particular averaging time for a pollutant, and the number of monitors that recorded a violation of the standard); revised State Implementation Plan (SIP) outline (covers sources of the problems, the proposed strategies for achieving attainment, and new state review procedures); maps of nonattainment areas, as designated; SAROAD (Storage and Retrieval of Aerometric Data) data; SAROAD data maps; power plant data; power plant maps; and county maps. States in Federal Region VIII are Colorado, Montana, North Dakota, South Dakota, Utah, and Wyoming. Federal Region IX includes Arizona, California, and Nevada. Federal Region X includes Idaho, Oregon, and Washington. (JGB)

  11. Structural integrity assessment of carbon and low-alloy steel pressure vessels using a simplified fracture mechanics procedure

    SciTech Connect (OSTI)

    Rana, M.D. . Research and Development Dept.)

    1994-08-01

    This paper describes a simplified fracture analysis procedure which was developed by Pellini to quantify fracture critical-crack sizes and crack-arrest temperatures of carbon and low-alloy steel pressure vessels. Fracture analysis diagrams have been developed using the simplified analysis procedure for various grades of carbon and low-alloy steels used in the construction of ASME, Section VIII, Division 1 pressure vessels. Structural integrity assessments have been conducted from the analysis diagrams.

  12. METAL MEDIA FILTERS, AG-1 SECTION FI

    SciTech Connect (OSTI)

    Adamson, D.

    2012-05-23

    One application of metal media filters is in various nuclear air cleaning processes including applications for protecting workers, the public and the environment from hazardous and radioactive particles. To support this application the development of the ASME AG-1 FI Standard on Metal Media has been under way for more than ten years. Development of the proposed section has required resolving several difficult issues associated with operating conditions (media velocity, pressure drop, etc.), qualification testing, and quality acceptance testing. Performance characteristics of metal media are dramatically different than the glass fiber media with respect to parameters like differential pressures, operating temperatures, media strength, etc. These differences make existing data for a glass fiber media inadequate for qualifying a metal media filter for AG-1. In the past much work has been conducted on metal media filters at facilities such as Lawrence Livermore National Laboratory (LLNL) and Savannah River National Laboratory (SRNL) to qualify the media as High Efficiency Particulate Air (HEPA) Filters. Particle retention testing has been conducted at Oak Ridge Filter Test Facility and at Air Techniques International (ATI) to prove that the metal media meets or exceeds the 99.97% particle retention required for a HEPA Filter. Even with his testing, data was lacking to complete an AG-1 FI Standard on metal media. With funding secured by Mississippi State University (MSU) from National Nuclear Security Administration (NNSA), a research test stand is being designed and fabricated at MSU's Institute for Clean Energy Technology (ICET) Facility to obtain qualification data on metal media. This in turn will support required data needed for the FI Standard. The paper will discuss in detail how the test stand at MSU will obtain the necessary data to complete the FI Standard.

  13. Closeout of IE Bulletin 83-05: ASME nuclear code pumps and spare parts manufactured by the Hayward Tyler Pump Company

    SciTech Connect (OSTI)

    Foley, W.J.; Dean, R.S.; Hennick, A. )

    1990-08-01

    Documentation is provided in this report to close IE Bulletin 83-05 regarding ASME nuclear code pumps and spare parts manufactured by the Hayward Tyler Pump Company (HTPC). The bulletin was issued (1) to alert holders of operating licenses and construction permits of nuclear power plants that HTPC failed to implement effectively their quality assurance (QA) program from 1977 to 1981 and (2) to require affected utilities to take action to resolve the potential for failure of the subject pumps and their spare parts. Evaluation of utility responses and NRC/Region inspection reports shows that reliability of the affected pumps was ensured by means of procedures and performance testing of the pumps as required by the bulletin. Based on the evaluation, in accordance with specific criteria, the bulletin is closed for 116 (98%) of the 118 facilities to which it was issued for action and which were not shut down indefinitely or permanently at the time of issuance of this report. A follow-up item is proposed for the two facilities with open bulletin status. Based on favorable results, a conclusion is presented to indicate that the bulletin concerns have been resolved.

  14. Proceedings of the 1996 spring technical conference of the ASME Internal Combustion Engine Division. Volume 2: Engine design and engine systems; ICE-Volume 26-2

    SciTech Connect (OSTI)

    Uzkan, T.

    1996-12-31

    Although the cost of the petroleum crude has not increased much within the last decade, the drive to develop internal combustion engines is still continuing. The basic motivation of this drive is to reduce both emissions and costs. Recent developments in computer chip production and information management technology have opened up new applications in engine controls and monitoring. The development of new information is continuing at a rapid pace. Some of these research and development results were presented at the 1996 Spring Technical Conference of the ASME Internal Combustion Engine Division in Youngstown, Ohio, April 21--24, 1996. The papers presented covered various aspects of the design, development, and application of compression ignition and spark ignition engines. The conference was held at the Holiday Inn Metroplex Complex and hosted by Altronic Incorporated of Girard, Ohio. The written papers submitted to the conference have been published in three conference volumes. Volume 2 includes the papers on the topics of engine design, engine systems, and engine user experience.

  15. RFP Section H and Section L Templates

    Broader source: Energy.gov [DOE]

    On April 26, 2011, two draft RFP Section H templates "Performance Requirements" and "Performance Evaluation and Measurement Plan" and one draft RFP Section L template "Proposal Preparation Instructions – Cover Letter and Volume I, Offer and Other Documents" were distributed for Procurement Director (PD), Head of Contracting Activity (HCA), General Counsel and National Nuclear Security Administration (NNSA) review and comment. All comments received were considered and changes were made as appropriate. The final version of the three aforementioned RFP Section H and L templates are available in STRIPES.

  16. SECTION L… ATTACHMENT H

    National Nuclear Security Administration (NNSA)

    III-SECTION J APPENDIX K TRANSITION PLAN To be Added at a Later Date

  17. PART III - SECTION J

    National Nuclear Security Administration (NNSA)

    E SECTION J APPENDIX E PERFORMANCE GUARANTEE AGREEMENT(S) [Note: To be inserted by the Contracting Officer prior to contract award. For Performance Guarantee Agreement(s) template, see Section L, Attachment A.]

  18. PART III - SECTION J

    National Nuclear Security Administration (NNSA)

    I SECTION J APPENDIX I SMALL BUSINESS SUBCONTRACTING PLAN [Note: To be inserted by the Contracting Officer prior to

  19. PART III - SECTION J

    National Nuclear Security Administration (NNSA)

    I SECTION J APPENDIX I SMALL BUSINESS SUBCONTRACTING PLAN Note: To be inserted by the Contracting Officer prior to...

  20. Tracking the Sun VIII

    SciTech Connect (OSTI)

    Barbose, Galen; Darghouth, Naim; Millstein, Dev; Spears, Mike; Wiser, Ryan; Buckley, Michael; Widiss, Rebecca; Grue, Nick

    2015-08-01

    Funded by the SunShot Initiative, this report summarizes trends in the installed price of grid-connected residential and non-residential PV systems in the United States.

  1. Section 106 Archaeology Guidance

    Broader source: Energy.gov [DOE]

    The Advisory Council on Historic Preservation's Section 106 guidance is designed to assist federal agencies in making effective management decisions about archaeological resources in completing the requirements of Section 106 of the National Historic Preservation Act (16 U.S.C. 470f) and its implementing regulations (36 CFR Part 800). This guidance highlights the decision-making role of the federal agency in the Section 106 process. It is also designed for use by State and Tribal Historic Preservation Officers, Indian tribes, Native Hawaiian organizations, and cultural resource management professionals when assisting federal agencies to meet their responsibilities under Section 106.

  2. 14655 Section D

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

    D Contract No. DE-AC06-05RL14655 A000 PART I - THE SCHEDULE SECTION D PACKAGING AND MARKING TABLE OF CONTENTS D.1 PACKAGING......

  3. PART III ? SECTION J

    National Nuclear Security Administration (NNSA)

    B, Page 1 SECTION J APPENDIX B AWARD FEE PLAN Note: To be inserted by the Contracting Officer after contract award....

  4. PART III ? SECTION J

    National Nuclear Security Administration (NNSA)

    M, Page 1 SECTION J APPENDIX M CONTRACTOR COMMITMENTS, AGREEMENTS, AND UNDERSTANDINGS Note: To be inserted by the Contracting Officer after contract award....

  5. ASME95_Gear.PDF

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

    91-97. THE SPECTRAL CONTENT OF THE TORQUE LOADS ON A TURBINE GEAR TOOTH 1 Herbert J. Sutherland Wind Energy Technology Sandia National Laboratories Albuquerque, NM 87185-0708 and...

  6. Sectional device handling tool

    DOE Patents [OSTI]

    Candee, Clark B.

    1988-07-12

    Apparatus for remotely handling a device in an irradiated underwater environment includes a plurality of tubular sections interconnected end-to-end to form a handling structure, the bottom section being adapted for connection to the device. A support section is connected to the top tubular section and is adapted to be suspended from an overhead crane. Each section is flanged at its opposite ends. Axially retractable bolts in each bottom flange are threadedly engageable with holes in the top flange of an adjacent section, each bolt being biased to its retracted position and retained in place on the bottom flange. Guide pins on each top flange cooperate with mating holes on adjacent bottom flanges to guide movement of the parts to the proper interconnection orientation. Each section carries two hydraulic line segments provided with quick-connect/disconnect fittings at their opposite ends for connection to the segments of adjacent tubular sections upon interconnection thereof to form control lines which are connectable to the device and to an associated control console.

  7. 14655 Section D

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

    D Contract No. DE-AC06-05RL14655 A000 PART I - THE SCHEDULE SECTION D PACKAGING AND MARKING TABLE OF CONTENTS D.1 PACKAGING......................................................................................................................................1 D.2 MARKING ..........................................................................................................................................1 D-i River Corridor Closure Contract Section D Contract No. DE-AC06-05RL14655 A000 PART I

  8. 14655 Section H

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

    Section H Contract No. DE-AC06-05RL14655 H-i PART I - THE SCHEDULE SECTION H SPECIAL CONTRACT REQUIREMENTS TABLE OF CONTENTS H.1 INCUMBENT EMPLOYEES HIRING PREFERENCES ................................................................... 1 H.2 PAY AND BENEFITS ....................................................................................................................... 1 H.3 LABOR RELATIONS

  9. 14655 Section I

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

    I Contract No. DE-AC06-05RL14655 A099 I-i PART II - CONTRACT CLAUSES SECTION I CONTRACT CLAUSES River Corridor Closure Contract Section I Contract No. DE-AC06-05RL14655 649 I-1 PART II - CONTRACT CLAUSES SECTION I CONTRACT CLAUSES I.1 FAR 52.252-2 CLAUSES INCORPORATED BY REFERENCE (FEB 1998) This contract incorporates one or more clauses by reference, with the same force and effect as if they were given in full text. Upon request, the Contracting Officer will make their full text available.

  10. 6Li Cross Section

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

    p, X) (Current as of 03012016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2004TU02 6Li(p, ): coincidence yields, deduced S-factors low 1, S-factors from ...

  11. 7Li Cross Section

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

    p, X) (Current as of 12162015) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1997GO13 7Li(pol. p, ): total , S-factor for capture to third-excited state 0 - ...

  12. PART III - SECTION J

    National Nuclear Security Administration (NNSA)

    E SECTION J APPENDIX E PERFORMANCE GUARANTEE AGREEMENT(S) Note: To be inserted by the Contracting Officer prior to contract award. For Performance Guarantee Agreement(s) template,...

  13. Section 1703 Loan Program

    Broader source: Energy.gov [DOE]

    Section 1703 of Title XVII of the Energy Policy Act of 2005 authorizes the U.S. Department of Energy to support innovative clean energy technologies that are typically unable to obtain conventional private financing due to high technology risks.

  14. PART III - SECTION J

    National Nuclear Security Administration (NNSA)

    J, Page 1 SECTION J APPENDIX J DIVERSITY PLAN GUIDANCE In accordance with Section I clause DEAR 970.5226-1, Diversity Plan, this Appendix provides guidance to assist the Contractor in understanding the information being sought by the Department of Energy, National Nuclear Security Administration (DOE/NNSA) for each of the diversity elements within the clause. The Contractor shall submit a Diversity Plan to the Contracting Officer for approval within 90 days after the effective date of this

  15. Section II INT

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

    6/14/11 Page 1 of 9 Printed copies of this document are uncontrolled. Retrieve latest version electronically. SANDIA CORPORATION SF 6432-IN (06/14/11) SECTION II GENERAL PROVISIONS FOR INTERNATIONAL COMMERCIAL TRANSACTIONS THE FOLLOWING CLAUSES APPLY TO THIS CONTRACT AS INDICATED UNLESS SPECIFICALLY DELETED, OR EXCEPT TO THE EXTENT THEY ARE SPECIFICALLY SUPPLEMENTED OR AMENDED IN WRITING IN THE SIGNATURE PAGE OR SECTION I OF THIS CONTRACT. IN01 ACCEPTANCE OF TERMS AND CONDITIONS This Contract

  16. Section 1251 Report Update

    National Nuclear Security Administration (NNSA)

    November 2010 Update to the National Defense Authorization Act of FY2010 Section 1251 Report New START Treaty Framework and Nuclear Force Structure Plans 1. Introduction This paper updates elements of the report that was submitted to Congress on May 13, 2010, pursuant to section 1251 of the National Defense Authorization Act for Fiscal Year 2010 (Public Law 111-84) ("1251 Report"). 2. National Nuclear Security Administration and modernization of the complex - an overview From FY 2005

  17. 14655 Section J

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

    6, Mod 420 J.6-1 ATTACHMENT J.6 SMALL BUSINESS SUBCONTRACTING PLAN Plateau Remediation Contract Section J Contract No. DE-AC06-08RL14788 Attachment J.6, Mod 420 J.6-2 SMALL BUSINESS SUBCONTRACTING PLAN for United States Department of Energy Plateau Remediation Contract Submitted by: CH2M HILL PLATEAU REMEDIATION COMPANY Prime Contractor FISCAL YEARS 2009-2018 (Base and Option Period) CONTRACT NUMBER DE-AC06-08RL14788 Revision 4 December 30, 2014 Plateau Remediation Contract Section J Contract

  18. 9Be Cross Section

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

    9Be(p, X) (Current as of 03012016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1997ZA06 9Be(p, ), (p, d): S-factor 16 - 390 keV X4 01232013 1973SI27 9Be(p, ...

  19. 4He Cross Section

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

    p, X) (Current as of 03012016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1974KR07 4He(p, p): 0.5 - 3 X4 10232014 2004PU02 4He(p, p): ( 128.7) ...

  20. 14655 Section C

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

    C Contract No. DE-AC06-05RL14655 226 C-i PART I - THE SCHEDULE SECTION C - STATEMENT OF WORK TABLE OF CONTENTS C.1 PURPOSE, OVERVIEW, END-STATES, AND ORGANIZATION ................................................... 1 C.1.1 PURPOSE AND OVERVIEW ................................................................................................ 1 C.1.2 END-STATES ........................................................................................................................ 1 C.1.3

  1. 14655 Section E

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

    E Contract No. DE-AC06-05RL14655 A000 PART I - THE SCHEDULE SECTION E INSPECTION AND ACCEPTANCE TABLE OF CONTENTS E.1 FAR 52.246-5 INSPECTION OF SERVICES - COST REIMBURSEMENT (APR 1984) .................1 E.2 FIELD INSPECTION ..........................................................................................................................1 E.3 DOE INSPECTION ............................................................................................................................2 E.4

  2. 19F Cross Section

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

    p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1990WA10 19F(p, n): σ < 30 X4 04/26/2012 2008CO03 19F(p, γ): σ Ecm = 200 - 700 keV X4 05/14/2014 1979SU13 19F(p, γ): σ 0.2 - 1.2 X4 05/06/2014 2006COZY 19F(p, γ1): capture yield 200 - 800 keV thin target 12/08/2014 19F(p, γ): capture yield thick target 19F(p, α2γ): capture yield thin target, thick target 2008CO03 19F(p, γ1): reaction cross section Ecm = 200 - 800 keV thin target, thick target

  3. Part III - Section J

    National Nuclear Security Administration (NNSA)

    Corporation Contract No. DE-AC04-94AL85000 Modification No. 585 Attachment 2 Page 1 of 5 Part III - Section J Appendix G List of Applicable Directives and NNSA Policy Letters In addition to the list of applicable directives referenced below, the contractor shall also comply with supplementary directives (e.g., manuals), which are invoked by a Contractor Requirements Document (CRD) attached to a directive referenced below. This List excludes directives that have been granted an exemption from the

  4. Part III - Section J

    National Nuclear Security Administration (NNSA)

    M280 Attachment 1 Page 1 of 5 Part III - Section J Appendix G List of Applicable Directives and NNSA Policy Letters In addition to the list of applicable directives referenced below, the contractor shall also comply with supplementary directives (e.g., manuals), which are invoked by a Contractor Requirements Document (CRD) attached to a directive referenced below. DIRECTIVE NUMBER DATE DOE DIRECTIVE TITLE APPH Chapter X Revision 10 09/08/98 Accounting Practices & Procedures Handbook Chapter

  5. PART III - SECTION J

    National Nuclear Security Administration (NNSA)

    L, Page 1 SECTION J APPENDIX L SPECIAL FINANCIAL INSTITUTION AGREEMENT FOR USE WITH THE PAYMENTS-CLEARED FINANCING ARRANGEMENT Note: (1) The Contractor shall enter into a new banking agreement(s) during the Transition Term of the Contract, utilizing the format contained in this Appendix and include other applicable Contract terms and conditions. (2) Items in brackets [ ] below are provided for clarification and will be removed from the document prior to execution. Agreement entered into this,

  6. 14655 Section J

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

    7, Modification 332 J.7-1 ATTACHMENT J.7 SMALL DISADVANTAGED BUSINESS PARTICIPATION PROGRAM TARGETS Plateau Remediation Contract Section J Contract No. DE-AC06-08RL14788 Attachment J.7, Modification 332 J.7-2 Small Disadvantaged Business (SDB) Participation Program Targets ATTACHMENT J.7 SMALL DISADVANTAGED BUSINESS PARTICIPATION PROGRAM TARGETS (a) OFFEROR - CH2M HILL Plateau Remediation Company - Prime: AREVA Federal Services, LLC; Fluor Federal Services, Inc. (base period only); East

  7. 14655 Section J

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

    8, Revision 3, 420 J.8-1 ATTACHMENT J.8 ADVANCE UNDERSTANDING OF COSTS In accordance with the Section H Clause entitled, Advance Understanding of Costs, this attachment sets forth the basis for determining the allowability of costs associated with expenditures that have cost implications under the Contract, that are not identified in other documents requiring the review and approval of the contracting officer. Unless a date is provided within an item of cost identified below, all items within

  8. 14655 Section J

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

    2 J-1 PART III - LIST OF DOCUMENTS, EXHIBITS, AND OTHER ATTACHMENTS SECTION J -- LIST OF ATTACHMENTS TABLE OF CONTENTS Attachment Number Title of Attachment Modification Number Number of Pages J.1 ABBREVIATIONS AND ACRONYM LIST 0 6 J.2 REQUIREMENTS SOURCES AND IMPLEMENTING DOCUMENTS 331 8 J.3 HANFORD SITE SERVICES AND INTERFACE REQUIREMENTS MATRIX 246 107 J.4 PERFORMANCE EVALUATION AND MEASUREMENT PLAN (PEMP) 249 50 J.5 PERFORMANCE GUARANTEE AGREEMENT 0 3 J.6 SMALL BUSINESS SUBCONTRACTING PLAN

  9. 14655 Section J

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

    8RL14655 640 PART III - LIST OF DOCUMENTS, EXHIBITS, AND OTHER ATTACHMENTS SECTION J LIST OF ATTACHMENTS TABLE OF CONTENTS ATTACHMENT J-1 TABLE OF RIVER CORRIDOR CLOSURE CONTRACT WORK SCOPE ATTACHMENT J-2 DOE DIRECTIVES APPLICABLE TO THE RIVER CORRIDOR CLOSURE CONTRACT ATTACHMENT J-3 PERFORMANCE GUARANTEE AGREEMENTS ATTACHMENT J-4 SMALL BUSINESS SUBCONTRACTING PLAN ATTACHMENT J-5 SMALL DISADVANTAGED BUSINESS PARTICIPATION PROGRAM TARGETS ATTACHMENT J-6 ADVANCE AGREEMENT, PERSONNEL, AND RELATED

  10. Section II INT

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

    (11-03-2010) Title: Standard Terms & Conditions for International Commercial Transactions Owner: Procurement Policy & Quality Dept Initial Release Date: 11/3/10 Page 1 of 8 PPQD-TMPLT-008R01 Template Release Date: 12/01/09 Printed copies of this document are uncontrolled. Before using a printed copy to perform work, verify the version against the electronic document to ensure you are using the correct version. SANDIA CORPORATION SF 6432-IN (11-03-2010) SECTION II GENERAL PROVISIONS FOR

  11. Section II INT

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

    IN (01-12-2010) Title: Standard Terms & Conditions for International Commercial Transactions Owner: Procurement Policy & Quality Dept Initial Release Date: 01/12/10 Page 1 of 6 PPQD-TMPLT-008R01 Template Release Date: 12/01/09 Printed copies of this document are uncontrolled. Before using a printed copy to perform work, verify the version against the electronic document to ensure you are using the correct version. SANDIA CORPORATION SF 6432-IN (01-12-2010) SECTION II GENERAL PROVISIONS

  12. HASQARD Section 4

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

    HASQARD Section 4.2.4, Volume 2, Revision 3 requires: "The field custodian shall seal the cap of the individual sample container so that any tampering is easy to detect. Custody seals shall be used to verify that sample integrity has been maintained during transport." The HASQARD Focus Group provides the following clarification to the requirement: Note: The presence of, or fixative residue from, custody seals can interfere with the functionality of equipment used during analysis (e.g.,

  13. HASQARD Section 4

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

    text of the sixth paragraph in HASQARD Volume 2, Revision 3, Section 4.2.4 is revised to say: "Custody seals shall be used to verify that sample integrity has been maintained during transport. The field custodian shall seal the cap of the individual sample container so that any tampering is easy to detect. In lieu of using a custody seal directly applied to sample containers, the sample container may be placed inside a secondary container that is sealed with a custody seal. Custody tape

  14. 10Be Cross Section

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

    Be(p, X) (Current as of 03/01/2016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1970GO04 10Be(p, γ0): σ 0.6 - 6.3 θ = 0°, θ = 90° 06/05/2012 1987ERZY 10Be(p, n): σ 0.9 - 2 X4 05/15/2012 The following references may be related but not included. 1991GOZV Back to (p, X) Main Page Back to (α, X) Main Page Back to Datacomp Home Page Last modified: 02 March 2016

  15. 14655 Section J

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

    2, Modification 476 J.2-1 ATTACHMENT J.2 REQUIREMENTS SOURCES AND IMPLEMENTING DOCUMENTS The following lists are provided in accordance with the Section I Clause entitled, DEAR 970.5204-2, Laws, Regulations, and DOE Directives. LIST A: APPLICABLE FEDERAL, STATE, AND LOCAL REGULATIONS Table J.2.1 Code of Federal Regulations (CFR) Document Number Title 10 CFR 63 Disposal of High-Level Radioactive Wastes in a Geologic Repository at Yucca Mountain, Nevada 10 CFR 71 Packaging And Transportation Of

  16. 14655 Section J

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

    0, Revision 5 J.10-1 ATTACHMENT J.10 WAGE DETERMINATIONS - SERVICE CONTRACT ACT (SCA) AND DAVIS-BACON ACT Plateau Remediation Contract Section J Contract No. DE-AC06-08RL14788 Attachment J.10, Revision 5 J.10-2 SERVICE CONTRACT ACT WAGE DETERMINATION WD 05-2569 (Rev.-18) was first posted on www.wdol.gov on 07/14/2015 ***************************************************************************** REGISTER OF WAGE DETERMINATIONS UNDER | U.S. DEPARTMENT OF LABOR THE SERVICE CONTRACT ACT | EMPLOYMENT

  17. Cross-Section Measurement

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

    Section Measurement of 2 H(n,np)n at 16 MeV in Symmetric Constant Relative Energy Configurations Alexander Hoff Couture A dissertation submitted to the faculty of the University of North Carolina at Chapel Hill in partial fulfillment of the requirements for the degree of Doctor of Philosophy in the Department of Physics and Astronomy. Chapel Hill 2011 Approved by: T. B. Clegg, Advisor C. R. Howell, Advisor H. J. Karwowski, Reader J. Lu, Reader J. Engel, Reader c 2011 Alexander Hoff Couture ALL

  18. Section L, Paragraph L-4

    National Nuclear Security Administration (NNSA)

    D SECTION L ATTACHMENT D CROSS REFERENCE MATRIX Section L Section M Offeror's Proposal Criterion 1: PAST PERFORMANCE L-15 (a) M-3 (a) Criterion 2: SITE ORGANIZATION AND...

  19. p- to n-type conductivity transition in 1.0 eV GaInNAs solar cells controlled by the V/III ratio

    SciTech Connect (OSTI)

    Langer, Fabian Perl, Svenja; Kamp, Martin; Höfling, Sven

    2015-02-09

    In this work, we report a p- to n-type conductivity transition of GaInNAs (1.0 eV bandgap) layers in p-i-n dilute nitride solar cells continuously controlled by the V/III ratio during growth. Near the transition region, we were able to produce GaInNAs layers with very low effective electrically active doping concentrations resulting in wide depleted areas. We obtained internal quantum efficiencies (IQEs) up to 85% at 0.2 eV above the bandgap. However, the high IQE comes along with an increased dark current density resulting in a decreased open circuit voltage of about 0.2 V. This indicates the formation of non-radiant defect centers related to the p-type to n-type transition. Rapid-thermal annealing of the solar cells on the one hand helps to anneal some of these defects but on the other hand increases the effective doping concentrations.

  20. 6Li Cross Section

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

    α, X) (Current as of 02/01/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1985NE05 6Li(α, γ): γ thick target yield resonance X4 02/15/2012 1966FO05 6Li(α, γ): σ 0.9 - 3.0 2 < Eγ < 4 MeV, 4 < Eγ < 7 MeV, thick target capture γ-ray yield, capture γ-ray yield of 2.43 MeV resonance 02/29/2012 1989BA24 6Li(α, γ): σ 1.085, 1.175 X4 02/15/2012 1979SP01 6Li(α, γ): thick target yield curve for 718 keV γ-rays 1140 - 1250 keV 1175 keV resonance 07/19/2011

  1. 19F Cross Section

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

    α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2008UG01 19F(α, p): yield curves, σ 792 - 1993 keV X4 09/14/2011 2005UG04 19F(α, p1γ): excitation curve 1238 - 2009 keV 1 11/30/2011 19F(α, p0): excitation curve 1 19F(α, p1): excitation curve 1 1984CS01 19F(α, α): σ 1.5 - 3.7 X4 09/14/2011 1994CH36 19F(α, α): σ 1.5 - 4.5 X4 09/14/2011 2000WR01 19F(α, n): neutron yields and σ 2.28 - 3.10 X4 09/14/2011 1977VA10 19F(α, n): differential

  2. 20Ne Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1981DY03 20Ne(p, p'γ): σ for production of γ-rays threshold - 23 1.63-MeV γ-rays X4 03/15/2011 20Ne(p, pαγ): σ for production of γ-rays threshold - 23 6.13-MeV γ-rays 1975RO08 20Ne(p, γ): S-factors 0.37 - 2.10 Direct Capture (DC) → 332-keV state, DC → 2425-keV state, tail of 2425-keV state X4 04/19/2011 20Ne(p, γ): differential σ at θγ = 90° DC → 332-keV state, 332-keV state →

  3. 10B Cross Section

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

    α, X) (Current as of 01/21/2015) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1992MC03 10B(α, α): σ relative to Rutherford scattering 1 - 3.3 X4 05/02/2012 1969GA01 10B(α, p), (α α'): relative σ at θ = 90° for Eγ = 1.0 - 3.5 0.170 MeV, 3.088 MeV, 3.682 MeV, 3.852 MeV, 0.717 MeV 06/18/2012 1973VA25 10B(α, n): laboratory differential σ 1.0 - 5.0 for n0: θ = 0°, θ = 90°, θ = 160° X4 04/04/2011 for n1: θ = 0°, θ = 90° for n23: θ = 0°, θ = 90° 10B(α, n):

  4. 11B Cross Section

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

    B(α, X) (Current as of 02/01/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1991WA02 11B(α, n): thick-target yield of Eα = 411, 605 and 606 keV resonance 350 - 2400 keV 1 X4 04/04/2011 11B(α, n): for 606-keV resonance 1 11B(α, n): for 411-keV resonance after subtraction of the 605-keV resonance 1 11B(α, n): S-factor 1 11B(α, n): S-factor for thick-target 400 - 500 keV 1 11B(α, n): S-factor for thin-target 1 1966MA04, Errata 11B(α, n): excitation curve < 4.5 for

  5. 11C Cross Section

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

    C(p, X) (Current as of 03/01/2016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2013SO11 11C(p, γ): deduced astrophysical reaction rates and S-factors X4 12/14/2015 2003LI51 11C(p, γ): deduced S-factor low X4 09/12/2011 2003TA02 11C(p, γ): deduced S-factor 0 - 0.7 X4 09/12/2011 2003KU36 11C(p, p): elastic scattering σ ~ 0.2 - 3.2 θcm = 180° 09/08/2011 Back to (p, X) Main Page Back to (α, X) Main Page Back to Datacomp Home Page Last modified: 02 March

  6. 12C Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2001NE15 12C(p, γ): σ, deduced S(E) ratio < 160 keV X4 10/28/2014 1993CH02 12C(p, X): σ for η production ≤ 0.9 GeV X4 03/07/2012 1974RO29 12C(p, γ): σ 150 - 3000 keV X4 08/27/2013 1951GO1B 12C(p, p): yield curve of elastic scattering 0.2 - 4.0 θ = 164° 11/05/2014 1976ME22 12C(p, p): absolute σ 0.3 - 2.0 X4 08/07/2013 2008BU19 12C(p, γ): σ, deduced S-factors. 354, 390, 460, 463, 565,

  7. 13C Cross Section

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

    p, X) (Current as of 03/01/2016) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2001NE15 13C(p, γ): σ, deduced S(E) ratio < 160 keV X4 09/12/2011 1994KI02 13C(p, γ): γ-ray yield, calculated S(E) 120 - 950 keV X4 09/12/2011 2008HE11 13C(p, γ): reaction yield at the resonance 448.5-keV for a fresh target and after an integrated charge of 1C 435 - 470 keV σ X4 11/07/2011 1991BR19 13C(p, γ): reaction yield near the resonance 0.44 - 0.6 483.3-keV, 0.55-MeV X4 11/07/2011

  8. 13C Cross Section

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

    α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2006JO11 13C(α, n): deduced S(E) ~ 0 - 1 from (1993BR17), from (1993DR08) X4 08/04/2011 2001HE22 13C(α, n): S(E) 0 - 2 S-factor 11/15/2011 2003KA51 13C(α, n): deduced S-factors, reaction rate Ecm ~ 200 - 800 keV X4 05/01/2012 1993DR08 13C(α, n): excitation function and S(E) ~ 275 - 1075 keV σ, S-factor X4 08/04/2011 2008HE11 13C(α, n): σ, reaction yields and S(E) Ecm = 320 - 700 keV σ, Table

  9. 14N Cross Section

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

    p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2003MU12 14N(p, γ): deduced astrophysical S-factors < 600 keV X4 05/06/2013 1990WA10 14N(p, n): σ < 30 X4 04/26/2012 2005CO16, 2006BE50 14N(p, γ): σ, deduced astrophysical S-factors, resonance strength 70 - 228 keV X4 05/08/2013 2006LE13 14N(p, γ): σ, deduced astrophysical S-factors 70 - 228 keV X4 05/30/2013 2005BR04, 2005BR15 14N(p, γ): astrophysical S-factors ~ 0.1 - 2.5 1 08/15/2013 2004FO02,

  10. 14N Cross Section

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

    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1971CO27 14N(α, γ): thick target yield 0.5 - 1.2 1 08/04/2011 2000GO43 14N(α, γ): resonance yields, deduced astrophysical reaction rates 550 - 1300 keV X4 03/01/2012 1973RO03 14N(α, γ): γ-ray yield 1.0 - 3.2 1 04/30/2012 1980MA26 14N(α, α): σ 1.5, 1.6 X4 03/01/2012 2007CH25 14N(α, γ): deduced resonance parameters 1620 - 1775 keV X4 03/01/2012 1994YE11 14N(α, α): σ(θ)/σ(Rutherford) 2

  11. 16O Cross Section

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

    p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1973MC12 16O(p, α): σ threshold - 7.7 X4 10/17/2012 1981DY03 16O(p, pα): σ for production of γ-rays threshold - 23 4.44-MeV γ-rays X4 03/15/2011 16O(p, p'): σ for production of γ-rays threshold - 23 6.13-MeV γ-rays 1997MO27 16O(p, p), (p, γ): elastic, capture σ Ecm = 200 - 3750 keV X4 03/28/2013 1973RO34 16O(p, γ): S(E) 0.3 - 3.1 S-Factor X4 05/10/2011 16O(p, γ): differential σ for the DC → ground

  12. 18O Cross Section

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

    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2003DA19 18O(α, γ): deduced resonance strengths ~ 470 - 770 keV X4 02/13/2012 1978TR05 18O(α, γ): excitation function for the 1.27 MeV secondary γ-ray transition 0.6 - 2.3 θγ = 0° 02/29/2012 1990VO06 18O(α, γ): resonance γ yields < 0.78 X4 02/13/2012 1973BA10 18O(α, n): σ with target thickness 1 - 5 6 keV, 13 keV 06/06/2011 1956BO61 18O(α, n): neutron yields 1.8 - 5.3 0° - 30° X4

  13. SECTION J, APPENDIX B - PEP

    National Nuclear Security Administration (NNSA)

    SECTION J APPENDIX B PERFORMANCE EVALUATION PLAN Replaced by Mods 002, 016, 020, 029, 0084 Intentionally left blank for Internet posting purposes. Section J, Appendix B, Page 1...

  14. SECTION J, APPENDIX B - PEP

    National Nuclear Security Administration (NNSA)

    SECTION J APPENDIX B PERFORMANCE EVALUATION PLAN Replaced by Mods 002, 016, 020, 029, 0084 Intentionally left blank for Internet posting purposes. Section J, Appendix B, Page 1

  15. Stress analysis and evaluation of a rectangular pressure vessel

    SciTech Connect (OSTI)

    Rezvani, M.A.; Ziada, H.H.; Shurrab, M.S.

    1992-10-01

    This study addresses structural analysis and evaluation of an abnormal rectangular pressure vessel, designed to house equipment for drilling and collecting samples from Hanford radioactive waste storage tanks. It had to be qualified according to ASME boiler and pressure vessel code, Section VIII; however, it had the cover plate bolted along the long face, a configuration not addressed by the code. Finite element method was used to calculate stresses resulting from internal pressure; these stresses were then used to evaluate and qualify the vessel. Fatigue is not a concern; thus, it can be built according to Section VIII, Division I instead of Division 2. Stress analysis was checked against the code. A stayed plate was added to stiffen the long side of the vessel.

  16. 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.

  17. 3H Cross Section

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

    3H(α, X) (Current as of 02/01/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2001TO07 3H(α, γ): deduced S-factor Ecm = 0.05 - 0.8 X4 01/09/2012 1994BR25 3H(α, γ): deduced σ and S-factor Ecm = 50 - 1200 keV X4 01/09/2012 1987SC18 3H(α, γ): σ, deduced S-factor Ecm = 79 - 464 keV X4 01/09/2012 1988SA13 3H(α, α): recoil σ 0.5 - 2.5 X4 01/09/2012 1987BU18 3H(α, γ): σ and S-factor 0.7 - 2 X4 01/09/2012 1968IV01 3H(α, α): elastic scattering σ 3 - 11 Table 9 X4

  18. 3He Cross Section

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

    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1982KR05 3He(α, γ): σ Ecm = 107 - 1266 keV X4 01/05/2012 1969NA24 3He(α, γ): σ and S-factor 164 - 245 keV σ, S(E) X4 07/19/2011 1984OS03 3He(α, γ): σ 165 - 1169 keV X4 01/05/2012 1982OS02 3He(α, γ): S-factor 165 - 1170 keV S34(Ecm) X4 07/19/2011 1988HI06 3He(α, γ): σ Ecm = 195 - 686 keV X4 01/05/2012 2007CO17 3He(α, γ): deduced σ and S-factor 220, 250, 400 keV X4 01/05/2012

  19. 20Ne Cross Section

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

    20Ne(α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1983SC17 20Ne(α, γ): deduced S-factor of capture σ 0.55 - 3.2 X4 09/15/2011 1997WI12 20Ne(α, γ): deduced primary transitions yield 1.64 - 2.65 X4 09/15/2011 1999KO34 20Ne(α, γ): γ-ray yield for the transition 1.9 - 2.8 g.s. 01/03/2012 1369 keV g.s. 10917 keV g.s., 1369 keV 11016 keV g.s. 1975KU06 20Ne(α, γ): σ 2.5 - 20 X4 09/15/2011 1968HI02 20Ne(α, γ): σ 3 - 6 X4 09/15/2011

  20. 10B Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2010LA11 10B(p, α): deduced S(E) E(cm) = 0 - 0.15 1 11/30/2011 1993AN06 10B(p, α): α yield E(cm) = 17 - 134 keV X4 11/07/2011 1993AN09 10B(p, α): absolute fusion σ and S(E) E(cm) = 48 - 159 keV X4 11/07/2011 1972SZ02 10B(p, α): total reaction σ and S(E) 60 - 180 keV 1 X4 03/03/2011 1983WI09 10B(p, γ): γ yield, capture σ(E) 0.07 - 2.2 X4 11/07/2011 2003TO21 10B(pol. p, γ): σ, deduced

  1. 11B Cross Section

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

    p, X) (Current as of 12/17/2015) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2004RO27, 2004SP03 11B(p, α): deduced σ, S-factor Ecm ~ 0 - 1 X4 11/07/2012 2010LA11 11B(p, α): deduced S-factor E(cm) = 0 - 0.6 1 11/30/2011 2000KE10 11B(pol. p, γ): σ, deduced S-factor < 100 keV X4 11/07/2012 1993AN06 11B(p, α): α yield E(cm) = 17 - 134 keV X4 11/29/2012 1979DA03 11B(p, 3α): σ 35.4 - 1500 keV X4 07/30/2014 1992CE02 11B(p, γ): deduced S-factor 40 - 180 keV X4 03/07/2012

  2. 12C Cross Section

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

    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2009MA70 12C(α, γ0): σ 0 - 2.27 X4 05/01/2012 2012OU01 12C(α, γ): deduced S-factor Ecm = 0.3 - 3.5 X4 02/12/2015 1997KU18 12C(α, γ): analyzed S-factor Ecm = 0.9 - 3 X4 05/10/2012 1987RE02 12C(α, γ): σ, deduced S-factor 0.94 - 2.84 X4 05/09/2012 2001HA31 12C(α, γ): deduced S-factors Ecm = 0.95 - 2.78 E1, E2 06/18/2012 2001KU09 12C(α, γ): deduced S-factor Ecm = 0.95 - 2.8 X4 05/09/2012

  3. 14C Cross Section

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

    C(p, X) (Incomplete) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1969SI04 14C(p, γ): γ-rays yield for 230 - 690 keV Eγ ≥ 2.8 MeV 08/15/2013 1990GO25 14C(p, γ): σ, deduced S-factor 250 - 740 keV X4 10/28/2014 1968HE12 14C(p, γ): γ-ray yield 0.6 - 2.7 γ0 01/06/2015 1991WA02 14C(p, n): σ 1.0 - 1.55 X4 10/28/2014 1968HA27 14C(p, p): σ at θcm = 1.0 - 2.7 39.2°, 54.7°, 90°, 125.3°, 161.4° 08/15/2013 1971KU01 14C(p, γ0): excitation function at θ = 90° 1.3 - 2.6 1

  4. 15N Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 1990WA10 15N(p, n): σ < 30 X4 04/26/2012 1982RE06 15N(p, α): σ 78 - 810 keV X4 09/12/2011 1979ZY02 15N(p, α0): σ, deduced S-factor 93 - 418 keV X4 09/12/2011 2010LE21, 2013DE03 15N(p, γ): σ, S-factors 130 - 1800 keV X4 05/01/2012 & 02/01/2016 2012IM02 15N(p, γ), (p, αγ): σ, S-factors 0.14 - 1.80 X4 02/01/2016 1974RO37 15N(p, γ), (p, αγ): σ 150 - 2500 keV X4 09/12/2011 1968GO07

  5. 15N Cross Section

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

    α, X) (Current as of 05/14/2012) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2002WI18 15N(α γ): σ 461 - 2642 keV X4 09/12/2011 1997WI12 15N(α γ): σ 0.65 - 2.65 X4 09/12/2011 1995WI26 15N(α γ): σ 0.67 - 0.69 X4 09/12/2011 1969AI01 15N(α γ): γ-ray excitation curve for 3.0 ≤ Eγ ≤ 7.0 MeV 2.5 - 3.2 1 11/30/2011 1977DI08 15N(α, γ): γ-ray excitation curve near Eα = 3.15 MeV for transitions to 3146 - 3158 keV five low-lying states, 4.65 MeV (13/2+) state

  6. 16O Cross Section

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

    6O(α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 1971TO06 16O(α, γ): σ 0.85 - 1.8 X4 09/15/2011 1953CA44 16O(α, α): σ 0.94 - 4.0 X4 09/15/2011 1997KU18 16O(α, γ): analyzed S-factor 1 - 3.25 X4 05/10/2012 1980MA27 16O(α, α): σ 1.305 - 1.330; 2.950 - 3.075 X4 02/14/2012 16O(α, γ): σ 1.37, 2.6, 2.9, 3.036 1987HA24 16O(α, γ): σ Ecm = 1.7 - 2.35 X4 02/14/2012 1990LE06 16O(α, α): σ 1.8 - 5 X4 03/12/2011 1985JA17 16O(α, α): σ 2

  7. 17O Cross Section

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

    p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2010SE11 17O(p, α): nuclear excitation function 0 - 0.7 1 06/22/2011 1973RO03 17O(p, γ): γ-ray yield 0.15 - 1.4 1 08/01/2012 2015BU02 17O(p, γ): total S(E)-factors 0.17 - 0.53 X4 03/03/2016 2012SC16, 2014DI01 17O(p, γ): σ, deduced S-factors Ecm = 0.2 - 0.4 X4 03/03/2016 1973RO34 17O(p, γ): S(E) 0.3 - 1.9 S-Factor X4 06/22/2011 17O(p, γ): σ for the γ-ray transition 0.94 → 0 MeV 17O(p, γ):

  8. 17O Cross Section

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

    α, X) (Current as of 02/08/2016) NSR Reaction Eα (MeV) Cross Section File X4 Dataset Date Added 2013BE11; see also 2012BEZP 17O(α, n), (α, γ): σ, S-factors 0.8 - 2.3 X4 02/12/2015 1973BA10 17O(α, n): neutron yields with target thickness 0.9 - 5.3 ~ 2.5 keV, 6 keV, 13 keV, ~ 35 keV 06/06/2011 1976MC12 17O(α, n1): yield of 1.63-MeV γ's 1.4 - 2.3 θγ = 50° 04/28/2011 17O(α, n0): yield of neutrons θn = 120° 17O(α, n1): yield of 1.63-MeV γ's 1.825 - 1.885 θγ = 0° 05/03/2011 17O(α,

  9. 18O Cross Section

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

    8O(p, X) (Current as of 05/15/2012) NSR Reaction Ep (MeV) Cross Section File X4 Dataset Date Added 2008LA06 18O(p, α): deduced S-factor Ecm = 0 - 1.5 θα = 46° 12/03/2012 1990CH32 18O(p, α): σ < 2 X4 10/04/2012 1990VO06 18O(p, γ): resonance γ yields < 0.22 X4 02/13/2012 2008LA13 18O(p, α): deduced σ 0 - 250 keV X4 10/20/2014 1973BA31 18O(p, n): total neutron-production σ < 5 1 X4 05/10/2011 1990WA10 18O(p, n): σ < 30 X4 04/26/2012 1979LO01 18O(p, α): σ 72 - 935 keV X4

  10. Section L, Paragraph L-4

    National Nuclear Security Administration (NNSA)

    D SECTION L ATTACHMENT D CROSS REFERENCE MATRIX Section L Section M Offeror's Proposal Criterion 1: PAST PERFORMANCE L-15 (a) M-3 (a) Criterion 2: SITE ORGANIZATION AND QUALIFICATIONS OF KEY PERSONNEL L-15 (b)(1) M-3 (b)(1) L-15 (b)(2) M-3 (b)(2) Criterion 3: SMALL BUSINESS PARTICIPATION L-15 (c) M-3 (c)

  11. Weld Repair of a Stamped Pressure Vessel in a Radiologically Controlled Zone

    SciTech Connect (OSTI)

    Cannell, Gary L.; Huth, Ralph J.; Hallum, Randall T.

    2013-08-26

    In September 2012 an ASME B&PVC Section VIII stamped pressure vessel located at the DOE Hanford Site Effluent Treatment Facility (ETF) developed a through-wall leak. The vessel, a steam/brine heat exchanger, operated in a radiologically controlled zone (by the CH2MHill PRC or CHPRC), had been in service for approximately 17 years. The heat exchanger is part of a single train evaporator process and its failure caused the entire system to be shut down, significantly impacting facility operations. This paper describes the activities associated with failure characterization, technical decision making/planning for repair by welding, logistical challenges associated with performing work in a radiologically controlled zone, performing the repair, and administrative considerations related to ASME code requirements.

  12. PART III-SECTION J

    National Nuclear Security Administration (NNSA)

    C SECTION J APPENDIX C TRANSITION PLAN Plan: [To be inserted by the Contracting Officer.] Requirements: In accordance with Section F, Deliverables During Transition, the Contractor shall submit a Transition Plan for the Contracting Officer's approval 10 days after Contract award. The Transition plan shall describe the process, details, schedule, and cost for providing an orderly transition during the Contract's Transition Term stated in Section F, F-3 Period of Performance. The Transition Plan

  13. PART III … SECTION J

    National Nuclear Security Administration (NNSA)

    B, Page 1 SECTION J APPENDIX B AWARD FEE PLAN [Note: To be inserted by the Contracting Officer after contract award.]

  14. PART III … SECTION J

    National Nuclear Security Administration (NNSA)

    M, Page 1 SECTION J APPENDIX M CONTRACTOR COMMITMENTS, AGREEMENTS, AND UNDERSTANDINGS [Note: To be inserted by the Contracting Officer after contract award.]

  15. SECTION J, APPENDIX A - SOW

    National Nuclear Security Administration (NNSA)

    0007749 SECTION J, APPENDIX A: STATEMENT OF WORK TABLE OF CONTENTS CHAPTER I. OBJECTIVES, SCOPE, AND REQUIREMENTS ......................................................................... 1 1.0 OBJECTIVE .................................................................................................................................................. 1 2.0 BACKGROUND

  16. SECTION M_Evaluation Factors

    National Nuclear Security Administration (NNSA)

    EVALUATION OF PROPOSALS .....................................................................................2 M-2 BASIS FOR CONTRACT AWARD ...................................................................................3 M-3 TECHNICAL AND MANAGEMENT CRITERIA ..........................................................3 M-4 COST CRITERION .............................................................................................................6 Section M, Page 2 M-1 EVALUATION OF PROPOSALS

  17. SECTION J - TABLE OF CONTENTS

    National Nuclear Security Administration (NNSA)

    Conformed to Mod 0108 DE-NA0000622 Section J Page i PART III - LIST OF DOCUMENTS, EXHIBITS, AND OTHER ATTACHMENTS SECTION J LIST OF APPENDICES TABLE OF CONTENTS Appendix A Statement of Work (Replaced by Mod 002; Modified Mod 016; Replaced Mod 029) Appendix B Performance Evaluation Plan (Replaced by Mods 002, 016, 020, 029, 0084) Appendix C Contractor's Transition Plan Appendix D Sensitive Foreign Nations Control Appendix E Performance Guarantee Agreement(s) Appendix F National Work Breakdown

  18. RFP Section H Clause Templates

    Office of Energy Efficiency and Renewable Energy (EERE)

    On May 3, 2011, twenty two draft Section H clause templates were distributed for Procurement Director (PD), Head of Contracting Activity (HCA), General Counsel and National Nuclear Security Administration (NNSA) review and comment. All comments received were considered and changes were made as appropriate including the elimination of six clauses. The final version of the sixteen RFP Section H clause templates identified below will be available in STRIPES.

  19. RFP Section L Attachment Templates

    Broader source: Energy.gov [DOE]

    On March 29,2010, six draft RFP Section L Attachment templates (Past Performance Information Questionnaire, Past Performance Questionnaire Cover Letter, Letter of Commitment, Past Performance Reference Information Form, ESH&Q Past Performance Information Form, and Resume Format) were distributed for Procurement Director (PD) and Head of Contracting Activity (HCA) review and comment. All comments received were considered and changes were made as appropriate. The final versions of the six aforementioned RFP Section L Attachment templates will be e-mailed directly to the Procurement Directors and made available in the STRIPES Library. For RFP's generated in STRIPES, the Section L Attachments should be identified in clause DOE-L-1033 and the file with each Attachment should be attached to the RFP.

  20. Transition section for acoustic waveguides

    DOE Patents [OSTI]

    Karplus, H.H.B.

    1975-10-28

    A means of facilitating the transmission of acoustic waves with minimal reflection between two regions having different specific acoustic impedances is described comprising a region exhibiting a constant product of cross-sectional area and specific acoustic impedance at each cross-sectional plane along the axis of the transition region. A variety of structures that exhibit this feature is disclosed, the preferred embodiment comprising a nested structure of doubly reentrant cones. This structure is useful for monitoring the operation of nuclear reactors in which random acoustic signals are generated in the course of operation.

  1. COS OBSERVATIONS OF METAL LINE AND BROAD LYMAN-{alpha} ABSORPTION IN THE MULTI-PHASE O VI AND Ne VIII SYSTEM AT z = 0.20701 TOWARD HE 0226-4110

    SciTech Connect (OSTI)

    Savage, B. D. [Department of Astronomy, University of Wisconsin-Madison, 475 North Charter Street, Madison, WI 53706 (United States); Lehner, N. [Department of Physics, University of Notre Dame, 225 Nieuwland Science Hall, Notre Dame, IN 46556 (United States); Narayanan, A. [Indian Institute of Space Science and Technology, Thiruvananthapuram 695547, Kerala (India)

    2011-12-20

    Observations of the QSO HE 0226-4110 (z{sub em} = 0.495) with the Cosmic Origins Spectrograph (COS) from 1134 to 1796 A with a resolution of {approx}17 km s{sup -1} and signal-to-noise ratio (S/N) per resolution element of 20-40 are used to study the multi-phase absorption system at z = 0.20701 containing O VI and Ne VIII. The system was previously studied with lower S/N observations with Far-Ultraviolet Spectroscopic Explorer (FUSE) and Space Telescope Imaging Spectrograph (STIS). The COS observations provide more reliable measures of the H I and metal lines present in the system and reveal the clear presence of broad Ly{alpha} (BLA) absorption with b = 72(+13, -6) km s{sup -1} and log N(H I) = 13.87 {+-} 0.08. Detecting BLAs associated with warm gas absorbers is crucial for determining the temperature, metallicity, and total baryonic content of the absorbers. The BLA is probably recording the trace amount of thermally broadened H I in the collisionally ionized plasma with log T {approx} 5.7 that also produces the O VI and Ne VIII absorption. The total hydrogen column in the collisionally ionized gas, log N(H) {approx} 20.1, exceeds that in the cooler photoionized gas in the system by a factor of {approx}22. The oxygen abundance in the collisionally ionized gas is [O/H] = -0.89 {+-} 0.08 {+-} 0.07. The absorber probably occurs in the circumgalactic environment (halo) of a foreground L = 0.25L{sub *} disk galaxy with an impact parameter of 109 h{sub 70}{sup -1} kpc identified by Mulchaey and Chen.

  2. ASM2010_Egluning_poster.pptx

    Office of Scientific and Technical Information (OSTI)

    and Environmental Research, Genomics:GTL Foundational Science through contract DE-AC02-05CH11231 between Lawrence Berkeley National Laboratory and the U. S. Department of Energy. ...

  3. ASM 2010_Jray_poster.ppt

    Office of Scientific and Technical Information (OSTI)

    and Environmental Research, Genomics:GTL Foundational Science through contract DE-AC02-05CH11231 between Lawrence Berkeley National Laboratory and the U. S. Department of Energy. ...

  4. ASM 2010_Lrajeev_poster.pptx

    Office of Scientific and Technical Information (OSTI)

    and Environmental Research, Genomics:GTL Foundational Science through contract DE-AC02-05CH11231 between Lawrence Berkeley National Laboratory and the U. S. Department of Energy. ...

  5. ASME1-96A.PDF

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

    annual energy capture. One such technique envisages the use of an adaptive or "smart" blade structure that could sense the wind velocity in some fashion and accordingly modify...

  6. ASME1-98b.PDF

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

    relations. For the bending- twist coupling the "stress-strain" relations at a point along the blade span are given by: American Institute of Aeronautics and Astronautics...

  7. ASME95_CurveFit.PDF

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

    MODELS ON FATIGUE LIFE PREDICTIONS 1 Herbert J. Sutherland and Paul S. Veers Wind Energy Technology Sandia National Laboratories Albuquerque, NM 87185-0708 ABSTRACT 1 The...

  8. Girrens and Livescu named ASME Fellows

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

    and spokesman for his or her particular industry. The recipients must have a documented history of successful major accomplishments in management and have received recognition...

  9. SECTION M_Evaluation Factors

    National Nuclear Security Administration (NNSA)

    EVALUATION OF PROPOSALS................................................................2 M-2 BASIS FOR CONTRACT AWARD.............................................................3 M-3 TECHNICAL AND MANAGEMENT CRITERIA...........................................3 M-4 COST CRITERION.................................................................................5 Section M, Page 2 M-1 EVALUATION OF PROPOSALS (a) This acquisition will be conducted using the policies and procedures in Federal

  10. SECTION M_Evaluation Factors

    National Nuclear Security Administration (NNSA)

    TABLE OF CONTENTS M-1 EVALUATION OF PROPOSALS......................................................................176 M-2 BASIS FOR CONTRACT AWARD...................................................................177 M-3 TECHNICAL AND MANAGEMENT CRITERIA..........................................177 M-4 COST CRITERION.............................................................................................179 Section M, Page 176 M-1 EVALUATION OF PROPOSALS (a) This acquisition will be

  11. SECTION J, APPENDIX A - SOW

    National Nuclear Security Administration (NNSA)

    Mod 002; Modified Mod 016; Replaced Mod 029; Modified Mod 0049) Honeywell FM&T, LLC Contract No. DE-NA0000622 SECTION J APPENDIX A STATEMENT OF WORK 09/19/12 TABLE OF CONTENTS CHAPTER I. OBJECTIVES, SCOPE, AND REQUIREMENTS ......................................................................... 1 1.0 OBJECTIVE .................................................................................................................................................. 1 2.0 BACKGROUND

  12. Transverse section radionuclide scanning system

    DOE Patents [OSTI]

    Kuhl, David E.; Edwards, Roy Q.

    1976-01-01

    This invention provides a transverse section radionuclide scanning system for high-sensitivity quantification of brain radioactivity in cross-section picture format in order to permit accurate assessment of regional brain function localized in three-dimensions. High sensitivity crucially depends on overcoming the heretofore known raster type scanning, which requires back and forth detector movement involving dead-time or partial enclosure of the scan field. Accordingly, this invention provides a detector array having no back and forth movement by interlaced detectors that enclose the scan field and rotate as an integral unit around one axis of rotation in a slip ring that continuously transmits the detector data by means of laser emitting diodes, with the advantages that increased amounts of data can be continuously collected, processed and displayed with increased sensitivity according to a suitable computer program.

  13. Cross Sections for (p, X)

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

    Cross Sections for (p, X) Reaction for Nuclei A = 3 - 20 Go to the Text Only below if you prefer to view the nuclides in a text list. 20Ne 19F 16O 17O 18O 14N 15N 11C 12C 13C 14C 10B 11B 7Be 9Be 10Be 6Li 7Li 3He 4He Note: Comments, and corrections are welcome. Please email us. List of available cross section data for A = 3 - 20 nuclides: Helium: 3He, 4He Lithium: 6Li, 7Li Beryllium: 7Be, 9Be, 10Be Boron: 10B, 11B Carbon: 11C, 12C, 13C, 14C Nitrogen: 14N, 15N Oxygen: 16O, 17O, 18O Fluorine: 19F

  14. Cross Sections for (α, X)

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

    Cross Sections for (α, X) Reaction for Nuclei A = 3 - 20 Go to the Text Only below if you prefer to view the nuclides in a text list. 20Ne 19F 16O 17O 18O 14N 15N 12C 13C 10B 11B 9Be 10Be 6Li 7Li 3He 4He 3H Note: Comments, and corrections are welcome. Please email us. List of available cross section data for A = 3 - 20 nuclides: Hydrogen: 3H Helium: 3He, 4He Lithium: 6Li, 7Li Beryllium: 9Be, 10Be Boron: 10B, 11B Carbon: 12C, 13C Nitrogen: 14N, 15N Oxygen: 16O, 17O, 18O Fluorine: 19F Neon: 20Ne

  15. PART III … SECTION J

    National Nuclear Security Administration (NNSA)

    18 Section J Appendix F List of Applicable Laws, Regulations, and DOE Directives In addition to the list of applicable directives referenced below, the Contractor shall also comply with supplementary directives (e.g., manuals), which are invoked by a Contractor Requirements Document (CRD) attached to a directive referenced below. This List excludes directives that have been granted an exemption from the CRD in whole or in part. For those Directives whereby the Contractor has been granted an

  16. Recommended Dosimetry Cross Section Compendium.

    Energy Science and Technology Software Center (OSTI)

    1994-07-11

    Version 00 The data is recommended for spectrum determination applications and for the prediction of neutron activation of typical radiation sensor materials. The library has been tested for consistency of the cross sections in a wide variety of neutron environments. The results and cautions from this testing have been documented. The data has been interfaced with radiation transport codes, such as TWODANT-SYS (CCC-547) and MCNP (CCC-200), in order to compare calculated and measured activities formore » benchmark reactor experiments.« less

  17. Turbine airfoil having outboard and inboard sections

    SciTech Connect (OSTI)

    Mazzola, Stefan; Marra, John J

    2015-03-17

    A turbine airfoil usable in a turbine engine and formed from at least an outboard section and an inboard section such that an inner end of the outboard section is attached to an outer end of the inboard section. The outboard section may be configured to provide a tip having adequate thickness and may extend radially inward from the tip with a generally constant cross-sectional area. The inboard section may be configured with a tapered cross-sectional area to support the outboard section.

  18. Part IV: Section D - Packaging and Marking

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

    PART I SECTION D PACKAGING AND MARKING DE-AC36-08GO28308 Modification M901 Section D - Page ii PART I SECTION D PACKAGING AND MARKING TABLE OF CONTENTS D.1 Packaging 1 D.2 Marking ...

  19. Section 999: Annual Plans | Department of Energy

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

    September 10, 2013 Draft 2014 Annual Plan Section 999: Draft 2014 Annual Plan July 8, 2013 2013 Annual Plan Section 999: 2013 Annual Plan August 3, 2012 2012 Annual Plan Section ...

  20. OpenEI Community - Section 7

    Open Energy Info (EERE)

    http:en.openei.orgcommunityblogidaho-meeting-2comments endangered species Fauna Fish and Wildlife Flora FWS Section 12 Section 7 Geothermal Regulatory Roadmap Wed, 05 Sep...

  1. Regulatory Review Comment Section | Department of Energy

    Office of Environmental Management (EM)

    Radiation Protection of the Public and the Environment Regulatory Review Comment Section Regulatory Review Comment Section DOE Comments on Radiation Protection (Atomic Energy ...

  2. Vermont Section 401 Water Quality Certification Application ...

    Open Energy Info (EERE)

    Abstract Application required for Section 401 water quality certification under the Clean Water Act. Form Type ApplicationNotice Form Topic Section 401 Water Quality...

  3. Section 3: Office Portfolio Management, Bioenergy Technologies...

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

    Portfolio Management 3-1 Last revised: March 2015 Section 3: Office Portfolio Management This section describes how the U.S. Department of Energy's (DOE's) Bioenergy Technologies ...

  4. Electron Photon Interaction Cross Sections

    Energy Science and Technology Software Center (OSTI)

    2014-11-01

    Version 00 The Electron Photon Interaction Cross Sections, EPICS, provides the atomic data needed to perform coupled Electron-Photon transport calculations, to produce accurate macroscopic results, such as energy deposit and dose. Atomic data is provided for elements, Z = 1 to 100, over the energy range 10 eV to 100 GeV; note that nuclear data, such as photo-nuclear, and data for compounds, are not included. All data is in a simple computer independent text formatmore » that is standard and presented to a high precision that can be easily read by computer codes written in any computer language, e.g., C, C++, and FORTRAN. EPICS includes four separate data bases that are designed to be used in combination, these include, • The Evaluated Electron Data Library (EEDL), to describe the interaction of electrons with matter. • The Evaluated Photon Data Library (EPDL), to describe the interaction of photons with matter. • The Evaluated Atomic Data Library (EADL), to describe the emission of electrons and photons back to neutrality following an ionizing event, caused by either electron or photon interactions. • The Evaluated Excitation Data Library (EXDL), to describe the excitation of atoms due to photon interaction. All of these are available in the Extended ENDL format (ENDLX) in which the evaluations were originally performed. The first three are also available in the ENDF format; as yet ENDF does not include formats to handle excitation data (EXDL).« less

  5. Elastic scattering and total cross sections

    SciTech Connect (OSTI)

    Cahn, R.N.

    1990-03-01

    This report discusses concepts of elastic scattering and cross sections of proton-proton interactions. (LSP)

  6. Part V: Section H: Special Contract Requirements

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

    DE-AC36-08GO28308 Modification M801 Section H - Page 2 of 50 PART I SECTION H SPECIAL CONTRACT REQUIREMENTS TABLE OF CONTENTS H.1 No Third Party Beneficiaries...

  7. Section 12 | OpenEI Community

    Open Energy Info (EERE)

    Contributor 4 September, 2012 - 21:36 Idaho Meeting 2 endangered species Fauna Fish and Wildlife Flora FWS Section 12 Section 7 The second Idaho GRR meeting was held today...

  8. Section 7 | OpenEI Community

    Open Energy Info (EERE)

    Contributor 4 September, 2012 - 21:36 Idaho Meeting 2 endangered species Fauna Fish and Wildlife Flora FWS Section 12 Section 7 The second Idaho GRR meeting was held today...

  9. Spontaneous Potential (book section) | Open Energy Information

    Open Energy Info (EERE)

    Reference LibraryAdd to library Book Section: Spontaneous Potential (book section) Author NA Published NA, The date "NA" was not understood.The date "NA" was not understood....

  10. OpenEI Community - Section 12

    Open Energy Info (EERE)

    http:en.openei.orgcommunityblogidaho-meeting-2comments endangered species Fauna Fish and Wildlife Flora FWS Section 12 Section 7 Wed, 05 Sep 2012 04:36:43 +0000 Kyoung 488...

  11. NAABB Full Final Report Section I

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

    REPORT SECTION I FULL FINAL REPORT SECTION I FULL FINAL REPORT SECTION I Program Overview Table of Contents Executive Summary ........................................................................................ iv Synopsis .......................................................................................................... 1 Perspective 1. NAABB was Preceded by the Aquatic Species Program ................ 29 Perspective 2. NAABB and the National Research Council Report on Sustainable

  12. SNL RML recommended dosimetry cross section compendium

    SciTech Connect (OSTI)

    Griffin, P.J.; Kelly, J.G.; Luera, T.F.; VanDenburg, J.

    1993-11-01

    A compendium of dosimetry cross sections is presented for use in the characterization of fission reactor spectrum and fluence. The contents of this cross section library are based upon the ENDF/B-VI and IRDF-90 cross section libraries and are recommended as a replacement for the DOSCROS84 multigroup library that is widely used by the dosimetry community. Documentation is provided on the rationale for the choice of the cross sections selected for inclusion in this library and on the uncertainty and variation in cross sections presented by state-of-the-art evaluations.

  13. Part IV: Section D - Packaging and Marking

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

    PART I SECTION D PACKAGING AND MARKING DE-AC36-08GO28308 Modification M901 Section D - Page ii PART I SECTION D PACKAGING AND MARKING TABLE OF CONTENTS D.1 Packaging 1 D.2 Marking 1 DE-AC36-08GO28308 Modification M901 Section D - Page 1 of 1 PART I SECTION D PACKAGING AND MARKING D.1 Packaging Preservation, packaging, and packing for shipment or mailing of all work delivered hereunder shall be in accordance with good commercial practice and adequate to insure acceptance by common carrier and

  14. Part IV: Section E - Inspection and Acceptance

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

    SECTION E INSPECTION AND ACCEPTANCE DE-AC36-08GO28308 Modification M901 Section E - Page ii PART I SECTION E INSPECTION AND ACCEPTANCE TABLE OF CONTENTS E.1 FAR 52.246-9 Inspection of Research and Development (Short Form) (Apr 1984) 1 E.2 Acceptance 1 E.3 Certification 1 DE-AC36-08GO28308 Modification M901 Section E - Page 1 of 1 PART I SECTION E INSPECTION AND ACCEPTANCE E.1 FAR 52.246-9 Inspection of Research and Development (Short Form) (Apr 1984) The Government has the right to inspect and

  15. Vertically stabilized elongated cross-section tokamak

    DOE Patents [OSTI]

    Sheffield, George V.

    1977-01-01

    This invention provides a vertically stabilized, non-circular (minor) cross-section, toroidal plasma column characterized by an external separatrix. To this end, a specific poloidal coil means is added outside a toroidal plasma column containing an endless plasma current in a tokamak to produce a rectangular cross-section plasma column along the equilibrium axis of the plasma column. By elongating the spacing between the poloidal coil means the plasma cross-section is vertically elongated, while maintaining vertical stability, efficiently to increase the poloidal flux in linear proportion to the plasma cross-section height to achieve a much greater plasma volume than could be achieved with the heretofore known round cross-section plasma columns. Also, vertical stability is enhanced over an elliptical cross-section plasma column, and poloidal magnetic divertors are achieved.

  16. Expandable mixing section gravel and cobble eductor

    DOE Patents [OSTI]

    Miller, Arthur L. (Kenyon, MN); Krawza, Kenneth I. (Lakeville, MN)

    1997-01-01

    In a hydraulically powered pump for excavating and transporting slurries in hich it is immersed, the improvement of a gravel and cobble eductor including an expandable mixing section, comprising: a primary flow conduit that terminates in a nozzle that creates a water jet internal to a tubular mixing section of the pump when water pressure is applied from a primary supply flow; a tubular mixing section having a center line in alignment with the nozzle that creates a water jet; a mixing section/exit diffuser column that envelopes the flexible liner; and a secondary inlet conduit that forms an opening at a bas portion of the column and adjacent to the nozzle and water jet to receive water saturated gravel as a secondary flow that mixes with the primary flow inside of the mixing section to form a combined total flow that exits the mixing section and decelerates in the exit diffuser.

  17. Cross Sections for Electron Collisions with Methane

    SciTech Connect (OSTI)

    Song, Mi-Young Yoon, Jung-Sik; Cho, Hyuck; Itikawa, Yukikazu; Karwasz, Grzegorz P.; Kokoouline, Viatcheslav; Nakamura, Yoshiharu; Tennyson, Jonathan

    2015-06-15

    Cross section data are compiled from the literature for electron collisions with methane (CH{sub 4}) molecules. Cross sections are collected and reviewed for total scattering, elastic scattering, momentum transfer, excitations of rotational and vibrational states, dissociation, ionization, and dissociative attachment. The data derived from swarm experiments are also considered. For each of these processes, the recommended values of the cross sections are presented. The literature has been surveyed through early 2014.

  18. Montana Watershed Protection Section Contacts Webpage | Open...

    Open Energy Info (EERE)

    contact information for the Watershed Protection Section of the Water Quality Planning Bureau. Author Montana Water Quality Planning Bureau Published State of Montana, Date Not...

  19. Section 106 Archaeology Guidance (ACHP, 2009)

    Broader source: Energy.gov [DOE]

    The Advisory Council on Historic Preservation's Section 106 guidance is designed to assist federal agencies in making effective management decisions about archaeological resources in completing the requirements of Section 106 of the National Historic Preservation Act (16 U.S.C. 470f) and its implementing regulations (36 CFR Part 800). This guidance highlights the decision-making role of the federal agency in the Section 106 process. It is also designed for use by State and Tribal Historic Preservation Officers, Indian tribes, Native Hawaiian organizations, and cultural resource management professionals when assisting federal agencies to meet their responsibilities under Section 106.

  20. ACHP - Section 106 Regulations Flowchart Explanatory Material...

    Open Energy Info (EERE)

    Explanatory Material Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: ACHP - Section 106 Regulations Flowchart Explanatory Material Abstract This...

  1. Microsoft Word - SECTION D.docx

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

    Occupational Medical Services at Hanford D-1 PART I - THE SCHEDULE SECTION D PACKAGING AND MARKING TABLE OF CONTENTS D.1 PACKAGING ......

  2. Cal. PRC Section 21065 - Environmental Quality Definitions |...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Cal. PRC Section 21065 - Environmental Quality DefinitionsLegal Abstract Contains...

  3. RPM Sections - RPM-2 RPM-2

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

    clock History Browse Pages Blog Labels Attachments Index Recent updates RSS feed builder Home RPM Sections Asset Management Information Technology (Assets) Lifecycle Management...

  4. Part IV: Section F - Deliveries or Performance

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

    F DELIVERIES OR PERFORMANCE DE-AC36-08GO28308 Modification M933 Section F - Page ii PART I SECTION F DELIVERIES OR PERFORMANCE TABLE OF CONTENT F.1 Term of Contract 1 F.2 Principal Place of Performance 1 F.3 FAR 52.242-15 Stop-Work Order (Aug 1989) (Alternate 1) (Apr 1984) 1 DE-AC36-08GO28308 Modification M933 Section F - Page 1 of 2 PART I SECTION F DELIVERIES OR PERFORMANCE F.1 Term of Contract (a) This contract shall be effective as specified in Block No. 28, Award Date, of SF 33, and shall

  5. Part IV: Section G - Contract Administration Data

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

    G CONTRACT ADMINISTRATION DATA DE-AC36-08GO28308 Modification M901 Section G - Page ii PART I SECTION G CONTRACT ADMINISTRATION DATA TABLE OF CONTENTS G.1 Contracting Officer's Representative(s) 1 G.2 Contract Administration 1 G.3 Modification Authority 1 G.4 Monthly Cost Reports 1 G.5 Indirect Charges 2 DE-AC36-08GO28308 Modification M901 Section G - Page 1 of 2 PART I SECTION G CONTRACT ADMINISTRATION DATA G.1 Contracting Officer's Representative(s) Contracting Officer's Representative(s)

  6. Part V: Section H - Special Contract Requirements

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

    H SPECIAL CONTRACT REQUIREMENTS DE-AC36-08GO28308 Modification M962 Section H - Page 2 of 52 PART I SECTION H SPECIAL CONTRACT REQUIREMENTS TABLE OF CONTENTS H.1 No Third Party Beneficiaries ............................................................................................. 4 H.2 Reserved ............................................................................................................................ 4 H.3 Employee Compensation: Pay and Benefits

  7. Part VI: Section I - Contract Clauses

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

    DE-AC36-08GO28308 Modification M1033 Section I - Page ii PART II SECTION I CONTRACT CLAUSES TABLE OF CONTENTS I.1 52.252-2 -- Clauses Incorporated by Reference (Feb 1998) ............................................................... 1 I.2 52.202-1 -- Definitions (Nov 2013) .................................................................................................... 1 I.3 52.203-3 -- Gratuities (Apr 1984)

  8. SECTION V. SUPERCONDUCTING CYCLOTRON AND INSTRUMENTATION

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

    H SECTION J APPENDIX H KEY PERSONNEL [Note: To be inserted by the Contracting Officer after

    B, Page 1 SECTION L ATTACHMENT B LISTING OF KEY PERSONNEL TITLE NAME [Note: Add/remove extra rows if needed]

    A, Page 1 SECTION L ATTACHMENT A PERFORMANCE GUARANTEE AGREEMENT For value received, and in consideration of, and in order to induce the United States (the Government) to enter into Contract [insert Contract number] for the management and operation of the Nevada National Security Site

  9. GTA Welding Research and Development for Plutonium Containment

    SciTech Connect (OSTI)

    Sessions, C.E.

    2002-02-21

    This paper discusses the development of two welding systems that are used to contain actinide metals and oxides for long term storage. The systems are termed the bagless transfer system (BTS) and the outer container welder (OCW) system. The BTS is so named because it permits the containment of actinides without a polymeric package (i.e., bag). The development of these two systems was directed by Department of Energy Standard 3013, hereafter referred to as DOE 3013. This document defines the product and container requirements. In addition, it references national codes and standards for leak rates, ANSI N14.5, and design, American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section VIII (BandPVC).

  10. EPAct Section 242 Comments and DOE Responses

    Office of Energy Efficiency and Renewable Energy (EERE)

    On July 2, 2014 in the Federal Register, the U.S. Department of Energy (DOE) published and requested comment on draft guidance for implementing Section 242 of the Energy Policy Act of 2005 (EPAct...