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Sample records for decision bp rod

  1. Record of Decision (ROD) | Department of Energy

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

    0, 2003 EIS-0349: Record of Decision Electrical Interconnection of the BP Cherry Point Cogeneration Project October 31, 2003 EIS-0312: Record of Decision Fish and Wildlife...

  2. Record of Decision (ROD) | Department of Energy

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

    Energy Projects October 25, 2005 EIS-0374: Record of Decision Klondike III Biglow Canyon Wind Integration Project September 21, 2005 EIS-0355: Record of Decision Remediation...

  3. Record of Decision (ROD) | Department of Energy

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

    19, 2012 EIS-0425: Record of Decision and Mitigation Action Plan Bonneville Power Administration Record of Decision and Mitigation Action Plan for the Mid-Columbia Restoration...

  4. Record of Decision (ROD) | Department of Energy

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

    December 15, 1999 EIS-0281: Record of Decision Sandia National LaboratoriesNew Mexico Site-Wide Environmental Impact Statement November 12, 1999 EIS-0222: Record of Decision...

  5. Record of Decision (ROD) | Department of Energy

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

    the Shepherds Flat Wind Energy Project June 10, 2008 EIS-0378: Record of Decision Port Angeles-Juan de Fuca Transmssion Proj June 4, 2008 EIS-0183: Record of Decision Electrical...

  6. Record of Decision (ROD) | Department of Energy

    Energy Savers [EERE]

    August 5, 2016 EIS-0491: Record of Decision (Lake Charles LNG Export Company, LLC) Lake ... DOE announced its decision in Lake Charles Exports, LLC (LCE), DOEFE Docket No. 11-59-LNG...

  7. Record of Decision (ROD) | Department of Energy

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

    EIS-0218: Revision to the Record of Decision Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel July 1, 2000 EIS-0285:...

  8. Record of Decision (ROD) | Department of Energy

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

    Amendment to Record of Decision Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs March 7,...

  9. Record of Decision (ROD) | Department of Energy

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

    April 8, 1988 EIS-0113: Record of Decision Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Site, Richland, Washington May 14, 1981 EIS-0046: Record of...

  10. Record of Decision (ROD) | Department of Energy

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

    Management December 13, 1996 EIS-0243: Record of Decision (December 1996) Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada...

  11. Record of Decision (ROD) | Department of Energy

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

    Revised by State September 25, 2009 EIS-0399: Record of Decision (WAPA) Montana Alberta Tie Ltd. 230-kV Transmission Line Project September 15, 2009 EIS-0312: Record of...

  12. Plutonium Consolidation Amended ROD

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

    Amended Record of Decision: Storage of Surplus Plutonium Materials at the Savannah River Site AGENCY: Department of Energy ACTION: Amended Record of Decision SUMMARY: The U.S. Department of Energy (DOE) is amending the Record of Decision (ROD) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement (DOE/EIS-0229, 1996; Storage and Disposition PEIS). Specifically, DOE has decided to take the actions necessary to transfer approximately 2,511

  13. Record of Decision for the Electrical Interconnection of the Windy Point Wind Energy Project.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration.

    2006-11-01

    The Bonneville Power Administration (BPA) has decided to offer contract terms for interconnection of 250 megawatts (MW) of power to be generated by the proposed Windy Point Wind Energy Project (Wind Project) into the Federal Columbia River Transmission System (FCRTS). Windy Point Partners, LLC (WPP) propose to construct and operate the proposed Wind Project and has requested interconnection to the FCRTS. The Wind Project will be interconnected at BPA's Rock Creek Substation, which is under construction in Klickitat County, Washington. The Rock Creek Substation will provide transmission access for the Wind Project to BPA's Wautoma-John Day No.1 500-kilovolt (kV) transmission line. BPA's decision to offer terms to interconnect the Wind Project is consistent with BPA's Business Plan Final Environmental Impact Statement (BP EIS) (DOE/EIS-0183, June 1995), and the Business Plan Record of Decision (BP ROD, August 15, 1995). This decision thus is tiered to the BP ROD.

  14. EIS-0409-ROD.pdf

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

    222-SA-02: Supplement Analysis EIS-0222-SA-02: Supplement Analysis Hanford Comprehensive Land-Use Plan Environmental Impact Statement DOE's Supplement Analysis evaluates present and proposed or reasonably foreseeable future programs, operations, and activities in the context of the Hanford Comprehensive Land-use Plan Environmental Impact Statement (HCP-EIS) (DOE/EIS-0222, 1999) and Record of Decision (ROD), and the 2008 HCP-EIS SA (DOE/EIS-0222-SA-01) and amended ROD (73 FR 55824, September 26,

  15. CONTROL ROD

    DOE Patents [OSTI]

    Walker, D.E.; Matras, S.

    1963-04-30

    This patent shows a method of making a fuel or control rod for a nuclear reactor. Fuel or control material is placed within a tube and plugs of porous metal wool are inserted at both ends. The metal wool is then compacted and the tube compressed around it as by swaging, thereby making the plugs liquid- impervious but gas-pervious. (AEC)

  16. BP-12 Final Proposal

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

    Rate Case Elements Step by Step Inactive Rate Cases BP-16 Rate Case BP-14 Rate Case BP-12 Rate Case REP-12 Proceeding Rate Information Residential Exchange Program Surplus Power...

  17. CONTROL ROD

    DOE Patents [OSTI]

    Zinn, W.H.; Ross, H.V.

    1958-11-18

    A control rod is described for a nuclear reactor. In certaln reactor designs it becomes desirable to use a control rod having great width but relatively llttle thickness. This patent is addressed to such a need. The neutron absorbing material is inserted in a triangular tube, leaving volds between the circular insert and the corners of the triangular tube. The material is positioned within the tube by the use of dummy spacers to achleve the desired absorption pattern, then the ends of the tubes are sealed with suitable plugs. The tubes may be welded or soldered together to form two flat surfaces of any desired width, and covered with sheetmetal to protect the tubes from damage. This design provides a control member that will not distort under the action of outside forces or be ruptured by gases generated within the jacketed control member.

  18. Draft Advice: ERDF ROD Amendment

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

    Advice: ERDF ROD Amendment 8/5/14 Author: Pam Larsen BACKGROUND The Department of Energy (DOE) is seeking to move forward with CERCLA cleanup at Hanford in a manner that addresses the RCRA Land Disposal Restrictions (LDRs) for a limited amount of large, heavy hazardous waste debris that is contaminated with radioactive material. The current plan contained in a Record of Decision (ROD) is to dispose of this material in the on-site EDRF landfill. DOE is seeking a CERCLA ARAR waiver to treat this

  19. EIS-0247: Record of Decision | Department of Energy

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

    Record of Decision EIS-0247: Record of Decision Construction and Operation of the Spallation Neutron Source The Department of Energy (DOE) is issuing this Record of Decision (ROD)...

  20. FUEL ROD ASSEMBLY

    DOE Patents [OSTI]

    Hutter, E.

    1959-09-01

    A cluster of nuclear fuel rods aod a tubular casing through which a coolant flows in heat-change contact with the ruel rods are described. The casting is of trefoil section and carries the fuel rods, each of which has two fin engaging the serrated fins of the other two fuel rods, whereby the fuel rods are held in the casing and are interlocked against relative longitudinal movement.

  1. BP-18 Rate Proceeding

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

    Skip navigation links Financial Information Financial Public Processes Asset Management Cost Verification Process Rate Cases BP-18 Rate Case Related Publications Meetings...

  2. BP-12 Rate Case

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

    Skip navigation links Financial Information Financial Public Processes Asset Management Cost Verification Process Rate Cases BP-18 Rate Case Related Publications Meetings...

  3. BP-16 Rate Case

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

    Skip navigation links Financial Information Financial Public Processes Asset Management Cost Verification Process Rate Cases BP-18 Rate Case Related Publications Meetings...

  4. Control rod drive

    DOE Patents [OSTI]

    Hawke, Basil C.

    1986-01-01

    A control rod drive uses gravitational forces to insert one or more control rods upwardly into a reactor core from beneath the reactor core under emergency conditions. The preferred control rod drive includes a vertically movable weight and a mechanism operatively associating the weight with the control rod so that downward movement of the weight is translated into upward movement of the control rod. The preferred control rod drive further includes an electric motor for driving the control rods under normal conditions, an electrically actuated clutch which automatically disengages the motor during a power failure and a decelerator for bringing the control rod to a controlled stop when it is inserted under emergency conditions into a reactor core.

  5. Piston rod seal

    DOE Patents [OSTI]

    Lindskoug, Stefan

    1984-01-01

    In a piston rod seal of the type comprising a gland through which the piston rod is passed the piston is provided with a sleeve surrounding the piston rod and extending axially so as to axially partly overlap the gland when the piston is in its bottom dead center position.

  6. CONTROL ROD DRIVE

    DOE Patents [OSTI]

    Chapellier, R.A.; Rogers, I.

    1961-06-27

    Accurate and controlled drive for the control rod is from an electric motor. A hydraulic arrangement is provided to balance a piston against which a control rod is urged by the application of fluid pressure. The electric motor drive of the control rod for normal operation is made through the aforementioned piston. In the event scramming is required, the fluid pressure urging the control rod against the piston is relieved and an opposite fluid pressure is applied. The lack of mechanical connection between the electric motor and control rod facilitates the scramming operation.

  7. CRUCIFORM CONTROL ROD JOINT

    DOE Patents [OSTI]

    Thorp, A.G. II

    1962-08-01

    An invention is described which relates to nuclear reactor control rod components and more particularly to a joint between cruciform control rod members and cruciform control rod follower members. In one embodiment this invention provides interfitting crossed arms at adjacent ends of a control rod and its follower in abutting relation. This holds the members against relative opposite longitudinal movement while a compression member keys the arms against relative opposite rotation around a common axis. Means are also provided for centering the control rod and its follower on a common axis and for selectively releasing the control rod from its follower for the insertion of a replacement of the control rod and reuse of the follower. (AEC)

  8. Revised Record of Decision for the Electrical Interconnection of the Summit/Westward Project

    SciTech Connect (OSTI)

    N /A

    2004-10-21

    The Bonneville Power Administration (BPA) has decided to amend its July 25, 2003, Record of Decision (ROD) regarding the proposed Summit/Westward Project (Project) to offer contract terms for an optional interconnection of this Project into the Federal Columbia River Transmission System (FCRTS). Under this optional interconnection plan, BPA would integrate electric power from the Project into the FCRTS at a point adjacent to Clatskanie People's Utility District (CPUD) existing Wauna Substation. In order to deliver power to this location, CPUD would develop a new substation (Bradbury Substation) at a site near the Project and a new 230-kV transmission line from there to CPUD's Wauna Substation, which is already connected to the FCRTS. As part of this revised decision, BPA will facilitate CPUD development of the Bradbury-Wauna transmission line by allowing joint use of BPA right-of-way. This will involve reconstructing a section of BPA's 115-kV Allston-Astoria No. 1 transmission line from single-circuit H-frame wood-pole design to double-circuit single metal pole design. Terms of BPA participation in CPUD's development of the Bradbury-Wauna transmission line will be documented in a Construction Agreement. This optional interconnection plan is in addition to BPA's previous offer for interconnection of the Project at BPA's Allston Substation, as documented in the July 25, 2003, ROD. As with the initial interconnection plan, the decision to offer terms to interconnect the Project through the optional interconnection plan is consistent with BPA's Business Plan Final Environmental Impact Statement (BP EIS) (DOE/EIS-0183, June 1995), and the Business Plan Record of Decision (BP ROD, August 1995). This decision thus is similarly tiered to the Business Plan ROD.

  9. Pilot-scale treatability test plan for the 200-BP-5 operable unit

    SciTech Connect (OSTI)

    Not Available

    1994-08-01

    This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-BP-5 Operable Unit. This treatability test plan has been prepared in response to an agreement between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology), as documented in Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994) and a recent 200 NPL Agreement Change Control Form (Appendix A). The agreement also requires that, following completion of the activities described in this test plan, a 200-BP-5 Operable Unit Interim Remedial Measure (IRM) Proposed Plan be developed for use in preparing an Interim Action Record of Decision (ROD). The IRM Proposed Plan will be supported by the results of this treatability test plan, as well as by other 200-BP-5 Operable Unit activities (e.g., development of a qualitative risk assessment). Once issued, the Interim Action ROD will specify the interim action(s) for groundwater contamination at the 200-BP-5 Operable Unit. The treatability test approach is to conduct a pilot-scale pump and treat test for each of the two contaminant plumes associated with the 200-BP-5 Operable Unit. Primary contaminants of concern are {sup 99}Tc and {sup 60}Co for underwater affected by past discharges to the 216-BY Cribs, and {sup 90}Sr, {sup 239/240}Pu, and Cs for groundwater affected by past discharges to the 216-B-5 Reverse Well. The purpose of the pilot-scale treatability testing presented in this testplan is to provide the data basis for preparing an IRM Proposed Plan. To achieve this objective, treatability testing must: Assess the performance of groundwater pumping with respect to the ability to extract a significant amount of the primary contaminant mass present in the two contaminant plumes.

  10. BP Solar | Open Energy Information

    Open Energy Info (EERE)

    Maryland Zip: 21703 Sector: Solar Product: Maryland-based subsidiary of BP Alternative Energy dealing with solar power. Website: www.bp.comgenericcountryjump. Coordinates:...

  11. Pull rod assembly

    DOE Patents [OSTI]

    Cioletti, O.C.

    1988-04-21

    A pull rod assembly comprising a pull rod having three peripheral grooves, a piston device including an adaptor ring and a seal ring, said piston device being mounted on the pull rod by a split ring retainer situated in one groove and extending into an interior groove in the adaptor and a resilient split ring retained in another groove and positioned to engage the piston device and to retain the seal on its adaptor.

  12. Pull rod assembly

    DOE Patents [OSTI]

    Cioletti, Olisse C. (Pittsburgh, PA)

    1990-01-01

    A pull rod assembly comprising a pull rod having three peripheral grooves, a piston device including an adaptor ring and a seal ring, said piston device being mounted on the pull rod by a split ring retainer situated in one groove and extending into an interior groove in the adaptor and a resilient split ring retained in another groove and positioned to engage the piston device and to retain the seal on its adaptor.

  13. CONTROL ROD DRIVE

    DOE Patents [OSTI]

    Chapellier, R.A.

    1960-05-24

    BS>A drive mechanism was invented for the control rod of a nuclear reactor. Power is provided by an electric motor and an outside source of fluid pressure is utilized in conjunction with the fluid pressure within the reactor to balance the loadings on the motor. The force exerted on the drive mechanism in the direction of scramming the rod is derived from the reactor fluid pressure so that failure of the outside pressure source will cause prompt scramming of the rod.

  14. Status of rod consolidation

    SciTech Connect (OSTI)

    Bailey, W.J.

    1985-04-01

    Two of the factors that need to be taken into account with rod consolidation are (1) the effects on rods from their removal from the fuel assembly and (2) the effects on rods as a result of the consolidation process. Potential components of both factors are described in the report. Discussed under (1) are scratches on the fuel rod surfaces, rod breakage, crud, extended burnup, and possible cladding embrittlement due to hydrogen injection at BWRs. Discussed under (2) are the increased water temperature (less than 10/sup 0/C) because of closer packing of the rods, formation of crevices between rods in the close-packed mode, contact with dissimilar metals, and the potential for rapid heating of fuel rods following the loss of water from a spent fuel storage pool. Another factor that plays an important role in rod consolidation is the cost of disposal of the nonfuel-bearing components of the fuel assembly. Also, the dose rate from the components - especially Inconel spacer grids - can affect the handling procedures. Several licensing issues that exist are described. A list of recommendations is provided. 98 refs., 5 figs., 5 tabs.

  15. Hydraulic control rod

    DOE Patents [OSTI]

    Treshow, Michael

    1976-01-01

    Apparatus for shifting a control rod into and out of a nuclear reactor utilizing as pressure fluid the fluid employed as coolant moderator in the reactor.

  16. EIS-0349: DOE Notice of Availability of the Record of Decision...

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

    Cogeneration Project, Washington and Oregon This notice announces the availability of the ROD to implement the proposed action identified in the BP Cherry Point Cogeneration ...

  17. State Concurrence with Record of Decision (ROD).

    Office of Legacy Management (LM)

  18. FUEL ROD CLUSTERS

    DOE Patents [OSTI]

    Schultz, A.B.

    1959-08-01

    A cluster of nuclear fuel rods and a tubular casing therefor through which a coolant flows in heat-exchange contact with the fuel rods is described. The fuel rcds are held in the casing by virtue of the compressive force exerted between longitudinal ribs of the fuel rcds and internal ribs of the casing or the internal surfaces thereof.

  19. BP Wind | Open Energy Information

    Open Energy Info (EERE)

    Wind Place: Houston, Texas Zip: 77002-2700 Sector: Wind energy Product: Department of BP Alternative Energy that deals with BP's interest in wind power. Coordinates: 29.76045,...

  20. BP America | Open Energy Information

    Open Energy Info (EERE)

    BP America Place: Warrenville, Illinois Zip: 60555-3938 Product: US operations of BP Plc. Coordinates: 33.547976, -81.811933 Show Map Loading map... "minzoom":false,"mappi...

  1. Control rod driveline and grapple

    DOE Patents [OSTI]

    Germer, John H.

    1987-01-01

    A control rod driveline and grapple is disclosed for placement between a control rod drive and a nuclear reactor control rod containing poison for parasitic neutron absorption required for reactor shutdown. The control rod is provided with an enlarged cylindrical handle which terminates in an upwardly extending rod to provide a grapple point for the driveline. The grapple mechanism includes a tension rod which receives the upwardly extending handle and is provided with a lower annular flange. A plurality of preferably six grapple segments surround and grip the control rod handle. Each grapple rod segment grips the flange on the tension rod at an interior upper annular indentation, bears against the enlarged cylindrical handle at an intermediate annulus and captures the upwardly flaring frustum shaped handle at a lower and complementary female segment. The tension rods and grapple segments are surrounded by and encased within a cylinder. The cylinder terminates immediately and outward extending annulus at the lower portion of the grapple segments. Excursion of the tension rod relative to the encasing cylinder causes rod release at the handle by permitting the grapple segments to pivot outwardly and about the annulus on the tension rod so as to open the lower defined frustum shaped annulus and drop the rod. Relative movement between the tension rod and cylinder can occur either due to electromagnetic release of the tension rod within defined limits of travel or differential thermal expansion as between the tension rod and cylinder as where the reactor exceeds design thermal limits.

  2. EIS-0349: Record of Decision | Department of Energy

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

    49: Record of Decision EIS-0349: Record of Decision Electrical Interconnection of the BP Cherry Point Cogeneration Project The Bonneville Power Administration (Bonneville) has...

  3. Fuel rod support grid

    DOE Patents [OSTI]

    Downs, Robert E.; Schwallie, Ambrose L.

    1985-01-01

    A grid for the support of nuclear fuel rods arranged in a triangular array. The grid is formed by concentric rings of strap joined by radially arranged web sections.

  4. Hanford 300 Area ROD

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

    300 Area ROD Briefing to the Hanford Advisory Board March 6, 2014 Larry Gadbois -- EPA Recap of the 300 Area ROD Primary new concept -- Uranium Sequestration: * Purpose: Accelerate restoration of groundwater uranium contamination. * Protect groundwater from downward leaching from the vadose zone (overlying soil). * Add phosphate to chemically bond with uranium into geologically stable autunite. Does not dissolve. * Dissolve phosphate in water, apply at ground surface, inject into the ground,

  5. Apex BP Solar | Open Energy Information

    Open Energy Info (EERE)

    Solar Jump to: navigation, search Name: Apex BP Solar Place: St Mathieu de Treviers, France Zip: 34270 Sector: Solar Product: Regional subsidiary of BP Solar. References: Apex BP...

  6. BP Clipper Wind JV | Open Energy Information

    Open Energy Info (EERE)

    JV Jump to: navigation, search Name: BP Clipper Wind JV Place: United Kingdom Product: joint venture formed between Clipper and BP Alternative Energy References: BP Clipper Wind...

  7. Record of Decision for Mars 2020 Mission

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

    ... Record of Decision for Mars 2020 Mission Mars 2020 Rover instrument selection. Mars 2020 Rover instrument selection. NASA issued a record of decision (ROD) to use a nuclear battery ...

  8. EIS-0183: Record of Decision | Department of Energy

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

    I therefore have determined that it is appropriate to tier this SN CRAC Record of Decision (ROD) to the August 15, 1995, Business Plan ROD for the Business Plan Final...

  9. Microsoft Word - S05069_ROD.doc

    Office of Legacy Management (LM)

    Record of Decision for DOE Areas at the Laboratory for Energy-Related Health Research University of California, Davis September 2009 LMS/LEH/S05069 This page intentionally left blank LMS/LEH/S05069 Record of Decision for DOE Areas at the Laboratory for Energy-Related Health Research University of California, Davis September 2009 This page intentionally left blank U.S. Department of Energy ROD for DOE Areas for LEHR September 2009 Doc. No. S05069, Rev. 0 Page i Contents Acronyms and Abbreviations

  10. EIS-0217: Supplemental Record of Decision | Department of Energy

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

    Management EIS-0217-ROD-1997.pdf (19.24 KB) More Documents & Publications EIS-0217: Supplemental Record of Decision EIS-0217: Record of Decision EIS-0217: Amended Record of Decision

  11. EIS-0200: Amendment to the Record of Decision | Department of...

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

    Amendment to the Record of Decision EIS-0200: Amendment to the Record of Decision Treatment and Storage of Transuranic Waste Under this amendment to its Record of Decision (ROD),...

  12. REACTOR CONTROL ROD OPERATING SYSTEM

    DOE Patents [OSTI]

    Miller, G.

    1961-12-12

    A nuclear reactor control rod mechanism is designed which mechanically moves the control rods into and out of the core under normal conditions but rapidly forces the control rods into the core by catapultic action in the event of an emergency. (AEC)

  13. SAFETY SYSTEM FOR CONTROL ROD

    DOE Patents [OSTI]

    Paget, J.A.

    1963-05-14

    A structure for monitoring the structural continuity of a control rod foi a neutron reactor is presented. A electric conductor readily breakable under mechanical stress is fastened along the length of the control rod at a plurality of positions and forms a closed circuit with remote electrical components responsive to an open circuit. A portion of the conductor between the control rod and said components is helically wound to allow free and normally unrestricted movement of the segment of conductor secured to the control rod relative to the remote components. Any break in the circuit is indicative of control rod breakage. (AEC)

  14. Locked-wrap fuel rod

    DOE Patents [OSTI]

    Kaplan, Samuel; Chertock, Alan J.; Punches, James R.

    1977-01-01

    A method for spacing fast reactor fuel rods using a wire wrapper improved by orienting the wire-wrapped fuel rods in a unique manner which introduces desirable performance characteristics not attainable by previous wire-wrapped designs. Use of this method in a liquid metal fast breeder reactor results in: (a) improved mechanical performance, (b) improved rod-to-rod contact, (c) reduced steel volume, and (d) improved thermal-hydraulic performance. The method produces a "locked wrap" design which tends to lock the rods together at each of the wire cluster locations.

  15. Contact: Rod Hunt

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

    Contact: Rod Hunt (208) 386-5254 Washington Group International Receives Contract Extension To Manage Transuranic Nuclear Waste for U.S. Department of Energy Five-Year Option Includes Aggressive New Performance Goals BOISE, Idaho - Washington Group International, Inc. (NASDAQ: WGII) today announced that its Washington TRU Solutions subsidiary has received a five-year contract extension to manage and operate the United States Department of Energy's Waste Isolation Pilot Plant (WIPP) in Carlsbad,

  16. EIS-0183: Record of Decision | Department of Energy

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

    in 2002, is described more fully in a separately issued Administrator's Record of Decision (ROD) that addresses the legal and policy rationale supporting the administrative...

  17. EIS-0183: Revised Record of Decision | Department of Energy

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

    Power Administration (BPA) has decided to amend its July 25, 2003, Record of Decision (ROD) regarding the proposed SummitWestward Project (Project) to offer contract...

  18. EIS-0451: Notice of Availability of Record of Decision | Department...

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

    Hooper Springs Transmission Project, Caribou County, Idaho DOE's Bonneville Power Administration issued a notice of availability of its Record of Decision (ROD) for the Hooper...

  19. EIS-0200: Revision to the Record of Decision | Department of...

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

    (DOE) is revising the Record of Decision (ROD) for its Waste Management Program: Treatment and Storage of Transuranic Waste prepared pursuant to the Waste Management...

  20. EIS-0228: Record of Decision | Department of Energy

    Office of Environmental Management (EM)

    Hydrodynamic Test Facility The Department of Energy (DOE) is issuing this Record of Decision (ROD) regarding the DOE's proposed Dual Axis Radiographic Hydrodynamic Test (DARHT) ...

  1. EIS-0236-S1: Record of Decision | Department of Energy

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

    is issuing this Record of Decision (ROD) for the National Ignition Facility (NIF), a key component of DOE's science-based stewardship of the nation's nuclear weapons stockpile. ...

  2. BP Plc | Open Energy Information

    Open Energy Info (EERE)

    navigation, search Name: BP Plc Place: London, United Kingdom Zip: SW1Y 4PD Sector: Biofuels, Solar, Wind energy Product: London-based producer and distributor of oil and gas...

  3. BP Alternative Energy | Open Energy Information

    Open Energy Info (EERE)

    BP Alternative Energy Jump to: navigation, search Name: BP Alternative Energy Place: London, United Kingdom Zip: SW1Y 4PD Product: London-based holding company for BP's activities...

  4. Fiber optic laser rod

    DOE Patents [OSTI]

    Erickson, G.F.

    1988-04-13

    A laser rod is formed from a plurality of optical fibers, each forming an individual laser. Synchronization of the individual fiber lasers is obtained by evanescent wave coupling between adjacent optical fiber cores. The fiber cores are dye-doped and spaced at a distance appropriate for evanescent wave coupling at the wavelength of the selected dye. An interstitial material having an index of refraction lower than that of the fiber core provides the optical isolation for effective lasing action while maintaining the cores at the appropriate coupling distance. 2 figs.

  5. BP Biofuels Brasil | Open Energy Information

    Open Energy Info (EERE)

    Biofuels Brasil Jump to: navigation, search Name: BP Biofuels Brasil Place: Campinas, Sao Paulo, Brazil Zip: 13025-320 Sector: Biofuels Product: Brazil based BP subsidiary focused...

  6. Reactor control rod timing system

    DOE Patents [OSTI]

    Wu, Peter T. K.

    1982-01-01

    A fluid driven jet-edge whistle timing system for control rods of a nuclear reactor for producing real-time detection of the timing of each control rod in its scram operation. An important parameter in reactor safety, particularly for liquid metal fast breeder reactors (LMFBR), is the time deviation between the time the control rod is released and the time the rod actually reaches the down position. The whistle has a nearly pure tone signal with center frequency (above 100 kHz) far above the frequency band in which the energy of the background noise is concentrated. Each control rod can be fitted with a whistle with a different frequency so that there is no ambiguity in differentiating the signal from each control rod.

  7. Reactor control rod timing system

    SciTech Connect (OSTI)

    Wu, P.T.

    1982-02-09

    A fluid driven jet-edge whistle timing system for control rods of a nuclear reactor for producing real-time detection of the timing of each control rod in its scram operation. An important parameter in reactor safety, particularly for liquid metal fast breeder reactors (LMFBR), is the time deviation between the time the control rod is released and the time the rod actually reaches the down position. The whistle has a nearly pure tone signal with center frequency (Above 100 kHz) far above the frequency band in which the energy of the background noise is concentrated. Each control rod can be fitted with a whistle with a different frequency so that there is no ambiguity in differentiating the signal from each control rod.

  8. Automatic safety rod for reactors

    DOE Patents [OSTI]

    Germer, John H.

    1988-01-01

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-core flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

  9. HAB response letter to the 100-F ROD

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

    response letter to the 100-F ROD The Board has received and is disappointed by the response from the Tri-Party Agencies provided to HAB Advice 280 on the 100-F RI/FS, and Proposed Plan. The response comments the Tri-Party Agencies provided show that none of the advice provided by the Board was accepted in the formulation of the record of decision (ROD) and remedial approach. The Board takes this opportunity to advise the Tri-Parties on a policy level about the Board's view on remediation

  10. BP-12 Final Models Datasets

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

    MB, XLS) Tier 2 Module of RAM RAM Tier 2 Pricing Module (4.8 MB, XLS) Tool Kit Files (TPP) ToolKit v4.8.1 BP-12 Final Studies Release 4-Aug-11 (12.5 MB, XLS) Risk Mod Output...

  11. Administrator's Final Record of Decision, BP-14 Power and Transmission...

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

    understanding of specific topics, generate ideas, and bring forward alternative proposals. The workshops placed significant emphasis on transmission and ancillary and control...

  12. NEUTRONIC REACTOR CONTROL ROD DRIVE APPARATUS

    DOE Patents [OSTI]

    Oakes, L.C.; Walker, C.S.

    1959-12-15

    ABS>A suspension mechanism between a vertically movable nuclear reactor control rod and a rod extension, which also provides information for the operator or an automatic control signal, is described. A spring connects the rod extension to a drive shift. The extension of the spring indicates whether (1) the rod is at rest on the reactor, (2) the rod and extension are suspended, or (3) the extension alone is suspended, the spring controlling a 3-position electrical switch.

  13. Stuck fuel rod capping sleeve

    DOE Patents [OSTI]

    Gorscak, Donald A.; Maringo, John J.; Nilsen, Roy J.

    1988-01-01

    A stuck fuel rod capping sleeve to be used during derodding of spent fuel assemblies if a fuel rod becomes stuck in a partially withdrawn position and, thus, has to be severed. The capping sleeve has an inner sleeve made of a lower work hardening highly ductile material (e.g., Inconel 600) and an outer sleeve made of a moderately ductile material (e.g., 304 stainless steel). The inner sleeve may be made of an epoxy filler. The capping sleeve is placed on a fuel rod which is then severed by using a bolt cutter device. Upon cutting, the capping sleeve deforms in such a manner as to prevent the gross release of radioactive fuel material

  14. Advanced gray rod control assembly

    DOE Patents [OSTI]

    Drudy, Keith J; Carlson, William R; Conner, Michael E; Goldenfield, Mark; Hone, Michael J; Long, Jr., Carroll J; Parkinson, Jerod; Pomirleanu, Radu O

    2013-09-17

    An advanced gray rod control assembly (GRCA) for a nuclear reactor. The GRCA provides controlled insertion of gray rod assemblies into the reactor, thereby controlling the rate of power produced by the reactor and providing reactivity control at full power. Each gray rod assembly includes an elongated tubular member, a primary neutron-absorber disposed within the tubular member said neutron-absorber comprising an absorber material, preferably tungsten, having a 2200 m/s neutron absorption microscopic capture cross-section of from 10 to 30 barns. An internal support tube can be positioned between the primary absorber and the tubular member as a secondary absorber to enhance neutron absorption, absorber depletion, assembly weight, and assembly heat transfer characteristics.

  15. Melt behavior of aluminum clad rods

    SciTech Connect (OSTI)

    Geiger, G.T.; Long, T.A.; DeWald, A.B. Jr.

    1994-08-01

    Since the Li-Al alloy cores in control rods used to control production reactors are susceptible to corrosion by heavy water, they were clad with Al. This paper reports results of an experimental and numerical study of the behavior of control rods heated to the point of clad and rod-core failure. Results show that the core of the rod melts first; the clad fails only after significant additional heating. Once the rod breaks and drops to the bottom of the quartz tube in the furnace, the lower section of the rod fails by ``poker-chipping`` downward as the topmost portion fails before the portion below it. Part of the core in the remaining top of the rod relocates immediately after rod separation, leaving a hollow tube of Al which also melts upon further heating.

  16. Control rods in LMFBRs: a physics assessment

    SciTech Connect (OSTI)

    McFarlane, H.F.; Collins, P.J.

    1982-08-01

    This physics assessment is based on roughly 300 control rod worth measurements in ZPPR from 1972 to 1981. All ZPPR assemblies simulated mixed-oxide LMFBRs, representing sizes of 350, 700, and 900 MWe. Control rod worth measurements included single rods, various combinations of rods, and Ta and Eu rods. Additional measurements studied variations in B/sub 4/C enrichment, rod interaction effects, variations in rod geometry, neutron streaming in sodium-filled channels, and axial worth profiles. Analyses were done with design-equivalent methods, using ENDF/B Version IV data. Some computations for the sensitivities to approximations in the methods have been included. Comparisons of these analyses with the experiments have allowed the status of control rod physics in the US to be clearly defined.

  17. BP Oil Spill Update | Department of Energy

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

    BP Oil Spill Update BP Oil Spill Update August 10, 2010 - 10:48am Addthis Sec. Chu working on solutions to the BP Oil spill with a member of the Federal Science Team. | Energy Department Photo | Sec. Chu working on solutions to the BP Oil spill with a member of the Federal Science Team. | Energy Department Photo | Secretary Chu Secretary Chu Former Secretary of Energy "We also must remain focused on helping the people, businesses and communities in the Gulf Coast region who have been

  18. BP and Hydrogen Pipelines | Department of Energy

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

    BP Environmental Commitment: Green corporate philosophy and senior management commitment hpwgwbpyoho.pdf (207.38 KB) More Documents & Publications Proceedings of the 2005 ...

  19. Tata BP Solar India | Open Energy Information

    Open Energy Info (EERE)

    search Name: Tata BP Solar India Place: Bangalore, Karnataka, India Zip: 561 229 Sector: Solar Product: Manufacturer of PV cells and modules, and solar passive products....

  20. Solid-state-laser-rod holder

    DOE Patents [OSTI]

    Gettemy, D.J.; Barnes, N.P.; Griggs, J.E.

    1981-08-11

    The disclosure relates to a solid state laser rod holder comprising Invar, copper tubing, and epoxy joints. Materials and coefficients of expansion of the components of the holder combine with the rod to produce a joint which will give before the rod itself will. The rod may be lased at about 70 to 80/sup 0/K and returned from such a temperature to room temperature repeatedly without its or the holder's destruction.

  1. Inverted Control Rod Lock-In Device

    DOE Patents [OSTI]

    Brussalis, W. G.; Bost, G. E.

    1962-12-01

    A mechanism which prevents control rods from dropping out of the reactor core in the event the vessel in which the reactor is mounted should capsize is described. The mechanism includes a pivoted toothed armature which engages the threaded control rod lead screw and prevents removal of the rod whenever the armature is not attracted by the provided electromagnetic means. (AEC)

  2. Letter: Quarry Residuals Operable Unit (QROU), Record of Decision (ROD).

    Office of Legacy Management (LM)

  3. Record of Decision - ROD - Long-Term Regional Dialogue - July...

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

    and Conservation Council CSE Customer Service Engineers CY Calendar Year DOE Richland United States Department of Energy, Hanford, Washington site DSIs Direct-Service...

  4. Administrator's Record of Decision (ROD) on New Large Single...

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

    continued PF firm power service from a new serving utility upon the following set of conditions: First, the transfer is to a public utility. Second, the load does not change...

  5. ELECTROMAGNETIC APPARATUS FOR MOVING A ROD

    DOE Patents [OSTI]

    Young, J.N.

    1958-04-22

    An electromagnetic apparatus for moving a rod-like member in small steps in either direction is described. The invention has particular application in the reactor field where the reactor control rods must be moved only a small distance and where the use of mechanical couplings is impractical due to the high- pressure seals required. A neutron-absorbing rod is mounted in a housing with gripping uaits that engage the rod, and coils for magnetizing the gripping units to make them grip, shift, and release the rod are located outside the housing.

  6. Portsmouth Decontamination and Decommissioning Record of Decision |

    Energy Savers [EERE]

    Department of Energy Decontamination and Decommissioning Record of Decision Portsmouth Decontamination and Decommissioning Record of Decision The Ohio Environmental Protection Agency (Ohio EPA) and the U.S. Department of Energy (DOE) have agreed upon a plan to demolish the large process buildings and other facilities undergoing decontamination and decommissioning (D&D) at the Portsmouth Gaseous Diffusion Plant. The Record of Decision (ROD) for the Process Buildings and Complex Facilities

  7. EIS-0283: Amended Record of Decision | Department of Energy

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

    83: Amended Record of Decision EIS-0283: Amended Record of Decision Surplus Plutonium Disposition Program EIS-0283-AmROD-2003a.pdf (50.43 KB) More Documents & Publications EIS-0229: Supplement Analysis (September 2007) EIS-0229: Amended Record of Decision EIS-0283-S2: Notice of Intent to Prepare a Supplemental Environmental Impact

  8. Fuel rod assembly to manifold attachment

    DOE Patents [OSTI]

    Donck, Harry A.; Veca, Anthony R.; Snyder, Jr., Harold J.

    1980-01-01

    A fuel element is formed with a plurality of fuel rod assemblies detachably connected to an overhead support with each of the fuel rod assemblies having a gas tight seal with the support to allow internal fission gaseous products to flow without leakage from the fuel rod assemblies into a vent manifold passageway system on the support. The upper ends of the fuel rod assemblies are located at vertically extending openings in the support and upper threaded members are threaded to the fuel rod assemblies to connect the latter to the support. The preferred threaded members are cap nuts having a dome wall encircling an upper threaded end on the fuel rod assembly and having an upper sealing surface for sealing contact with the support. Another and lower seal is achieved by abutting a sealing surface on each fuel rod assembly with the support. A deformable portion on the cap nut locks the latter against inadvertent turning off the fuel rod assembly. Orienting means on the fuel rod and support primarily locates the fuel rods azimuthally for reception of a deforming tool for the cap nut. A cross port in the fuel rod end plug discharges into a sealed annulus within the support, which serves as a circumferential chamber, connecting the manifold gas passageways in the support.

  9. LOFT lead rod test results evaluation. [PWR

    SciTech Connect (OSTI)

    Driskell, W.B.; Tolman, E.L.

    1980-07-30

    The purpose for evaluating the LOFT Lead Rod Test (simulations of large break, loss-of-coolant accidents) data was to determine; (a) if the centerline thermocouple and fuel rod elongation sensor data show indications of the collapsed fuel rod cladding, (b) the capability of the FRAP-T5 computer code to accurately predict cladding collapse, and (c) if cladding surface thermocouples enhance fuel rod cooling. With consideration to unresolved questions on data integrity, it was concluded that: the fuel rod centerline thermocouple and elongation sensor data do show indications of the fuel rod cladding collapse; the FRAP-T5 code conservatively predicts cladding collapse; and there is an indication that cladding surface thermocouples are enhancing fuel rod cooling.

  10. DOE Issues Record of Decision for the Uranium Leasing Program

    Broader source: Energy.gov [DOE]

    In a Record of Decision (ROD) published in the Federal Register today, the Department of Energy (DOE) announced that it has decided to continue management of the Uranium Leasing Program (ULP) for...

  11. EIS-0226: Revision to the Record of Decision | Department of...

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

    of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase (WIPP ROD), 63 FR 3624 (Jan. 23, 1998). DOE has decided to dispose of up to 2,500 cubic...

  12. EIS-0026: Record of Decision | Department of Energy

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

    PDF icon EIS-0026-ROD-1998.pdf More Documents & Publications EIS-0200: Record of Decision EIS-0026-S2: Final Supplemental Environmental Impact Statement EIS-0026-SA-02: Supplement ...

  13. High temperature control rod assembly

    SciTech Connect (OSTI)

    Vollman, Russell E.

    1991-01-01

    A high temperature nuclear control rod assembly comprises a plurality of substantially cylindrical segments flexibly joined together in succession by ball joints. The segments are made of a high temperature graphite or carbon-carbon composite. The segment includes a hollow cylindrical sleeve which has an opening for receiving neutron-absorbing material in the form of pellets or compacted rings. The sleeve has a threaded sleeve bore and outer threaded surface. A cylindrical support post has a threaded shaft at one end which is threadably engaged with the sleeve bore to rigidly couple the support post to the sleeve. The other end of the post is formed with a ball portion. A hollow cylindrical collar has an inner threaded surface engageable with the outer threaded surface of the sleeve to rigidly couple the collar to the sleeve. the collar also has a socket portion which cooperates with the ball portion to flexibly connect segments together to form a ball and socket-type joint. In another embodiment, the segment comprises a support member which has a threaded shaft portion and a ball surface portion. The threaded shaft portion is engageable with an inner threaded surface of a ring for rigidly coupling the support member to the ring. The ring in turn has an outer surface at one end which is threadably engageably with a hollow cylindrical sleeve. The other end of the sleeve is formed with a socket portion for engagement with a ball portion of the support member. In yet another embodiment, a secondary rod is slidably inserted in a hollow channel through the center of the segment to provide additional strength. A method for controlling a nuclear reactor utilizing the control rod assembly is also included.

  14. Reactor control rod timing system. [LMFBR

    DOE Patents [OSTI]

    Wu, P.T.K.

    1980-03-18

    A fluid driven jet-edge whistle timing system is described for control rods of a nuclear reactor for producing real-time detection of the timing of each control rod in its scram operation. An important parameter in reactor safety, particularly for liquid metal fast breeder reactors (LMFBR), is the time deviation between the time the control rod is released and the time the rod actually reaches the down position. The whistle has a nearly pure tone signal with center frequency (above 100 kHz) far above the frequency band in which the energy of the background noise is concentrated. Each control rod can be fitted with a whistle with a different frequency so that there is no ambiguity in differentiating the signal from each control rod.

  15. Fuel rod retention device for a nuclear reactor

    DOE Patents [OSTI]

    Hylton, Charles L.

    1984-01-01

    A device is described for supporting a nuclear fuel rod in a fuel rod assembly which allows the rod to be removed without disturbing other rods in the assembly. A fuel rod cap connects the rod to a bolt which is supported in the assembly end fitting by means of a locking assembly. The device is designed so that the bolt is held securely during normal reactor operation yet may be easily disengaged and the fuel rod removed when desired.

  16. Automatic safety rod for reactors. [LMFBR

    DOE Patents [OSTI]

    Germer, J.H.

    1982-03-23

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

  17. EA-314-A BP Energy Co | Department of Energy

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

    EA-314-A BP Energy Co Order authorizing BP Energy Co to export electric energy to Mexico. File EA-314-A BP Energy.docx More Documents & Publications EA-379 FreePoint Commodities ...

  18. Temperature actuated automatic safety rod release

    DOE Patents [OSTI]

    Hutter, Ernest; Pardini, John A.; Walker, David E.

    1987-01-01

    A temperature-actuated apparatus is disclosed for releasably supporting a safety rod in a nuclear reactor, comprising a safety rod upper adapter having a retention means, a drive shaft which houses the upper adapter, and a bimetallic means supported within the drive shaft and having at least one ledge which engages a retention means of the safety rod upper adapter. A pre-determined increase in temperature causes the bimetallic means to deform so that the ledge disengages from the retention means, whereby the bimetallic means releases the safety rod into the core of the reactor.

  19. Temperature actuated automatic safety rod release

    DOE Patents [OSTI]

    Hutter, E.; Pardini, J.A.; Walker, D.E.

    1984-03-13

    A temperature-actuated apparatus is disclosed for releasably supporting a safety rod in a nuclear reactor, comprising a safety rod upper adapter having a retention means, a drive shaft which houses the upper adapter, and a bimetallic means supported within the drive shaft and having at least one ledge which engages a retention means of the safety rod upper adapter. A pre-determined increase in temperature causes the bimetallic means to deform so that the ledge disengages from the retention means, whereby the bimetallic means releases the safety rod into the core of the reactor.

  20. US EPA record of decision review for landfills: Sanitary landfill (740-G), Savannah River Site

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    This report presents the results of a review of the US Environmental Protection Agency (EPA) Record of Decision System (RODS) database search conducted to identify Superfund landfill sites where a Record of Decision (ROD) has been prepared by EPA, the States or the US Army Corps of Engineers describing the selected remedy at the site. ROD abstracts from the database were reviewed to identify site information including site type, contaminants of concern, components of the selected remedy, and cleanup goals. Only RODs from landfill sites were evaluated so that the results of the analysis can be used to support the remedy selection process for the Sanitary Landfill at the Savannah River Site (SRS).

  1. Apparatus and method for detecting defective fuel rods

    SciTech Connect (OSTI)

    Jester, A.; Lawrie, W.E.; Womack, R.E.

    1980-03-18

    Defects in the fuel rods of nuclear fuel assemblies are ascertained and located by ultrasonic means. The fuel assemblies are subjected to ultrasonic waves. Differences in fuel rod resonance is indicative of defective rods.

  2. Method speeds tapered rod design for directional well

    SciTech Connect (OSTI)

    Hu Yongquan; Yuan Xiangzhong

    1995-10-16

    Determination of the minimum rod diameter, from statistical relationships, can decrease the time needed for designing a sucker-rod string for a directional well. A tapered rod string design for a directional well is more complex than for a vertical well. Based on the theory of a continuous beam column, the rod string design in a directional well is a trial and error method. The key to reduce the time to obtain a solution is to rapidly determine the minimum rod diameter. This can be done with a statistical relationship. The paper describes sucker rods, design method, basic analysis rod design, and minimum rod diameter.

  3. DEVICE FOR CONTROLLING INSERTION OF ROD

    DOE Patents [OSTI]

    Beaty, B.J.

    1958-10-14

    A device for rapidly inserting a safety rod into a nuclear reactor upon a given signal or in the event of a power failure in order to prevent the possibility of extensive damage caused by a power excursion is described. A piston is slidably mounted within a vertical cylinder with provision for an electromagnetic latch at the top of the cylinder. This assembly, with a safety rod attached to the piston, is mounted over an access port to the core region of the reactor. The piston is normally latched at the top of the cylinder with the safety rod clear of the core area, however, when the latch is released, the piston and rod drop by their own weight to insert the rod. Vents along the side of the cylinder permit the escape of the air entrapped under the piston over the greater part of the distance, however, at the end of the fall the entrapped air is compressed thereby bringing the safety rod gently to rest, thus providing for a rapid automatic insertion of the rod with a minimum of structural shock.

  4. Control Rod Malfunction at the NRAD Reactor

    SciTech Connect (OSTI)

    Thomas L. Maddock

    2010-05-01

    The neutron Radiography Reactor (NRAD) is a training, research, and isotope (TRIGA) reactor located at the INL. The reactor is normally shut down by the insertion of three control rods that drop into the core when power is removed from electromagnets. During a routine shutdown, indicator lights on the console showed that one of the control rods was not inserted. It was initially thought that the indicator lights were in error because of a limit switch that was out of adjustment. Through further testing, it was determined that the control rod did not drop when the scram switch was initially pressed. The control rod anomaly led to a six month shutdown of the reactor and an in depth investigation of the reactor protective system. The investigation looked into: scram switch operation, console modifications, and control rod drive mechanisms. A number of latent issues were discovered and corrected during the investigation. The cause of the control rod malfunction was found to be a buildup of corrosion in the control rod drive mechanism. The investigation resulted in modifications to equipment, changes to both operation and maintenance procedures, and additional training. No reoccurrences of the problem have been observed since corrective actions were implemented.

  5. EA-315-A BP Energy Co | Department of Energy

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

    -A BP Energy Co EA-315-A BP Energy Co Order authorizing BP Energy Co to export electric energy to Canada. EA-315-A BP Energy_CN_0.pdf (857.25 KB) More Documents & Publications Application to export electric energy OE Docket No. EA-315-A BP Energy EA-97-D Portland General Electric Company EA-249-C Exelon Generation Company, LLC

  6. High temperature control rod assembly

    SciTech Connect (OSTI)

    Vollman, R.E.

    1991-12-24

    This patent describes a control rod assembly for use in nuclear reactor control. It comprises segments, each the segment being made of a graphite composite material, each the segment having a chamber for containing neutron-absorbing material, wherein the chamber compromises a hollow cylindrical sleeve having a first end formed with an opening for receiving the neutron-absorbing material, and having a second end formed with a sleeve bore and an outer sleeve surface; a cylindrical weight-bearing support post positioned substantially centrally of the sleeve, the support post having a first end formed as a ball surface portion and a second end formed as a ball surface portion and a second end formed as a shaft, the shaft being engageable with the sleeve bore for rigidly coupling the support post axially within the hollow sleeve, a hollow cylindrical collar having a socket lip portion correspondingly shaped to receive the ball surface portion of an adjacent support post, and having an inner surface for engaging the outer sleeve surface on the second end of the sleeve to rigidly couple the collar to the sleeve.

  7. Control rod drive hydraulic system

    DOE Patents [OSTI]

    Ose, Richard A.

    1992-01-01

    A hydraulic system for a control rod drive (CRD) includes a variable output-pressure CR pump operable in a charging mode for providing pressurized fluid at a charging pressure, and in a normal mode for providing the pressurized fluid at a purge pressure, less than the charging pressure. Charging and purge lines are disposed in parallel flow between the CRD pump and the CRD. A hydraulic control unit is disposed in flow communication in the charging line and includes a scram accumulator. An isolation valve is provided in the charging line between the CRD pump and the scram accumulator. A controller is operatively connected to the CRD pump and the isolation valve and is effective for opening the isolation valve and operating the CRD pump in a charging mode for charging the scram accumulator, and closing the isolation valve and operating the CRD pump in a normal mode for providing to the CRD through the purge line the pressurized fluid at a purge pressure lower than the charging pressure.

  8. ROD INTERNAL PRESSURE QUANTIFICATION AND DISTRIBUTION ANALYSIS...

    Office of Scientific and Technical Information (OSTI)

    and densities of each fuel rod in FRAPCON-3.5. A methodology is developed which tracks inter-cycle assembly movements and assembly batch fabrication information to build...

  9. Control rod for a nuclear reactor

    DOE Patents [OSTI]

    Roman, Walter G.; Sutton, Jr., Harry G.

    1979-01-01

    A control rod assembly for a nuclear reactor is disclosed having a remotely disengageable coupling between the control rod and the control rod drive shaft. The coupling is actuated by first lowering then raising the drive shaft. The described motion causes axial repositioning of a pin in a grooved rotatable cylinder, each being attached to different parts of the drive shaft which are axially movable relative to each other. In one embodiment, the relative axial motion of the parts of the drive shaft is used either to couple or to uncouple the connection by forcing resilient members attached to the drive shaft into or out of shouldered engagement, respectively, with an indentation formed in the control rod.

  10. Double-clad nuclear fuel safety rod

    DOE Patents [OSTI]

    McCarthy, William H.; Atcheson, Donald B.; Vaidyanathan, Swaminathan

    1984-01-01

    A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

  11. Measurements of control rod efficiency in RBMK critical assembly upon dropping of the rods

    SciTech Connect (OSTI)

    Zhitarev, V. E. Kachanov, V. M.; Sergevnin, A. Yu.; Lebedev, G. V.

    2014-12-15

    The efficiency of control rods in the RBMK critical assembly was measured in the case where one manual-control rod (MCR) is dropped from a steady critical state, and several other MCRs were additionally dropped after 44 s. The measured number of neutrons in the assembly during and after dropping of the rods was used to calculate the efficiency values of the rods by solution of the system of point kinetics equations. A series of methods of the initial data treatment for determination of the desired values of reactivity without the calculated corrections were used.

  12. International symposium on fuel rod simulators: development and application

    SciTech Connect (OSTI)

    McCulloch, R.W.

    1981-05-01

    Separate abstracts are included for each of the papers presented concerning fuel rod simulator operation and performance; simulator design and evaluation; clad heated fuel rod simulators and fuel rod simulators for cladding investigations; fuel rod simulator components and inspection; and simulator analytical modeling. Ten papers have previously been input to the Energy Data Base.

  13. Nuclear reactor remote disconnect control rod coupling indicator

    DOE Patents [OSTI]

    Vuckovich, Michael

    1977-01-01

    A coupling indicator for use with nuclear reactor control rod assemblies which have remotely disengageable couplings between the control rod and the control rod drive shaft. The coupling indicator indicates whether the control rod and the control rod drive shaft are engaged or disengaged. A resistive network, utilizing magnetic reed switches, senses the position of the control rod drive mechanism lead screw and the control rod position indicating tube, and the relative position of these two elements with respect to each other is compared to determine whether the coupling is engaged or disengaged.

  14. EIS-0283-S2: Record of Decision | Department of Energy

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

    Record of Decision EIS-0283-S2: Record of Decision Surplus Plutonium Disposition Environmental Impact Statement The Department of Energy/National Nuclear Security Administration issued a Record of Decision for the 2015 Final Surplus Plutonium Disposition Supplemental Environmental Impact Statement (DOE/EIS-0283-S2). For more information on this project, see the project webpage: http://energy.gov/node/299815. DOWNLOAD DOCUMENT EIS-0283-S2_ROD.pdf (238.95 KB) More Documents & Publications

  15. EIS-0447: Record of Decision | Department of Energy

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

    Record of Decision EIS-0447: Record of Decision Champlain Hudson Power Express Transmission Line Project, New York DOE announced its decision to grant a Presidential permit to Champlain Hudson Power Express, Inc., to construct, operate, maintain, and connect a new 1000-megawatt electric transmission line across the U.S./Canada border near Champlain, New York, to New York City. EIS-0447-ROD-2014.pdf (58.24 KB) More Documents & Publications Application for Presidential Permit OE Docket No.

  16. EIS-0451: Record of Decision | Department of Energy

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

    51: Record of Decision EIS-0451: Record of Decision Hooper Springs Transmission Project, Caribou County, Idaho DOE's Bonneville Power Administration issued a Record of Decision and Mitigation Action Plan for the Hooper Springs Transmission Project. EIS-0451-ROD-MAP-2015.pdf (1.72 MB) More Documents & Publications EIS-0451: Supplemental Draft Environmental Impact Statement EIS-0451: Final Environmental Impact Statement EIS-0451: Draft

  17. EIS-0478: Record of Decision | Department of Energy

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

    78: Record of Decision EIS-0478: Record of Decision Antelope Valley Station to Neset Transmission Project, Mercer, Dunn, Billings, Williams, McKenzie, and Mountrail Counties, North Dakota DOE's Western Area Power Administration issued a record of decision to grant Basin Electric Power Cooperative's request to interconnect the Antelope Valley Station to Neset Transmission Project to Western's Williston Substation and Williston to Charlie Creek transmission line. EIS-0478-ROD-2014.pdf (195.66 KB)

  18. EIS-0488: Record of Decision | Department of Energy

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

    Record of Decision EIS-0488: Record of Decision Cameron Liquefaction Project, Cameron Parish, Louisiana DOE issued a Record of Decision and Floodplain Statement of Findings for the Cameron liquefied natural gas export application to non-free trade agreement countries. EIS-0488-ROD-FRversion-2014.pdf (179.64 KB) More Documents & Publications CAMERON LNG, LLC - FE DKT. NO. 15-36-LNG (FTA) Cameron LNG LLC - 14-001-CIC Cameron LNG LLC Final Order

  19. EIS-0493: Record of Decision | Department of Energy

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

    Record of Decision EIS-0493: Record of Decision Corpus Christi LNG Terminal and Pipeline Project, Nueces and San Patricio Counties, Texas DOE announced its decision to authorize the export of liquefied natural gas from an export terminal on the north shore of Corpus Christi Bay in Nueces and San Patricio Counties, Texas. EIS-0493-ROD-2015.pdf (179.78 KB) More Documents & Publications Order 3638: Corpus Christi Liquefaction Project Corpus Christi Liquefaction Terminal SEMI-ANNUAL REPORTS FOR

  20. EIS-0229: Amended Record of Decision | Department of Energy

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

    9: Amended Record of Decision EIS-0229: Amended Record of Decision Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic Environmental Impact Statement The U.S. Department of Energy (DOE) is amending the Record of Decision (ROD) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement (DOE/EIS-0229, 1996; Storage and Disposition PEIS). Specifically, DOE has decided to take the actions necessary to transfer

  1. EIS-0310: Amended Record of Decision | Department of Energy

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

    10: Amended Record of Decision EIS-0310: Amended Record of Decision Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the United States The Department of Energy (DOE) is amending its Record of Decision (ROD) (66 FR 7877, January 26, 2001) for its Final Programmatic Environmental Impact Statement for Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the United States, Including the

  2. DOE Amends Record of Decision for Plutonium Consolidation | Department of

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

    Energy DOE Amends Record of Decision for Plutonium Consolidation DOE Amends Record of Decision for Plutonium Consolidation DOE amended the Record of Decision (ROD) for the Storage and Disposition of Weapons-Usable Fissile Materials Programmatic Environmental Impact Statement. Specifically, DOE decided to take the actions necessary to transfer approximately 2,511 additional 3013-compliant packages containing surplus non-pit weapons-usable plutonium metals and oxides to the Savannah River Site

  3. EA-314 BP Energy Company | Department of Energy

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

    electric energy to Mexico PDF icon EA-314 BP Energy Company More Documents & Publications EA-318 CSW Power Marketing PP-89-1 Bangor Hydro-Electric Company EA-314-A BP Energy Co

  4. EA-315 BP Energy Company | Department of Energy

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

    energy to Canada EA-315 BP Energy Company (3.57 MB) More Documents & Publications EA-315-A BP Energy Co EA-97-D Portland General Electric Company EA-342 Royal Bank of Canada

  5. EA-314 BP Energy Company | Department of Energy

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

    to export electric energy to Mexico EA-314 BP Energy Company More Documents & Publications EA-318 CSW Power Marketing EA-314-A BP Energy Co PP-89-1 Bangor Hydro-Electric Company...

  6. BP Purui New Energy Co | Open Energy Information

    Open Energy Info (EERE)

    Zip: 710021 Sector: Solar Product: China Xinjiang Sunoasis and BP Solar are planning a joint venture which will be called BP New Energy Co, and will focus on their combined...

  7. Draft HAB Letter Regarding the PW-1,3,6/CW-5 Record of Decision

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

    - RAPPIC Committees Draft Letter v.1 - PW-1,3,6CW-5 ROD - Cimon, Larsen, Smith Page 11 Draft HAB Letter Regarding the PW-1,3,6CW-5 Record of Decision 1 Address Dear :...

  8. Magnetic switch for reactor control rod

    DOE Patents [OSTI]

    Germer, John H.

    1986-01-01

    A magnetic reed switch assembly for activating an electromagnetic grapple utilized to hold a control rod in position above a reactor core. In normal operation the magnetic field of a permanent magnet is short-circuited by a magnetic shunt, diverting the magnetic field away from the reed switch. The magnetic shunt is made of a material having a Curie-point at the desired release temperature. Above that temperature the material loses its ferromagnetic properties, and the magnetic path is diverted to the reed switch which closes and short-circuits the control circuit for the control rod electromagnetic grapple which allows the control rod to drop into the reactor core for controlling the reactivity of the core.

  9. Magnetic switch for reactor control rod. [LMFBR

    DOE Patents [OSTI]

    Germer, J.H.

    1982-09-30

    A magnetic reed switch assembly is described for activating an electromagnetic grapple utilized to hold a control rod in position above a reactor core. In normal operation the magnetic field of a permanent magnet is short-circuited by a magnetic shunt, diverting the magnetic field away from the reed switch. The magnetic shunt is made of a material having a Curie-point at the desired release temperature. Above that temperature the material loses its ferromagnetic properties, and the magnetic path is diverted to the reed switch which closes and short-circuits the control circuit for the control rod electro-magnetic grapple which allows the control rod to drop into the reactor core for controlling the reactivity of the core.

  10. System analysis for sucker-rod pumping

    SciTech Connect (OSTI)

    Schmidt, Z.; Doty, D.R.

    1989-05-01

    Pumping free gas in an oil well can significantly decrease the efficiency of a sucker-rod-pumping installation. Pump placement depth and use of a downhole gas/liquid separator (gas anchor) were found to be significant variables in improving the overall efficiency. A procedure is presented that shows when and to what degree the use of a gas anchor improves the efficiency of a sucker-rod pumping system. It was found that at lower pump intake pressures, the gas anchor usually improves efficiency, but at higher pump intake pressures, use of a gas anchor produces no positive effect. Also, elevating the pump to the highest position that still allows proper pump loading was found to reduce the operating costs of a sucker-rod-pumping installation significantly. Finally, a procedure is presented to calculate directly the pump volumetric efficiency and required volumetric pump displacement rate.

  11. HIGH STRENGTH CONTROL RODS FOR NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Lustman, B.; Losco, E.F.; Cohen, I.

    1961-07-11

    Nuclear reactor control rods comprised of highly compressed and sintered finely divided metal alloy panticles and fine metal oxide panticles substantially uniformly distributed theretbrough are described. The metal alloy consists essentially of silver, indium, cadmium, tin, and aluminum, the amount of each being present in centain percentages by weight. The oxide particles are metal oxides of the metal alloy composition, the amount of oxygen being present in certain percentages by weight and all the oxygen present being substantially in the form of metal oxide. This control rod is characterized by its high strength and resistance to creep at elevated temperatures.

  12. Nuclear reactor fuel rod attachment system

    DOE Patents [OSTI]

    Not Available

    1980-09-17

    A reusable system is described for removably attaching a nuclear reactor fuel rod to a support member. A locking cap is secured to the fuel rod and a locking strip is fastened to the support member. The locking cap has two opposing fingers shaped to form a socket having a body portion. The locking strip has an extension shaped to rigidly attach to the socket's body portion. The locking cap's fingers are resiliently deflectable. For attachment, the locking cap is longitudinally pushed onto the locking strip causing the extension to temporarily deflect open the fingers to engage the socket's body portion. For removal, the process is reversed.

  13. Control rod drive for reactor shutdown

    DOE Patents [OSTI]

    McKeehan, Ernest R.; Shawver, Bruce M.; Schiro, Donald J.; Taft, William E.

    1976-01-20

    A means for rapidly shutting down or scramming a nuclear reactor, such as a liquid metal-cooled fast breeder reactor, and serves as a backup to the primary shutdown system. The control rod drive consists basically of an in-core assembly, a drive shaft and seal assembly, and a control drive mechanism. The control rod is driven into the core region of the reactor by gravity and hydraulic pressure forces supplied by the reactor coolant, thus assuring that common mode failures will not interfere with or prohibit scramming the reactor when necessary.

  14. Method for producing titanium aluminide weld rod

    DOE Patents [OSTI]

    Hansen, Jeffrey S.; Turner, Paul C.; Argetsinger, Edward R.

    1995-01-01

    A process for producing titanium aluminide weld rod comprising: attaching one end of a metal tube to a vacuum line; placing a means between said vacuum line and a junction of the metal tube to prevent powder from entering the vacuum line; inducing a vacuum within the tube; placing a mixture of titanium and aluminum powder in the tube and employing means to impact the powder in the tube to a filled tube; heating the tube in the vacuum at a temperature sufficient to initiate a high-temperature synthesis (SHS) reaction between the titanium and aluminum; and lowering the temperature to ambient temperature to obtain a intermetallic titanium aluminide alloy weld rod.

  15. Improving fuel-rod performance. [PWR; BWR

    SciTech Connect (OSTI)

    Ocken, H.; Knott, S.

    1981-03-01

    To reduce the risk of fuel-rod failures, utilities operate their nuclear reactors within conservative limits on power increases proposed by nuclear-fuel vendors. Of particular concern to US utilities is that adopting these limits results in an industrywide average plant capacity loss of 3% in BWR designs and 0.3% in PWR designs. To replace lost BWR capacity by other generating means currently costs the utilities $150 million annually, and losses for PWRs are about $20 million. Efforts are therefore being made to identify the factors responsible for Zircaloy degradation under PCI condition and to improve nuclear-fuel-rod design and reactor operation.

  16. Properly spaced rod guides reduce wear in directional wells

    SciTech Connect (OSTI)

    Duan, Y.; Yuan, X. )

    1994-10-17

    In deviated wells, guides or wheels properly placed on the rode string can prevent both wear on the tubing and the rods. Proper placement involves integrating information on hole trajectory, rod string properties, and economics. Too many guides or wheels will increase polished rod load, thereby increasing recovery cost. But two few guides or improper spacing of guides can either prevent rod and tubing wear nor lower polished rod load. Consequently, optimal rod guide spacing is required. The paper discusses a stress analysis, spacing and deflection, and optimal spacing.

  17. Method and means of packaging nuclear fuel rods for handling

    DOE Patents [OSTI]

    Adam, Milton F.

    1979-01-01

    Nuclear fuel rods, especially spent nuclear fuel rods that may show physical distortion, are encased within a metallic enclosing structure by forming a tube about the fuel rod. The tube has previously been rolled to form an overlapping tubular structure and then unrolled and coiled about an axis perpendicular to the tube. The fuel rod is inserted into the tube as the rolled tube is removed from a coiled strip and allowed to reassume its tubular shape about the fuel rod. Rollers support the coiled strip in an open position as the coiled strip is uncoiled and allowed to roll about the fuel rod.

  18. Modeling and simulation performance of sucker rod beam pump

    SciTech Connect (OSTI)

    Aditsania, Annisa; Rahmawati, Silvy Dewi Sukarno, Pudjo; Soewono, Edy

    2015-09-30

    Artificial lift is a mechanism to lift hydrocarbon, generally petroleum, from a well to surface. This is used in the case that the natural pressure from the reservoir has significantly decreased. Sucker rod beam pumping is a method of artificial lift. Sucker rod beam pump is modeled in this research as a function of geometry of the surface part, the size of sucker rod string, and fluid properties. Besides its length, sucker rod string also classified into tapered and un-tapered. At the beginning of this research, for easy modeling, the sucker rod string was assumed as un-tapered. The assumption proved non-realistic to use. Therefore, the tapered sucker rod string modeling needs building. The numerical solution of this sucker rod beam pump model is computed using finite difference method. The numerical result shows that the peak of polished rod load for sucker rod beam pump unit C-456-D-256-120, for non-tapered sucker rod string is 38504.2 lb, while for tapered rod string is 25723.3 lb. For that reason, to avoid the sucker rod string breaks due to the overload, the use of tapered sucker rod beam string is suggested in this research.

  19. BP Cherry Point Cogeneration Project, Draft Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2003-09-19

    respective decision-making processes associated with the Applicant's request to interconnect to Bonneville's transmission system and proposed location of the project within wetland areas. Therefore, this Draft EIS serves as the environmental review document for SEPA and for NEPA as required by Bonneville for the interconnection and the Corps for its 404 individual permit. The EIS addresses direct, indirect, and cumulative impacts of the proposed project, and potential mitigation measures proposed by the Applicant, as well as measures recommended by EFSEC. The information and resulting analysis presented in this Draft EIS are based primarily on information provided by the Applicant in the ASC No. 2002-01 (BP 2002). Where additional information was used to evaluate the potential impacts associated with the proposed action, that information has been referenced. EFSEC's environmental consultant, Shapiro and Associates, Inc., did not perform additional studies during the preparation of this Draft EIS.

  20. Wear simulation of sucker rod couplings

    SciTech Connect (OSTI)

    Schumacher, W.J. )

    1991-09-01

    This paper reports that sucker rod strings are devices used to actuate pumps located at the bottom of oil wells. The individual rods are connected together by threaded couplings. Since the couplings have a larger diameter than the rods, they sometimes contact the inside diameter of the tubing during the up and down pumping cycle. Usually, this is not problem unless buckling occurs in the downstroke; however, this can lead to accelerated wear of the coupling and tubing. In nonvertical wells (offset, deviated, or slanted), the contact is more severe and rapid wear takes place. Couplings are more easily replaced during shutdowns; it is very important to minimize wear to tubing since it is virtually impossible to replace. TRIBONIC 20, an iron-based alloy containing approximately 13% Mn, 5% Si, 5.5% Cr, and 5% Ni, was laboratory evaluated to determine whether or not it could solve the sucker rod coupling-production tubing wear problem. The alloy demonstrated outstanding wear resistance both to itself and in protecting type 1019 steel.

  1. Piston rod seal for a Stirling engine

    DOE Patents [OSTI]

    Shapiro, Wilbur

    1984-01-01

    In a piston rod seal for a Stirling engine, a hydrostatic bearing and differential pressure regulating valve are utilized to provide for a low pressure differential across a rubbing seal between the hydrogen and oil so as to reduce wear on the seal.

  2. CONTROL ROD ALLOY CONTAINING NOBLE METAL ADDITIONS

    DOE Patents [OSTI]

    Anderson, W.K.; Ray, W.E.

    1960-05-01

    Silver-base alloys suitable for use in the fabrication of control rods for neutronic reactors are given. The alloy consists of from 0.5 wt.% to about 1.5 wt.% of a noble metal of platinum, ruthenium, rhodium, osmium, or palladium, up to 10 wt.% of cadmium, from 2 to 20 wt.% indium, the balance being silver.

  3. Hanford Site - 200-BP-5 | Department of Energy

    Office of Environmental Management (EM)

    BP-5 Hanford Site - 200-BP-5 July 1, 2014 - 12:00pm Addthis US Department of Energy Groundwater Database Groundwater Master Report InstallationName, State: Hanford, WA Responsible DOE Office: Office of Environmental Management Plume Name: 200-BP-5 Remediation Contractor: CHPRC PBS Number: 30 Report Last Updated: July 2014 with CY2013 data Contaminants Halogenated VOCs/SVOCs Present?: No Fuel Present? No Metals Present? Yes Isotopes Present? Yes Explosives Present? No Other Contaminants? Yes

  4. DOE signs Record of Decision selecting Hot Isostatic Pressing Technology

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

    for Treatment of High Level Waste Calcine DOE signs Record of Decision selecting Hot Isostatic Pressing Technology for Treatment of High Level Waste Calcine The U.S. Department of Energy (DOE) has signed the Record of Decision (ROD) for the treatment of high level waste calcine at the Department's Idaho Site, meeting a legal commitment to the State of Idaho for a decision no later than the end of 2009. Hot Isostatic Pressing Unit DOE today announced its decision to treat high-level waste

  5. DOE Signs Decision to Move Moab Tailings | Department of Energy

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

    Decision to Move Moab Tailings DOE Signs Decision to Move Moab Tailings September 14, 2005 - 10:23am Addthis WASHINGTON, DC - U.S. Secretary of Energy Samuel W. Bodman today announced that a Record of Decision (ROD) clearing the way for the removal of 11.9 million tons of radioactive Uranium Mill Tailings from the banks the Colorado River in Utah has been signed. Under the Moab Uranium Mill Tailings Remedial Action Project Site Record of Decision, the tailings will be moved, predominately by

  6. BP Energy India Private Limited BPEIPL | Open Energy Information

    Open Energy Info (EERE)

    India Private Limited BPEIPL Jump to: navigation, search Name: BP Energy India Private Limited (BPEIPL) Place: India Sector: Wind energy Product: India-based, subsidiary of Green...

  7. BP Gas Power and Renewables | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: BP Gas, Power and Renewables Place: Central Milton Keynes, United Kingdom Zip: MK9 1ES Sector: Renewable Energy Product: Subsidiary of...

  8. BP Statistical Review of World Energy | Open Energy Information

    Open Energy Info (EERE)

    OpenEI The BP Statistical Review of World Energy is an Excel spreadsheet which contains consumption and production data for Coal, Natural Gas, Nuclear, Oil, and Hydroelectric...

  9. Variable flow control for a nuclear reactor control rod

    DOE Patents [OSTI]

    Carleton, Richard D.; Bhattacharyya, Ajay

    1978-01-01

    A variable flow control for a control rod assembly of a nuclear reactor that depends on turbulent friction though an annulus. The annulus is formed by a piston attached to the control rod drive shaft and a housing or sleeve fitted to the enclosure housing the control rod. As the nuclear fuel is burned up and the need exists for increased reactivity, the control rods are withdrawn, which increases the length of the annulus and decreases the rate of coolant flow through the control rod assembly.

  10. Amended Record of Decision for the Idaho High-Level Waste (HLW) and Facilities Disposition Final Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) is amending its Record of Decision (ROD) published December 19, 2005 (70 Federal Register (FR) 75165), pursuant to the Idaho HIgh-Level Waste and Facilities...

  11. Nuclear reactor fuel rod attachment system

    DOE Patents [OSTI]

    Christiansen, David W. (Kennewick, WA)

    1982-01-01

    A reusable system for removably attaching a nuclear reactor fuel rod (12) to a support member (14). A locking cap (22) is secured to the fuel rod (12) and a locking strip (24) is fastened to the support member (14). The locking cap (22) has two opposing fingers (24a and 24b) shaped to form a socket having a body portion (26). The locking strip has an extension (36) shaped to rigidly attach to the socket's body portion (26). The locking cap's fingers are resiliently deflectable. For attachment, the locking cap (22) is longitudinally pushed onto the locking strip (24) causing the extension (36) to temporarily deflect open the fingers (24a and 24b) to engage the socket's body portion (26). For removal, the process is reversed.

  12. HTGR green rod intercomparison. I. Hydrogen assay

    SciTech Connect (OSTI)

    Meier, M.M.; Adams, E.L.

    1981-01-01

    A /sup 252/Cf hydrogen monitor has been used to determine the hydrogen content of each of the 144 unfired (green) fuel rods being circulated in the New Brunswick Laboratory fuel measurement evaluation program. The monitor was calibrated with standards fabricated by Los Alamos Scientific Laboratory (LASL) Analytical Chemistry Group, CMB-1. Measurements were made relative to these standards and overall accuracies of +-3% were achieved.

  13. ELECTROMAGNETIC APPARATUS FOR MOVING A ROD

    DOE Patents [OSTI]

    Young, J.N.

    1957-08-20

    An electromagnetic device for moving an object in a linear path by increments is described. The device is specifically adapted for moving a neutron absorbing control rod into and out of the core of a reactor and consists essentially of an extension member made of magnetic material connected to one end of the control rod and mechanically flexible to grip the walls of a sleeve member when flexed, a magnetic sleeve member coaxial with and slidable between limit stops along the flexible extension, electromagnetic coils substantially centrally located with respect to the flexible extension to flex the extension member into gripping engagement with the sleeve member when ener gized, moving electromagnets at each end of the sleeve to attract the sleeve when energized, and a second gripping electromagnet positioned along the flexible extension at a distance from the previously mentioned electromagnets for gripping the extension member when energized. In use, the second gripping electromagnet is deenergized, the first gripping electromagnet is energized to fix the extension member in the sleeve, and one of the moving electromagnets is energized to attract the sleeve member toward it, thereby moving the control rod.

  14. EM Issues Amended Decision to Expand Use of Nuclear Facility

    Broader source: Energy.gov [DOE]

    AIKEN, S.C. – EM issued an amended Record of Decision (ROD) to the Savannah River Site (SRS) Spent Nuclear Fuel Environmental Impact Statement to expand the operations of the H-Canyon Facility at SRS to support a major nuclear non-proliferation goal and save taxpayer dollars.

  15. Microsoft Word - Leucadia ROD.docx

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

    [6450-01-P] DEPARTMENT OF ENERGY Record of Decision and Floodplain Statement of Findings for the Lake Charles Carbon Capture and Sequestration Project AGENCY: Department of Energy ACTION: Record of Decision SUMMARY: The U.S. Department of Energy (DOE) announces its decision to provide cost-shared funding to Leucadia Energy, LLC (Leucadia) for its Lake Charles Carbon Capture and Sequestration project (Lake Charles CCS project) under DOE's Industrial Carbon Capture Sequestration (ICCS) Program.

  16. ALLOY COMPOSITION FOR NEUTRONIC REACTOR CONTROL RODS

    DOE Patents [OSTI]

    Lustman, B.; Losco, E.F.; Snyder, H.J.; Eggleston, R.R.

    1963-01-22

    This invention relates to alloy compositons suitable as cortrol rod material consisting of, by weight, from 85% to 85% Ag, from 2% to 20% In, from up to 10% of Cd, from up to 5% Sn, and from up to 1.5% Al, the amount of each element employed being determined by the equation X + 2Y + 3Z + 3W + 4V = 1.4 and less, where X, Y, Z, W, and V represent the atom fractions of the elements Ag, Cd, In, Al and Sn. (AEC)

  17. Nondestructive assay of green HTGR fuel rods

    SciTech Connect (OSTI)

    Barschall, H.H.; Meier, M.M.; Parker, J.L.

    1981-05-01

    This report describes the nondestructive (NDA) work done at Los Alamos during 1979 and 1980 as part of the New Brunswick Laboratory-sponsored evaluation of NDA of the uranium content of fabricated fuel rods for high-temperature gas-cooled reactors (HTGR). The methods used (delayed neutron and passive gamma ray) are concisely described, and the results are summarized and compared in graphical and tabular form. The results indicate that, with the use of proper physical standards, accuracies within about 1 percent should be achievable by NDA procedures.

  18. Rodded shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Golden, Martin P.; Govi, Aldo R.

    1978-01-01

    A top mounted nuclear reactor diverse rodded shutdown system utilizing gas fed into a pressure bearing bellows region sealed at the upper extremity to an armature. The armature is attached to a neutron absorber assembly by a series of shafts and connecting means. The armature is held in an uppermost position by an electromagnet assembly or by pressurized gas in a second embodiment. Deenergizing the electromagnet assembly, or venting the pressurized gas, causes the armature to fall by the force of gravity, thereby lowering the attached absorber assembly into the reactor core.

  19. Convergent synthesis of multiporphyrin light-harvesting rods

    DOE Patents [OSTI]

    Lindsey, Jonathan S.; Loewe, Robert S.

    2003-08-05

    The present invention provides a convergent method for the synthesis of light harvesting rods. The rods are oligomers of the formula A.sup.1 (A.sup.b+1).sub.b, wherein b is at least 1, A.sup.1 through A.sup.b+1 are covalently coupled rod segments, and each rod segment A.sup.1 through A.sup.1+b comprises a compound of the formula X.sup.1 (X.sup.m+1).sub.m wherein m is at least 1 and X.sup.1 through X.sup.m+1 are covalently coupled porphyrinic macrocycles. Light harvesting arrays and solar cells containing such light harvesting rods are also described, along with intermediates useful in such methods and rods produced by such methods.

  20. Mr. Rod Beever, Retrospective Review Comment | Department of Energy

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

    Mr. Rod Beever, Retrospective Review Comment Mr. Rod Beever, Retrospective Review Comment The following content was created in response to the Federal Register, Vol. 81,No.90 published May 10, 2016 in regards to reducing regulatory burden via a Request for Information (RFI). This is part of the implementation of Executive Order 13563. Mr. Rod Beever, Retrospective Review Comment (254.11 KB) More Documents & Publications SEVENTH RFI COMMENTS ON REDUCING REGULATORY BURDEN Notice of

  1. Meet CMI Researcher Rod Eggert | Critical Materials Institute

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

    Rod Eggert Image of Rod Eggert, researcher at Critical Materials Institute CMI researcher Rod Eggert is a geochemist turned economist. More formally, he is professor and former director of the Division of Economics and Business at the Colorado School of Mines, where he has taught since 1986. As deputy director of the Critical Materials Institute, he works with the director and the rest of the leadership team to guide and manage CMI, oversee the supply-chain and economic analysis that provides

  2. CASL-U-2015-0249-000 Rod Cusping

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

    Rod Cusping Treatment in MPACT CASL is currently developing a new core simulator called MPACT to solve neutron transport problems for light- water nuclear reactors....

  3. Nuclear fuel rods along the sand dunes

    SciTech Connect (OSTI)

    Regan, M.B.

    1993-05-10

    Just north of the small town of Covert, Michigan, Consumers Power Co. officials and environmental activists are locked in a battle that marks a new phase in the nation's long-running struggle over nuclear power. The company's Palisades power plant reactor needs refueling. But the utility has no more room for the spent fuel rods it must place in its water-filled storage pool. So Consumers is taking advantage of a 1990 Nuclear Regulatory Commission rule that lets utilities store waste above ground without agency review. Palisades officials plan to transfer older radioactive fuel rods from its storage pool into concrete and steel silo-like casks on a site overlooking Lake Michigan. Over the next decade, nearly half of the nation's 109 operating nuclear plants will run out of space in water-filled storage pools and be forced to consider aboveground storage. The Palisades plant is causing a stir because it is the first to exploit the 1990 NRC rule, which doesn't require utilities to seek approval for waste-storage sites as long as the waste is stored in an approved container. Before 1990, five other utilities had received the agency O.K. for above-ground storage - but only after a lengthy and exhaustive analysis of each site.

  4. DOE signs Record of Decision selecting Hot Isostatic Pressing Technology

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

    for Treatment of High Level Waste Calcine NEWS MEDIA CONTACT: Brad Bugger (208) 526-0833 Danielle Miller (208) 526-5709 FOR IMMEDIATE RELEASE: December 28, 2009 DOE signs Record of Decision selecting Hot Isostatic Pressing Technology for Treatment of High Level Waste The U.S. Department of Energy (DOE) has signed the Record of Decision (ROD) for the treatment of high level waste calcine at the Department�s Idaho Site, meeting a legal commitment to the State of Idaho for a decision no

  5. EIS-0387: Record of Decision | Department of Energy

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

    87: Record of Decision EIS-0387: Record of Decision Y-12 National Security Complex The National Nuclear Security Administration (NNSA) of the U.S. Department of Energy (DOE) is issuing this Record of Decision (ROD) for the Y-12 National Security Complex (Y-12) in Oak Ridge, Tennessee based on information and analyses contained in the Final Site-Wide Environmental Impact Statement for the Y-12 National Security Complex, DOE/EIS-0387 (Y-12 Final SWEIS, Y-12 SWEIS or 2011 Y- 12 SWEIS) issued on

  6. EIS-0426: Record of Decision | Department of Energy

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

    26: Record of Decision EIS-0426: Record of Decision DOE/NNSA is issuing this Record of Decision (ROD) for the continued management, operation, and activities of the Nevada National Security Site (NNSS) and Off-Site Locations in the State of Nevada pursuant to the Final Site-Wide Environmental Impact Statement for the Continued Operation of the Department of Energy/National Nuclear Security Administration Nevada National Security Site and Off-Site Locations in the State of Nevada, DOE/EIS-0426

  7. BP SunOasis Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Co Ltd Place: Xi'an, Shaanxi Province, China Zip: 710016 Sector: Solar Product: Solar module manufacturer. References: BP SunOasis Co Ltd1 This article is a stub. You can help...

  8. Yieldably mounted lubricant control assemblies for piston rods

    SciTech Connect (OSTI)

    Meijer, R.J.; Ziph, B. Godett, T.M.

    1986-04-01

    This patent describes an engine having a housing comprising a cylinder within which a piston reciprocates and a piston rod extending from the piston through a bore which extends in the housing from the cylinder to a crankcase and a lubricant control assembly which is disposed within the bore in cooperative arrangement with the piston rod and functions to separate the cylinder from the crankcase while allowing the piston rod to reciprocate axially through a lubricant control portion of the lubricant control assembly which is in forceful contact around the piston rod, the improvement which comprises a compliant housing for mounting the lubricant control assembly on the engine housing. The compliant housing is operatively disposed between the engine housing and the lubricant control portion to allow the lubricant control portion to be radially displaced with respect to the bore and thereby comply with radial displacement of the reciprocating piston rod while maintaining substantially full effectiveness of the lubricant control portion acting on the piston rod. The lubricant control assembly consists of a tubular part, means attaching the tubular part to the compliant housing such that the tubular part can comply with radial displacement of the reciprocating piston rod, and force-applying means acting between the tubular part and the lubricant control portion for urging the lubricant control portion into forceful contact around the reciprocating piston rod.

  9. CONTROL ROD FOR A NUCLEAR REACTOR AND METHOD OF PREPARATION

    DOE Patents [OSTI]

    Hausner, H.H.

    1958-12-30

    BS>An improved control rod is presented for a nuclear reactor. This control rod is comprised of a rare earth metal oxide or rare earth metal carbide such as gadolinium oxide or gadolinium carbide, uniformly distributed in a metal matrix having a low cross sectional area of absorption for thermal neutrons, such as aluminum, beryllium, and zirconium.

  10. 100-F/IU Area ROD

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

    Area ROD Christopher Guzzetti US EPA Topics  15 waste sites with ICs for contamination at depth  1 waste site with IC for Irrigation  MNA for Groundwater 15 ft HH GW/SW 15 waste sites with deep ICs IC Boundaries Waste site with IC for Irrigation Waste site with IC for Irrigation Max Conc. 3.23 mg/kg 22 ft. 0.27 mg/kg 48.9 ft. Max Conc. 7.5 mg/kg CVP ND 20 µg/L Interim 10 µg/L Final Waste Site vs. Cr6 Plume MNA for Groundwater  Timeframes to achieve cleanup levels are based on the

  11. Nuclear reactor shutdown control rod assembly

    DOE Patents [OSTI]

    Bilibin, Konstantin

    1988-01-01

    A temperature responsive, self-actuated nuclear reactor shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear reactor resulting in automatic reduction of the reactor powder.

  12. Semiconductor Quantum Rods as Single Molecule FluorescentBiological Labels

    SciTech Connect (OSTI)

    Fu, Aihua; Gu, Weiwei; Boussert, Benjamine; Koski, Kristie; Gerion, Daniele; Manna, Liberato; Le Gros, Mark; Larabell, Carolyn; Alivisatos, A. Paul

    2006-05-29

    In recent years, semiconductor quantum dots have beenapplied with great advantage in a wide range of biological imagingapplications. The continuing developments in the synthesis of nanoscalematerials and specifically in the area of colloidal semiconductornanocrystals have created an opportunity to generate a next generation ofbiological labels with complementary or in some cases enhanced propertiescompared to colloidal quantum dots. In this paper, we report thedevelopment of rod shaped semiconductor nanocrystals (quantum rods) asnew fluorescent biological labels. We have engineered biocompatiblequantum rods by surface silanization and have applied them fornon-specific cell tracking as well as specific cellular targeting. Theproperties of quantum rods as demonstrated here are enhanced sensitivityand greater resistance for degradation as compared to quantum dots.Quantum rods have many potential applications as biological labels insituations where their properties offer advantages over quantumdots.

  13. 12.03.13 FG2 ROD

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

    Exports, LLC Application to Export Liquefied Natural Gas to Non-Free Trade Agreement Countries AGENCY: Office of Fossil Energy, Department of Energy. ACTION: Record of decision. SUMMARY: The U.S. Department of Energy (DOE) announces its decision in Lake Charles Exports, LLC (LCE), DOE/FE Docket No. 11-59-LNG, to issue DOE/FE Order No. 3324-A, granting final long-term, multi contract authorization for LCE to engage in the export of domestically produced liquefied natural gas (LNG) from the Lake

  14. 12.03.13 FG2 ROD

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

    LNG Export Company, LLC Application to Export Liquefied Natural Gas to Non-Free Trade Agreement Countries AGENCY: Office of Fossil Energy, Department of Energy. ACTION: Record of decision. SUMMARY: The U.S. Department of Energy (DOE) announces its decision in Lake Charles LNG Export Company, LLC (Lake Charles LNG Export), DOE/FE Docket No. 13-04-LNG 1 , to issue DOE/FE Order No. 3868 granting final long-term, multi contract authorization for Lake Charles LNG Export to engage in export of

  15. Defective fuel rod detection in operating pressurized water reactors during periods of continuously decreasing fuel rod integrity levels

    SciTech Connect (OSTI)

    Zanker, H. )

    1989-09-01

    Periods of continuously decreasing levels of fuel rod integrity due to debris-induced cladding damage, vibration-induced fretting wear of the cladding, etc. cause difficulties in the assessment of fuel rod performance from coolant activity data. The calculational models currently in use for this purpose in nuclear power plants are not sufficiently capable of indicating cases in which they are invalid. This can mislead reactor operators by misinterpretation of the coolant activity data, especially in situations where fast reactions are necessary. A quick test of validity is suggested to check the applicability of the currently available calculational models for estimating the number and average size of fuel rod defects. This paper describes how to recognize immediately periods of continuously decreasing levels of fuel rod integrity in order to prevent complications in routine power plant maintenance as well as accident situations caused by more severe fuel rod degradation.

  16. Marine04 Marine radiocarbon age calibration, 26 ? 0 ka BP

    SciTech Connect (OSTI)

    Hughen, K; Baille, M; Bard, E; Beck, J; Bertrand, C; Blackwell, P; Buck, C; Burr, G; Cutler, K; Damon, P; Edwards, R; Fairbanks, R; Friedrich, M; Guilderson, T; Kromer, B; McCormac, F; Manning, S; Bronk-Ramsey, C; Reimer, P; Reimer, R; Remmele, S; Southon, J; Stuiver, M; Talamo, S; Taylor, F; der Plicht, J v; Weyhenmeyer, C

    2004-11-01

    New radiocarbon calibration curves, IntCal04 and Marine04, have been constructed and internationally ratified to replace the terrestrial and marine components of IntCal98. The new calibration datasets extend an additional 2000 years, from 0-26 ka cal BP (Before Present, 0 cal BP = AD 1950), and provide much higher resolution, greater precision and more detailed structure than IntCal98. For the Marine04 curve, dendrochronologically dated tree-ring samples, converted with a box-diffusion model to marine mixed-layer ages, cover the period from 0-10.5 ka cal BP. Beyond 10.5 ka cal BP, high-resolution marine data become available from foraminifera in varved sediments and U/Th-dated corals. The marine records are corrected with site-specific {sup 14}C reservoir age information to provide a single global marine mixed-layer calibration from 10.5-26.0 ka cal BP. A substantial enhancement relative to IntCal98 is the introduction of a random walk model, which takes into account the uncertainty in both the calendar age and the radiocarbon age to calculate the underlying calibration curve. The marine datasets and calibration curve for marine samples from the surface mixed layer (Marine04) are discussed here. The tree-ring datasets, sources of uncertainty, and regional offsets are presented in detail in a companion paper by Reimer et al.

  17. Anisotropy in CdSe quantum rods

    SciTech Connect (OSTI)

    Li, Liang-shi

    2003-09-01

    The size-dependent optical and electronic properties of semiconductor nanocrystals have drawn much attention in the past decade, and have been very well understood for spherical ones. The advent of the synthetic methods to make rod-like CdSe nanocrystals with wurtzite structure has offered us a new opportunity to study their properties as functions of their shape. This dissertation includes three main parts: synthesis of CdSe nanorods with tightly controlled widths and lengths, their optical and dielectric properties, and their large-scale assembly, all of which are either directly or indirectly caused by the uniaxial crystallographic structure of wurtzite CdSe. The hexagonal wurtzite structure is believed to be the primary reason for the growth of CdSe nanorods. It represents itself in the kinetic stabilization of the rod-like particles over the spherical ones in the presence of phosphonic acids. By varying the composition of the surfactant mixture used for synthesis we have achieved tight control of the widths and lengths of the nanorods. The synthesis of monodisperse CdSe nanorods enables us to systematically study their size-dependent properties. For example, room temperature single particle fluorescence spectroscopy has shown that nanorods emit linearly polarized photoluminescence. Theoretical calculations have shown that it is due to the crossing between the two highest occupied electronic levels with increasing aspect ratio. We also measured the permanent electric dipole moment of the nanorods with transient electric birefringence technique. Experimental results on nanorods with different sizes show that the dipole moment is linear to the particle volume, indicating that it originates from the non-centrosymmetric hexagonal lattice. The elongation of the nanocrystals also results in the anisotropic inter-particle interaction. One of the consequences is the formation of liquid crystalline phases when the nanorods are dispersed in solvent to a high enough

  18. COAXIAL CONTROL ROD DRIVE MECHANISM FOR NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Fox, R.J.; Oakes, L.C.

    1959-04-14

    A drive mechanism is presented for the control rod or a nuclear reactor. In this device the control rod is coupled to a drive shaft which extends coaxially through the rotor of an electric motor for relative rotation with respect thereto. A gear reduction mehanism is coupled between the rotor and the drive shaft to convert the rotary motion of the motor into linear motion of the shaft with a comparatively great reduction in speed, thereby providing relatively glow linear movement of the shaft and control rod for control purposes.

  19. System for fuel rod removal from a reactor module

    DOE Patents [OSTI]

    Matchett, Richard L.; Roof, David R.; Kikta, Thomas J.; Wilczynski, Rosemarie; Nilsen, Roy J.; Bacvinskas, William S.; Fodor, George

    1990-01-01

    A robotic system for remote underwater withdrawal of the fuel rods from fuel modules of a light water breeder reactor includes a collet/grapple assembly for gripping and removing fuel rods in each module, which is positioned by use of a winch and a radial support means attached to a vertical support tube which is mounted over the fuel module. A programmable logic controller in conjunction with a microcomputer, provides control for the accurate positioning and pulling force of the rod grapple assembly. Closed circuit television cameras are provided which aid in operator interface with the robotic system.

  20. System for fuel rod removal from a reactor module

    DOE Patents [OSTI]

    Matchett, R.L.; Fodor, G.; Kikta, T.J.; Bacvinsicas, W.S.; Roof, D.R.; Nilsen, R.J.; Wilczynski, R.

    1988-07-28

    A robotic system for remote underwater withdrawal of the fuel rods from fuel modules of a light water breeder reactor includes a collet/grapple assembly for gripping and removing fuel rods in each module, which is positioned by use of a winch and a radial support means attached to a vertical support tube which is mounted over the fuel module. A programmable logic controller in conjunction with a microcomputer, provides control for the accurate positioning and pulling force of the rod grapple assembly. Closed circuit television cameras are provided which aid in operator interface with the robotic system. 7 figs.

  1. Large-eddy simulation, fuel rod vibration and grid-to-rod fretting in pressurized water reactors

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

    Christon, Mark A.; Lu, Roger; Bakosi, Jozsef; Nadiga, Balasubramanya T.; Karoutas, Zeses; Berndt, Markus

    2016-06-29

    Grid-to-rod fretting (GTRF) in pressurized water reactors is a flow-induced vibration phenomenon that results in wear and fretting of the cladding material on fuel rods. GTRF is responsible for over 70% of the fuel failures in pressurized water reactors in the United States. Predicting the GTRF wear and concomitant interval between failures is important because of the large costs associated with reactor shutdown and replacement of fuel rod assemblies. The GTRF-induced wear process involves turbulent flow, mechanical vibration, tribology, and time-varying irradiated material properties in complex fuel assembly geometries. This paper presents a new approach for predicting GTRF induced fuelmore » rod wear that uses high-resolution implicit large-eddy simulation to drive nonlinear transient dynamics computations. The GTRF fluid–structure problem is separated into the simulation of the turbulent flow field in the complex-geometry fuel-rod bundles using implicit large-eddy simulation, the calculation of statistics of the resulting fluctuating structural forces, and the nonlinear transient dynamics analysis of the fuel rod. Ultimately, the methods developed here, can be used, in conjunction with operational management, to improve reactor core designs in which fuel rod failures are minimized or potentially eliminated. Furthermore, robustness of the behavior of both the structural forces computed from the turbulent flow simulations and the results from the transient dynamics analyses highlight the progress made towards achieving a predictive simulation capability for the GTRF problem.« less

  2. EIS-0287: Amended Record of Decision | Department of Energy

    Office of Environmental Management (EM)

    Disposition Final Environmental Impact Statement Revised by State The U.S. Department of Energy is amending its initial ROD published December 19, 2005, pursuant to the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, issued in October 2002. Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement Revised by State, DOE/EIS-0287 (January 2010) 75 FR 137 (2.25 MB) More Documents & Publications

  3. Square Grains in Asymmetric Rod-Coil Block Copolymers (Journal...

    Office of Scientific and Technical Information (OSTI)

    Unlike the rounded grains that are well known to form in most soft materials, square grains of microphase-separated lamellae are observed in thin films of a rod-coil block ...

  4. Hydrodynamic interactions in metal rod-like particle suspensions...

    Office of Scientific and Technical Information (OSTI)

    and experimental study of the role of hydrodynamic interactions on the motion and dispersion of metal rod-like particles in the presence of an externally applied electric field. ...

  5. Fuel axial relocation in ballooning fuel rods. [PWR; BWR

    SciTech Connect (OSTI)

    Siefken, L.J.

    1983-01-01

    Fuel movement, in the longitudinal direction in ballooning fuel rods, shifts the position of heat generation and may cause an increase in cladding temperature in the ballooning region. This paper summarizes the axial fuel relocation data obtained in fuel rod tests conducted in the United States and the Federal Republic of Germany, describes a model for calculating fuel axial relocation, and gives a quantitative analysis of the impact of fuel relocation on cladding temperature. The amount of fuel relocation in 18 ballooned fuel rods was determined from neutron radiographs, niobium gamma decay counts, and photomicrographs. The fuel rods had burnups in the range of 0 to 35,000 MWd/t and cladding hoop strains varying from 0 to 72%.

  6. Control and shim rod arrangement with moveable plugs

    DOE Patents [OSTI]

    Smith, Montford H.

    1976-03-30

    This invention relates to a control and shim rod arrangement for a nuclear reactor. A second shield of concrete completely encloses a biological shield. Moveable plugs are mounted in said shield.

  7. Natural convection burnout heat flux limit for control rods

    SciTech Connect (OSTI)

    Britt, T.E.

    1986-04-14

    Technical Standard 105-3.05, Safety Circuits, does not require the Septifoil Supply Header Pressure Very Low safety circuit for current charges. This document develops a new requirement for this circuit based on the burnout heat flux of a control rod under natural convective cooling. Specifically, the Septifoil Supply Header Pressure Very Low safety circuit will be required whenever the calculated control rod operating heat flux exceeds 155,000 pcu/ft{sup 2}-hr.

  8. Apparatus for injection casting metallic nuclear energy fuel rods

    DOE Patents [OSTI]

    Seidel, Bobby R.; Tracy, Donald B.; Griffiths, Vernon

    1991-01-01

    Molds for making metallic nuclear fuel rods are provided which present reduced risks to the environment by reducing radioactive waste. In one embodiment, the mold is consumable with the fuel rod, and in another embodiment, part of the mold can be re-used. Several molds can be arranged together in a cascaded manner, if desired, or several long cavities can be integrated in a monolithic multiple cavity re-usable mold.

  9. Double-clad nuclear-fuel safety rod

    DOE Patents [OSTI]

    McCarthy, W.H.; Atcheson, D.B.

    1981-12-30

    A device for shutting down a nuclear reactor during an undercooling or overpower event, whether or not the reactor's scram system operates properly. This is accomplished by double-clad fuel safety rods positioned at various locations throughout the reactor core, wherein melting of a secondary internal cladding of the rod allows the fuel column therein to shift from the reactor core to place the reactor in a subcritical condition.

  10. Fission gas release restrictor for breached fuel rod

    DOE Patents [OSTI]

    Kadambi, N. Prasad; Tilbrook, Roger W.; Spencer, Daniel R.; Schwallie, Ambrose L.

    1986-01-01

    In the event of a breach in the cladding of a rod in an operating liquid metal fast breeder reactor, the rapid release of high-pressure gas from the fission gas plenum may result in a gas blanketing of the breached rod and rods adjacent thereto which impairs the heat transfer to the liquid metal coolant. In order to control the release rate of fission gas in the event of a breached rod, the substantial portion of the conventional fission gas plenum is formed as a gas bottle means which includes a gas pervious means in a small portion thereof. During normal reactor operation, as the fission gas pressure gradually increases, the gas pressure interiorly of and exteriorly of the gas bottle means equalizes. In the event of a breach in the cladding, the gas pervious means in the gas bottle means constitutes a sufficient restriction to the rapid flow of gas therethrough that under maximum design pressure differential conditions, the fission gas flow through the breach will not significantly reduce the heat transfer from the affected rod and adjacent rods to the liquid metal heat transfer fluid flowing therebetween.

  11. EIS-0222: Amended Record of Decision | Department of Energy

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

    Amended Record of Decision EIS-0222: Amended Record of Decision Hanford Comprehensive Land-Use Plan In amending the 1999 ROD, DOE seeks to clarify two points: that when considering land-use proposals, DOE will use regulatory processes in addition to the implementing procedures in Chapter 6 of the HCP-EIS to ensure consistency with CLUP land-use designations, and that DOE will continue to apply the process under HCP-EIS Chapter 6 to modify or amend the CLUP, as needed. DOE/EIS-0222, Amended

  12. EIS-0460: Record of Decision | Department of Energy

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

    0: Record of Decision EIS-0460: Record of Decision FutureGen 2.0 Project, Morgan County, Illinois DOE has decided to proceed with cost-shared funding for the FutureGen 2.0 Project, providing the Alliance with $1 billion through cooperative agreements to support the planning, design, construction, and operation of a prototype power plant, including the capture, conveyance, and sequestration of carbon dioxide (CO2). EIS-0460-ROD-FRversion-2014.pdf (233.4 KB) More Documents & Publications

  13. Linear motion device and method for inserting and withdrawing control rods

    DOE Patents [OSTI]

    Smith, Jay E.

    1984-01-01

    A linear motion device, more specifically a control rod drive mechanism (CRDM) for inserting and withdrawing control rods into a reactor core, is capable of independently and sequentially positioning two sets of control rods with a single motor stator and rotor. The CRDM disclosed can control more than one control rod lead screw without incurring a substantial increase in the size of the mechanism.

  14. Letter: Quarry Residual Operable Unity (QROU) Draft Final Record of Decision (ROD).

    Office of Legacy Management (LM)

  15. Rod internal pressure quantification and distribution analysis using Frapcon

    SciTech Connect (OSTI)

    Bratton, Ryan N; Jessee, Matthew Anderson; Wieselquist, William A

    2015-09-01

    This report documents work performed supporting the Department of Energy (DOE) Office of Nuclear Energy (NE) Fuel Cycle Technologies Used Fuel Disposition Campaign (UFDC) under work breakdown structure element 1.02.08.10, ST Analysis. In particular, this report fulfills the M4 milestone M4FT- 15OR0810036, Quantify effects of power uncertainty on fuel assembly characteristics, within work package FT-15OR081003 ST Analysis-ORNL. This research was also supported by the Consortium for Advanced Simulation of Light Water Reactors (http://www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725. The discharge rod internal pressure (RIP) and cladding hoop stress (CHS) distributions are quantified for Watts Bar Nuclear Unit 1 (WBN1) fuel rods by modeling core cycle design data, operation data (including modeling significant trips and downpowers), and as-built fuel enrichments and densities of each fuel rod in FRAPCON-3.5. A methodology is developed which tracks inter-cycle assembly movements and assembly batch fabrication information to build individual FRAPCON inputs for each evaluated WBN1 fuel rod. An alternate model for the amount of helium released from the zirconium diboride (ZrB2) integral fuel burnable absorber (IFBA) layer is derived and applied to FRAPCON output data to quantify the RIP and CHS for these types of fuel rods. SCALE/Polaris is used to quantify fuel rodspecific spectral quantities and the amount of gaseous fission products produced in the fuel for use in FRAPCON inputs. Fuel rods with ZrB2 IFBA layers (i.e., IFBA rods) are determined to have RIP predictions that are elevated when compared to fuel rod without IFBA layers (i.e., standard rods) despite the fact that IFBA rods often have reduced fill pressures and annular fuel pellets. The primary contributor to elevated RIP predictions at burnups less than and greater than 30 GWd

  16. A Multi-Stage Wear Model for Grid-to-Rod Fretting of Nuclear Fuel Rods

    SciTech Connect (OSTI)

    Blau, Peter Julian

    2014-01-01

    The wear of fuel rod cladding against the supporting structures in the cores of pressurized water nuclear reactors (PWRs) is an important and potentially costly tribological issue. Grid-to-rod fretting (GTRF), as it is known, involves not only time-varying contact conditions, but also elevated temperatures, flowing hot water, aqueous tribo-corrosion, and the embrittling effects of neutron fluences. The multi-stage, closed-form analytical model described in this paper relies on published out-of-reactor wear and corrosion data and a set of simplifying assumptions to portray the conversion of frictional work into wear depth. The cladding material of interest is a zirconium-based alloy called Zircaloy-4, and the grid support is made of a harder and more wear-resistant material. Focus is on the wear of the cladding. The model involves an incubation stage, a surface oxide wear stage, and a base alloy wear stage. The wear coefficient, which is a measure of the efficiency of conversion of frictional work into wear damage, can change to reflect the evolving metallurgical condition of the alloy. Wear coefficients for Zircaloy-4 and for a polyphase zirconia layer were back-calculated for a range of times required to wear to a critical depth. Inputs for the model, like the friction coefficient, are taken from the tribology literature in lieu of in-reactor tribological data. Concepts of classical fretting were used as a basis, but are modified to enable the model to accommodate the complexities of the PWR environment. Factors like grid spring relaxation, pre-oxidation of the cladding, multiple oxide phases, gap formation, impact, and hydrogen embrittlement are part of the problem definition but uncertainties in their relative roles limits the ability to validate the model. Sample calculations of wear depth versus time in the cladding illustrate how GTRF wear might occur in a discontinuous fashion during months-long reactor operating cycles. A means to account for grid/rod gaps

  17. Microsoft Word - S04623_AMC ROD.doc

    Office of Legacy Management (LM)

    Office of Legacy Management Record of Decision for Amchitka Surface Closure, Alaska August ... U.S. Department of Energy Office of Legacy Management Record of Decision for ...

  18. Strategy for Fuel Rod Receipt, Characterization, Sample Allocation for the Demonstration Sister Rods

    SciTech Connect (OSTI)

    Marschman, Steven C.; Warmann, Stephan A.; Rusch, Chris

    2014-03-01

    , inert gas backfilling, and transfer to an Independent Spent Fuel Storage Installation (ISFSI) for multi-year storage. To document the initial condition of the used fuel prior to emplacement in a storage system, “sister ” fuel rods will be harvested and sent to a national laboratory for characterization and archival purposes. This report supports the demonstration by describing how sister rods will be shipped and received at a national laboratory, and recommending basic nondestructive and destructive analyses to assure the fuel rods are adequately characterized for UFDC work. For this report, a hub-and-spoke model is proposed, with one location serving as the hub for fuel rod receipt and characterization. In this model, fuel and/or clad would be sent to other locations when capabilities at the hub were inadequate or nonexistent. This model has been proposed to reduce DOE-NE’s obligation for waste cleanup and decontamination of equipment.

  19. Secretary Chu Postpones China Trip to Continue Work on BP Oil...

    Energy Savers [EERE]

    Postpones China Trip to Continue Work on BP Oil Spill Response Efforts Secretary Chu Postpones China Trip to Continue Work on BP Oil Spill Response Efforts May 21, 2010 - 12:00am ...

  20. Synthesis of carbon micro-rods via a solvothermal route

    SciTech Connect (OSTI)

    Mi Yuanzhu Hu Weibing; Dan Youmeng

    2009-04-02

    Novel carbon micro-rods with regular and uniform shape have been synthesized in high yield by magnesium acetate and n-butyl alcohol as the precursors via a solvothermal route. The resulting products were characterized by combined techniques including X-ray powder diffraction (XRD), scanning electron microscopy (SEM), transmission electron microscopy (TEM), energy-dispersive X-ray (EDX) and Raman spectroscopy. The carbon micro-rods exhibit diameters ranging from 500 nm to 1 {mu}m and up to 5-10 {mu}m in length. We have found that the optimal reaction conditions for the growth of the carbon micro-rods were 500 deg. C and 12 h.

  1. Simulations of optical sensors fabricated from metallic rods couplers

    SciTech Connect (OSTI)

    Singh, M. R.; Balakrishanan, Shankar

    2014-03-31

    We have developed the optical sensing mechanism of photonic couplers fabricated from the periodically arranged metallic rods. The metallic rod lattice is embedded between two dielectric material waveguides. This structure is called metallic coupler. Using the transfer matrix method, expressions for the reflection and transmission coefficients of electromagnetic wave propagating in waveguides have been obtained. We found that for certain energies, the electromagnetic wave is totally reflected from the coupler. Similarly, for a certain energy range the light is totally transmitted. It has also been found that by changing the periodicity of the metallic rods, the transmitted energy can be reflected. The periodicity of the metallic lattice can be modified by applying an external stress or pressure. In other words, the system can be used as stress and pressure sensors. The present findings can be used to make new types photonic sensors.

  2. Visual inspections of N Reactor horizontal control rod channels

    SciTech Connect (OSTI)

    Woodruff, E.M.

    1990-07-01

    This document describes the examination of thirteen horizontal control rod channels during the N Reactor Surveillance Program campaigns of 1987 and 1988. Traverses with miniature video cameras recorded the condition and relative positions of graphite blocks that form channel walls. The major conclusion confirms that no conditions exist that would prevent rod insertion. Where encroachment of broken filler block keys into the channel indicated a potential for rod motion impairment their removal by displacement into gaps between blocks was performed as preventive maintenance. In some locations a chisel was used in clearing keys lodged in gaps between tube blocks. Other observations include counts of safety balls observed in channels, breaks in tube blocks and Tee-bars and separations at Tee-bar junctions that results from axial graphite contraction. 15 refs., 18 figs., 6 tabs.

  3. Relocation and freezing of liquefied fuel-rod material. [PWR

    SciTech Connect (OSTI)

    Moore, R.L.; Broughton, J.M.

    1982-01-01

    Severe degraded core cooling accidents, such as occurred at TMI-2 can potentially reach temperatures in excess of cladding melting. When the molten cladding is in contact with UO/sub 2/ fuel, the UO/sub 2/ will be dissolved contributing significantly to the total amount of liquefied material flowing down the rod and eventually freezing in a lower, cooler region of the core. The primary objectives of this paper are to evaluate the relocation and freezing characteristics of liquefied fuel rod material over a wide range of system conditions, physical characteristics of the fuel rod and liquefied material, and material thermo-physical properties to determine the relative influence of the controlling parameters. First the analytical model used in the analysis is briefly reviewed. The results of the analyses are then presented and discussed, and this is followed by the conclusions.

  4. WA_02_034_BP_SOLAR_INTERNATIONAL_LLC_Waiver_of_Domestic_and_.pdf |

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

    Department of Energy 4_BP_SOLAR_INTERNATIONAL_LLC_Waiver_of_Domestic_and_.pdf WA_02_034_BP_SOLAR_INTERNATIONAL_LLC_Waiver_of_Domestic_and_.pdf (734.86 KB) More Documents & Publications WA_02_035_BP_SOLAR_INTERNATIONAL_Waiver_of_Domestic_and_Fore.pdf WA_06_016_BP_SOLAR_INTERNATIONAL_Waiver_of_Patent_Rights_Und

  5. WA_02_035_BP_SOLAR_INTERNATIONAL_Waiver_of_Domestic_and_Fore.pdf |

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

    Department of Energy 5_BP_SOLAR_INTERNATIONAL_Waiver_of_Domestic_and_Fore.pdf WA_02_035_BP_SOLAR_INTERNATIONAL_Waiver_of_Domestic_and_Fore.pdf (1.18 MB) More Documents & Publications WA_06_016_BP_SOLAR_INTERNATIONAL_Waiver_of_Patent_Rights_Und.pdf WA_02_034_BP_SOLAR_INTERNATIONAL_LLC_Waiver_of_Domestic_and_

  6. A new method for measurement of safety rod drop times

    SciTech Connect (OSTI)

    Pesic, M.; Stefanovic, D. ); Marinkovic, P. )

    1992-10-01

    In this paper, a new method for the accurate measurement of safety rod drop times is proposed. It is based on a fast electromagnetic transducer and an analog-to-digital converter (ADC) conected to a computer system. Evaluation of recorded data is conducted by a developed computer code. The first measurements performed at the HERBE fast-thermal RB reactor show that a relative uncertainty (confidence level 95%) of less than 6% can be achieved in determination of rod drop time (with time intervals ranging from 0.4-10.0 s). Further improvements in accuracy are possible.

  7. Nondestructive assay of sphere-pac fuel rods

    SciTech Connect (OSTI)

    Allen, E.J.; Angelini, P.; Baker, S.P.; Heck, J.L.; Mack, J.E.

    1981-03-01

    Nondestructive assay (NDA) methods were studied for application to sphere-pac fuel with a high gamma ray background. It was decided that the NDA method selected should be capable of measuring total fissile content of each fuel rod as well as determining the axial fissile distribution because assay techniques that employ detection of spontaneous or induced gamma ray emission are not practicable because of the high gamma ray background of candidate fuels. Therefore, methods employing neutron detection were studied for use with sphere-pac fuel rods.

  8. CW-5, PW- 1,3,6 ROD concerns

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

    DRAFT, DRAFT, DRAFT Compiled by: Shelley Cimon January 5, 2012 The following are submittals via e-mail and from the last RAP meeting to be considered as the committee begins further discussions on recommendations for the development of the 200 Area CW-5; 200 Area PW-1; 200Area PW-3; and PW-6 ROD Work Plan. 1) The Community Acceptability criteria discussion in the ROD failed to note the very strong objections to the PP from the HAB as well as the overwhelming public opposition voiced at community

  9. Lightweight piston-rod assembly for a reciprocating machine

    DOE Patents [OSTI]

    Corey, John A.; Walsh, Michael M.

    1986-01-01

    In a reciprocating machine, there is provided a hollow piston including a dome portion on one end and a base portion on the opposite end. The base portion includes a central bore into which a rod is hermetically fixed in radial and angular alignment. The extending end of the rod has a reduced diameter portion adapted to fit into the central bore of a second member such as a cross-head assembly, and to be secured thereto in radial and axial alignment with the piston.

  10. Well Placement Decision Process

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

    Well Placement Decision Process Well Placement Decision Process Determining where to place a well is a multi-step process. August 1, 2013 Investigation process for determining where to place a sentinel well Investigation process for determining where

  11. 2007 Wholesale Power Rate Adjustment Proceeding (WP-07) : Administrator's Final Record of Decision.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration.

    2006-07-01

    This Record of Decision (ROD) contains the decisions of the Bonneville Power Administration (BPA), based on the record compiled in this rate proceeding, with respect to the adoption of power rates for the three-year rate period commencing October 1, 2006, through September 30, 2009. This ''2007 Wholesale Power Rate Adjustment Proceeding'' is designed to establish replacement rate schedules and General Rate Schedule Provisions (GRSPs) for those that expire on September 30, 2006. This power rate case also establishes the General Transfer Agreement (GTA) Delivery Charge for the period of October 1, 2007, through September 30, 2009. BPA's Power Subscription Strategy and Record of Decision (Subscription Strategy), as well as other Agency processes, provide much of the policy context for this rate case and are described in Section 2. This ROD follows a full evidentiary hearing and briefing, including an Oral Argument before the BPA Administrator. Sections 3 through 18, including any appendices or attachments, present the issues raised by parties in this proceeding, the parties positions, BPA staff positions on the issues, BPA's evaluations of the positions, and the Administrator's decisions. Parties had the opportunity to file briefs on exceptions to the Draft ROD, before issuance of this Final Record of Decision.

  12. Feasibility study report for the 200-BP-1 operable unit

    SciTech Connect (OSTI)

    Not Available

    1993-06-01

    This feasibility study examines a range of alternatives and provides recommendations for selecting a preferred alternative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965--1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area, groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-levels of contamination with cesium-137, radium-226, strontium-90, thorium-228, and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9{times}10{sup {minus}5}.

  13. Fabrication of control rods for the High Flux Isotope Reactor

    SciTech Connect (OSTI)

    Sease, J.D.

    1998-03-01

    The High Flux Isotope Reactor (HFIR) is a research-type nuclear reactor that was designed and built in the early 1960s and has been in continuous operation since its initial criticality in 1965. Under current plans, the HFIR is expected to continue in operation until 2035. This report updates ORNL/TM-9365, Fabrication Procedure for HFIR Control Plates, which was mainly prepared in the early 1970's but was not issued until 1984, and reflects process changes, lessons learned in the latest control rod fabrication campaign, and suggested process improvements to be considered in future campaigns. Most of the personnel involved with the initial development of the processes and in part campaigns have retired or will retire soon. Because their unlikely availability in future campaigns, emphasis has been placed on providing some explanation of why the processes were selected and some discussions about the importance of controlling critical process parameters. Contained in this report is a description of the function of control rods in the reactor, the brief history of the development of control rod fabrication processes, and a description of procedures used in the fabrication of control rods. A listing of the controlled documents and procedures used in the last fabrication campaigns is referenced in Appendix A.

  14. Simulation of thermal-well sucker-rod pumping

    SciTech Connect (OSTI)

    Wong, A. (Alberta Oil Sands Technology and Research Authority (CA)); Sudol, T.A. (Alberta Research Council (CA))

    1992-05-01

    A major problem experienced in pumping thermal wells is low volumetric efficiencies resulting from steam and noncondensable gas interference. This paper examines the results of physical simulations performed on a full-scale sucker-rod pump test facility and numerical simulations that used an equation of state (EOS) to predict theoretical volumetric pump efficiencies.

  15. Waterside corrosion of Zircaloy fuel rods. Final report. [PWR

    SciTech Connect (OSTI)

    Garzarolli, F.; Jung, W.; Schoenfeld, H.; Garde, A.M.; Parry, G.W.; Smerd, P.G.

    1982-12-01

    There is an economic incentive to extend average fuel-rod-discharge burnup to about 50 GWd/t. For these higher burnups it is necessary to know if increased waterside corrosion of the cladding will influence fuel-rod performance. For this reason, EPRI sponsored a joint program with C-E and KWU with the objective of investigating PWR waterside corrosion. This final report presents and discusses the results of various subtasks that comprised this project. In the review of corrosion data and models in the literature it was concluded that the PWR environment enhances the corrosion rate by about three times that expected from ex-reactor tests. A large number of fuel rods were characterized in both spent-fuel-pool and hot-cell campaigns. Chemical, physical and microstructural attributes of irradiated and unirradiated oxide films were measured. These included determinations of chemical composition, crystal structure, microstructure, density, specific heat, thermal conductivity, and post-irradiation autoclave corrosion behavior. Procedures used to calculate the fuel-rod surface temperature were reviewed. A model has been developed to predict in-reactor corrosion behavior.

  16. Record of Decision Tank Farm Soil and INTEC Groundwater

    SciTech Connect (OSTI)

    L. S. Cahn

    2007-05-01

    This decision document presents the selected remedy for Operable Unit (OU) 3-14 tank farm soil and groundwater at the Idaho Nuclear Technology and Engineering Center (INTEC), which is located on the Idaho National Laboratory (INL) Site. The tank farm was initially evaluated in the OU 3-13 Record of Decision (ROD), and it was determined that additional information was needed to make a final decision. Additional information has been obtained on the nature and extent of contamination in the tank farm and on the impact of groundwater. The selected remedy was chosen in accordance with the Comprehensive Environmental Response, Liability and Compensation Act of 1980 (CERCLA) (42 USC 9601 et seq.), as amended by the Superfund Amendments and Reauthorization Act of 1986 (Public Law 99-499) and the National Oil and Hazardous Substances Pollution Contingency Plan (40 CFR 300). The selected remedy is intended to be the final action for tank far soil and groundwater at INTEC.

  17. Rod-shaped Nuclei at Extreme Spin and Isospin (Journal Article...

    Office of Scientific and Technical Information (OSTI)

    Rod-shaped Nuclei at Extreme Spin and Isospin Citation Details In-Document Search Title: Rod-shaped Nuclei at Extreme Spin and Isospin Authors: Zhao, P. W. ; Itagaki, N. ; Meng, J. ...

  18. Rod-shaped Nuclei at Extreme Spin and Isospin (Journal Article...

    Office of Scientific and Technical Information (OSTI)

    Rod-shaped Nuclei at Extreme Spin and Isospin Title: Rod-shaped Nuclei at Extreme Spin and Isospin Authors: Zhao, P. W. ; Itagaki, N. ; Meng, J. Publication Date: 2015-07-08 OSTI ...

  19. Fluid Dynamics in Sucker Rod Pumps Cutler, R.P.; Mansure, A.J...

    Office of Scientific and Technical Information (OSTI)

    Fluid Dynamics in Sucker Rod Pumps Cutler, R.P.; Mansure, A.J. 02 PETROLEUM; FLOW MODELS; MATHEMATICAL MODELS; OIL WELLS; PETROLEUM; ROD PUMPS; SANDIA NATIONAL LABORATORIES Sucker...

  20. A VU governance process applied to a Bison Fuel Rod Validation...

    Office of Scientific and Technical Information (OSTI)

    A VU governance process applied to a Bison Fuel Rod Validation exercise. Citation Details In-Document Search Title: A VU governance process applied to a Bison Fuel Rod Validation ...

  1. Fluid Dynamics in Sucker Rod Pumps (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Sucker rod pumps are installed in approximately 90% of all oil wells in the U.S. Although ... Subject: 02 PETROLEUM; FLOW MODELS; MATHEMATICAL MODELS; OIL WELLS; PETROLEUM; ROD PUMPS; ...

  2. Superfund Record of Decision (EPA Region 2): Love Canal (93rd Street School), Niagara County, City of Niagara Falls, NY. (Third remedial action), (amendment), May 1991. Final report

    SciTech Connect (OSTI)

    Not Available

    1991-05-15

    The Love Canal (93rd Street) site is an inactive hazardous waste site located in Niagara Falls, New York. The 19-acre 93rd Street School site, one of several operable units for the Love Canal Superfund site, is the focus of the Record of Decision (ROD). The fill material is reported to contain fly ash and BHC (a pesticide) waste. The ROD amends the 1988 ROD, and addresses final remediation of onsite contaminated soil through excavation and offsite disposal. The primary contaminants of concern affecting the soil are VOCs including toluene and xylenes; other organics including PAHs and pesticides; and metals including arsenic, chromium, and lead.

  3. Reversible Bending Fatigue Testing on Zry-4 Surrogate Rods

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Bevard, Bruce Balkcom; Howard, Rob L

    2014-01-01

    Testing high-burnup spent nuclear fuel (SNF) presents many challenges in areas such as specimen preparation, specimen installation, mechanical loading, load control, measurements, data acquisition, and specimen disposal because these tasks are complicated by the radioactivity of the test specimens. Research and comparison studies conducted at Oak Ridge National Laboratory (ORNL) resulted in a new concept in 2010 for a U-frame testing setup on which to perform hot-cell reversible bending fatigue testing. Subsequently, the three-dimensional finite element analysis and the engineering design of components were completed. In 2013 the ORNL team finalized the upgrade of the U-frame testing setup and the integration of the U-frame setup into a Bose dual linear motor test bench to develop a cyclic integrated reversible-bending fatigue tester (CIRFT). A final check was conducted on the CIRFT test system in August 2013, and the CIRFT was installed in the hot cell in September 2013 to evaluate both the static and dynamic mechanical response of SNF rods under simulated loads. The fatigue responses of Zircaloy-4 (Zry-4) cladding and the role of pellet pellet and pellet clad interactions are critical to SNF vibration integrity, but such data are not available due to the unavailability of an effective testing system. While the deployment of the developed CIRFT test system in a hot cell will provide the opportunity to generate the data, the use of a surrogate rod has proven quite effective in identifying the underlying deformation mechanism of an SNF composite rod under an equivalent loading condition. This paper presents the experimental results of using surrogate rods under CIRFT reversible cyclic loading. Specifically, monotonic and cyclic bending tests were conducted on surrogate rods made of a Zry-4 tube and alumina pellet inserts, both with and without an epoxy bond.

  4. DOE Amends Decision for the Remediation of the Moab Uranium Mill Tailings

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

    in Moab, Utah | Department of Energy Amends Decision for the Remediation of the Moab Uranium Mill Tailings in Moab, Utah DOE Amends Decision for the Remediation of the Moab Uranium Mill Tailings in Moab, Utah February 29, 2008 - 11:43am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced an amendment to its 2005 Record of Decision (ROD) for the Moab Uranium Mill Tailings Remedial Action (UMTRA) Project to allow for the use of truck or rail in transporting residual

  5. Method of increasing magnetostrictive response of rare earth-iron alloy rods

    DOE Patents [OSTI]

    Verhoeven, J.D.; McMasters, O.D.; Gibson, E.D.; Ostenson, J.E.; Finnemore, D.K.

    1989-04-04

    This invention comprises a method of increasing the magnetostrictive response of rare earth-iron (RFe) magnetostrictive alloy rods by a thermal-magnetic treatment. The rod is heated to a temperature above its Curie temperature, viz. from 400 to 600 C; and, while the rod is at that temperature, a magnetic field is directionally applied and maintained while the rod is cooled, at least below its Curie temperature. 2 figs.

  6. Method of increasing magnetostrictive response of rare earth-iron alloy rods

    DOE Patents [OSTI]

    Verhoeven, John D.; McMasters, O. Dale; Gibson, Edwin D.; Ostenson, Jerome E.; Finnemore, Douglas K.

    1989-04-04

    This invention comprises a method of increasing the magnetostrictive response of rare earth-iron (RFe) magnetostrictive alloy rods by a thermal-magnetic treatment. The rod is heated to a temperature above its Curie temperature, viz. from 400.degree. to 600.degree. C.; and, while the rod is at that temperature, a magnetic field is directionally applied and maintained while the rod is cooled, at least below its Curie temperature.

  7. Control rod system useable for fuel handling in a gas-cooled nuclear reactor

    DOE Patents [OSTI]

    Spurrier, Francis R.

    1976-11-30

    A control rod and its associated drive are used to elevate a complete stack of fuel blocks to a position above the core of a gas-cooled nuclear reactor. A fuel-handling machine grasps the control rod and the drive is unlatched from the rod. The stack and rod are transferred out of the reactor, or to a new location in the reactor, by the fuel-handling machine.

  8. Linear motion device and method for inserting and withdrawing control rods

    DOE Patents [OSTI]

    Smith, J.E.

    Disclosed is a linear motion device and more specifically a control rod drive mechanism (CRDM) for inserting and withdrawing control rods into a reactor core. The CRDM and method disclosed is capable of independently and sequentially positioning two sets of control rods with a single motor stator and rotor. The CRDM disclosed can control more than one control rod lead screw without incurring a substantial increase in the size of the mechanism.

  9. Decision Summaries | Department of Energy

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

    Information Center » Decision Summaries Decision Summaries July 29, 2016 Summary of Decisions - July 25, 2016 - July 29, 2016 Decisions were issued on: - Personnel Security (10 CFR Part 710) - Freedom of Information Act Appeal July 22, 2016 Summary of Decisions - July 18, 2016 - July 22, 2016 Decisions were issued on: - Personnel Security (10 CFR Part 710) - Freedom of Information Act Appeal July 15, 2016 Summary of Decisions - July 11, 2016 - July 15, 2016 Decisions were issued on: - Personnel

  10. Ex post power economic analysis of record of decision operational restrictions at Glen Canyon Dam.

    SciTech Connect (OSTI)

    Veselka, T. D.; Poch, L. A.; Palmer, C. S.; Loftin, S.; Osiek, B; Decision and Information Sciences; Western Area Power Administration

    2010-07-31

    On October 9, 1996, Bruce Babbitt, then-Secretary of the U.S. Department of the Interior signed the Record of Decision (ROD) on operating criteria for the Glen Canyon Dam (GCD). Criteria selected were based on the Modified Low Fluctuating Flow (MLFF) Alternative as described in the Operation of Glen Canyon Dam, Colorado River Storage Project, Arizona, Final Environmental Impact Statement (EIS) (Reclamation 1995). These restrictions reduced the operating flexibility of the hydroelectric power plant and therefore its economic value. The EIS provided impact information to support the ROD, including an analysis of operating criteria alternatives on power system economics. This ex post study reevaluates ROD power economic impacts and compares these results to the economic analysis performed prior (ex ante) to the ROD for the MLFF Alternative. On the basis of the methodology used in the ex ante analysis, anticipated annual economic impacts of the ROD were estimated to range from approximately $15.1 million to $44.2 million in terms of 1991 dollars ($1991). This ex post analysis incorporates historical events that took place between 1997 and 2005, including the evolution of power markets in the Western Electricity Coordinating Council as reflected in market prices for capacity and energy. Prompted by ROD operational restrictions, this analysis also incorporates a decision made by the Western Area Power Administration to modify commitments that it made to its customers. Simulated operations of GCD were based on the premise that hourly production patterns would maximize the economic value of the hydropower resource. On the basis of this assumption, it was estimated that economic impacts were on average $26.3 million in $1991, or $39 million in $2009.

  11. Record of Decision Available

    Broader source: Energy.gov [DOE]

    DOE has recently published its Record of Decision announcing and explaining DOE’s chosen project alternative and describing any commitments for mitigating potential environmental impacts. The NEPA...

  12. A rod pumping system to reduce lifting costs

    SciTech Connect (OSTI)

    Tait, H.C.; Hamilton, R.M.

    1983-02-01

    Rising costs of artificial lift operations are a growing concern to producers in maintaining efficient and profitable performance. A new long stroke sucker rod pumping system has been developed to minimize the impact of these rising costs. This new system results from a broad development project involving evaluation of all system components. Performance results to date confirm achievement of reduced overall operating costs as a result of the performance characteristics of this system.

  13. Tapered laser rods as a means of minimizing the path length of trapped barrel mode rays

    DOE Patents [OSTI]

    Beach, Raymond J.; Honea, Eric C.; Payne, Stephen A.; Mercer, Ian; Perry, Michael D.

    2005-08-30

    By tapering the diameter of a flanged barrel laser rod over its length, the maximum trapped path length of a barrel mode can be dramatically reduced, thereby reducing the ability of the trapped spontaneous emission to negatively impact laser performance through amplified spontaneous emission (ASE). Laser rods with polished barrels and flanged end caps have found increasing application in diode array end-pumped laser systems. The polished barrel of the rod serves to confine diode array pump light within the rod. In systems utilizing an end-pumping geometry and such polished barrel laser rods, the pump light that is introduced into one or both ends of the laser rod, is ducted down the length of the rod via the total internal reflections (TIRs) that occur when the light strikes the rod's barrel. A disadvantage of using polished barrel laser rods is that such rods are very susceptible to barrel mode paths that can trap spontaneous emission over long path lengths. This trapped spontaneous emission can then be amplified through stimulated emission resulting in a situation where the stored energy available to the desired lasing mode is effectively depleted, which then negatively impacts the laser's performance, a result that is effectively reduced by introducing a taper onto the laser rod.

  14. Techniques and equipment for assessing the structural integrity of subterranean tower anchor rods

    DOE Patents [OSTI]

    Hinz, William R.; Parker, Matthew J.

    2001-01-01

    Techniques and equipment for evaluating structural integrity of buried anchor rods in situ are disclosed. The techniques avoid excavation of soil and avoid, or at least reduce, the possibility of damage to the rods or the concrete in which they may be embedded when evaluations are conducted. Instead, ultrasonic energy is transmitted through the rod from a portable transducer, and returned energy (in either or both of direct and mode-converted states) may be analyzed to assist in detecting flaws, corrosion, wastage, or other degradation of the rod. Data from a field evaluation may be compared with baseline data maintained either for a specific rod or for rods of similar composition and length (or both), and periodic field evaluations of a rod may be used to analyze trends in its structure over time.

  15. Microstructure of electrolytically deuterium-loaded palladium rods

    SciTech Connect (OSTI)

    Chen, S.K.; Wan, C.M.; Liu, E.H.; Chu, S.B.; Liang, C.Y.; Yuan, L.J.; Wan, C.C.

    1996-03-01

    Microstructural studies were conducted on palladium specimens that were taken from ambient-temperature heavy water and elevated temperature molten-salt electrolytic experiments. Both scanning electron microscopy (SEM) and transmission electron microscopy (TEM) were used to investigate the surface and interior portions of these specimens. A subgrain structure could be observed by SEM on the surface along the longitudinal direction and on the surface taken from the cross section of the deuterium-charged specimen rod; the thermoelectrochemical etching process was consequently applied to the deuterium-charged specimen rod. A TEM bright field and selected area diffraction pattern technique verified that dislocation cells and subgrains exist in the deuterium-charged specimens. If cold fusion effects exist in the palladium microstructure, which consists of dislocation cells and subgrains, understanding the cold fusion phenomenon in the microstructure is necessary, and pursuant to this understanding, electrolytic experiments of a palladium rod in molten salt and of heavy water may be useful. 4 refs., 8 figs.

  16. Hybrid nuclear reactor grey rod to obtain required reactivity worth

    DOE Patents [OSTI]

    Miller, John V.; Carlson, William R.; Yarbrough, Michael B.

    1991-01-01

    Hybrid nuclear reactor grey rods are described, wherein geometric combinations of relatively weak neutron absorber materials such as stainless steel, zirconium or INCONEL, and relatively strong neutron absorber materials, such as hafnium, silver-indium cadmium and boron carbide, are used to obtain the reactivity worths required to reach zero boron change load follow. One embodiment includes a grey rod which has combinations of weak and strong neutron absorber pellets in a stainless steel cladding. The respective pellets can be of differing heights. A second embodiment includes a grey rod with a relatively thick stainless steel cladding receiving relatively strong neutron absorber pellets only. A third embodiment includes annular relatively weak netron absorber pellets with a smaller diameter pellet of relatively strong absorber material contained within the aperture of each relatively weak absorber pellet. The fourth embodiment includes pellets made of a homogeneous alloy of hafnium and a relatively weak absorber material, with the percentage of hafnium chosen to obtain the desired reactivity worth.

  17. DOE Makes Public Detailed Information on the BP Oil Spill | Department of

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

    Energy Public Detailed Information on the BP Oil Spill DOE Makes Public Detailed Information on the BP Oil Spill June 8, 2010 - 12:00am Addthis WASHINGTON - As part of the Obama Administration's ongoing commitment to transparency surrounding the response to the BP oil spill, U.S. Energy Secretary Steven Chu announced today that Department is providing online access to schematics, pressure tests, diagnostic results and other data about the malfunctioning blowout preventer. Secretary Chu

  18. WA_06_016_BP_SOLAR_INTERNATIONAL_Waiver_of_Patent_Rights_Und.pdf |

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

    Department of Energy 6_016_BP_SOLAR_INTERNATIONAL_Waiver_of_Patent_Rights_Und.pdf WA_06_016_BP_SOLAR_INTERNATIONAL_Waiver_of_Patent_Rights_Und.pdf (1.22 MB) More Documents & Publications WA_07_016_OSRAM_SYLVANIA_Waiver_of_Patent_Rights_Under_a_DOE.pdf Advance Patent Waiver W(A)2005-060 WA_02_035_BP_SOLAR_INTERNATIONAL_Waiver_of_Domestic_and_Fore

  19. Power Subscription Strategy: Administrator`s Record of Decision.

    SciTech Connect (OSTI)

    United States. Bonneville Power Administration

    1998-12-01

    The Bonneville Power Administration (BPA) has decided to adopt a Power Subscription Strategy for entering into new power sales contracts with its Pacific Northwest customers. The Strategy equitably distributes the electric power generated by the Federal Columbia River Power System (FCRPS) within the framework of existing law. The Power Subscription Strategy addresses the availability of power; describes power products; lays out strategies for pricing, including risk management; and discusses contract elements. In proceeding with this Subscription Strategy, BPA is guided by and committed to the Fish and Wildlife funding Principles for the BPA announced by the Vice President of the US in September 1998. This Record of Decision (ROD) addresses the issues raised by commenters who responded to BPA`s Power Subscription Strategy Proposal during and after the comment period that began with the release of the Proposal on September 18, 1998. The ROD is organized in approximately the same way as the Proposal and the Power Subscription Strategy that BPA developed based on the comments received. Abbreviations of party names used in citations appear in the section just preceding this introduction; a list of all the commenters follows the text of the ROD.

  20. Photo Release: U.S. Energy Secretary Chu at BP Command Center in Houston |

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

    Department of Energy Release: U.S. Energy Secretary Chu at BP Command Center in Houston Photo Release: U.S. Energy Secretary Chu at BP Command Center in Houston May 28, 2010 - 12:00am Addthis Washington D.C. --- At the request of President Obama, U.S. Energy Secretary Steven Chu has been helping oversee BP's "top kill" efforts from the BP Command Center in Houston. Below are two photographs from this week. Photo credit: Department of Energy. Secretary Steven Chu and National

  1. Microsoft PowerPoint - BP 2030 Outlook (EIA conference Apr 2011).ppt

    U.S. Energy Information Administration (EIA) Indexed Site

    BP Energy Outlook 2030 Washington, DC 26 April 2011 Energy Outlook 2030 2 © BP 2011 Global trends US particulars What can bend the trend? Outline Energy Outlook 2030 3 © BP 2011 Non-OECD economies drive consumption growth Billion toe Billion toe 0 2 4 6 8 10 12 14 16 18 1990 2000 2010 2020 2030 OECD Non-OECD 0 2 4 6 8 10 12 14 16 18 1990 2000 2010 2020 2030 Renewables Hydro Nuclear Coal Gas Oil * * Includes biofuels Energy Outlook 2030 4 © BP 2011 Gas and renewables win as fuel shares

  2. H:\cindy_pratt\hlw rod.tif

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

    RECORD OF DECISION For The Idaho High- Level Waste and Facilities Disposition Final Environmental Impact Statement December 2005 United States Department of Energy 1 U.S. DEPARTMENT OF ENERGY Office of Environmental Management Record of Decision for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement SUMMARY: DOE is making decisions pursuant to the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (Final EIS)

  3. CHPE_ROD_FR_10-01-2014.pdf

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

    258 Federal Register / Vol. 79, No. 190 / Wednesday, October 1, 2014 / Notices DEPARTMENT OF ENERGY [OE Docket No. PP-362] Record of Decision for Issuing a Presidential Permit to Champlain Hudson Power Express, Inc., for the Champlain Hudson Power Express Transmission Line Project AGENCY: Office of Electricity Delivery and Energy Reliability, U.S. Department of Energy. ACTION: Record of decision. SUMMARY: The Department of Energy (DOE) announces its decision to issue a Presidential permit to

  4. Microsoft Word - FINAL ROD - Port Townsend FINAL BLACKLINE 11...

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

    AUTHENTICATED EXTENSION AMENDMENT TO PORT TOWNSEND PAPER CORPORATION'S POWER SALES AGREEMENT ADMINISTRATOR'S RECORD OF DECISION November 2, 2012 i TABLE OF CONTENTS I. INTRODUCTION...

  5. Baseline Risk Assessment for 200-BP-5 Groundwater Operable Unit |

    Office of Environmental Management (EM)

    BIA Providers Conference Energy Track BIA Providers Conference Energy Track December 2, 2015 - 10:00am Addthis Dec. 2-3, 2015 Anchorage, Alaska Dena'ina Center The DOE Office of Indian Energy offered an energy track at the 25th Annual BIA Tribal Providers Conference Dec. 2-3, 2015. The track featured breakout sessions on a variety of topics to help tribal energy leaders and professionals make informed decisions about energy projects. Download agenda and presentations. Addthis Related Articles

  6. Rod consolidation of RG and E's (Rochester Gas and Electric Corporation) spent PWR (pressurized water reactor) fuel

    SciTech Connect (OSTI)

    Bailey, W.J.

    1987-05-01

    The rod consolidation demonstration involved pulling the fuel rods from five fuel assemblies from Unit 1 of RG and E's R.E. Ginna Nuclear Power Plant. Slow and careful rod pulling efforts were used for the first and second fuel assemblies. Rod pulling then proceeded smoothly and rapidly after some minor modifications were made to the UST and D consolidation equipment. The compaction ratios attained ranged from 1.85 to 2.00 (rods with collapsed cladding were replaced by dummy rods in one fuel assembly to demonstrate the 2:1 compaction ratio capability). This demonstration involved 895 PWR fuel rods, among which there were some known defective rods (over 50 had collapsed cladding); no rods were broken or dropped during the demonstration. However, one of the rods with collapsed cladding unexplainably broke during handling operations (i.e., reconfiguration in the failed fuel canister), subsequent to the rod consolidation demonstration. The broken rod created no facility problems; the pieces were encapsulated for subsequent storage. Another broken rod was found during postdemonstration cutting operations on the nonfuel-bearing structural components from the five assemblies; evidence indicates it was broken prior to any rod consolidation operations. During the demonstration, burnish-type lines or scratches were visible on the rods that were pulled; however, experience indicates that such lines are generally produced when rods are pulled (or pushed) through the spacer grids. Rods with collapsed cladding would not enter the funnel (the transition device between the fuel assembly and the canister that aids in obtaining high compaction ratios). Reforming of the flattened areas of the cladding on those rods was attempted to make the rod cross sections more nearly circular; some of the reformed rods passed through the funnel and into the canister.

  7. Air Sparging Decision Tool

    Energy Science and Technology Software Center (OSTI)

    1996-06-10

    The Air Sparging Decision Tool is a computer decision aid to help environmental managers and field practitioners in evaluating the applicability of air sparging to a wide range of sites and for refining the operation of air sparging systems. The program provides tools for the practitioner to develop the conceptual design for an air sparging system suitable for the identified site. The Tool provides a model of the decision making process, not a detailed designmore » of air sparging systems. The Tool will quickly and cost effectively assist the practitioner in screening for applicability of the technology at a proposed site.« less

  8. Record of Decision Issued for the FutureGen 2.0 Project

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) has decided to provide financial assistance to the FutureGen Industrial Alliance (the Alliance) for the FutureGen 2.0 Project. DOE will provide approximately $1 billion of in cost-shared funding (the majority of which was appropriated under the American Recovery and Reinvestment Act) through cooperative agreements with the Alliance, as described in DOE's Record of Decision (ROD).

  9. Rewetting of a low superheated rod with saturated water

    SciTech Connect (OSTI)

    Portillo, O.; Reyes, R.; Wayner, P.C. Jr.

    1999-07-01

    The study of the rewetting of a superheated surface has application in several technological fields. It is related to the control mechanism for loss of coolant accident (LOCA) in nuclear reactors. An adsorption model as the precursory mechanism for rewetting of a superheated surface is extended from its application to non-polar liquids to a polar fluid, and modeling calculations are compared with experimental data found in the literature. The adsorption model is based on interfacial forces acting at the tip of the rewetting front, the three-phase region. In this region, solid, liquid and vapor interfaces generate a contact angle that depends on the degree of superheat and describes the velocity of rewetting. The contact angle is a function of interfacial forces calculated through the disjoining pressure of the adsorbed film precursory of the rewetting. The influences of van der Waals and electrostatic intermolecular forces in the film thickness are analyzed. The authors find that the order of magnitude of the film thickness in the controlling region is of a few angstroms: thus, only van der Waals intermolecular forces define the interactions. For the prediction of the velocity of rewetting the temperature profile along the rod's surface is required and a one-dimensional and a two-dimensional heat conduction balances are solved. The thermophysical properties in the adsorption model are predicted by ASPEN PLUS data bank and from ASME steam tables. Variations of the predicted values have a strong influence on the results. The surface boundary condition on the rod contains an evaporative heat transfer coefficient that is calculated from the fitted experimental rewetting velocities and the two-dimensional temperature field in the rod. Using this calculation scheme the values of the evaporative heat transfer coefficient are obtained in the normal range of values. Therefore the adsorption model gives results that are consistent with experimental observations.

  10. Superfund record of decision (EPA Region 2): Renora, Inc., operable unit 2, Edison Township, Middlesex County, NJ, September 30, 1994

    SciTech Connect (OSTI)

    1995-04-01

    This Record of Decision (ROD) Amendment documents the U.S. Environmental Protection Agency`s (EPA`s) selection of a modified remedy for the Renora, Inc. site. The initial ROD for the Renora site included the excavation and off-site disposal of soils contaminated with polychlorinated biphenyls, (PCBs) and biodegradation of PAH-contaminated soils. The first phase of the remedy, involving the PCB-contaminated soils, has been completed. Therefore, the remedy will be modified to include the removal of surface soils contaminated with PAHs.

  11. A rod pumping system for California lift requirements

    SciTech Connect (OSTI)

    Tait, H.C.

    1983-03-01

    Artificial lift requirements in California oil fields cover a full range of demanding operating and environmental conditions. These extend from typical demands of lifting depth and volume, to atypical requirements of heavy crude, thermal enhancement and the unique environmental restrictions of our urban sites and offshore fields. A new rod pumping system has been developed which deals with these requirements. Performance results to date confirm reduced power consumption and improved pumping performance. Combined with the compact equipment size, these characteristics appear to offer benefits to California operators.

  12. Automatic inspection system for nuclear fuel pellets or rods

    DOE Patents [OSTI]

    Miller, Jr., William H.; Sease, John D.; Hamel, William R.; Bradley, Ronnie A.

    1978-01-01

    An automatic inspection system is provided for determining surface defects on cylindrical objects such as nuclear fuel pellets or rods. The active element of the system is a compound ring having a plurality of pneumatic jet units directed into a central bore. These jet units are connected to provide multiple circuits, each circuit being provided with a pressure sensor. The outputs of the sensors are fed to a comparator circuit whereby a signal is generated when the difference of pressure between pneumatic circuits, caused by a defect, exceeds a pre-set amount. This signal may be used to divert the piece being inspected into a "reject" storage bin or the like.

  13. Fail-safe storage rack for irradiated fuel rod assemblies

    DOE Patents [OSTI]

    Lewis, Donald R. (Pocatello, ID)

    1993-01-01

    A fail-safe storage rack is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

  14. Fail-safe storage rack for irradiated fuel rod assemblies

    DOE Patents [OSTI]

    Lewis, D.R.

    1993-03-23

    A fail-safe storage rack is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

  15. Decision Summaries | Department of Energy

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

    January 16, 2014 Summary of Decisions - December 30, 2013 - January 3, 2014 Decisions were issued on: - Privacy Act Appeal January 10, 2014 Summary of Decisions - MM DD YYYY - MM...

  16. Decision Analysis for EGS

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

    Decision Analysis for EGS Herbert H. Einstein Massachusetts Institute of Technology April 22, 2013 This presentation does not contain any proprietary confidential, or otherwise restricted information. Insert photo of your choice MIT 2 | US DOE Geothermal Office eere.energy.gov DECISION ANALYSIS FOR EGS Relevance/Impact of Research OBJECTIVES CHALLENGE - How to develop EGS projects that are affected by many unknown and variable factors. Uncertainties, particularly those related to the subsurface,

  17. Report on the evaluation of the tritium producing burnable absorber rod lead test assembly. Revision 1

    SciTech Connect (OSTI)

    1997-03-01

    This report describes the design and fabrication requirements for a tritium-producing burnable absorber rod lead test assembly and evaluates the safety issues associated with tritium-producing burnable absorber rod irradiation on the operation of a commercial light water reactor. The report provides an evaluation of the tritium-producing burnable absorber rod design and concludes that irradiation can be performed within U.S. Nuclear Regulatory Commission regulations applicable to a commercial pressurized light water reactor.

  18. Considerations for sensitivity analysis, uncertainty quantification, and data assimilation for grid-to-rod fretting

    SciTech Connect (OSTI)

    Michael Pernice

    2012-10-01

    Grid-to-rod fretting is the leading cause of fuel failures in pressurized water reactors, and is one of the challenge problems being addressed by the Consortium for Advanced Simulation of Light Water Reactors to guide its efforts to develop a virtual reactor environment. Prior and current efforts in modeling and simulation of grid-to-rod fretting are discussed. Sources of uncertainty in grid-to-rod fretting are also described.

  19. Reduction of ahead of schedule anodes through anode rod quality control

    SciTech Connect (OSTI)

    Baillargeon, F.; Menard, Y.; Perron, C.; Proulx, A.L.

    1996-10-01

    One of the major causes of ahead of schedule anodes reported in recent years by the P155 potroom operation was related to the inherent weakness in the rod welded joints. The development and implementation of an apparatus and procedure to measure, detect and reject the faulty rods prior to anode rodding, will be presented and discussed. The technology has not only significantly reduced the number of ahead of schedule anodes, it has also provided useful information concerning other process improvements.

  20. Method of bundling rods so as to form an optical fiber preform

    DOE Patents [OSTI]

    Kliner, Dahv A. V. (San Ramon, CA); Koplow, Jeffery P. (Washington, DC)

    2004-03-30

    The present invention provides a simple method for fabricating fiber-optic glass preforms having complex refractive index configurations and/or dopant distributions in a radial direction with a high degree of accuracy and precision. The method teaches bundling together a plurality of glass rods of specific physical, chemical, or optical properties and wherein the rod bundle is fused in a manner that maintains the cross-sectional composition and refractive-index profiles established by the position of the rods.

  1. Final Report: Contractor Readiness Assessment (CRA) for TREAT Fuel Movement and Control Rod Drives Isolation

    SciTech Connect (OSTI)

    Rowsell, David Leon

    2015-06-01

    This report documents the Contractor Readiness Assessment (CRA) for TREAT Fuel Movement and Control Rod Drives Isolation. The review followed the approved Plan of Action (POA) and Implementation Plan (IP) using the identified core requirements. The activity was limited scope focusing on the control rod drives functional isolation and fuel element movement. The purpose of this review is to ensure the facility's readiness to move fuel elements thus supporting inspection and functionally isolate the control rod drives to maintain the required shutdown margin.

  2. Decision Summaries | Department of Energy

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

    December 21, 2012 Summary of Decisions - December 17, 2012 - December 21, 2012 Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)...

  3. Decision Summaries | Department of Energy

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

    January 16, 2015 Summary of Decisions - January 12, 2015 - January 16, 2015 Decisions were issued on: - Freedom of Information Act Appeal - Refund Proceeding January 9, 2015...

  4. A VU governance process applied to a Bison Fuel Rod Validation...

    Office of Scientific and Technical Information (OSTI)

    Title: A VU governance process applied to a Bison Fuel Rod Validation exercise. Authors: Knupp, Patrick Michael Publication Date: 2012-09-01 OSTI Identifier: 1055887 Report ...

  5. Detection and mitigating rod drive control system degradation in Westinghouse PWRs

    SciTech Connect (OSTI)

    Gunther, W.; Sullivan, K.

    1990-01-01

    A study of the effects of aging on the Westinghouse Control Rod Drive (CRD) System was performed as part of the US NRC's Nuclear Plant aging Research (NPAR) Program. For the study, the CRD system boundary includes the power and logic cabinets associated with the manual control rod movement, and the control rod mechanism itself. The aging-related degradation of the interconnecting cables and connectors and the rod position indicating system also were considered. This paper presents the results of that study pertaining to the electrical and instrumentation portions of the CRD system including ways to detect and mitigate system degradation.

  6. Control of Prestressing Force in Rod for Reducing Bending in Beams

    SciTech Connect (OSTI)

    Wong, M. B.

    2010-05-21

    This paper presents a method to determine the prestressing force required in a rod for reducing the bending effects in a beam. The rod is positioned underneath the beam such that the prestressing force is counteracting the effects of beam bending. It has been found that the prestressing force may also increase the bending as a result of P-delta effect. Therefore, the choice of both the prestressing force and the rod eccentricity from the beam axis is important in determining the appropriate actions to resist the bending of the beam. Over-prestressing the rod may even induce bending or buckling failure in the beam in the reverse direction.

  7. Lazy decision trees

    SciTech Connect (OSTI)

    Friedman, J.H.; Yun, Yeogirl; Kohavi, R.

    1996-12-31

    Lazy learning algorithms, exemplified by nearest-neighbor algorithms, do not induce a concise hypothesis from a given training set; the inductive process is delayed until a test instance is given. Algorithms for constructing decision trees, such as C4.5, ID3, and CART create a single {open_quotes}best{close_quotes} decision tree during the training phase, and this tree is then used to classify test instances. The tests at the nodes of the constructed tree are good on average, but there may be better tests for classifying a specific instance. We propose a lazy decision tree algorithm-LazyDT-that conceptually constructs the {open_quotes}best{close_quote} decision tree for each test instance. In practice, only a path needs to be constructed, and a caching scheme makes the algorithm fast. The algorithm is robust with respect to missing values without resorting to the complicated methods usually seen in induction of decision trees. Experiments on real and artificial problems are presented.

  8. In-pile post-DNB behavior of a nine-rod PWR-type fuel bundle

    SciTech Connect (OSTI)

    Gunnerson, F.S.; MacDonald, P.E.

    1980-01-01

    The results of an in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod, PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation are presented. Primary emphasis is placed on the DNB and post-DNB events including rod-to-rod interactions, return to nucleate boiling (RNB), and fuel rod failure. A comparison of the DNB behavior of the individual bundle rods with single-rod data obtained from previous PCM tests is also made.

  9. Secretary Chu Postpones China Trip to Continue Work on BP Oil Spill

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

    Response Efforts | Department of Energy Postpones China Trip to Continue Work on BP Oil Spill Response Efforts Secretary Chu Postpones China Trip to Continue Work on BP Oil Spill Response Efforts May 21, 2010 - 12:00am Addthis Washington DC -- Energy Secretary Steven Chu will postpone a trip to China, scheduled for next week, at the request of President Obama and stay in the country to continue his work on response efforts to the BP oil spill. "Finding a solution to this crisis is a

  10. EIS-0236: Record of Decision

    Broader source: Energy.gov [DOE]

    Record of Decision Programmatic Environmental Impact Statement for Stockpile Stewardship and Management

  11. Decision Impact Assessment Model

    Energy Science and Technology Software Center (OSTI)

    1991-08-01

    DIAMOND represents the decision-making environment that utility planners and executives face. Users interact with the model after every year or two of simulation, which provides an opportunity to modify past decisions as well as to make new decisions. For example, construction of a power plant can be started one year, and if circumstances change, the plant can be accelerated, mothballed, cancelled, or continued as originally planned. Similarly, the marketing and financial incentives for demand-side managementmore » programs can be changed from year to year. This frequent user interaction with the model, an operational game, should build greater understanding and insights among utility planners about the risks associated with different types of resources.« less

  12. Robust Decision Making

    SciTech Connect (OSTI)

    Christopher A. Dieckmann, PE, CSEP-Acq

    2010-07-01

    The Idaho National Laboratory (INL) is funded through the Department of Energy (DOE) Office of Nuclear Energy and other customers who have direct contracts with the Laboratory. The people, equipment, facilities and other infrastructure at the laboratory require continual investment to maintain and improve the laboratory’s capabilities. With ever tightening federal and customer budgets, the ability to direct investments into the people, equipment, facilities and other infrastructure which are most closely aligned with the laboratory’s mission and customers’ goals grows increasingly more important. The ability to justify those investment decisions based on objective criteria that can withstand political, managerial and technical criticism also becomes increasingly more important. The Systems Engineering tools of decision analysis, risk management and roadmapping, when properly applied to such problems, can provide defensible decisions.

  13. Analytical model for transient gas flow in nuclear fuel rods. [PWR; BWR

    SciTech Connect (OSTI)

    Rowe, D.S.; Oehlberg, R.N.

    1981-08-01

    An analytical model for calculating gas flow and pressure inside a nuclear fuel rod is presented. Such a model is required to calculate the pressure loading of cladding during ballooning that could occur for postulated reactor accidents. The mathematical model uses a porous media (permeability) concept to define the resistance to gas flow along the fuel rod. 7 refs.

  14. Code System to Calculate Fuel Rod Thermal Performance.

    Energy Science and Technology Software Center (OSTI)

    2000-11-27

    Version: 00 GT2R2 is Revision 2 of GAPCON-THERMAL-2 and is used to calculate the thermal behavior of a nuclear fuel rod during normal steady-state operation. The program was developed as a tool for estimating fuel-cladding gap conductances and fuel-stored energy. Models used include power history, fission gas generation and release, fuel relocation and densification, and fuel-cladding gap conductance. The gas release and relocation models can be used to make either best-estimate or conservative predictions. Themore » code is used by the United States Nuclear Regulatory Commission for audit calculations of nuclear fuel thermal performance computer codes.« less

  15. Examination of spent PWR fuel rods after 15 years in dry storage.

    SciTech Connect (OSTI)

    Einziger, R.E.; Tsai, H.C.; Billone, M.C.; Hilton, B.A.

    2002-02-11

    Virginia Power Surry Nuclear Station Pressurized Water Reactor (PWR) fuel was stored in a dry inert atmosphere Castor V/21 cask at the Idaho National Environmental and Engineering Laboratory (INEEL) for 15 years at peak cladding temperatures decreasing from about 350 to 150 C. Prior to the storage, the loaded cask was subjected to extensive thermal benchmark tests. The cask was opened to examine the fuel for degradation and to determine if it was suitable for extended storage. No rod breaches had occurred and no visible degradation or crud/oxide spallation were observed. Twelve rods were removed from the center of the T11 assembly and shipped from INEEL to the Argonne-West HFEF for profilometric scans. Four of these rods were punctured to determine the fission gas release from the fuel matrix and internal pressure in the rods. Three of the four rods were cut into five segments each, then shipped to the Argonne-East AGHCF for detailed examination. The test plan calls for metallographic examination of six samples from two of the rods, microhardness and hydrogen content measurements at or near the six metallographic sample locations, tensile testing of six samples from the two rods, and thermal creep testing of eight samples from the two rods to determine the extent of residual creep life. The results from the profilometry (12 rods), gas release measurements (4 rods), metallographic examinations (2 samples from 1 rod), and microhardness and hydrogen content characterization (2 samples from 1 rod) are reported here. The tensile and creep studies are just starting and will be reported at a later date, along with the additional characterization work to be performed. Although only limited prestorage characterization is available, a number of preliminary conclusions can be drawn based on comparison with characterization of Florida Power Turkey Point rods of a similar vintage. Based on this comparison, it appears that little or no cladding thermal creep and fission gas

  16. Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage

    SciTech Connect (OSTI)

    Einziger, R.E.; Tsai, H.C.; Billone, M.C.; Hilton, B.A.

    2002-07-01

    Virginia Power Surry Nuclear Station Pressurized Water Reactor (PWR) fuel was stored in a dry inert atmosphere Castor V/21 cask at the Idaho National Environmental and Engineering Laboratory (INEEL) for 15 years at peak cladding temperatures decreasing from about 350 to 150 deg. C. Prior to the storage, the loaded cask was subjected to extensive thermal benchmark tests. The cask was opened to examine the fuel for degradation and to determine if it was suitable for extended storage. No rod breaches had occurred and no visible degradation or crud/oxide spallation were observed. Twelve rods were removed from the center of the T11 assembly and shipped from INEEL to the Argonne-West HFEF for profilometric scans. Four of these rods were punctured to determine the fission gas release from the fuel matrix and internal pressure in the rods. Three of the four rods were cut into five segments each, then shipped to the Argonne-East AGHCF for detailed examination. The test plan calls for metallographic examination of six samples from two of the rods, microhardness and hydrogen content measurements at or near the six metallographic sample locations, tensile testing of six samples from the two rods, and thermal creep testing of eight samples from the two rods to determine the extent of residual creep life. The results from the profilometry (12 rods), gas release measurements (4 rods), metallographic examinations (2 samples from 1 rod), and microhardness and hydrogen content characterization (2 samples from 1 rod) are reported here. The tensile and creep studies are just starting and will be reported at a later date, along with the additional characterization work to be performed. Although only limited pre-storage characterization is available, a number of preliminary conclusions can be drawn based on comparison with characterization of Florida Power Turkey Point rods of a similar vintage. Based on this comparison, it appears that little or no cladding thermal creep and fission

  17. Homogenization of a thin plate reinforced with periodic families of rigid rods

    SciTech Connect (OSTI)

    Nazarov, Sergei A; Sweers, Guido H; Slutskij, Andrey S

    2011-08-31

    The asymptotics of the solution to the elastic bending problem for a thin plate reinforced with several periodic families of closely spaced but disjoint rods are constructed and justified, the result of homogenization being substantially different from the case when the rods are welded together into a single periodic mesh. The material in the rods is assumed to be appreciably more rigid than that in the plate. An averaged fourth-order differential operator is obtained from summing the nonelliptic operators generated by each of the families of the rods. This operator is shown to be elliptic if and only if the rods from at least two families are nonparallel. As a simplified example, the paper examines a similar stationary heat conduction problem. Bibliography: 24 titles.

  18. Fuel-rod response during the large-break LOCA Test LOC-6. [PWR

    SciTech Connect (OSTI)

    Vinjamuri, K.; Cook, B.A.; Hobbins, R.R.

    1981-01-01

    The large break Loss of Coolant Accident (LOCA) Test LOC-6 was conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory by EG and G Idaho, Inc. The objectives of the PBF LOCA tests are to obtain in-pile cladding ballooning data under blowdown and reflood conditions and assess how well out-of-pile ballooning data represent in-pile fuel rod behavior. The primary objective of the LOC-6 test was to determine the effects of internal rod pressures and prior irradiation on the deformation behavior of fuel rods that reached cladding temperatures high in the alpha phase of zircaloy. Test LOC-6 was conducted with four rods of PWR 15 x 15 design with the exception of fuel stack length (89 cm) and enrichment (12.5 W% /sup 235/U). Each rod was surrounded by an individual flow shroud.

  19. Peircean Decision Aid

    Energy Science and Technology Software Center (OSTI)

    2008-08-14

    The Peircean decision aid (PDA) is a decision support architecture and embedded functionality that supports a decision maker in very complex environments dealing with massive amounts of disparate data, information and knowledge. The solution generated is a hybrid system solution employing a number of technologies that are based on Peircean reasoning, modal logic, and formal concept analysis. The system convolves data/information with knowledge to create a virtual belief state that is passed to a decisionmore » maker for consideration. The system can capture categorized knowledge or it can inductively learn or acquire new knowledge from suites of observations. Captured knowledge is used to abductively generate hypotheses that are potential explanations to observations or collected data. The zero order modal logic architecture is designed to augment knowledge update and belief revision and can be extended to include disjunctive screening of collected data. While intended to be a library for integration into a decision support architecture it possesses a basic stand-alone GUI for use as an analysis support tool.« less

  20. Microsoft PowerPoint - RHWM_for_BP-14_T1SFCO_Computation.ppt

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

    1.1 0.0 0.6 10. PASA to BPA SNX DE-MS79-94BP93658 0.4 0.3 0.3 11. PASA to BPA Xchg Nrg DE-MS79-94BP93658 1.9 1.6 1.7 12. PPL to BPA So Idaho (netted 0 with Table 3.4 line 26)...

  1. Measurements of Spin Dynamics Reveal that Shape of Excitons in Quantum Rod Heterostructures Changes with Size (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-06-01

    Using femtosecond cross-polarized transient grating (CPTG) and polarization anisotropy, NREL was able to probe the extent of electronic delocalization in CdSe/CdS quantum rod heterostructures (QRH) with a 'dot-in-rod' geometry.

  2. Parallel Operation of Multiple Closely Spaced Small Aspect Ratio Rod Pinches

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

    Harper-Slaboszewicz, Victor J.; Leckbee, Joshua; Bennett, Nichelle; Madrid, Elizabeth A.; Rose, David V.; Thoma, Carsten; Welch, Dale R.; Lake, Patrick W.; McCourt, Andrew L.

    2014-12-10

    A series of simulations and experiments to resolve questions about the operation of arrays of closely spaced small aspect ratio rod pinches has been performed. Design and post-shot analysis of the experimental results are supported by 3D particle-in-cell simulations. Both simulations and experiments support these conclusions. Penetration of current to the interior of the array appears to be efficient, as the current on the center rods is essentially equal to the current on the outer rods. Current loss in the feed due to the formation of magnetic nulls was avoided in these experiments by design of the feed surface ofmore » the cathode and control of the gap to keep the electric fields on the cathode below the emission threshold. Some asymmetry in the electron flow to the rod was observed, but the flow appeared to symmetrize as it reached the end of the rod. Interaction between the rod pinches can be controlled to allow the stable and consistent operation of arrays of rod pinches.« less

  3. Effect of rod bow to partial closure on critical heat flux in PWR fuel assembly

    SciTech Connect (OSTI)

    Macbuff, R.B.; Fighetti, C.F.

    1983-07-01

    The effects of partial closure due to bowed rods on critical heat flux (CHF) in a pressurized water reactor rod bundle were evaluated by conducting tests in an electrically heated test section. The test section consisted of a 5x5 square rod array with 24 heated rods of 9.14 mm (0.360 in) diameter, each with a heated length of 3.66 m (12 ft) with Exxon Nuclear Company spacer grids on a 0.521 m (20.5 in) pitch. The central rod was a 12.2 mm (0.480 in) diameter unheated guide tube. The gap between two centrally located high powered rods was reduced 71% from nominal. The bow was approximately mid-span between two grids in the region in which CHF was observed in unbowed test sections. The results of these tests indicate a reduction in CHF of approximately 5% at 2400 psia and no reduction at 2000 psia when test repeatability is taken into consideration. The reduction in CHF at 2400 psia is substantially smaller than that inferred by linear interpolation of previously reported test results at 50 and 100% reduction of spacing. The local nature of CHF reduction due to rod bow was confirmed.

  4. Internal hydriding in irradiated defected Zircaloy fuel rods: A review (LWBR Development Program)

    SciTech Connect (OSTI)

    Clayton, J C

    1987-10-01

    Although not a problem in recent commercial power reactors, including the Shippingport Light Water Breeder Reactor, internal hydriding of Zircaloy cladding was a persistent cause of gross cladding failures during the 1960s. It occurred in the fuel rods of water-cooled nuclear power reactors that had a small cladding defect. This report summarizes the experimental findings, causes, mechanisms, and methods of minimizing internal hydriding in defected Zircaloy-clad fuel rods. Irradiation test data on the different types of defected fuel rods, intentionally fabricated defected and in-pile operationally defected rods, are compared. Significant factors affecting internal hydriding in defected Zircaloy-clad fuel rods (defect hole size, internal and external sources of hydrogen, Zircaloy cladding surface properties, nickel alloy contamination of Zircaloy, the effect of heat flux and fluence) are discussed. Pertinent in-pile and out-of-pile test results from Bettis and other laboratories are used as a data base in constructing a qualitative model which explains hydrogen generation and distribution in Zircaloy cladding of defected water-cooled reactor fuel rods. Techniques for minimizing internal hydride failures in Zircaloy-clad fuel rods are evaluated.

  5. Nondestructive post-irradiation examination of Loop-1, S1 and B1 rods

    SciTech Connect (OSTI)

    Bratton, R.L.

    1997-05-01

    As a part of the Pacific Northwest National Laboratory`s Tritium Target Development Program, eleven tritium target rods were irradiated in the Advanced Test Reactor located at the Idaho National Engineering and Environmental Laboratory during 1991. Both nondestructive and destructive post-irradiation examination on all eleven rods was planned under the Tritium Target Development Program. Funding for the program was reduced in 1991 resulting in the early removal of the program experiments before reaching their irradiation goals. Post-irradiation examination was only performed on one of the irradiated rods at the Pacific Northwest National Laboratory before the program was terminated in 1992. On December 6, 1995, the Secretary of Energy announced the pursuit of the Commercial Light-Water Reactor option for producing tritium establishing the Tritium Target Qualification Program at the Pacific Northwest National Laboratory. This program decided to pursue nondestructive and destructive post-irradiation examination of the ten remaining rods from the previous program. The ten rods comprise three experiments. The Loop-1 experiment irradiated eight target rods in a loop configuration for 217 irradiation days. The other two rods were irradiated in two separate irradiation experiments, designated as S1 and B1 for 143 effective full-power days, but at different power levels. After the ten rods were transferred from the ATR Canal to the Hot Fuels Examination Facility, the following examinations were performed: (1) visual examination and photography; (2) neutron radiography; (3) axial gamma scanning; (4) contact profilometry measurement; (5) bow and length measurements; (6) rod puncture and plenum gas analysis/measurement of plenum gas quantity; (7) void volume determination; and (8) internal pressure determination. This report presents the data collected during these examinations.

  6. Decision Summaries | Department of Energy

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

    July 10, 2015 Summary of Decisions - July 6, 2015 - July 10, 2015 Decisions were issued on: - Personnel Security (10 CFR Part 710) - Whistleblower Protection (10 CFR Part 708) July...

  7. Decision Summaries | Department of Energy

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

    July 25, 2014 Summary of Decisions - July 21, 2014 - July 25, 2014 Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710) July 18,...

  8. Decision Summaries | Department of Energy

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

    June 21, 2013 Summary of Decisions - June 17, 2013 - June 21, 2013 Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710) June 14,...

  9. EIS-0435: Record of Decision

    Broader source: Energy.gov [DOE]

    Record of Decision for the Modification of the Groton Generation Station Interconnection Agreement, Brown County, South Dakota (December 2011)

  10. Piezoelectric effect in InAs/InP quantum rod nanowires grown on silicon substrate

    SciTech Connect (OSTI)

    Anufriev, Roman; Chauvin, Nicolas Bru-Chevallier, Catherine; Khmissi, Hammadi; Naji, Khalid; Gendry, Michel; Patriarche, Gilles

    2014-05-05

    We report on the evidence of a strain-induced piezoelectric field in wurtzite InAs/InP quantum rod nanowires. This electric field, caused by the lattice mismatch between InAs and InP, results in the quantum confined Stark effect and, as a consequence, affects the optical properties of the nanowire heterostructure. It is shown that the piezoelectric field can be screened by photogenerated carriers or removed by increasing temperature. Moreover, a dependence of the piezoelectric field on the quantum rod diameter is observed in agreement with simulations of wurtzite InAs/InP quantum rod nanowire heterostructures.

  11. CASL - CFD-Based Turbulence Force Evaluation for Grid-to-Rod Fretting

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

    Phenomena CFD-Based Turbulence Force Evaluation for Grid-to-Rod Fretting Phenomena Article Background: Roger Lu - #83 - L1:CASL.P5.02 - Determine extent structural analysis amplifies (or damps) differences in pressure forces between different CFD codes for analysis of GTRF phenomenon (CASL.012) based on "CASL report CFD Turbulence Force Calculations and Grid-to-Rod Fretting Simulation" CFD-Based Turbulence Force Evaluation for Grid-to-Rod Fretting Phenomena R. Y. Lu and Z. Karoutas

  12. INTERCOMPARISON OF RESULTS FOR A PWR ROD EJECTION ACCIDENT

    SciTech Connect (OSTI)

    DIAMOND,D.J.; ARONSON,A.; JO,J.; AVVAKUMOV,A.; MALOFEEV,V.; SIDOROV,V.; FERRARESI,P.; GOUIN,C.; ANIEL,S.; ROYER,M.E.

    1999-10-01

    This study is part of an overall program to understand the uncertainty in best-estimate calculations of the local fuel enthalpy during the rod ejection accident. Local fuel enthalpy is used as the acceptance criterion for this design-basis event and can also be used to estimate fuel damage for the purpose of determining radiological consequences. The study used results from neutron kinetics models in PARCS, BARS, and CRONOS2, codes developed in the US, the Russian Federation, and France, respectively. Since BARS uses a heterogeneous representation of the fuel assembly as opposed to the homogeneous representations in PARCS and CRONOS, the effect of the intercomparison was primarily to compare different intra-assembly models. Quantitative comparisons for core power, reactivity, assembly fuel enthalpy and pin power were carried out. In general the agreement between methods was very good providing additional confidence in the codes and providing a starting point for a quantitative assessment of the uncertainty in calculated fuel enthalpy using best-estimate methods.

  13. Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (DOE/EIS-0287) (11/28/06)

    Office of Environmental Management (EM)

    811 Federal Register / Vol. 71, No. 228 / Tuesday, November 28, 2006 / Notices Information Relay Service (FIRS) at 1-800-877-8339. [FR Doc. E6-20124 Filed 11-27-06; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement AGENCY: Department of Energy. ACTION: Amended Record of Decision. SUMMARY: The U.S. Department of Energy (DOE) is amending its Record of Decision (ROD) published

  14. Property:NEPA Decision | Open Energy Information

    Open Energy Info (EERE)

    Decision Jump to: navigation, search Property Name NEPA Decision Property Type Page Description Files documenting decisions on NEPA Docs This is a property of type Page. Pages...

  15. High-Quality Manganese-Doped Zinc Sulfide Quantum Rods with Tunable...

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

    High-Quality Manganese-Doped Zinc Sulfide Quantum Rods with Tunable Dual-Color and Multiphoton Emissions Authors: Deng, Z., Tong, L., Flores, M., Lin, S., Cheng, J.-X., Yan, H.,...

  16. Fission gas release from UO{sub 2+x} in defective light water reactor fuel rods

    SciTech Connect (OSTI)

    Skim, Y. S.

    1999-11-12

    A simplified semi-empirical model predicting fission gas release form UO{sub 2+x} fuel to the fuel rod plenum as a function of stoichiometry excess (x) is developed to apply to the fuel of a defective LWR fuel rod in operation. The effect of fuel oxidation in enhancing gas diffusion is included as a parabolic dependence of the stoichiometry excess. The increase of fission gas release in a defective BWR fuel rod is at the most 3 times higher than in an intact fuel rod because of small extent of UO{sub 2} oxidation. The major enhancement contributor in fission gas release of UO{sub 2+x} fuel is the increased diffusivity due to stoichiometry excess rather than the higher temperature caused by degraded fuel thermal conductivity.

  17. FY2015 Status Report: CIRFT Testing of High-Burnup Used Nuclear Fuel Rods

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

    from Pressurized Water Reactor and BWR Environments | Department of Energy FY2015 Status Report: CIRFT Testing of High-Burnup Used Nuclear Fuel Rods from Pressurized Water Reactor and BWR Environments FY2015 Status Report: CIRFT Testing of High-Burnup Used Nuclear Fuel Rods from Pressurized Water Reactor and BWR Environments High-burnup spent nuclear fuel cladding has a significant amount of microcracks and hydrides which will reduce the stress intensity required for crack growth.

  18. Coefficient indicates if rod pump can unload water from gas well

    SciTech Connect (OSTI)

    Hu Yongquan; Wu Zhijun

    1995-09-11

    A sucker rod pump can efficiently dewater gas wells if the separation coefficient is sufficiently high. To determine this separation coefficient, it is not sufficient to only know if the system meets the criteria of rod string stress, horsehead load, and crankshaft torque. This paper reviews water production and gas locking problems at the Sichuan gas field and identifies the methodologies used to optimize the pumping efficiency of the area wells.

  19. NotCal04 - Comparison / Calibration 14C records 26-50 cal kBP

    SciTech Connect (OSTI)

    der Plicht, J v; Beck, J; Bard, E; Baille, M

    2004-11-11

    The radiocarbon calibration curve, IntCal04, extends back to 26 cal kBP. While several high resolution records exist beyond this limit, these data sets exhibit discrepancies one to another of up to several millennia. As a result, no calibration curve for the time range 26-50 cal kBP can be recommended as yet, but in this paper the IntCal04 working group compares the available data sets and offers a discussion of the information that they hold.

  20. Requirements to coordinate agreements, milestones and decision...

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

    to coordinate agreements, milestones and decision documents (AMDD) Requirements to coordinate agreements, milestones and decision documents (AMDD) Environmental agreements,...

  1. Latent effects decision analysis

    DOE Patents [OSTI]

    Cooper, J. Arlin; Werner, Paul W.

    2004-08-24

    Latent effects on a system are broken down into components ranging from those far removed in time from the system under study (latent) to those which closely effect changes in the system. Each component is provided with weighted inputs either by a user or from outputs of other components. A non-linear mathematical process known as `soft aggregation` is performed on the inputs to each component to provide information relating to the component. This information is combined in decreasing order of latency to the system to provide a quantifiable measure of an attribute of a system (e.g., safety) or to test hypotheses (e.g., for forensic deduction or decisions about various system design options).

  2. Administrator's Final Record of Decision

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

    with my recent decision during the Integrated Program Review to convert funding for BPA's Energy Efficiency program from capital to expense, eliminating the growth of long-term...

  3. Large-eddy simulations of turbulent flow for grid-to-rod fretting in nuclear reactors

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

    Bakosi, J.; Christon, M. A.; Lowrie, R. B.; Pritchett-Sheats, L. A.; Nourgaliev, R. R.

    2013-07-12

    The grid-to-rod fretting (GTRF) problem in pressurized water reactors is a flow-induced vibration problem that results in wear and failure of the fuel rods in nuclear assemblies. In order to understand the fluid dynamics of GTRF and to build an archival database of turbulence statistics for various configurations, implicit large-eddy simulations of time-dependent single-phase turbulent flow have been performed in 3 × 3 and 5 × 5 rod bundles with a single grid spacer. To assess the computational mesh and resolution requirements, a method for quantitative assessment of unstructured meshes with no-slip walls is described. The calculations have been carriedmore » out using Hydra-TH, a thermal-hydraulics code developed at Los Alamos for the Consortium for Advanced Simulation of Light water reactors, a United States Department of Energy Innovation Hub. Hydra-TH uses a second-order implicit incremental projection method to solve the singlephase incompressible Navier-Stokes equations. The simulations explicitly resolve the large scale motions of the turbulent flow field using first principles and rely on a monotonicity-preserving numerical technique to represent the unresolved scales. Each series of simulations for the 3 × 3 and 5 × 5 rod-bundle geometries is an analysis of the flow field statistics combined with a mesh-refinement study and validation with available experimental data. Our primary focus is the time history and statistics of the forces loading the fuel rods. These hydrodynamic forces are believed to be the key player resulting in rod vibration and GTRF wear, one of the leading causes for leaking nuclear fuel which costs power utilities millions of dollars in preventive measures. As a result, we demonstrate that implicit large-eddy simulation of rod-bundle flows is a viable way to calculate the excitation forces for the GTRF problem.« less

  4. Phase 1 remedial investigation report for 200-BP-1 operable unit. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The US Department of Energy (DOE) Hanford Site, in Washington State is organized into numerically designated operational areas including the 100, 200, 300, 400, 600, and 1100 Areas. The US Environmental Protection Agency (EPA), in November 1989 included the 200 Areas of the Hanford Site on the National Priority List (NPL) under the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA). Inclusion on the NPL initiated the remedial investigation (RD process for the 200-BP-1 operable unit. These efforts are being addressed through the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989) which was negotiated and approved by the DOE, the EPA, and the State of Washington Department of Ecology (Ecology) in May 1989. This agreement, known as the Tri-Party Agreement, governs all CERCLA efforts at Hanford. In March of 1990, the Department of Energy, Richland Operations (DOE-RL) issued a Remedial Investigation/Feasibility Study (RI/FS) work plan (DOE-RL 1990a) for the 200-BP-1 operable unit. The work plan initiated the first phase of site characterization activities associated with the 200-BP-1 operable unit. The purpose of the 200-BP-1 operable unit RI is to gather and develop the necessary information to adequately understand the risks to human health and the environment posed by the site and to support the development and analysis of remedial alternatives during the FS. The RI analysis will, in turn, be used by Tri-Party Agreement signatories to make a risk-management-based selection of remedies for the releases of hazardous substances that have occurred from the 200-BP-1 operable unit.

  5. Waste-to-energy: Decision making and the decisions made

    SciTech Connect (OSTI)

    Schexnayder, S.M. ); Wolfe, A.K. )

    1993-01-01

    During the early 1980s, it was projected that waste-to-energy (WTE) facilities would manage as much as half of all municipal solid waste by the turn of the century. However, during the latter part of the 1980s, the cancellation rate for WTE facilities grew to the point that the portion of the waste stream WTE will handle in the long-term future is less certain. This study, conducted as part of a larger study, identifies factors that influence municipalities, decisions regarding WTE. This study takes a broad perspective about decision-making within communities, emphasizing the context within which decisions were made and the decision-making process. It does not seek to judge the correctness of the decisions.

  6. Waste-to-energy: Decision making and the decisions made

    SciTech Connect (OSTI)

    Schexnayder, S.M.; Wolfe, A.K.

    1993-05-01

    During the early 1980s, it was projected that waste-to-energy (WTE) facilities would manage as much as half of all municipal solid waste by the turn of the century. However, during the latter part of the 1980s, the cancellation rate for WTE facilities grew to the point that the portion of the waste stream WTE will handle in the long-term future is less certain. This study, conducted as part of a larger study, identifies factors that influence municipalities, decisions regarding WTE. This study takes a broad perspective about decision-making within communities, emphasizing the context within which decisions were made and the decision-making process. It does not seek to judge the correctness of the decisions.

  7. Evaulation of power-reactor fuel-rod-analysis capabilities. Phase 1 topical report. Volume 2. Code evaluation. [PWR; BWR

    SciTech Connect (OSTI)

    Coleman, D.R.

    1983-09-01

    FRAPCON-2 (V1M4) was applied to generate fuel performance predictions for 60 rods of a recently evaluated power reactor data sample. Rod design, operational, and performance data was obtained from the RPRI Fuel Performance Data Base. The data was systematically processed to generate code input parameters. FRAPCON was initially applied for scoping studies to identify the best estimate mechanical response and fission gas release modeling options. Based on final scoping results, the balance of rods were analyzed with FRACAS-2 mechanics and FASTGRASS gas release models. Comparisons between measured and calculated fuel and cladding deformation, fission gas release, internal pressure, and gas composition are presented and interpreted relative to code error magnitudes, distributions, and trends versus rod design and operating parameters. The results indicate the FRAPCON-2 has best estimate capability for analysis of moderate duty fuel rod performance, provided that rod fabrication parameters are well characterized, and the fuel is dimensionally stable.

  8. Prediction of number of breached rods following a LBLOCA of Candu plants using a BEPU approach

    SciTech Connect (OSTI)

    Bang, Y. S.; Kim, K.; Seul, K. W.; Woo, S. W.; Han, B. S.

    2012-07-01

    Radioactive doses following design basis accidents (DBA) have been important safety criteria of Candu nuclear power plant and they have been predicted in terms of the number of breached fuel rods. To support the licensing review on this concern, an analysis of LBLOCA has been conducted by using the BEPU method of KINS, KINS-REM. Number of Breached Rods (NBR) following a LBLOCA was predicted at 95 percentile probabilistic upper level in 95 percentile confidence level. Peak Cladding Temperatures (PCT) of the 84 bundles in the core pass 4 were calculated from the 124 MARS code runs in which the uncertainties of 10 major parameters including fuel thermal conductivity and break flow model were implemented. The fuel rod breaching criteria, PCT>1477 K, was used to determine the NBR 95/95. From the calculation, the predicted NBR 95/95 was 1591 rods and the calculated maximum NBR was lower than 2000 rods. Through the further improvements in feedback of the channel power behavior to thermalhydraulic calculation and in channel group modeling, NBR in more reliable level can be expected. (authors)

  9. Control rod calibration and reactivity effects at the IPEN/MB-01 reactor

    SciTech Connect (OSTI)

    Pinto, Letícia Negrão; Gonnelli, Eduardo; Santos, Adimir dos

    2014-11-11

    Researches that aim to improve the performance of neutron transport codes and quality of nuclear cross section databases are very important to increase the accuracy of simulations and the quality of the analysis and prediction of phenomena in the nuclear field. In this context, relevant experimental data such as reactivity worth measurements are needed. Control rods may be made of several neutron absorbing materials that are used to adjust the reactivity of the core. For the reactor operation, these experimental data are also extremely important: with them it is possible to estimate the reactivity worth by the movement of the control rod, understand the reactor response at each rod position and to operate the reactor safely. This work presents a temperature correction approach for the control rod calibration problem. It is shown the control rod calibration data of the IPEN/MB-01 reactor, the integral and differential reactivity curves and a theoretical analysis, performed by the MCNP-5 reactor physics code, developed and maintained by Los Alamos National Laboratory, using the ENDF/B-VII.0 nuclear data library.

  10. Field measurements to support IAEA procedures development for fuel assembly and fuel rod active length verification

    SciTech Connect (OSTI)

    Belew, W.L.; Cooley, J.N.; Whitaker, J.M.

    1992-07-17

    The activities performed in verification of reactor fuel rods and assemblies by International Atomic Energy Agency (IAEA) safeguards inspectors include measurements of the length of the enriched uranium sections in fuel assemblies and fuel rods. These measurements are normally made with the IAEA hand-held gamma monitor (HM-4) on fuel elements containing only enriched uranium. Many fuel rods currently in use contain natural uranium end sections and several different [sup 235]U enrichment zones. To support development of standard procedures for IAEA nondestructive assay (NDA) measurements, a field measurement campaign was carried out to evaluate the FM-4 measurements and to investigate the feasibility of extending the HM-4 measurements to fuel rods and assemblies containing both natural and enriched uranium sections. The results show that the enriched fuel length can be measured to within [plus minus] 1 to 2 cm in the presence of natural uranium sections and to within [plus minus] 0.5 = when only enriched uranium is present. Based on the results from these measurements, a standard procedure, Measurement of Active Fuel Length in Fuel Assemblies and Fuel Rods Using the HM-4,'' has been drafted for review by the IAEA.

  11. Field measurements to support IAEA procedures development for fuel assembly and fuel rod active length verification

    SciTech Connect (OSTI)

    Belew, W.L.; Cooley, J.N.; Whitaker, J.M.

    1992-07-17

    The activities performed in verification of reactor fuel rods and assemblies by International Atomic Energy Agency (IAEA) safeguards inspectors include measurements of the length of the enriched uranium sections in fuel assemblies and fuel rods. These measurements are normally made with the IAEA hand-held gamma monitor (HM-4) on fuel elements containing only enriched uranium. Many fuel rods currently in use contain natural uranium end sections and several different {sup 235}U enrichment zones. To support development of standard procedures for IAEA nondestructive assay (NDA) measurements, a field measurement campaign was carried out to evaluate the FM-4 measurements and to investigate the feasibility of extending the HM-4 measurements to fuel rods and assemblies containing both natural and enriched uranium sections. The results show that the enriched fuel length can be measured to within {plus_minus} 1 to 2 cm in the presence of natural uranium sections and to within {plus_minus} 0.5 = when only enriched uranium is present. Based on the results from these measurements, a standard procedure, ``Measurement of Active Fuel Length in Fuel Assemblies and Fuel Rods Using the HM-4,`` has been drafted for review by the IAEA.

  12. Thermal-hydraulics of the PFB/LOFT lead rod loss-of-coolant experiments. [PWR

    SciTech Connect (OSTI)

    Varacalle, D.J. Jr.; Garner, R.W.; MacDonald, P.E.; Cox, W.R.

    1980-01-01

    Results of the four PBF/LOFT Lead Rod sequential blowdown tests conducted in the Power Burst Facility (PBF) are presented. The primary objective of the test series was to evaluate the extent of mechanical deformation that would be expected to occur to low pressure (0.1 MPa), light water reactor design fuel rods subjected to a series of nuclear blowdown tests, and to determine if subjecting deformed fuel rods to subsequent testing would result in rod failure. The extent of mechanical deformation (buckling, collapse, or waisting of the cladding) was evaluated by comparison of cladding temperature versus system pressure response with out-of-pile experimental data, and by posttest visual examinations and cladding diametral measurements. Tests LLR-3, LLR-5, LLR-4, and LLR-4A were performed at system conditions of 595/sup 0/K coolant inlet temperature, 15.5 MPa system pressure, and 41, 46, 57 and 56 kW/m test rod peak linear powers, respectively, at initiation of blowdown. Cladding temperatures during the tests ranged from 870 to 1260/sup 0/K.

  13. Study of thermal effects in an Nd doped phosphate glass laser rod

    SciTech Connect (OSTI)

    Uppal, J.S.; Monga, J.C.; Bhawalkar, D.D.

    1986-12-01

    Measurement of thermal effects in LHG-8 Nd:glass laser rod during the transient and the cooling phases are presented. The induced thermal lensing is determined by passing a He-Ne probe beam through the rod and measuring the changes in the intensity of the probe beam transmitted through an out-of-focus iris placed near the focal plane of an external lens. Expression for the power of the Gaussian beam transmitted through a stressed laser rod placed between two crossed polarizers is derived. The values of the induced focal length corresponding to the temperature gradient deducted from the measurements of induced birefringence, an independent observable of thermal effects are obtained. These value are found to be in fairly good agreement with the directly measured values.

  14. Laser rods with undoped, flanged end-caps for end-pumped laser applications

    DOE Patents [OSTI]

    Meissner, Helmuth E.; Beach, Raymond J.; Bibeau, Camille; Sutton, Steven B.; Mitchell, Scott; Bass, Isaac; Honea, Eric

    1999-01-01

    A method and apparatus for achieving improved performance in a solid state laser is provided. A flanged, at least partially undoped end-cap is attached to at least one end of a laserable medium. Preferably flanged, undoped end-caps are attached to both ends of the laserable medium. Due to the low scatter requirements for the interface between the end-caps and the laser rod, a non-adhesive method of bonding is utilized such as optical contacting combined with a subsequent heat treatment of the optically contacted composite. The non-bonded end surfaces of the flanged end-caps are coated with laser cavity coatings appropriate for the lasing wavelength of the laser rod. A cooling jacket, sealably coupled to the flanged end-caps, surrounds the entire length of the laserable medium. Radiation from a pump source is focussed by a lens duct and passed through at least one flanged end-cap into the laser rod.

  15. Fluid intensifier having a double acting power chamber with interconnected signal rods

    DOE Patents [OSTI]

    Whitehead, John C.

    2001-01-01

    A fluid driven reciprocating apparatus having a double acting power chamber with signal rods serving as high pressure pistons, or to transmit mechanical power. The signal rods are connected to a double acting piston in the power chamber thereby eliminating the need for pilot valves, with the piston being controlled by a pair of intake-exhaust valves. The signal rod includes two spaced seals along its length with a vented space therebetween so that the driving fluid and driven fluid can't mix, and performs a switching function to eliminate separate pilot valves. The intake-exhaust valves can be integrated into a single housing with the power chamber, or these valves can be built into the cylinder head only of the power chamber, or they can be separate from the power chamber.

  16. Decision Analysis for EGS | Department of Energy

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

    Decision Analysis for EGS Decision Analysis for EGS Decision Analysis for EGS presentation at the April 2013 peer review meeting held in Denver, Colorado. decision_egs_einstein_peer2013.pdf (911.67 KB) More Documents & Publications Decision Analysis for EGS Seismic Technology Adapted to Analyzing and Developing Geothermal Systems Below Surface-Exposed High-Velocity Rocks Alum Innovative Exploration

  17. High strength, low carbon, dual phase steel rods and wires and process for making same

    DOE Patents [OSTI]

    Thomas, Gareth; Nakagawa, Alvin H.

    1986-01-01

    A high strength, high ductility, low carbon, dual phase steel wire, bar or rod and process for making the same is provided. The steel wire, bar or rod is produced by cold drawing to the desired diameter in a single multipass operation a low carbon steel composition characterized by a duplex microstructure consisting essentially of a strong second phase dispersed in a soft ferrite matrix with a microstructure and morphology having sufficient cold formability to allow reductions in cross-sectional area of up to about 99.9%. Tensile strengths of at least 120 ksi to over 400 ksi may be obtained.

  18. L3:VRI.PSS.P1.01 Rod Schmidt SNL

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

    P1.01 Rod Schmidt SNL Completed: 10/29/10 CASL-U-2010-0006-000 Introduction to LIME: A Lightweight Integrating Multi-physics Environment for Coupling Codes 1 Rod Schmidt Sandia National Labs LIME version 0.6 Oct 29, 2010 CASL-U-2010-0006-000 2 Outline * Some Multi-physics Coupling Issues and Terms * Background on LIME Development * Description of LIME * Use of LIME to create multi-physics applications CASL-U-2010-0006-000 3 What do we mean by "coupled" physics? * The solution of one

  19. FRAP-T6 calculations of fuel-rod behavior during overpower transients. [PWR; BWR

    SciTech Connect (OSTI)

    Chambers, R.; Resch, S.C.

    1982-01-01

    The performance of the FRAP-T6 computer code in calculating fuel rod failure and fission gas release during overpower transient events was analyzed. Comparisons of the code's calculations with experiment data was used to determine the accuracy of the code in these two performance areas. First, the ability of the code to replicate observed failure trends as functions of power, ramp rate, hold time, burnup, pellet-cladding gap size, cladding thickness, and fuel density was examined. Then, the capability of the code's fission gas release model to duplicate experiment measurements of unfailed rods was tested at various burnups.

  20. Superfund record of decision (EPA Region 4): Marine Corps Logistics Base, operable unit 5 (PSC 8), Albany, GA, June 23, 1995

    SciTech Connect (OSTI)

    1996-05-01

    The Record of Decision (ROD) document presents the selected Interim Remedial Action (IRA) for Potential Source of Contamination (PSC) 8 of the Marine Corps Logistics Base (MCLB) Albany. PSC 8 addresses a former grit disposal area and PSC 14 is the former domestic wastewater treatment facility. The selected IRA for PSC 8 includes excavation of contaminated soil, transportation offsite to a federally-permitted landfil for disposal and restoration of the excavation area.

  1. Maintaining a Critical Spectra within Monteburns for a Gas-Cooled Reactor Array by Way of Control Rod Manipulation

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

    Adigun, Babatunde John; Fensin, Michael Lorne; Galloway, Jack D.; Trellue, Holly Renee

    2016-06-07

    Our burnup study examined the effect of a predicted critical control rod position on the nuclide predictability of several axial and radial locations within a 4×4 graphite moderated gas cooled reactor fuel cluster geometry. To achieve this, a control rod position estimator (CRPE) tool was developed within the framework of the linkage code Monteburns between the transport code MCNP and depletion code CINDER90, and four methodologies were proposed within the tool for maintaining criticality. Two of the proposed methods used an inverse multiplication approach - where the amount of fissile material in a set configuration is slowly altered until criticalitymore » is attained - in estimating the critical control rod position. Another method carried out several MCNP criticality calculations at different control rod positions, then used a linear fit to estimate the critical rod position. The final method used a second-order polynomial fit of several MCNP criticality calculations at different control rod positions to guess the critical rod position. The results showed that consistency in prediction of power densities as well as uranium and plutonium isotopics was mutual among methods within the CRPE tool that predicted critical position consistently well. Finall, while the CRPE tool is currently limited to manipulating a single control rod, future work could be geared toward implementing additional criticality search methodologies along with additional features.« less

  2. Analytical Data Report for Sediment Samples Collected From 200 BP 5 OU, C7514 (299-E28-30) L-Well

    SciTech Connect (OSTI)

    Lindberg, Michael J.

    2010-06-18

    This an analytical data report for samples received from BP-5 L Well. This report is being prepared for CHPRC.

  3. RETScreen International Clean Energy Decision Support Centre...

    Open Energy Info (EERE)

    decision-making tools (i.e. RETScreen Software) that reduce the cost of pre-feasibility studies; disseminating knowledge to help people make better decisions; and by...

  4. Decision Support Tool: Integrated REDD+ accounting frameworks...

    Open Energy Info (EERE)

    Decision Support Tool: Integrated REDD+ accounting frameworks: Nested national approaches Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Decision Support Tool:...

  5. Government Performance Result Act (GPRA) / Portfolio Decision...

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

    Government Performance Result Act (GPRA) Portfolio Decision Support (PDS) Government Performance Result Act (GPRA) Portfolio Decision Support (PDS) 2009 DOE Hydrogen Program...

  6. Assessment of existing Sierra/Fuego capabilities related to grid-to-rod-fretting (GTRF).

    SciTech Connect (OSTI)

    Turner, Daniel Zack; Rodriguez, Salvador B.

    2011-06-01

    The following report presents an assessment of existing capabilities in Sierra/Fuego applied to modeling several aspects of grid-to-rod-fretting (GTRF) including: fluid dynamics, heat transfer, and fluid-structure interaction. We compare the results of a number of Fuego simulations with relevant sources in the literature to evaluate the accuracy, efficiency, and robustness of using Fuego to model the aforementioned aspects. Comparisons between flow domains that include the full fuel rod length vs. a subsection of the domain near the spacer show that tremendous efficiency gains can be obtained by truncating the domain without loss of accuracy. Thermal analysis reveals the extent to which heat transfer from the fuel rods to the coolant is improved by the swirling flow created by the mixing vanes. Lastly, coupled fluid-structure interaction analysis shows that the vibrational modes of the fuel rods filter out high frequency turbulent pressure fluctuations. In general, these results allude to interesting phenomena for which further investigation could be quite fruitful.

  7. Thermal treatment for increasing magnetostrictive response of rare earth-iron alloy rods

    DOE Patents [OSTI]

    Verhoeven, John D.; McMasters, O. D.

    1989-07-18

    Magnetostrictive rods formed from rare earth-iron alloys are subjected to a short time heat treatment to increase their Magnetostrictive response under compression. The heat treatment is preferably carried out at a temperature of from 900.degree. to 1000.degree. C. for 20 minutes to six hours.

  8. Thermal treatment for increasing magnetostrictive response of rare earth-iron alloy rods

    DOE Patents [OSTI]

    Verhoeven, J.D.; McMasters, O.D.

    1989-07-18

    Magnetostrictive rods formed from rare earth-iron alloys are subjected to a short time heat treatment to increase their magnetostrictive response under compression. The heat treatment is preferably carried out at a temperature of from 900 to 1,000 C for 20 minutes to six hours.

  9. Resonance hybridization and near field properties of strongly coupled plasmonic ring dimer-rod nanosystem

    SciTech Connect (OSTI)

    Koya, Alemayehu Nana; Ji, Boyu; Hao, Zuoqiang; Lin, Jingquan

    2015-09-21

    Combined effects of polarization, split gap, and rod width on the resonance hybridization and near field properties of strongly coupled gold dimer-rod nanosystem are comparatively investigated in the light of the constituent nanostructures. By aligning polarization of the incident light parallel to the long axis of the nanorod, introducing small split gaps to the dimer walls, and varying width of the nanorod, we have simultaneously achieved resonance mode coupling, huge near field enhancement, and prolonged plasmon lifetime. As a result of strong coupling between the nanostructures and due to an intense confinement of near fields at the split and dimer-rod gaps, the extinction spectrum of the coupled nanosystem shows an increase in intensity and blueshift in wavelength. Consequently, the near field lifespan of the split-nanosystem is prolonged in contrast to the constituent nanostructures and unsplit-nanosystem. On the other hand, for polarization of the light perpendicular to the long axis of the nanorod, the effect of split gap on the optical responses of the coupled nanosystem is found to be insignificant compared to the parallel polarization. These findings and such geometries suggest that coupling an array of metallic split-ring dimer with long nanorod can resolve the huge radiative loss problem of plasmonic waveguide. In addition, the Fano-like resonances and immense near field enhancements at the split and dimer-rod gaps imply the potentials of the nanosystem for practical applications in localized surface plasmon resonance spectroscopy and sensing.

  10. Evaluation of fission gas release in high-burnup light water reactor fuel rods

    SciTech Connect (OSTI)

    Barner, J.O.; Cunningham, M.E.; Freshley, M.D.; Lanning, D.D. )

    1993-05-01

    Research to define the behavior of Zircaloy-clad light water reactor (LWR) UO[sub 2] fuel irradiated to high burnup levels was conducted as part of the High Burnup Effects Program (HBEP). The HBEP was a 12-yr program that ultimately acquired, characterized, irradiated, and examined after irradiation 82 LWR fuel rods ranging in rod-average fuel burnup from 22 to 69 MWd/kgM with a peak pellet burnup of 83 MWd/kg M. A principal emphasis of the HBEP was to evaluate the effect of high burnup on fission gas release. It was confirmed that fission gas release remained as dependent on design and irradiation history parameters at high burnup levels as at low to moderate burnup levels. One observed high-burnup effect was the development of a burnup-dependent microstructure at the fuel pellet surface when pellet-edge burnup exceeded 65 MWd/kgM. This low-temperature rim region' was characterized by a loss of optically definable grain structure, a high volume of porosity, and diffusion of fission gas from the UO[sub 2] matrix to the porosity. Although the rim region has the potential for enhanced fission gas release, it is concluded that no significant enhancement of rod-average fission gas release at high burnup levels was observed for the examined fuel rods.

  11. 3D Simulation of Missing Pellet Surface Defects in Light Water Reactor Fuel Rods

    SciTech Connect (OSTI)

    B.W. Spencer; J.D. Hales; S.R. Novascone; R.L. Williamson

    2012-09-01

    The cladding on light water reactor (LWR) fuel rods provides a stable enclosure for fuel pellets and serves as a first barrier against fission product release. Consequently, it is important to design fuel to prevent cladding failure due to mechanical interactions with fuel pellets. Cladding stresses can be effectively limited by controlling power increase rates. However, it has been shown that local geometric irregularities caused by manufacturing defects known as missing pellet surfaces (MPS) in fuel pellets can lead to elevated cladding stresses that are sufficiently high to cause cladding failure. Accurate modeling of these defects can help prevent these types of failures. Nuclear fuel performance codes commonly use a 1.5D (axisymmetric, axially-stacked, one-dimensional radial) or 2D axisymmetric representation of the fuel rod. To study the effects of MPS defects, results from 1.5D or 2D fuel performance analyses are typically mapped to thermo-mechanical models that consist of a 2D plane-strain slice or a full 3D representation of the geometry of the pellet and clad in the region of the defect. The BISON fuel performance code developed at Idaho National Laboratory employs either a 2D axisymmetric or 3D representation of the full fuel rod. This allows for a computational model of the full fuel rod to include local defects. A 3D thermo-mechanical model is used to simulate the global fuel rod behavior, and includes effects on the thermal and mechanical behavior of the fuel due to accumulation of fission products, fission gas production and release, and the effects of fission gas accumulation on thermal conductivity across the fuel-clad gap. Local defects can be modeled simply by including them in the 3D fuel rod model, without the need for mapping between two separate models. This allows for the complete set of physics used in a fuel performance analysis to be included naturally in the computational representation of the local defect, and for the effects of the

  12. Electromagnetic methods for measuring materials properties of cylindrical rods and array probes for rapid flaw inspection

    SciTech Connect (OSTI)

    Sun, Haiyan

    2005-05-01

    The case-hardening process modifies the near-surface permeability and conductivity of steel, as can be observed through changes in alternating current potential drop (ACPD) along a rod. In order to evaluate case depth of case hardened steel rods, analytical expressions are derived for the alternating current potential drop on the surface of a homogeneous rod, a two-layered and a three-layered rod. The case-hardened rod is first modeled by a two-layer rod that has a homogeneous substrate with a single, uniformly thick, homogeneous surface layer, in which the conductivity and permeability values differ from those in the substrate. By fitting model results to multi-frequency ACPD experimental data, estimates of conductivity, permeability and case depth are found. Although the estimated case depth by the two-layer model is in reasonable agreement with the effective case depth from the hardness profile, it is consistently higher than the effective case depth. This led to the development of the three-layer model. It is anticipated that the new three-layered model will improve the results and thus makes the ACPD method a novel technique in nondestructive measurement of case depth. Another way to evaluate case depth of a case hardened steel rod is to use induction coils. Integral form solutions for an infinite rod encircled by a coaxial coil are well known, but for a finite length conductor, additional boundary conditions must be satisfied at the ends. In this work, calculations of eddy currents are performed for a two-layer conducting rod of finite length excited by a coaxial circular coil carrying an alternating current. The solution is found using the truncated region eigenfunction expansion (TREE) method. By truncating the solution region to a finite length in the axial direction, the magnetic vector potential can be expressed as a series expansion of orthogonal eigenfunctions instead of as a Fourier integral. Closed-form expressions are derived for the electromagnetic

  13. Characterization of Suspect Fuel Rod Pieces from the 105 K West Basin

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Pool, Karl N.; Thornton, Brenda M.

    2006-07-25

    This report provides physical and radiochemical characterization results from examinations and laboratory analyses performed on {approx}0.55-inch diameter rod pieces found in the 105 K West (KW) Basin that were suspected to be from nuclear reactor fuel. The characterization results will be used to establish the technical basis for adding this material to the contents of one of the final Multi-Canister Overpacks (MCOs) that will be loaded out of the KW Basin in late FY2006 or at a later time depending on project priorities. Fifteen fuel rod pieces were found during the clean out of the KW Basin. Based on lack of specific credentials, documentation, or obvious serial numbers, none of the items could be positively identified nor could their sources or compositions be described. Item weights and dimensions measured in the KW Basin indicated densities consistent with the suspect fuel rods containing uranium dioxide (UO2), uranium metal, or being empty. Extensive review of the Hanford Site technical literature led to the postulation that these pieces likely were irradiated test fuel prepared to support of the development of the Hanford ''New Production Reactor'', later called N Reactor. To obtain definitive data on the composition of the suspect fuel, 4 representative fuel rod pieces, with densities corresponding to oxide fuel were selected from the 15 items, and shipped from the KW Basin to the Pacific Northwest National Laboratory's (PNNL) Radiological Processing Laboratory (RPL; also known at the 325 Building) for examinations and characterization. The three fuel rod that were characterized appear to contain slightly irradiated UO2 fuel, originally of natural enrichment, with zirconium cladding. The uranium-235 isotopic concentrations decreased by the irradiation and become slightly lower than the natural enrichment of 0.72% to range from 0.67 to 0.71 atom%. The plutonium concentrations, ranged from about 200 to 470 grams per metric ton of uranium and ranged in

  14. Investigation of Backscatter X-ray imaging techniques for Uranium Dioxide Fuel Rods

    SciTech Connect (OSTI)

    Jackson, Timothy D; Hollenbach, Daniel F; Shedlock, Daniel

    2011-01-01

    Radiography by Selective Detection (RSD), was investigated for its ability to determine the presence and types of defects in a UO{sub 2} fuel rod surrounded by zirconium cladding. Images created using a Monte Carlo model compared favorably with actual X-ray backscatter images from mock fuel rods. A fuel rod was modeled as a rectangular parallelepiped with zirconium cladding, and pencil beam X-ray sources of 160 kVp (79 keV avg) and 480 kVp (218 keV avg) were generated using the Monte Carlo N-Particle Transport Code to attempt to image void and palladium (Pd) defects in the interior and on the surface of the fuel pellet. It was found that the 160 kVp spectrum was unable to detect the presence of interior defects, whereas the 480 kVp spectrum detected them with both the standard and the RSD backscatter methods, though the RSD method was very inefficient. It was also found that both energy spectra were able to detect void and Pd defects on the surface using both imaging methods. Additionally, two mock fuel rods were imaged using a backscatter X-ray imaging system, one consisting of hafnium pellets in a Zircaloy-4 cladding and the other consisting of steel pellets in a Zircalloy-4 cladding which was then encased in a steel cladding (a double encapsulation configuration employed in irradiation and experiments). It was found that the system was capable of detecting individual HfO{sub 2} pellets in a Zircaloy-4 cladding and may be capable of detecting individual steel pellets in the double-encapsulated sample. It is expected that the system would also be capable of detecting individual UO{sub 2} pellets in a Zircaloy-4 cladding, though no UO{sub 2} fuel rod was available for imaging.

  15. Feasibility study report for the 200-BP-1 operable unit. Revision 1

    SciTech Connect (OSTI)

    Not Available

    1994-01-01

    This feasibility study (FS) examines a range of alternatives and provides recommendations for selecting a preferred altemative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965-1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-:levels of contamination with cesium-137, radium-226, strontium-90, thorium-228 and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9 {times} 10{sup 5}.

  16. Program Evaluation: Informed Decisions | Department of Energy

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

    Why, What, & When to Evaluate » Program Evaluation: Informed Decisions Program Evaluation: Informed Decisions Evaluation activities support decision-making that can contribute to efficient and effective management of programs. Evaluative information should be available to inform decisions made during the critical planning, budgeting, analysis, implementation, and benefits reporting/ communications cycles of the program. Program evaluation can provide essential information to inform

  17. Fuel Rod Thermal-Mechanical Behavior, Versions FRAPCON2, FRAPCON2/VIM4 & FRAPCON2/VIM5.

    Energy Science and Technology Software Center (OSTI)

    2002-03-25

    Version 02 This package contains three versions of the FRAPCON series of fuel rod response modeling programs. The FRAPCON series, like the earlier FRAP-S and GAPCON-THERMAL codes, is designed to predict the steady-state long-term burnup response of oxide fuel rods in light water reactors (LWRs). In addition, these codes generate the initial conditions for transient fuel rod analysis by the FRAP-T6 or thermal-hydraulic analysis programs. The FRAPCON2 programs calculate the temperature, pressure, deformation, and failuremore » histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include heat conduction through the fuel and cladding, cladding elastic and plastic deformation, fuel-cladding mechanical interaction, fission gas release, fuel rod internal gas pressure, heat transfer between fuel and cladding, cladding oxidation, and heat transfer from cladding to coolant. Material properties, water properties, and heat transfer correlation data are included. The FRAPCON series replaced the FRAP-S1, FRAP-S2, and FRAP-S3 series of programs. The fuel temperature computation used in the FRAPCON series was taken from the GAPCON-THERMAL2 code (NESC 618). FRAPCON2/VIM4 generates the initial conditions for transient fuel rod analysis used either by FRAP-T6 (NESC 658) or RELAP4/MOD7 (NESC 369).« less

  18. Initial Decision and Risk Analysis

    SciTech Connect (OSTI)

    Engel, David W.

    2012-02-29

    Decision and Risk Analysis capabilities will be developed for industry consideration and possible adoption within Year 1. These tools will provide a methodology for merging qualitative ranking of technology maturity and acknowledged risk contributors with quantitative metrics that drive investment decision processes. Methods and tools will be initially introduced as applications to the A650.1 case study, but modular spreadsheets and analysis routines will be offered to industry collaborators as soon as possible to stimulate user feedback and co-development opportunities.

  19. Terahertz electromagnetic wave generation and amplification by an electron beam in the elliptical plasma waveguides with dielectric rod

    SciTech Connect (OSTI)

    Rahmani, Z. Jazi, B.; Heidari-Semiromi, E.

    2014-09-15

    The propagation of electromagnetic waves in an elliptical plasma waveguide including strongly magnetized plasma column and a dielectric rod is investigated. The dispersion relation of guided hybrid electromagnetic waves is obtained. Excitation of the waves by a thin annular relativistic elliptical electron beam will be studied. The time growth rate of electromagnetic waves is obtained. The effects of relative permittivity constant of dielectric rod, radius of dielectric rod, accelerating voltage, and current density of the annular elliptical beam on the growth rate and the frequency spectra are numerically presented.

  20. Evaluation of the thermal-hydraulic response and fuel rod thermal and mechanical deformation behavior during the power burst facility test LOC-3. [PWR

    SciTech Connect (OSTI)

    Yackle, T.R.; MacDonald, P.E.; Broughton, J.M.

    1980-01-01

    An evaluation of the results from the LOC-3 nuclear blowdown test conducted in the Power Burst Facility is presented. The test objective was to examine fuel and cladding behavior during a postulated cold leg break accident in a pressurized water reactor (PWR). Separate effects of rod internal pressure and the degree of irradiation were investigated in the four-rod test. Extensive cladding deformation (ballooning) and failure occurred during blowdown. The deformation of the low and high pressure rods was similar; however, the previously irradiated test rod deformed to a greater extent than a similar fresh rod exposed to identical system conditions.

  1. Measurement of Fresh Fuel Rods to Demonstrate Compliance with Criticality Safety Limits

    SciTech Connect (OSTI)

    Miko, David K.; Desimone, David J.

    2015-11-03

    In order to operate TA-66 as a radiological facility with the quantity of nuclear material required to fulfil its mission, a criticality safety evaluation was required. This evaluation defined the control parameters for operations at the facility. The resulting evaluation for TA-66 placed limits on the amount of SNM, as well as other materials such as beryllium. In addition, there is a limit on the number of uranium fuel rods allowed subject to enrichment, outer diameter, and overall length restrictions. The enrichments for the rods to be shipped to TA-66 were documented in LA-UR-13-23581, but the outer diameter and length were not documented. This report provides this information.

  2. External attachment of titanium sheathed thermocouples to zirconium nuclear fuel rods for the LOFT reactor

    SciTech Connect (OSTI)

    Welty, R.K.

    1980-01-01

    The Exxon Nuclear Company, Inc., acting as a Subcontractor to EG and G Idaho Inc., Idaho National Engineering Laboratory, Idaho Falls, Idaho, has developed a welding process to attach titanium sheathed thermocouples to the outside of the zircaloy clad fuel rods. The fuel rods and thermocouples are used to test simulated loss-of-coolant accident (LOCA) conditions in a pressurized water reactor (LOFT Reactor, Idaho National Laboratory). A laser beam was selected as the optimum welding process because of the extremely high energy input per unit volume that can be achieved allowing local fusion of a small area irrespective of the difference in material thickness to be joined. A commercial pulsed laser and energy control system was installed along with specialized welding fixtures. Laser room facility requirements and tolerances were established. Performance qualifications, and detailed welding procedures were also developed. Product performance tests were conducted to assure that engineering design requirements could be met on a production basis.

  3. Method of forming magnetostrictive rods from rare earth-iron alloys

    DOE Patents [OSTI]

    McMasters, O.D.

    1986-09-02

    Rods of magnetostrictive alloys of iron with rare earth elements are formed by flowing a body of rare earth-iron alloy in a crucible enclosed in a chamber maintained under an inert gas atmosphere, forcing such molten rare-earth-iron alloy into a hollow mold tube of refractory material positioned with its lower end portion within the molten body by means of a pressure differential between the chamber and mold tube and maintaining a portion of the molten alloy in the crucible extending to a level above the lower end of the mold tube so that solid particles of higher melting impurities present in the alloy collect at the surface of the molten body and remain within the crucible as the rod is formed in the mold tube. 5 figs.

  4. Method of forming magnetostrictive rods from rare earth-iron alloys

    DOE Patents [OSTI]

    McMasters, O. Dale

    1986-09-02

    Rods of magnetrostructive alloys of iron with rare earth elements are formed by flowing a body of rare earth-iron alloy in a crucible enclosed in a chamber maintained under an inert gas atmosphere, forcing such molten rare-earth-iron alloy into a hollow mold tube of refractory material positioned with its lower end portion within the molten body by means of a pressure differential between the chamber and mold tube and maintaining a portion of the molten alloy in the crucible extending to a level above the lower end of the mold tube so that solid particles of higher melting impurities present in the alloy collect at the surface of the molten body and remain within the crucible as the rod is formed in the mold tube.

  5. FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

    SciTech Connect (OSTI)

    Lanning, D.D.; Beyer, C.E.; Painter, C.L.

    1997-12-01

    This volume describes the fuel rod material and performance models that were updated for the FRAPCON-3 steady-state fuel rod performance code. The property and performance models were changed to account for behavior at extended burnup levels up to 65 Gwd/MTU. The property and performance models updated were the fission gas release, fuel thermal conductivity, fuel swelling, fuel relocation, radial power distribution, solid-solid contact gap conductance, cladding corrosion and hydriding, cladding mechanical properties, and cladding axial growth. Each updated property and model was compared to well characterized data up to high burnup levels. The installation of these properties and models in the FRAPCON-3 code along with input instructions are provided in Volume 2 of this report and Volume 3 provides a code assessment based on comparison to integral performance data. The updated FRAPCON-3 code is intended to replace the earlier codes FRAPCON-2 and GAPCON-THERMAL-2. 94 refs., 61 figs., 9 tabs.

  6. FY15 Status Report: CIRFT Testing of Spent Nuclear Fuel Rods from Boiler Water Reactor Limerick

    SciTech Connect (OSTI)

    Wang, Jy-An John; Wang, Hong; Jiang, Hao

    2015-06-01

    The objective of this project is to perform a systematic study of used nuclear fuel (UNF, also known as spent nuclear fuel [SNF]) integrity under simulated transportation environments using the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL) in August 2013. Under Nuclear Regulatory Commission (NRC) sponsorship, ORNL completed four benchmark tests, four static tests, and twelve dynamic or cycle tests on H. B. Robinson (HBR) high burn-up (HBU) fuel. The clad of the HBR fuels was made of Zircaloy-4. Testing was continued in fiscal year (FY) 2014 using Department of Energy (DOE) funds. The additional CIRFT was conducted on three HBR rods (R3, R4, and R5) in which two specimens failed and one specimen was tested to over 2.23 10⁷ cycles without failing. The data analysis on all the HBR UNF rods demonstrated that it is necessary to characterize the fatigue life of the UNF rods in terms of (1) the curvature amplitude and (2) the maximum absolute of curvature extremes. The maximum extremes are significant because they signify the maximum of tensile stress for the outer fiber of the bending rod. CIRFT testing has also addressed a large variation in hydrogen content on the HBR rods. While the load amplitude is the dominant factor that controls the fatigue life of bending rods, the hydrogen content also has an important effect on the lifetime attained at each load range tested. In FY 15, ten SNF rod segments from BWR Limerick were tested using ORNL CIRFT, with one under static and nine dynamic loading conditions. Under static unidirectional loading, a moment of 85 N·m was obtained at maximum curvature 4.0 m⁻¹. The specimen did not show any sign of failure in three repeated loading cycles to almost same maximum curvature. Ten cyclic tests were conducted with amplitude varying from 15.2 to 7.1 N·m. Failure was observed in nine of the tested rod specimens. The cycles to failure were

  7. Synthesis and Raman spectrum of crystalline indium oxide micro-rods with rectangular cross-section

    SciTech Connect (OSTI)

    Yadav, Kavita Mehta, B. R. Singh, J. P.

    2014-04-24

    Indium oxide (IO) micro-rods with rectangular cross section were synthesized without catalyst in chemical vapor deposition (CVD) system by carbothermal reduction of indium oxide at 900 °C. The rectangular micro-rods (RMRs) were grown on Si substrate in presence of water vapors and Ar atmosphere. Water was used as oxidizing reagent which controls the In/O stoichiometry in RMRs. The IO RMRs have dimensions of about 20 μm in length and about 1 μm width. The growth process involved in formation of RMRs is vapor-solid (VS) mechanism. Raman analysis was performed to obtain the phonon modes of the RMRs and the peaks of Raman spectrum were indexed to the modes being associated with bcc−In{sub 2}O{sub 3}.

  8. Accelerated high-temperature tests with spent PWR and BWR fuel rods under dry storage conditions

    SciTech Connect (OSTI)

    Porsch, G.; Fleisch, J.; Heits, B.

    1986-09-01

    Accelerated high-temperature tests on 25 intact pressurized water and boiling water reactor rods were conducted for more than 16 months at 400, 430, and 450/sup 0/C in a helium gas atmosphere. The pretest characterized rods were examined by nondestructive methods after each of the three test cycles. No cladding breaches occurred and the creep deformation remained below 1%, which was in good agreement with model calculations. The test atmospheres were analyzed for /sup 85/Kr and tritium. The /sup 85/Kr concentrations were negligible and the tritium release agreed with the theoretical predictions. It can be concluded that for Zircaloy-clad fuel, cladding temperatures up to 450/sup 0/C are acceptable for dry storage in inert cover gases.

  9. Effects of thermocouple installation and location on fuel rod temperature measurements. [PWR; BWR

    SciTech Connect (OSTI)

    McCormick, R.D.

    1983-01-01

    This paper describes the results of analyses of nuclear fuel rod cladding temperature data obtained during in-reactor experiments under steady state and transient (simulated loss-of-coolant accident) operating conditions. The objective of the analyses was to determine the effect of thermocouple attachment method and location on measured thermal response. The use of external thermocouples increased the time to critical heat flux (CHF), reduced the blowdown peak temperature, and enhanced rod quench. A comparison of laser welded and resistance welded external thermocouple responses showed that the laser welding technique reduced the indicated cladding steady state temperatures and provided shorter time-to-CHF. A comparison of internal welded and embedded thermocouples indicated that the welded technique gave generally unsatisfactory cladding temperature measurements. The embedded thermocouple gave good, consistent results, but was possibly more fragile than the welded thermocouples. Detailed descriptions of the thermocouple designs, attachment methods and locations, and test conditions are provided.

  10. Effects of stacking faults on the electronic structures of quantum rods

    SciTech Connect (OSTI)

    Wang, Lin-Wang

    2004-03-30

    Atomistic semiempirical pseudopotential method is used to study the effects of stacking faults in a wurtzite structure quantum rod. It is found that a single stacking fault can cause a 10-50 meV change in the conduction state eigen energy, and a localization in the electron wave function. However, the effects on the hole eigen energies and wave functions are very small.

  11. Isotopic Details of the Spent Catawba-1 MOX Fuel Rods at ORNL

    SciTech Connect (OSTI)

    Ellis, Ronald James

    2015-04-01

    The United States Department of Energy funded Shaw/AREVA MOX Services LLC to fabricate four MOX Lead Test Assemblies (LTA) from weapons-grade plutonium. A total of four MOX LTAs (including MX03) were irradiated in the Catawba Nuclear Station (Unit 1) Catawba-1 PWR which operated at a total thermal power of 3411 MWt and had a core with 193 total fuel assemblies. The MOX LTAs were irradiated along with Duke Energy s irradiation of eight Westinghouse Next Generation Fuel (NGF) LEU LTAs (ref.1) and the remaining 181 LEU fuel assemblies. The MX03 LTA was irradiated in the Catawba-1 PWR core (refs.2,3) during cycles C-16 and C-17. C-16 began on June 5, 2005, and ended on November 11, 2006, after 499 effective full power days (EFPDs). C-17 started on December 29, 2006, (after a shutdown of 48 days) and continued for 485 EFPDs. The MX03 and three other MOX LTAs (and other fuel assemblies) were discharged at the end of C-17 on May 3, 2008. The design of the MOX LTAs was based on the (Framatome ANP, Inc.) Mark-BW/MOX1 17 17 fuel assembly design (refs. 4,5,6) for use in Westinghouse PWRs, but with MOX fuel rods with three Pu loading ranges: the nominal Pu loadings are 4.94 wt%, 3.30 wt%, and 2.40 wt%, respectively, for high, medium, and low Pu content. The Mark-BW/MOX1 (MOX LTA) fuel assembly design is the same as the Advanced Mark-BW fuel assembly design but with the LEU fuel rods replaced by MOX fuel rods (ref. 5). The fabrication of the fuel pellets and fuel rods for the MOX LTAs was performed at the Cadarache facility in France, with the fabrication of the LTAs performed at the MELOX facility, also in France.

  12. Summary of dynamic analyses of the advanced neutron source reactor inner control rods

    SciTech Connect (OSTI)

    Hendrich, W.R.

    1995-08-01

    A summary of the structural dynamic analyses that were instrumental in providing design guidance to the Advanced Neutron source (ANS) inner control element system is presented in this report. The structural analyses and the functional constraints that required certain performance parameters were combined to shape and guide the design effort toward a prediction of successful and reliable control and scram operation to be provided by these inner control rods.

  13. Models for the Configuration and Integrity of Partially Oxidized Fuel Rod Cladding at High Temperatures

    SciTech Connect (OSTI)

    Siefken, L.J.

    1999-01-01

    Models were designed to resolve deficiencies in the SCDAP/RELAP5/MOD3.2 calculations of the configuration and integrity of hot, partially oxidized cladding. These models are expected to improve the calculations of several important aspects of fuel rod behavior. First, an improved mapping was established from a compilation of PIE results from severe fuel damage tests of the configuration of melted metallic cladding that is retained by an oxide layer. The improved mapping accounts for the relocation of melted cladding in the circumferential direction. Then, rules based on PIE results were established for calculating the effect of cladding that has relocated from above on the oxidation and integrity of the lower intact cladding upon which it solidifies. Next, three different methods were identified for calculating the extent of dissolution of the oxidic part of the cladding due to its contact with the metallic part. The extent of dissolution effects the stress and thus the integrity of the oxidic part of the cladding. Then, an empirical equation was presented for calculating the stress in the oxidic part of the cladding and evaluating its integrity based on this calculated stress. This empirical equation replaces the current criterion for loss of integrity which is based on temperature and extent of oxidation. Finally, a new rule based on theoretical and experimental results was established for identifying the regions of a fuel rod with oxidation of both the inside and outside surfaces of the cladding. The implementation of these models is expected to eliminate the tendency of the SCDAP/RELAP5 code to overpredict the extent of oxidation of the upper part of fuel rods and to underpredict the extent of oxidation of the lower part of fuel rods and the part with a high concentration of relocated material. This report is a revision and reissue of the report entitled, Improvements in Modeling of Cladding Oxidation and Meltdown.

  14. A thermal-hydraulic code for transient analysis in a channel with a rod bundle

    SciTech Connect (OSTI)

    Khodjaev, I.D.

    1995-09-01

    The paper contains the model of transient vapor-liquid flow in a channel with a rod bundle of core of a nuclear power plant. The computer code has been developed to predict dryout and post-dryout heat transfer in rod bundles of nuclear reactor core under loss-of-coolant accidents. Economizer, bubble, dispersed-annular and dispersed regimes are taken into account. The computer code provides a three-field representation of two-phase flow in the dispersed-annular regime. Continuous vapor, continuous liquid film and entrained liquid drops are three fields. For the description of dispersed flow regime two-temperatures and single-velocity model is used. Relative droplet motion is taken into account for the droplet-to-vapor heat transfer. The conservation equations for each of regimes are solved using an effective numerical technique. This technique makes it possible to determine distribution of the parameters of flows along the perimeter of fuel elements. Comparison of the calculated results with the experimental data shows that the computer code adequately describes complex processes in a channel with a rod bundle during accident.

  15. Laser rods with undoped, flanged end-caps for end-pumped laser applications

    DOE Patents [OSTI]

    Meissner, H.E.; Beach, R.J.; Bibeau, C.; Sutton, S.B.; Mitchell, S.; Bass, I.; Honea, E.

    1999-08-10

    A method and apparatus for achieving improved performance in a solid state laser is provided. A flanged, at least partially undoped end-cap is attached to at least one end of a laserable medium. Preferably flanged, undoped end-caps are attached to both ends of the laserable medium. Due to the low scatter requirements for the interface between the end-caps and the laser rod, a non-adhesive method of bonding is utilized such as optical contacting combined with a subsequent heat treatment of the optically contacted composite. The non-bonded end surfaces of the flanged end-caps are coated with laser cavity coatings appropriate for the lasing wavelength of the laser rod. A cooling jacket, sealably coupled to the flanged end-caps, surrounds the entire length of the laserable medium. Radiation from a pump source is focused by a lens duct and passed through at least one flanged end-cap into the laser rod. 14 figs.

  16. Biosynthesis and recovery of rod-shaped tellurium nanoparticles and their bactericidal activities

    SciTech Connect (OSTI)

    Zare, Bijan; Faramarzi, Mohammad Ali; Sepehrizadeh, Zargham; Shakibaie, Mojtaba; Rezaie, Sassan; Shahverdi, Ahmad Reza

    2012-11-15

    Highlights: ► Biosynthesis of rod shape tellurium nanoparticles with a hexagonal crystal structure. ► Extraction procedure for isolation of tellurium nanoparticles from Bacillus sp. BZ. ► Extracted tellurium nanoparticles have good bactericidal activity against some bacteria. -- Abstract: In this study, a tellurium-transforming Bacillus sp. BZ was isolated from the Caspian Sea in northern Iran. The isolate was identified by various tests and 16S rDNA analysis, and then used to prepare elemental tellurium nanoparticles. The isolate was subsequently used for the intracellular biosynthesis of elemental tellurium nanoparticles. The biogenic nanoparticles were released by liquid nitrogen and purified by an n-octyl alcohol water extraction system. The shape, size, and composition of the extracted nanoparticles were characterized. The transmission electron micrograph showed rod-shaped nanoparticles with dimensions of about 20 nm × 180 nm. The energy dispersive X-ray and X-ray diffraction spectra respectively demonstrated that the extracted nanoparticles consisted of only tellurium and have a hexagonal crystal structure. This is the first study to demonstrate a biological method for synthesizing rod-shaped elemental tellurium by a Bacillus sp., its extraction and its antibacterial activity against different clinical isolates.

  17. Benchmark Evaluation of the HTR-PROTEUS Absorber Rod Worths (Core 4)

    SciTech Connect (OSTI)

    John D. Bess; Leland M. Montierth

    2014-06-01

    PROTEUS was a zero-power research reactor at the Paul Scherrer Institute (PSI) in Switzerland. The critical assembly was constructed from a large graphite annulus surrounding a central cylindrical cavity. Various experimental programs were investigated in PROTEUS; during the years 1992 through 1996, it was configured as a pebble-bed reactor and designated HTR-PROTEUS. Various critical configurations were assembled with each accompanied by an assortment of reactor physics experiments including differential and integral absorber rod measurements, kinetics, reaction rate distributions, water ingress effects, and small sample reactivity effects [1]. Four benchmark reports were previously prepared and included in the March 2013 edition of the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook) [2] evaluating eleven critical configurations. A summary of that effort was previously provided [3] and an analysis of absorber rod worth measurements for Cores 9 and 10 have been performed prior to this analysis and included in PROTEUS-GCR-EXP-004 [4]. In the current benchmark effort, absorber rod worths measured for Core Configuration 4, which was the only core with a randomly-packed pebble loading, have been evaluated for inclusion as a revision to the HTR-PROTEUS benchmark report PROTEUS-GCR-EXP-002.

  18. Record of Decision for Tank Farm Soil and INTEC Groundwater, Operable Unit 3-14

    SciTech Connect (OSTI)

    L. S. Cahn

    2007-05-16

    This decision document presents the selected remedy for Operable Unit (OU) 3-14 tank farm soil and groundwater at the Idaho Nuclear Technology and Engineering Center (INTEC), which is located on the Idaho National Laboratory (INL) Site. The tank farm was initially evaluated in the OU 3-13 Record of Decision (ROD), and it was determined that additional information was needed to make a final decision. Additional information has been obtained on the nature and extent of contamination in the tank farm and on the impact to groundwater. The selected remedy was chosen in accordance with the Comprehensive Environmental Response, Liability and Compensation Act of 1980 (CERCLA) (42 USC 9601 et seq.), as amended by the Superfund Amendments and Reauthorization Act of 1986 (Public Law 99-499) and the National Oil and Hazardous Substances Pollution Contingency Plan (40 CFR 300). The selected remedy is intended to be the final action for tank farm soil and groundwater at INTEC. The response action selected in this ROD is necessary to protect the public health, welfare, or the environment from actual or threatened releases of hazardous substances into the environment. Such a release or threat of release may present an imminent and substantial endangerment to public health, welfare, or the environment. The remedial actions selected in this ROD are designed to reduce the potential threats to human health and the environment to acceptable levels. In addition, DOE-ID, EPA, and DEQ (the Agencies) have determined that no action is necessary under CERCLA to protect public health, welfare, or the environment at 16 sites located outside the tank farm boundary. The purposes of the selected remedy are to (1) contain contaminated soil as the radionuclides decay in place, (2) isolate current and future workers and biological receptors from contact with contaminated soil, and (3) restore the portion of Snake River Plain Aquifer contaminated by INTEC releases to Idaho Ground Water Quality

  19. CRC DEPLETION CALCULATIONS FOR THE RODDED ASSEMBLIES IN BATCHES 1, 2, 3, AND 1X OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-09-03

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain rodded fuel assemblies from batches 1, 2, 3, and 1X of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A rodded assembly is one that contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) for some period of time during its irradiation history. The objective of this analysis is to provide SAS2H calculated isotopic compositions of depleted fuel and depleted burnable poison for each fuel assembly to be used in subsequent CRC reactivity calculations containing the fuel assemblies.

  20. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 1, 2, AND 3 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-29

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 1, 2, and 3 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  1. Two-stage epitaxial growth of vertically-aligned SnO2 nano-rods on(001) ceria

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

    Solovyov, Vyacheslav F.; Wu, Li-jun; Rupich, Martin W.; Sathyamurthy, Srivatsan; Li, Xiaoping; Li, Qiang

    2014-09-20

    Growth of high-aspect ratio oriented tin oxide, SnO2, nano-rods is complicated by a limited choice of matching substrates. We show that a (001) cerium oxide, CeO2, surface uniquely enables epitaxial growth of tin-oxide nano-rods via a two-stage process. First, (100) oriented nano-wires coat the ceria surface by lateral growth, forming a uniaxially-textured SnO2 deposit. Second, vertical SnO2nano-rods nucleate on the deposit by homoepitaxy. We demonstrate growth of vertically oriented 1-2 μm long nano-rods with an average diameter of ≈20 nm.

  2. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 4 AND 5 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-30

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 4 and 5 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  3. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 8 AND 9 CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Michael L. Wilson

    2001-02-08

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 8 and 9 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  4. Two-stage epitaxial growth of vertically-aligned SnO2 nano-rods on (001) ceria

    SciTech Connect (OSTI)

    Solovyov, VF; Wu, LJ; Rupich, MW; Sathyamurthy, S; Li, XP; Li, Q

    2014-12-15

    Growth of high-aspect ratio oriented tin oxide, SnO2, nano-rods is complicated by a limited choice of matching substrates. We show that a (001) cerium oxide, CeO2, surface uniquely enables epitaxial growth of tin-oxide nano-rods via a two-stage process. First, (100) oriented nano-wires coat the ceria surface by lateral growth, forming a uniaxially-textured SnO2 deposit. Second, vertical SnO2 nano-rods nucleate on the deposit by homoepitaxy. We demonstrate growth of vertically oriented 1-2 mu m long nano-rods with an average diameter of approximate to 20 nm. 2014 Elsevier B.V. All rights reserved.

  5. Fuel performance improvement program: description and characterization of HBWR Series H-2, H-3, and H-4 test rods

    SciTech Connect (OSTI)

    Guenther, R.J.; Barner, J.O.; Welty, R.K.

    1980-03-01

    The fabrication process and as-built characteristics of the HBWR Series H-2 and H-3 test rods, as well as the three packed-particle (sphere-pac) rods in HBWR Series H-4 are described. The HBWR Series H-2, H-3, and H-4 tests are part of the irradiation test program of the Fuel Performance Improvement Program. Fifteen rods were fabricated for the three test series. Rod designs include: (1) a reference dished pellet design incorporating chamfered edges, (2) a chamfered, annular pellet design combined with graphite-coated cladding, and (3) a sphere-pac design. Both the annular-coated and sphere-pac designs include internal pressurization using helium.

  6. EIS-0340: Record of Decision | Department of Energy

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

    40-ROD-2005.pdf More Documents & Publications EIS-0340: Draft Environmental Impact Statement EIS-0340: Final Environmental Impact Statement EA-1173: Final Environmental Assessment...

  7. Reaching Grid Parity Using BP Solar Crystalline Silicon Technology: A Systems Class Application

    SciTech Connect (OSTI)

    Cunningham, Daniel W; Wohlgemuth, John; Carlson, David E; Clark, Roger F; Gleaton, Mark; Posbic, John P; Zahler, James

    2010-12-06

    The primary target market for this program was the residential and commercial PV markets, drawing on BP Solar's premium product and service offerings, brand and marketing strength, and unique routes to market. These two markets were chosen because: (1) in 2005 they represented more than 50% of the overall US PV market; (2) they are the two markets that will likely meet grid parity first; and (3) they are the two market segments in which product development can lead to the added value necessary to generate market growth before reaching grid parity. Federal investment in this program resulted in substantial progress toward the DOE TPP target, providing significant advancements in the following areas: (1) Lower component costs particularly the modules and inverters. (2) Increased availability and lower cost of silicon feedstock. (3) Product specifically developed for residential and commercial applications. (4) Reducing the cost of installation through optimization of the products. (5) Increased value of electricity in mid-term to drive volume increases, via the green grid technology. (6) Large scale manufacture of PV products in the US, generating increased US employment in manufacturing and installation. To achieve these goals BP Solar assembled a team that included suppliers of critical materials, automated equipment developers/manufacturers, inverter and other BOS manufacturers, a utility company, and University research groups. The program addressed all aspects of the crystalline silicon PV business from raw materials (particularly silicon feedstock) through installation of the system on the customers site. By involving the material and equipment vendors, we ensured that supplies of silicon feedstock and other PV specific materials like encapsulation materials (EVA and cover glass) will be available in the quantities required to meet the DOE goals of 5 to 10 GW of installed US PV by 2015 and at the prices necessary for PV systems to reach grid parity in 2015

  8. Characterization of Suspect Fuel Rod Pieces from the 105 K West Basin

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Pool, Karl N.; Thornton, Brenda M.

    2006-09-15

    This report provides physical and radiochemical characterization results from examinations and laboratory analyses performed on ~0.55-inch diameter rod pieces found in the 105 K West (KW) Basin that were suspected to be from nuclear reactor fuel. The characterization results will be used to establish the technical basis for adding this material to the contents of one of the final Multi-Canister Overpacks (MCOs) that will be loaded out of the KW Basin in late FY2006 or at a later time depending on project priorities. Fifteen fuel rod pieces were found during the clean out of the KW Basin. Based on lack of specific credentials, documentation, or obvious serial numbers, none of the items could be positively identified nor could their sources or compositions be described. Item weights and dimensions measured in the KW Basin indicated densities consistent with the suspect fuel rods containing uranium dioxide (UO2), uranium metal, or being empty. Extensive review of the Hanford Site technical literature led to the postulation that these pieces likely were irradiated test fuel prepared to support of the development of the Hanford “New Production Reactor,” later called N Reactor. To obtain definitive data on the composition of the suspect fuel, 4 representative fuel rod pieces, with densities corresponding to oxide fuel were selected from the 15 items, and shipped from the KW Basin to the Pacific Northwest National Laboratory’s (PNNL) Radiological Processing Laboratory (RPL; also known at the 325 Building) for examinations and characterization. The three fuel rod that were characterized appear to contain slightly irradiated UO2 fuel, originally of natural enrichment, with zirconium cladding. The uranium-235 isotopic concentrations decreased by the irradiation and become slightly lower than the natural enrichment of 0.72% to range from 0.67 to 0.71 atom%. The plutonium concentrations, ranged from about 200 to 470 grams per metric ton of uranium and ranged in Plutonium

  9. Analysis of photonic band gaps in two-dimensional photonic crystals with rods covered by a thin interfacial layer

    SciTech Connect (OSTI)

    Trifonov, T.; Marsal, L.F.; Pallares, J.; Rodriguez, A.; Alcubilla, R.

    2004-11-15

    We investigate different aspects of the absolute photonic band gap (PBG) formation in two-dimensional photonic structures consisting of rods covered with a thin dielectric film. Specifically, triangular and honeycomb lattices in both complementary arrangements, i.e., air rods drilled in silicon matrix and silicon rods in air, are studied. We consider that the rods are formed of a dielectric core (silicon or air) surrounded by a cladding layer of silicon dioxide (SiO{sub 2}), silicon nitride (Si{sub 3}N{sub 4}), or germanium (Ge). Such photonic lattices present absolute photonic band gaps, and we study the evolution of these gaps as functions of the cladding material and thickness. Our results show that in the case of air rods in dielectric media the existence of dielectric cladding reduces the absolute gap width and may cause complete closure of the gap if thick layers are considered. For the case of dielectric rods in air, however, the existence of a cladding layer can be advantageous and larger absolute PBG's can be achieved.

  10. First interim examination of defected BWR and PWR rods tested in unlimited air at 229/sup 0/C

    SciTech Connect (OSTI)

    Einziger, R.E.; Cook, J.A.

    1983-01-01

    A five-year whole rod test was initiated to investigate the long-term stability of spent fuel rods under a variety of possible dry storage conditions. Both PWR and BWR rods were included in the test. The first interim examination was conducted after three months of testing to determine if there was any degradation in those defected rods stored in an unlimited air atmosphere. Visual observations, diametral measurements and radiographic smears were used to assess the degree of cladding deformation and particulate dispersal. The PWR rod showed no measurable change from the pre-test condition. The two original artificial defects had not changed in appearance and there was no diametral growth of the cladding. One of the defects in BWR rod showed significant deformation. There was approximately 10% cladding strain at the defect site and a small axial crack had formed. The fuel in the defect did not appear to be friable. The second defect showed no visible change and no cladding strain. Following examination, the test was continued at 230/sup 0/C. Another interim examination is planned during the summer of 1983. This paper discusses the details and meaning of the data from the first interim examination.

  11. Screening of Potential Remediation Methods for the 200-BP-5 Operable Unit at the Hanford Site

    SciTech Connect (OSTI)

    Truex, Michael J.; Dresel, P. EVAN; Nimmons, Michael J.; Johnson, Christian D.

    2006-09-21

    A screening-level evaluation of potential remediation methods for application to the contaminants of concern (COC) in the 200-BP-5 Operable Unit at the Hanford Site was conducted based on the methods outlined in the Guidance for Conducting Remedial Investigations and Feasibility Studies under CERCLA Interim Final (EPA 1988). The scope of this screening was to identify the most promising remediation methods for use in the more detailed analysis of remediation alternatives that will be conducted as part of the full feasibility study. The screening evaluation was conducted for the primary COC (potential major risk drivers) identified in the groundwater sampling and analysis plan for the operable unit (DOE/RL-2001-49, Rev. 1) with additions.

  12. Superfund record of decision amendment (EPA Region 4): Wrigley Charcoal Superfund Site, Hickman County, Wrigley, TN, February 2, 1995

    SciTech Connect (OSTI)

    1995-03-01

    This decision document presents the selected Interim Remedial Action (IRA) for the Wrigley Charcoal Site, in Wrigley, Hickman County, Tennessee. The U.S. EPA has modified a wide variety of items that require immediate response action for the first step of cleanup activities to be taken at the Wrigley Charcoal Site. The major goal of these cleanup activities is to address the most serious threats at the Wrigley Charcoal Site by removing contaminated media from the Primary Site flood plain, remediating wastes at the Storage Basin, and through limited access restrictions at the Primary Site and the Storage Basin. The cleanup activities as presented in this IRA Record of Decision (ROD) Amendment will achieve significant risk reduction and will prepare the Site for future remedial activities.

  13. EIS-0218: Revised Record of Decision

    Office of Energy Efficiency and Renewable Energy (EERE)

    Revision of the Record of Decision for a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel

  14. Summary of Decisions- July 9- 13, 2012

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710) - Application for Exception

  15. Superfund Record of Decision (EPA Region 8): Anaconda Smelter site, (Operable Unit 11 - Flue Dust), Deer Lodge County, Anaconda, MT. (Second remedial action), September 1991

    SciTech Connect (OSTI)

    Not Available

    1991-09-23

    The 6,000-acre Anaconda Smelter site is a former copper and ore processing facility in Deer Lodge County, Montana. Land use in the area is predominantly residential. The site is bounded on the north and east, respectively, by the Warm Springs Creek and Mill Creek, both of which are potential sources of drinking water. From 1884 until 1980 when activities ceased, the site was used for ore processing and smelting operations. In 1988, EPA conducted an investigation to determine the nature and extent of the flue dust contamination. A 1988 ROD addressed the Mill Creek Operable Unit (OU15) and documented the relocation of residents from the community surrounding the smelter site as the selected remedial action. The Record of Decision (ROD) addresses the Flue Dust Operable Unit (OU11). The primary contaminants of concern affecting this site from the flue dust materials are metals including arsenic, cadmium, and lead. The selected remedial action for the site is included.

  16. Superfund Record of Decision (EPA Region 2): Sayreville Landfill site, Borough of Sayreville, Middlesex County, New Jersey (first remedial action), September 28, 1990

    SciTech Connect (OSTI)

    Not Available

    1990-09-28

    The 35-acre Sayreville Landfill site is an inactive municipal and industrial landfill in the Borough of Sayreville, Middlesex County, New Jersey. Beginning in 1971, the landfill was used to dispose of municipal and hazardous wastes, including an estimated 50 to 150 drums containing hazardous wastes. The drums were buried in a 20-acre area of the site. In 1977, landfill operations ceased, but subsequent unauthorized dumping of hazardous waste may have occurred. In 1980, a landfill closure plan was implemented by the borough, but was not properly completed. In 1981, the State excavated 30 drums containing benzene, pesticide-, and acid-contaminated liquids. The Record of Decision (ROD) addresses remediation of onsite drummed wastes. A subsequent ROD will address further source remediation (leachate) and remediation of ground and surface waters. The primary contaminants of concern affecting the soil and debris are VOCs including benzene, toluene, and xylenes; other organics including pesticides and phenols; acids; and metals including arsenic, chromium, and lead.

  17. Record of Decision for Ground Water | Department of Energy

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

    Record of Decision for Ground Water Record of Decision for Ground Water Record of Decision for Ground Water (April 1997) Record of Decision for Ground Water (625.12 KB) More Documents & Publications EIS-0198: Record of Decision EIS-0170: Record of Decision (April 1997) EIS-0251: Second Record of Decision (May 1997)

  18. EIS-0395: Record of Decision | Department of Energy

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

    Decision EIS-0395: Record of Decision San Luis Rio Colorado Project PDF icon Record of Decision for the Western Area Power Administration San Luis Rio Colorado Project, DOE...

  19. EIS-0289: Record of Decision | Department of Energy

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

    9: Record of Decision EIS-0289: Record of Decision JEA Circulating Fluidized Bed Combustor Project, Jacksonville, Duval County, FL Record of Decision; JEA Circulating Fluidized Bed...

  20. EIS-0229: Amended Record of Decision (April 2002) | Department...

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

    Decision (April 2002) EIS-0229: Amended Record of Decision (April 2002) Surplus Plutonium Disposition Program Amended Record of Decision: The U.S. Department of Energy's National...

  1. EIS-0378: Record of Decision | Department of Energy

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

    : Record of Decision EIS-0378: Record of Decision Port Angeles-Juan de Fuca Transmssion Project The Department of Energy announces its decision to implement its proposed actions...

  2. Summary of Decisions - March 16, 2015 - March 20, 2015 | Department...

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

    No decisions were issued during this week. Addthis Related Articles Summary of Decisions - March 2, 2015 - March 6, 2015 Summary of Decisions - November 2, 2015 - November 6, 2015...

  3. EIS-0323: Record of Decision | Department of Energy

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

    of Decision EIS-0323: Record of Decision Record of Decision for the Sacramento Area Voltage Support Environmental Impact Statement (DOEEIS-0323) (011204) PDF icon Record of...

  4. EIS-0410: Record of Decision | Department of Energy

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

    0: Record of Decision EIS-0410: Record of Decision Keystone Oil Pipeline Project Record of Decision for the Western Area Power Administration to modify three existing substation...

  5. EIS-0474: Record of Decision | Department of Energy

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

    Record of Decision EIS-0474: Record of Decision Southline Transmission Line Project; Arizona and New Mexico DOE's Western Area Power Administration issued a Record of Decision for ...

  6. EIS-0383: Record of Decision | Department of Energy

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

    Record of Decision EIS-0383: Record of Decision Orlando Gasification Project, Orlando, Orange County, FL Record of Decision for the environmental impact statement (EIS) (DOE...

  7. cognitive-based-decision-making

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

    November 29, 2011 From Cognitive-Based Decision Making To Car-Following Modeling: Beyond an Accident-Free Environment Dr. Samer Hamdar Assistant professor, George Washington University Tuesday, November 29, 2011 - 10am Argonne TRACC Building 222, Room D-233 In the year 2005, the monetary cost of injuries related to traffic accidents reached 625 billion USD (U. S. Dollars) in the U.S.A. only. Based on the National Highway Traffic Safety Agency (NHSTA) studies, 5 accident types of interest can be

  8. Simulation of human decision making

    DOE Patents [OSTI]

    Forsythe, J. Chris; Speed, Ann E.; Jordan, Sabina E.; Xavier, Patrick G.

    2008-05-06

    A method for computer emulation of human decision making defines a plurality of concepts related to a domain and a plurality of situations related to the domain, where each situation is a combination of at least two of the concepts. Each concept and situation is represented in the computer as an oscillator output, and each situation and concept oscillator output is distinguishable from all other oscillator outputs. Information is input to the computer representative of detected concepts, and the computer compares the detected concepts with the stored situations to determine if a situation has occurred.

  9. DESIGN OF WIRE-WRAPPED ROD BUNDLE MATCHED INDEX-OF-REFRACTION EXPERIMENTS

    SciTech Connect (OSTI)

    Hugh McIlroy; Hongbin Zhang; Kurt Hamman

    2008-05-01

    Experiments will be conducted in the Idaho National Laboratory (INL) Matched Index-of-Refraction (MIR) Flow Facility [1] to characterize the three-dimensional velocity and turbulence fields in a wire-wrapped rod bundle typically employed in liquid-metal cooled fast reactors and to provide benchmark data for computer code validation. Sodium cooled fast reactors are under consideration for use in the U.S. Department of Energy (DOE) Global Nuclear Energy Partnership (GNEP) program. The experiment model will be constructed of quartz components and the working fluid will be mineral oil. Accurate temperature control (to within 0.05 oC) matches the index-of-refraction of mineral oil with that of quartz and renders the model transparent to the wavelength of laser light employed for optical measurements. The model will be a scaled 7-pin rod bundle enclosed in a hexagonal canister. Flow field measurements will be obtained with a LaVision 3-D particle image velocimeter (PIV) and complimented by near-wall velocity measurements obtained from a 2-D laser Doppler velocimeter (LDV). These measurements will be used as benchmark data for computational fluid dynamics (CFD) validation. The rod bundle model dimensions will be scaled up from the typical dimensions of a fast reactor fuel assembly to provide the maximum Reynolds number achievable in the MIR flow loop. A range of flows from laminar to fully-turbulent will be available with a maximum Reynolds number, based on bundle hydraulic diameter, of approximately 22,000. The fuel pins will be simulated by 85 mm diameter quartz tubes (closed on the inlet ends) and the wire-wrap will be simulated by 25 mm diameter quartz rods. The canister walls will be constructed from quartz plates. The model will be approximately 2.13 m in length. Bundle pressure losses will also be measured and the data recorded for code comparisons. The experiment design and preliminary CFD calculations, which will be used to provide qualitative hydrodynamic

  10. Ground-State Properties of a One-Dimensional System of Hard Rods

    SciTech Connect (OSTI)

    Mazzanti, F.; Astrakharchik, G. E.; Boronat, J.; Casulleras, J.

    2008-01-18

    A quantum Monte Carlo simulation of a system of bosonic hard rods in one dimension is presented and discussed. The calculation is exact since the analytical form of the wave function is known and is in excellent agreement with predictions obtained from asymptotic expansions valid at large distances. The analysis of the static structure factor and the pair distribution function indicates that a solidlike and a gaslike phases exist at high and low densities, respectively. The one-body density matrix decays following a power law at large distances and produces a divergence in the low density momentum distribution at k=0 which can be identified as a quasicondensate.

  11. Composition and method of preparation of solid state dye laser rods

    DOE Patents [OSTI]

    Hermes, Robert E.

    1992-01-01

    The present invention includes solid polymeric-host laser rods prepared using bulk polymerization of acrylic acid ester comonomers which, when admixed with dye(s) capable of supporting laser oscillation and polymerized with a free radical initiator under mild thermal conditions, produce a solid product having the preferred properties for efficient lasing. Unsaturated polymerizable laser dyes can also be employed as one of the comonomers. Additionally, a method is disclosed which alleviates induced optical stress without having to anneal the polymers at elevated temperatures (>85.degree. C.).

  12. North Dome decision expected soon

    SciTech Connect (OSTI)

    Not Available

    1981-08-01

    Decisions soon will be made which will set in motion the development of Qatar's huge North Dome gas field. The government and state company, Qatar General Petroleum Corp. (QGPC) is studying the results of 2 feasibility studies on the economics of LNG export, although initially North Dome exploitation will be aimed at the domestic market. Decisions on the nature and timing of the North Dome development are the most important that have had to be faced in the short 10-yr history of the small Gulf state. The country's oil production is currently running at approximately 500,000 bpd, with 270,000 bpd originating from 3 offshore fields. Output is expected to decline through 1990, and it generally is accepted that there is little likelihood of further major crude discoveries. Therefore, Qatar has to begin an adjustment from an economy based on oil to one based on gas, while adhering to the underlying tenets of long-term conservation and industrial diversification.

  13. FRAPCON-2: A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods

    SciTech Connect (OSTI)

    Berna, G. A; Bohn, M. P.; Rausch, W. N.; Williford, R. E.; Lanning, D. D.

    1981-01-01

    FRAPCON-2 is a FORTRAN IV computer code that calculates the steady state response of light Mater reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, deformation, and tai lure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (a) heat conduction through the fuel and cladding, (b) cladding elastic and plastic deformation, (c) fuel-cladding mechanical interaction, (d) fission gas release, (e} fuel rod internal gas pressure, (f) heat transfer between fuel and cladding, (g) cladding oxidation, and (h) heat transfer from cladding to coolant. The code contains necessary material properties, water properties, and heat transfer correlations. FRAPCON-2 is programmed for use on the CDC Cyber 175 and 176 computers. The FRAPCON-2 code Is designed to generate initial conditions for transient fuel rod analysis by either the FRAP-T6 computer code or the thermal-hydraulic code, RELAP4/MOD7 Version 2.

  14. BP Exploration`s Pompano subsea development: Operational strategy for a subsea project

    SciTech Connect (OSTI)

    Clarke, D.G.; Cordner, J.P.

    1996-12-31

    On a platform, facility modifications to cope with unexpected operating conditions or unanticipated problems may be made relatively easily at moderate cost. In contrast, subsea systems are placed on the seabed often beyond diver depth and are difficult if not impossible to retrieve or modify. Consequently the design must be optimized up front and have sufficient inherent flexibility to cope with the unexpected. It is therefore critical to develop an operational strategy in conjunction with suppliers, designers and operational staff, concurrently with the design. Input from Operations personnel is necessary from project conception throughout detailed design, fabrication, system integrating testing, installation and commissioning. This paper discusses BP Exploration`s work on the Pompano subsea project in the Gulf of Mexico and addresses many of the practical aspects in which Operations staff need to become involved with throughout a subsea project to ensure a problem free start-up and operation. It will provide a useful guide for Operations groups involved in the planning and operation of a subsea development

  15. 200-BP-1 Prototype Hanford Barrier -- 15 Years of Performance Monitoring

    SciTech Connect (OSTI)

    Ward, Anderson L.; Draper, Kathryn E.; Link, Steven O.; Clayton, Ray E.

    2011-09-30

    Monitoring is an essential component of engineered barrier system design and operation. A composite capacitive cover, including a capillary break and an evapotranspiration (ET) barrier at the Hanford Site, is generating data that can be used to help resolve these issues. The prototype Hanford barrier was constructed over the 216-B-57 Crib in 1994 to evaluate surface-barrier constructability, construction costs, and physical and hydrologic performance at the field scale. The barrier has been routinely monitored between November 1994 and September 1998 as part of a Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) treatability test of barrier performance for the 200 BP 1 Operable Unit. Since FY 1998, monitoring has focused on a more limited set of key water balance, stability, and biotic parameters. In FY 2009, data collection was focused on: (1) water-balance monitoring, consisting of precipitation, runoff, soil moisture storage, and drainage measurements with evapotranspiration calculated by difference; (2) stability monitoring, consisting of asphalt-layer-settlement, basalt-side-slope-stability, and surface-elevation measurements; (3) vegetation dynamics; and (4) animal use. September 2009 marked 15 years since the start of monitoring and the collection of performance data. This report describes the results of monitoring activities during the period October 1, 2008, through September 30, 2009, and summarizes the 15 years of performance data collected from September 1994 through September 2009.

  16. Alternative S2 Hinge Regions of the Myosin Rod Affect Myofibrillar Structure and Myosin Kinetics

    SciTech Connect (OSTI)

    Miller, Mark S.; Dambacher, Corey M.; Knowles, Aileen F.; Braddock, Joan M.; Farman, Gerrie P.; Irving, Thomas C.; Swank, Douglas M.; Bernstein, Sanford I.; Maughan, David W.

    2009-07-01

    The subfragment 2/light meromyosin 'hinge' region has been proposed to significantly contribute to muscle contraction force and/or speed. Transgenic replacement of the endogenous fast muscle isovariant hinge A (exon 15a) in Drosophila melanogaster indirect flight muscle with the slow muscle hinge B (exon 15b) allows examination of the structural and functional changes when only this region of the myosin molecule is different. Hinge B was previously shown to increase myosin rod length, increase A-band and sarcomere length, and decrease flight performance compared to hinge A. We applied additional measures to these transgenic lines to further evaluate the consequences of modifying this hinge region. Structurally, the longer A-band and sarcomere lengths found in the hinge B myofibrils appear to be due to the longitudinal addition of myosin heads. Functionally, hinge B, although a significant distance from the myosin catalytic domain, alters myosin kinetics in a manner consistent with this region increasing myosin rod length. These structural and functional changes combine to decrease whole fly wing-beat frequency and flight performance. Our results indicate that this hinge region plays an important role in determining myosin kinetics and in regulating thick and thin filament lengths as well as sarcomere length.

  17. Zirconium-based alloys, nuclear fuel rods and nuclear reactors including such alloys, and related methods

    DOE Patents [OSTI]

    Mariani, Robert Dominick

    2014-09-09

    Zirconium-based metal alloy compositions comprise zirconium, a first additive in which the permeability of hydrogen decreases with increasing temperatures at least over a temperature range extending from 350.degree. C. to 750.degree. C., and a second additive having a solubility in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. At least one of a solubility of the first additive in the second additive over the temperature range extending from 350.degree. C. to 750.degree. C. and a solubility of the second additive in the first additive over the temperature range extending from 350.degree. C. to 750.degree. C. is higher than the solubility of the second additive in zirconium over the temperature range extending from 350.degree. C. to 750.degree. C. Nuclear fuel rods include a cladding material comprising such metal alloy compositions, and nuclear reactors include such fuel rods. Methods are used to fabricate such zirconium-based metal alloy compositions.

  18. Nanostructures of Liquid Crystal Phases in Mixtures of Bent-core and Rod-shaped Molecules

    SciTech Connect (OSTI)

    S Hong; R Verduzco; J Gleeson; S Sprunt; A Jakli

    2011-12-31

    We report small angle x-ray scattering (SAXS) studies of isotropic, nematic, and smectic mesophases formed by binary mixtures of bent-core (BC) and rod-shaped (RS) molecules. While optical studies indicate that the components are fully miscible, SAXS reveals fascinating structures that are consistent with segregation on a nanoscopic scale. We find that tilted smectic clusters, which have been previously reported in both the nematic and isotropic states of the pure BC materials, are also present in mixtures with up to 50 wt% of the RS compound; this is consistent with previous dielectric and flexoelectric studies on such mixtures. Unexpectedly in this concentration range the clusters are present in the isotropic and in the induced smectic phase range, as well as throughout the nematic phase. The results in the smectic phase also reveal complex layering phenomena, providing important insight into the interaction between bent and rod-shaped molecules. These studies will be crucial in the design of promising new functional nanomaterials.

  19. Nanostructures of liquid crystal phases in mixtures of bent-core and rod-shaped molecules

    SciTech Connect (OSTI)

    Hong, S. H.; Gleeson, J. T.; Sprunt, S.; Verduzco, R.; Jakli, A.

    2011-06-15

    We report small angle x-ray scattering (SAXS) studies of isotropic, nematic, and smectic mesophases formed by binary mixtures of bent-core (BC) and rod-shaped (RS) molecules. While optical studies indicate that the components are fully miscible, SAXS reveals fascinating structures that are consistent with segregation on a nanoscopic scale. We find that tilted smectic clusters, which have been previously reported in both the nematic and isotropic states of the pure BC materials, are also present in mixtures with up to 50 wt% of the RS compound; this is consistent with previous dielectric and flexoelectric studies on such mixtures. Unexpectedly in this concentration range the clusters are present in the isotropic and in the induced smectic phase range, as well as throughout the nematic phase. The results in the smectic phase also reveal complex layering phenomena, providing important insight into the interaction between bent and rod-shaped molecules. These studies will be crucial in the design of promising new functional nanomaterials.

  20. Production optimization of sucker rod pumping wells producing viscous oil in Boscan field, Venezuela

    SciTech Connect (OSTI)

    Guirados, C.; Sandoval, J.; Rivas, O.; Troconis, H.

    1995-12-31

    Boscan field is located in the western coast of Maracaibo lake and is operated by Maraven S.A., affiliate of Petroleos de Venezuela S.A. It has 315 active wells, 252 of which are produced with sucker rod pumping. Other artificial lift methods currently applied in this field are hydraulic (piston) pumping (39 wells) and ESP (24 wells). This paper presents the results of the production optimization of two sucker rod pumping wells of Boscan field producing viscous oil. This optimization has been possible due to the development of a new production scheme and the application of system analysis in completion design. The new production scheme involves the utilization of a subsurface stuffing box assembly and a slotted housing, both designed and patented by Intevep S.A., affiliate of Petroleos de Venezuela S.A. The completion design method and software used in the optimization study were also developed by Intevep S.A. The new production scheme and design method proved to be effective in preventing the causes of the above mentioned problems, allowing the increase of oil production under better operating conditions.

  1. Facts about the Plutonium Record of Decision | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Facts about the Plutonium Record of Decision Facts about the Plutonium Record of Decision

  2. Microsoft Word - DRAFT PTPC WTL ROD 5 1 12 FINAL.doc

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

    DRAFT RECORD OF DECISION: DRAFT AMENDMENT TO FIRM POWER SALES AGREEMENT WITH PORT TOWNSEND PAPER CORPORATION, CONTRACT NO. 11PB-12330 May 3, 2012 i TABLE OF CONTENTS I....

  3. Critical Decision Handbook | Department of Energy

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

    Critical Decision Handbook Critical Decision Handbook This Handbook is designed as a practical tool for the Office of Environmental Management (EM) Federal Project Directors (FPDs), Integrated Project Teams (IPTs), Technical Authority Board (TAB), and senior management to ensure that issues and risks that could challenge the success of EM projects are identified early and proactively addressed. Critical Decision Handbook (3.64 MB) More Documents & Publications Standard Review Plan - Overview

  4. Tank Farm Area Cleanup Decision-Making

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

    Area Cleanup Decision-Making Groundwater Vadose Zone Single Shell Tank System Closure (tanks, structures and pipelines) * Washington State Hazardous Waste Management Act (Resource...

  5. Simulation, Modeling & Decision Science | The Ames Laboratory

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

    Research Laboratory focuses on integration of information technologies and cognition into the engineering process to support decision making for and the realization of...

  6. Creating ensembles of decision trees through sampling

    DOE Patents [OSTI]

    Kamath, Chandrika; Cantu-Paz, Erick

    2005-08-30

    A system for decision tree ensembles that includes a module to read the data, a module to sort the data, a module to evaluate a potential split of the data according to some criterion using a random sample of the data, a module to split the data, and a module to combine multiple decision trees in ensembles. The decision tree method is based on statistical sampling techniques and includes the steps of reading the data; sorting the data; evaluating a potential split according to some criterion using a random sample of the data, splitting the data, and combining multiple decision trees in ensembles.

  7. STABILIZED RARE EARTH OXIDES FOR A CONTROL ROD AND METHOD OF PREPARATION

    DOE Patents [OSTI]

    McNees, R.A.; Potter, R.A.

    1964-01-14

    A method is given for preparing mixed oxides of the formula MR/sub x/O/ sub 12/ wherein M is tungsten or molybdenum and R is a rare earth in the group consisting of samarium, europium, dysprosium, and gadolinium and x is 4 to 5. Oxides of this formula, and particularly the europiumcontaining species, are useful as control rod material for water-cooled nuclear reactors owing to their stability, favorable nuclear properties, and resistance to hydration. These oxides may be utilized as a dispersion in a stainlesssteel matrix. Preparation of these oxides is effected by blending tungsten oxide or molybdenum oxide with a rare earth oxide, compressing the mixture, and firing at an elevated temperature in an oxygen-containing atmosphere. (AEC)

  8. Fabrication of carbon nanotube emitters on the graphite rod and their high field emission performance

    SciTech Connect (OSTI)

    Sun, Yuning; Hoon Shin, Dong; Nam Yun, Ki; Song, Yenan; Saito, Yahachi; Jin Lee, Cheol

    2014-01-27

    Carbon nanotube (CNT) emitters with small emission area were fabricated on graphite rods using CNT films. By introducing the edge polishing process, the field emission performance of the CNT emitter was much improved, which showed a very high emission current of 6.34 mA (1.6 A/cm{sup 2}) under an applied electric field of 5.3 V/μm. It also indicates good long-term emission stability, which reveals no degradation in the emission current for 20 h. The emission patterns demonstrate uniform and well-focused electron beam spots. The enhanced field emission performance is mainly attributed to the suppressed edge emission after the edge polishing process.

  9. Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior

    SciTech Connect (OSTI)

    R. L. Williamson

    2011-08-01

    A powerful multidimensional fuels performance analysis capability, applicable to both steady and transient fuel behavior, is developed based on enhancements to the commercially available ABAQUS general-purpose thermomechanics code. Enhanced capabilities are described, including: UO2 temperature and burnup dependent thermal properties, solid and gaseous fission product swelling, fuel densification, fission gas release, cladding thermal and irradiation creep, cladding irradiation growth, gap heat transfer, and gap/plenum gas behavior during irradiation. This new capability is demonstrated using a 2D axisymmetric analysis of the upper section of a simplified multipellet fuel rod, during both steady and transient operation. Comparisons are made between discrete and smeared-pellet simulations. Computational results demonstrate the importance of a multidimensional, multipellet, fully-coupled thermomechanical approach. Interestingly, many of the inherent deficiencies in existing fuel performance codes (e.g., 1D thermomechanics, loose thermomechanical coupling, separate steady and transient analysis, cumbersome pre- and post-processing) are, in fact, ABAQUS strengths.

  10. Synthesis and Analysis of Alpha Silicon Carbide Components for Encapsulation of Fuel Rods and Pellets

    SciTech Connect (OSTI)

    Kevin M. McHugh; John E. Garnier; George W. Griffith

    2011-09-01

    The chemical, mechanical and thermal properties of silicon carbide (SiC) along with its low neutron activation and stability in a radiation field make it an attractive material for encapsulating fuel rods and fuel pellets. The alpha phase (6H) is particularly stable. Unfortunately, it requires very high temperature processing and is not readily available in fibers or near-net shapes. This paper describes an investigation to fabricate a-SiC as thin films, fibers and near-net-shape products by direct conversion of carbon using silicon monoxide vapor at temperatures less than 1700 C. In addition, experiments to nucleate the alpha phase during pyrolysis of polysilazane, are also described. Structure and composition were characterized using scanning electron microscopy, energy dispersive spectroscopy and X-ray diffraction. Preliminary tensile property analysis of fibers was also performed.

  11. Controlled rolling process for dual phase steels and application to rod, wire, sheet and other shapes

    DOE Patents [OSTI]

    Thomas, G.; Ahn, J.H.; Kim, N.J.

    1986-10-28

    An improved, energy efficient, hot rolling method for direct production of cold formable dual-phase steel is provided. The steel is heated to completely austenitize it and then continuously hot rolled and cooled down into the ferrite-austenite two phase region to a temperature which is just below the effective Ar[sub 3] temperature. The hot rolled steel is then rapidly quenched to provide an alloy containing strong, tough lath martensite (fibers) in a ductile soft ferrite matrix. The method is particularly useful for providing rods in which form the alloy is capable of being drawn into high strength wire or the like in a cold drawing operation without any intermediate annealing or patenting, and has excellent strength, ductility and fatigue characteristics. 3 figs.

  12. Enhancing the ABAQUS Thermomechanics Code to Simulate Steady and Transient Fuel Rod Behavior

    SciTech Connect (OSTI)

    R. L. Williamson; D. A. Knoll

    2009-09-01

    A powerful multidimensional fuels performance capability, applicable to both steady and transient fuel behavior, is developed based on enhancements to the commercially available ABAQUS general-purpose thermomechanics code. Enhanced capabilities are described, including: UO2 temperature and burnup dependent thermal properties, solid and gaseous fission product swelling, fuel densification, fission gas release, cladding thermal and irradiation creep, cladding irradiation growth , gap heat transfer, and gap/plenum gas behavior during irradiation. The various modeling capabilities are demonstrated using a 2D axisymmetric analysis of the upper section of a simplified multi-pellet fuel rod, during both steady and transient operation. Computational results demonstrate the importance of a multidimensional fully-coupled thermomechanics treatment. Interestingly, many of the inherent deficiencies in existing fuel performance codes (e.g., 1D thermomechanics, loose thermo-mechanical coupling, separate steady and transient analysis, cumbersome pre- and post-processing) are, in fact, ABAQUS strengths.

  13. Controlled rolling process for dual phase steels and application to rod, wire, sheet and other shapes

    DOE Patents [OSTI]

    Thomas, Gareth; Ahn, Jae-Hwan; Kim, Nack-Joon

    1986-01-01

    An improved, energy efficient, hot rolling method for direct production of cold formable dual-phase steel is provided. The steel is heated to completely austenitize it and then continuously hot rolled and cooled down into the ferrite-austenite two phase region to a temperature which is just below the effective Ar.sub.3 temperature. The hot rolled steel is then rapidly quenched to provide an alloy containing strong, tough lath martensite (fibers) in a ductile soft ferrite matrix. The method is particularly useful for providing rods in which form the alloy is capable of being drawn into high strength wire or the like in a cold drawing operation without any intermediate annealing or patenting, and has excellent strength, ductility and fatigue characteristics.

  14. Production of energetic neutral particles and low energy electrons from four anode rods ion source

    SciTech Connect (OSTI)

    Mostafa, O. A.; El-Khabeary, H.; Abdel Reheem, A. M.

    2013-11-15

    The factors affecting the energetic neutral current, the low energy electron current, and the positive ion current emerging from a four-anode-rods ion source have been studied using argon gas. The neutral and electron current were measured using a simple, new technique. It was found that the energetic neutral current and the electron current depend on the positive ion current and the gas pressure. The ratio of the neutral and electron current to the positive ion current increases by increasing the gas pressure. Also it was found that at a pressure equal to 9 10{sup ?4} mmHg, the ratio of the neutral to the positive ion current reaches 2.34 while the ratio of the electron current to the positive ion current reaches 1.7.

  15. Licensing of spent fuel dry storage and consolidated rod storage: A Review of Issues and Experiences

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-02-01

    The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs.

  16. Bending testing and characterization of surrogate nuclear fuel rods made of Zircaloy-4 cladding and aluminum oxide pellets

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

    Wang, Hong; Wang, Jy-An John

    2016-07-20

    We studied behavior of surrogate nuclear fuel rods made of Zircaloy-4 (Zry-4) cladding with alumina pellets under reversed cyclic bending. Tests were performed under load or moment control at 5 Hz, and an empirical correlation was established between rod fatigue life and amplitude of the applied moment. Fatigue response of Zry-4 cladding was further characterized by using flexural rigidity. Degradation of flexural rigidity was shown to depend on the moment applied and the prefatigue condition of specimens. Pellet-to-pellet interface (PPI), pellet-to-cladding interface (PCI), and pellet condition all affect surrogate rod failure. Bonding/debonding of PPI/PCI and pellet fracturing contribute to surrogatemore » rod bending fatigue. Also, the effect of sensor spacing on curvature measurement using three-point deflections was studied; the method based on effective specimen gauge length is effective in sensor spacing correction. Finally, we developed the database and gained understanding in this study such that it will serve as input to analysis of SNF vibration integrity.« less

  17. Thermal performance of a buried nuclear waste storage container storing a hybrid mix of PWR and BWR spent fuel rods

    SciTech Connect (OSTI)

    Johnson, G.L.

    1988-09-01

    Lawrence Livermore National Laboratory will design, model, and test nuclear waste packages for use at the Nevada Nuclear Waste Storage Repository at Yucca Mountain, Nevada. One such package would store lightly packed spent fuel rods from both pressurized and boiling water reactors. The storage container provides the primary containment of the nuclear waste and the spent fuel rod cladding provides secondary containment. A series of transient conduction and radiation heat transfer analyses was run to determine for the first 1000 yr of storage if the temperature of the tuff at the borehole wall ever falls below 97{degree}C and whether the cladding of the stored spent fuel ever exceeds 350{degree}C. Limiting the borehole to temperatures of 97{degree}C or greater helps minimize corrosion by assuring that no condensed water collects on the container. The 350{degree}C cladding limit minimizes the possibility of creep-related failure in the spent fuel rod cladding. For a series of packages stored in a 8 x 30 m borehole grid where each package contains 10-yr-old spent fuel rods generating 4.74 kW or more, the borehole wall stays above 97{degree}C for the full 1000-yr analysis period.

  18. EIS-0220: Amended Record of Decision | Department of Energy

    Office of Environmental Management (EM)

    Materials: Savannah River Site Waste Management In this amended ROD, DOE is announcing that it ... a small portion of a second type of nuclear materials analyzed in the IMNM EIS. ...

  19. Summary of Decisions - February 8, 2016 - February 12, 2016 | Department

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

    of Energy 8, 2016 - February 12, 2016 Summary of Decisions - February 8, 2016 - February 12, 2016 February 12, 2016 - 1:44pm Addthis No reportable decisions were issued during this week Addthis Related Articles Summary of Decisions - December 24, 2012 - December 28, 2012 Summary of Decisions - December 31, 2012 - January 4, 2013 Summary of Decisions - March 2, 2015 - March 6

  20. Summary of Decisions - December 24, 2012 - December 28, 2012 | Department

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

    of Energy 24, 2012 - December 28, 2012 Summary of Decisions - December 24, 2012 - December 28, 2012 December 28, 2012 - 1:22pm Addthis No decisions were issued during this week. Addthis Related Articles Summary of Decisions - December 31, 2012 - January 4, 2013 Summary of Decisions - March 2, 2015 - March 6, 2015 Summary of Decisions - March 16, 2015 - March 20

  1. Summary of Decisions - December 31, 2012 - January 4, 2013 | Department

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

    of Energy 31, 2012 - January 4, 2013 Summary of Decisions - December 31, 2012 - January 4, 2013 January 4, 2013 - 8:38am Addthis No decisions were issued during this week Addthis Related Articles Summary of Decisions - December 24, 2012 - December 28, 2012 Summary of Decisions - January 5, 2015 - January 9, 2015 Summary of Decisions - March 2, 2015 - March 6, 2015

  2. Superfund record of decision: Memphis Defense Depot (DLA), Aka: Defense depot, operable unit 1, Memphis, TN. (Interim remedial action), May 1, 1996

    SciTech Connect (OSTI)

    1997-04-01

    This decision document (Record of Decision (ROD)) presents the selected interim remedial action (IRA) for the DDMT site, Memphis, Tennessee. The major components of the selected IRA for OU-1 include: evaluation of aquifer characteristics which may include installation of a pump test well; installation of additional monitoring wells to locate the western edge of the groundwater plume; installation of recovery wells along the leading edge of the plume; obtaining discharge permit for disposal of recovered groundwater to the T.E. Maxson Wastewater Treatment Plant publicly owned treatment works (POTW) or municipal sewer system; operation of the system of recovery wells unit the risk associated with the contaminants is reduced to acceptable levels or until the final remedy is in place; and chemical analysis will be conducted to monitor the quality of the discharge in accordance with the city discharge permit requirements; the permit will include parameters to be monitored and frequency.

  3. Analytical Data Report for Sediment Samples Collected From 200 BP 5 OU, C7515 (299-E24-25) M-Well

    SciTech Connect (OSTI)

    Lindberg, Michael J.

    2010-06-18

    This is an analytical data report for sediments received from BP 5 M Well for geochemical studies. Data will be reported to CH2M HILL Plateau Remediation Company (CHPRC).

  4. Structural Insights into Membrane Targeting by the Flagellar Calcium-binding Protein (FCaBP) a Myristoylated and Palmitoylated Calcium Sensor in Trypanosoma cruzi

    SciTech Connect (OSTI)

    J Wingard; J Ladner; M Vanarotti; A Fisher; H Robinson; K Buchanan; D Engman; J Ames

    2011-12-31

    The flagellar calcium-binding protein (FCaBP) of the protozoan Trypanosoma cruzi is targeted to the flagellar membrane where it regulates flagellar function and assembly. As a first step toward understanding the Ca{sup 2+}-induced conformational changes important for membrane-targeting, we report here the x-ray crystal structure of FCaBP in the Ca{sup 2+}-free state determined at 2.2{angstrom} resolution. The first 17 residues from the N terminus appear unstructured and solvent-exposed. Residues implicated in membrane targeting (Lys-19, Lys-22, and Lys-25) are flanked by an exposed N-terminal helix (residues 26-37), forming a patch of positive charge on the protein surface that may interact electrostatically with flagellar membrane targets. The four EF-hands in FCaBP each adopt a 'closed conformation' similar to that seen in Ca{sup 2+}-free calmodulin. The overall fold of FCaBP is closest to that of grancalcin and other members of the penta EF-hand superfamily. Unlike the dimeric penta EF-hand proteins, FCaBP lacks a fifth EF-hand and is monomeric. The unstructured N-terminal region of FCaBP suggests that its covalently attached myristoyl group at the N terminus may be solvent-exposed, in contrast to the highly sequestered myristoyl group seen in recoverin and GCAP1. NMR analysis demonstrates that the myristoyl group attached to FCaBP is indeed solvent-exposed in both the Ca{sup 2+}-free and Ca{sup 2+}-bound states, and myristoylation has no effect on protein structure and folding stability. We propose that exposed acyl groups at the N terminus may anchor FCaBP to the flagellar membrane and that Ca{sup 2+}-induced conformational changes may control its binding to membrane-bound protein targets..

  5. Superfund record of decision (EPA Region 1): Fletcher`s Paint Works and Storage, Milford, NH, September 30, 1998

    SciTech Connect (OSTI)

    1999-03-01

    This decision document presents the selected remedial action for the Fletcher`s Paint Works and Storage Facility Superfund Site (Site) located in Milford, New Hampshire. This ROD sets forth the selected remedy for Operable Unit On at the Fletcher`s Paint Site, which involves the excavation and on-site treatment of principal threat wastes which consist of primarily PCB contaminated soils, the replacement of those treated soils at the Site, and placement of a soil and asphalt cover over the residual low level threat wastes. The selected remedy also includes monitored natural attenuation of the contaminated groundwater in the overburdened and bedrock aquifers and institutional controls to prevent future ingestion of contaminated groundwater, as well as restrictions on the use and assess to the subsurface soils at the Elm Street Site.

  6. P:\\DECISION\\0071.tee.wpd

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

    number of the decision in the search engine located at http:www.oha.doe.govsearch.htm. ... (firm in bankruptcy); the firm's only employee capable of preparing the report is ill ...

  7. Decisions that led to Y-12

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

    Decisions that led to Y-12 Last week we saw the political and organizational changes that led up to the Manhattan Project being created on August 13, 1942. The S-1 Executive ...

  8. Final decisions that led to Y-12

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

    decisions that led to Y-12 As we have seen earlier in this series, Ernest O. Lawrence and ... By late 1942, progress on the reactor technology being led by Enrico Fermi at the ...

  9. Quality Assurance for Critical Decision Reviews RM

    Broader source: Energy.gov [DOE]

    The purpose of this Quality Assurance for Capital Project Critical Decision Review Module (QA RM) is to identify, integrate, and clarify the QA performance objectives, criteria, and guidance needed...

  10. 5(b)/9(c) Record of Decision

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

    of the limit. See NRP080005, at 2-3. Evaluation and Decision: BPA acknowledges that a literal reading of the calculation method referenced in Seattle et al.'s comment is...

  11. EIS-0275: Record of Decision | Department of Energy

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

    5: Record of Decision EIS-0275: Record of Decision Disposal of the S1C Prototype Reactor Plant This Record of Decision has been prepared on the proposed disposal of the defueled...

  12. EIS-0377: Record of Decision | Department of Energy

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

    Record of Decision EIS-0377: Record of Decision Big Stone II Power Plant and Transmission Project Department of Energy announces its record of decision for the Big Stone II Power...

  13. Property:NEPA Decision Url | Open Energy Information

    Open Energy Info (EERE)

    Decision Url Jump to: navigation, search Property Name NEPA Decision Url Property Type URL Description URLs to decisions on NEPA Docs This is a property of type URL. Retrieved from...

  14. Geospatial Decision Making System - Energy Innovation Portal

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

    Biomass and Biofuels Biomass and Biofuels Find More Like This Return to Search Geospatial Decision Making System Idaho National Laboratory Contact INL About This Technology Technology Marketing Summary The INL has developed a geospatial decision making process to assist agricultural producers in optimizing operating conditions of combine harvesters which detects the presence of grain and distinguishes between that and residual plant material. Upon detecting grain in the process, the system sends

  15. Parallel object-oriented decision tree system

    DOE Patents [OSTI]

    Kamath; Chandrika , Cantu-Paz; Erick

    2006-02-28

    A data mining decision tree system that uncovers patterns, associations, anomalies, and other statistically significant structures in data by reading and displaying data files, extracting relevant features for each of the objects, and using a method of recognizing patterns among the objects based upon object features through a decision tree that reads the data, sorts the data if necessary, determines the best manner to split the data into subsets according to some criterion, and splits the data.

  16. EIS-0374: Record of Decision | Department of Energy

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

    Record of Decision EIS-0374: Record of Decision Klondike III Biglow Canyon Wind Integration Project The Bonneville Power Administration (BPA) has decided to implement the Proposed...

  17. EIS-0427: Record of Decision | Department of Energy

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

    7: Record of Decision EIS-0427: Record of Decision Interconnection of the Grapevine Canyon Wind Project, Coconino County, Arizona Western Area Power Administration (Western)...

  18. EIS-0345: Record of Decision | Department of Energy

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

    Record of Decision EIS-0345: Record of Decision Electrical Interconnection of the Plymouth Generating Facility The Bonneville Power Administration (BPA) has decided to implement...

  19. EIS-0413: Record of Decision | Department of Energy

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

    3: Record of Decision EIS-0413: Record of Decision Searchlight Wind Energy Project, Searchlight, NV After considering potential environmental impacts, Western Area Power ...

  20. EIS-0319: Record of Decision | Department of Energy

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

    Record of Decision EIS-0319: Record of Decision Relocation of Technical Area 18 Capabilities and Materials at the Los Alamos National Laboratory The Department of Energy's (DOE's)...

  1. EIS-0197: Record of Decision (November 1996) | Department of...

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

    Record of Decision (November 1996) EIS-0197: Record of Decision (November 1996) Delivery of the Canadian Entitlement The United States Entity (the Administrator of the Bonneville...

  2. EIS-0372: Record of Decision and Floodplain Statement of Findings...

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

    Record of Decision and Floodplain Statement of Findings EIS-0372: Record of Decision and Floodplain Statement of Findings Bangor Hydro-Electric Company Northeast Reliability...

  3. EIS-0119: Amended Record of Decision | Department of Energy

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

    : Amended Record of Decision EIS-0119: Amended Record of Decision Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington DOE has decided to...

  4. EIS-0246: Record of Decision | Department of Energy

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

    : Record of Decision EIS-0246: Record of Decision Wildlife Mitigation Program BPA has decided to adopt the set of prescriptions (goals, strategies, and procedural requirements)...

  5. EIS-0456: Record of Decision and Floodplain Statement of Findings...

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

    Record of Decision and Floodplain Statement of Findings EIS-0456: Record of Decision and Floodplain Statement of Findings Cushman Hydroelectric Project, Mason County, Washington...

  6. EIS-0230: Record of Decision | Department of Energy

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

    30: Record of Decision EIS-0230: Record of Decision Electrical Interconnection of the Chehalis Generation Facility Bonneville Power Administration (BPA) has decided to offer...

  7. EIS-0343: Record of Decision | Department of Energy

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

    Record of Decision EIS-0343: Record of Decision Electrical Interconnection of the COB Energy Facility The Bonneville Power Administration (BPA) has decided to offer contract terms...

  8. EIS-0198: Record of Decision | Department of Energy

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

    8: Record of Decision EIS-0198: Record of Decision Uranium Mill Tailings Remedial Action (UMTRA) Ground Water Project (April 1997) The Department of Energy (DOE) is issuing this...

  9. EIS-0330: Record of Decision | Department of Energy

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

    Record of Decision EIS-0330: Record of Decision Wallula-McNary Transmission Line Project and Wallula Power Project The Bonneville Power Administration (BPA) has decided to...

  10. EIS-0240: Record of Decision | Department of Energy

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

    : Record of Decision EIS-0240: Record of Decision Disposition of Surplus Highly Envirched Uranium The Department of Energy (DOE) has decided to implement a program to make surplus...

  11. EIS-0183: Record of Decision | Department of Energy

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

    in the wholesale power market. PDF icon DOEEIS-0183, Administrator's Record of Decision, Bonneville Power Administration, GNA Cliffs Energy Project, Record of Decision...

  12. EIS-0197: Supplement to Record of Decision | Department of Energy

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

    Supplement to Record of Decision EIS-0197: Supplement to Record of Decision Delivery of the Canadian Entitlement The United States Entity has decided to supplement an earlier...

  13. EIS-0225: Record of Decision | Department of Energy

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

    : Record of Decision EIS-0225: Record of Decision Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components The Department of Energy is issuing...

  14. EIS-0454: Record of Decision | Department of Energy

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

    Record of Decision EIS-0454: Record of Decision Tonopah Solar Energy, LLC, Crescent Dunes Solar Energy Project (September 2011) For more information, contact: Ms. Angela Colamaria,...

  15. Decision Support for Operations and Maintenance (DSOM) - Energy...

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

    Decision Support for Operations and Maintenance (DSOM) Pacific Northwest National ... The Decision Support for Operations and Maintenance (DSOM) system is an expert ...

  16. EIS-0082-S2: Record of Decision | Department of Energy

    Energy Savers [EERE]

    Record of Decision EIS-0082-S2: Record of Decision Savannah River Site Salt Processing Alternatives, Aiken, South Carolina The Savannah River Site Salt Processing Alternatives ...

  17. EIS-0440: Record of Decision | Department of Energy

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

    0: Record of Decision EIS-0440: Record of Decision Quartzsite Solar Energy Project, La Paz County, AZ After considering potential environmental impacts, Western Area Power ...

  18. EIS-0161: Record of Decision | Department of Energy

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

    of Decision Tritium Supply and Recycling The Department of Energy (DOE) is issuing this Record of Decision regarding DOE's proposal for Tritium Supply and Recycling Facilities. ...

  19. EIS-0421: Record of Decision | Department of Energy

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

    Decision EIS-0421: Record of Decision Big Eddy-Knight Transmission Project Wasco County, Oregon and Klickitat County, Washington For more information contact: Ms. Stacy Mason,...

  20. EIS-0325: Record of Decision | Department of Energy

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

    Record of Decision EIS-0325: Record of Decision Schultz-Hanford Area Transmission Line Project Bonneville Power Administration has decided to implement the Agency Preferred...

  1. EIS-0255: Record of Decision | Department of Energy

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

    of Decision EIS-0255: Record of Decision Execution of Agreements to Install Additional Wind Turbines at the Wyoming Windpower Plant BPA has decided to execute one or more...

  2. Materials Down Select Decisions Made Within DOE's Chemical Hydrogen...

    Office of Environmental Management (EM)

    Down Select Decisions Made Within DOE's Chemical Hydrogen Storage Center of Excellence Materials Down Select Decisions Made Within DOE's Chemical Hydrogen Storage Center of ...

  3. Summary of Decisions - January 5, 2015 - January 9, 2015 | Department...

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

    the noted period. Addthis Related Articles Summary of Decisions - January 13, 2014 - January 17, 2014 Summary of Decisions - May 12, 2014 - May 16, 2014...

  4. DOE Secretarial Memorandum on Improved Decision Making through...

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

    Memorandum on Improved Decision Making through the Integration of Program and Project ... DOE Secretarial Memorandum on Improved Decision Making through the Integration of Program ...

  5. EIS-0217: Amended Record of Decision | Department of Energy

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

    Amended Record of Decision EIS-0217: Amended Record of Decision Savannah River Site Waste Management, Savannah River Operations Office, Aiken, South Carolina This Record of ...

  6. Record of Decision; Defense Waste Processing Facility at the...

    Office of Environmental Management (EM)

    Record of Decision; Defense Waste Processing Facility at the Savannah River Site, Aiken, SC AGENCY: Department of Energy, DOE. ACTION: Record of Decision, Defense Waste Processing ...

  7. EIS-0312: Record of Decision (2012) | Department of Energy

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

    Bonneville Power Administration Administrator's Record of Decision: Columbia Basin Fish Accords Memorandum of Agreement (MOA) with the Kalispel Tribe This Record of Decision...

  8. EIS-0397: Record of Decision | Department of Energy

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

    Record of Decision EIS-0397: Record of Decision Lyle Falls Fish Passage Project The Bonneville Power Administration (BPA) has decided to fund modifications to the existing Lyle...

  9. EIS-0266: Record of Decision | Department of Energy

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

    6: Record of Decision EIS-0266: Record of Decision Fourmile Hill Geothermal Development Project Power Purchase and Transmission Service Agreements The Bonneville Power...

  10. EIS-0332: Record of Decision | Department of Energy

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

    Record of Decision EIS-0332: Record of Decision McNary-John Day Transmission Line Project Bonneville Power Administration has decided to implement the proposed action identified in...

  11. Reduction of Transient Particulate Matter Spikes with Decision...

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

    Reduction of Transient Particulate Matter Spikes with Decision Tree Based Control Using a non-parametric decision tree to measure transient PM could correctly identify 94% of high ...

  12. Record of Decision for the Uranium Leasing Program Programmatic...

    Office of Environmental Management (EM)

    Record of Decision for the Uranium Leasing Program Programmatic Environmental Impact Statement Record of Decision for the Uranium Leasing Program Programmatic Environmental Impact ...

  13. DOE Defends Decision to Revoke Energy Star Designation for Certain...

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

    Decision to Revoke Energy Star Designation for Certain LG Refrigerators DOE Defends Decision to Revoke Energy Star Designation for Certain LG Refrigerators December 23, 2009 -...

  14. Plutonium Record of Decision Statement from NNSA Adminstrator Frank Klotz |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) Plutonium Record of Decision Statement from NNSA Adminstrator Frank Klotz Plutonium Record of Decision Statement from NNSA Administrator Frank G. Klotz

  15. Study of the Variation of Transverse Voltage in the 4 Rod Crab Cavity for LHC

    SciTech Connect (OSTI)

    B. Hall, G. Burt, C. Lingwood, R. Rimmer, H. Wang

    2011-04-01

    The planned high luminosity upgrade to LHC will utilise crab cavities to rotate the beam in order to increase the luminosity in the presence of a finite crossing angle. A compact design is required in order for the cavities to fit between opposing beam-lines. In this paper we discuss we discuss one option for the LHC crab cavity based on a 4 rod TEM deflecting cavity. Due to the large transverse size of the LHC beam the cavity is required to have a large aperture while maintaining a constant transverse voltage across the aperture. The cavity has been optimised to minimise the variation of the transverse voltage while keeping the peak surface electric and magnetic fields low for a given kick. This is achieved while fitting within the strict design space of the LHC. The variation of deflecting voltage across the aperture has been studied numerically and compared with numerical and analytical estimates of other deflecting cavity types. Performance measurements an aluminium prototype of this cavity are presented and compared to the simulated design.

  16. Effective delivery of recombinant proteins to rod photoreceptors via lipid nanovesicles

    SciTech Connect (OSTI)

    Asteriti, Sabrina; Dal Cortivo, Giuditta; Pontelli, Valeria; Cangiano, Lorenzo; Buffelli, Mario; Dell’Orco, Daniele

    2015-06-12

    The potential of liposomes to deliver functional proteins in retinal photoreceptors and modulate their physiological response was investigated by two experimental approaches. First, we treated isolated mouse retinas with liposomes encapsulating either recoverin, an important endogenous protein operating in visual phototransduction, or antibodies against recoverin. We then intravitrally injected in vivo liposomes encapsulating either rhodamin B or recoverin and we investigated the distribution in retina sections by confocal microscopy. The content of liposomes was found to be released in higher amount in the photoreceptor layer than in the other regions of the retina and the functional effects of the release were in line with the current model of phototransduction. Our study sets the basis for quantitative investigations aimed at assessing the potential of intraocular protein delivery via biocompatible nanovesicles, with promising implications for the treatment of retinal diseases affecting the photoreceptor layer. - Highlights: • Recombinant proteins encapsulated in nano-sized liposomes injected intravitreally reach retinal photoreceptors. • The phototransduction cascade in rods is modulated by the liposome content. • Mathematical modeling predicts the alteration of the photoresponses following liposome fusion.

  17. Experimental study of the deformation of Zircaloy PWR fuel rod cladding under mainly convective cooling

    SciTech Connect (OSTI)

    Hindle, E.D.; Mann, C.A.

    1982-01-01

    Zircaloy-4 cladding specimens 450 mm long were filled with alumina pellets and tested at temperatures between 630 and 915 degree C in flowing steam at atmospheric pressure. Internal test pressures were in the range 0.69 to 11.0 MPa. The length of cladding strained 33 percent or more was greatest (about 20 times the original diameter) when the initial pressure was 1.38/plus or minus/0.17MPa. This results from oxidation strengthening of the surface layers acting as an additional mechanism for stabilizing the deformation or partial superplastic deformation, or both. For adjacent rods in a fuel assembly not to touch at any temperature, the pressure would have to be less than about 1 MPa. These results are compared with those form multirod tests elsewhere, and it is suggested that heat transfer has a dominant effect in determining deformation. The implications for the behavior of fuel elements in a loss-of-coolant accident are outlined. 37 refs.

  18. Lifetime of PWR silver-indium-cadmium control rods. Final report

    SciTech Connect (OSTI)

    Sipush, P.J.; Woodcock, J.; Chickering, R.W.

    1986-03-01

    A hot cell examination was performed on selected rodlets of a lead rod cluster control assembly (RCCA) which had experienced eleven cycles of operation in Point Beach Unit 1. The principal purpose of the program was to evaluate the performance of RCCAs. The hot cell examination of the rodlets involved detailed visual inspections, profilometry, metallography, cladding chemistry, dosimetry, scanning electron microscopy, corrosion tests, microhardness tests, absorber density measurements, and cladding tensile tests. Wear scars and a hairline crack in the cladding were evaluated. The results of the examinations and analysis of WEPCO site photographs led to an estimate of the service life for RCCAs which are used in Westinghouse 14 x 14 fuel assemblies. Also, wear scar widths were correlated with wear scar depths. The correlation may be used to estimate wear scar depths based on site photographs of wear scars for 14 x 14 RCCAs. The results of the program may be used as guidelines for RCCAs for 15 x 15 and 17 x 17 Westinghouse fuel designs. 10 refs., 89 figs., 26 tabs.

  19. Decision insight into stakeholder conflict for ERN.

    SciTech Connect (OSTI)

    Siirola, John; Tidwell, Vincent Carroll; Benz, Zachary O.; Stansbury, Melanie; Richards, Elizabeth H.; Turnley, Jessica Glicken; Warrender, Christina E.; Morrow, James Dan

    2012-02-01

    Participatory modeling has become an important tool in facilitating resource decision making and dispute resolution. Approaches to modeling that are commonly used in this context often do not adequately account for important human factors. Current techniques provide insights into how certain human activities and variables affect resource outcomes; however, they do not directly simulate the complex variables that shape how, why, and under what conditions different human agents behave in ways that affect resources and human interactions related to them. Current approaches also do not adequately reveal how the effects of individual decisions scale up to have systemic level effects in complex resource systems. This lack of integration prevents the development of more robust models to support decision making and dispute resolution processes. Development of integrated tools is further hampered by the fact that collection of primary data for decision-making modeling is costly and time consuming. This project seeks to develop a new approach to resource modeling that incorporates both technical and behavioral modeling techniques into a single decision-making architecture. The modeling platform is enhanced by use of traditional and advanced processes and tools for expedited data capture. Specific objectives of the project are: (1) Develop a proof of concept for a new technical approach to resource modeling that combines the computational techniques of system dynamics and agent based modeling, (2) Develop an iterative, participatory modeling process supported with traditional and advance data capture techniques that may be utilized to facilitate decision making, dispute resolution, and collaborative learning processes, and (3) Examine potential applications of this technology and process. The development of this decision support architecture included both the engineering of the technology and the development of a participatory method to build and apply the technology

  20. Prototypical Rod Consolidation Demonstration Project. Phase 3, Final report: Volume 1, Cold checkout test report, Book 1

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 1 discusses the following topics: the background of the project; test program description; summary of tests and test results; problem evaluation; functional requirements confirmation; recommendations; and completed test documentation for tests performed in Phase 3.

  1. Impact of the control rod consumption on the reactivity control of a SFR break-even core

    SciTech Connect (OSTI)

    Blanchet, D.; Fontaine, B.

    2012-07-01

    Current design studies on Sodium Fast Reactor (SFR) differ from those performed in the past by the fact that design criteria are now those of the Generation IV reactors. In order to improve their safety, reactors with break-even cores are preferred because they minimize the needs in terms of reactivity control and limit the consequences of control rod withdrawal. Furthermore, as the reactivity control needs are low, break-even core enables the use of absorbing materials with reduced efficiency (natural boron, hafnium...). Nevertheless, the use of control rods with few absorbing materials may present the disadvantage of a non-negligible ({approx}10%) loss of efficiency due to their consumption under irradiation. This paper presents a methodology to calculate accurately and analyze this consumption. (authors)

  2. Evaluation of flow redistribution due to flow blockage in rod bundles using COBRA code simulation. Final report. [PWR

    SciTech Connect (OSTI)

    Prelewicz, D.A.; Caruso, M.A.

    1981-01-01

    During a Loss-of-Coolant Accident, fuel rod cladding may reach temperatures approaching 2200/sup 0/F. At these temperatures, swelling and rupture of the cladding may occur. The resulting flow blockage will affect steam flow and heat transfer in the bundle during the period of reflooding. The COBRA-IV-I subchannel computer code was used to simulate flow redistribution due to sleeve blockages in the FLECHT-SEASET 21-rod bundle and plate blockages in the JAERI Slab Core Test Facility. Sensitivity studies were conducted to determine the effects of spacer grid and blockage interaction, sleeve shape effects, sleeve length effects, blockage magnitude and distribution, thermally induced mixing and bundle average velocity on flow redistribution. Pressure drop due to sleeve blockages was also calculated for several blockage configurations.

  3. Common cause failure analysis of the rodded scram system of the Arkansas Nuclear One-Unit 1 Plant

    SciTech Connect (OSTI)

    Montague, D.F.; Campbell, D.J.; Flanagan, G.F.

    1986-10-01

    This study demonstrates the use of a formal method for common cause failure analysis in a reliability analysis of the Arkansas Nuclear One - Unit 1 rodded scram system. The scram system failure of interest is loss of capability of the system to shut the reactor down when required. The results of this analysis support the ATWS program sponsored by the US Nuclear Regulatory Commission. The methods used in this analysis support the NRC's Risk Methods Integration and Evaluation Program (RMIEP).

  4. Plutonium-238 Transuranic Waste Decision Analysis

    SciTech Connect (OSTI)

    Brown, Mike; Lechel, David J.; Leigh, C.D.

    1999-06-29

    Five transuranic (TRU) waste sites in the Department of Energy (DOE) complex, collectively, have more than 2,100 cubic meters of Plutonium-238 (Pu-238) TRU waste that exceed the wattage restrictions of the Transuranic Package Transporter-II (TRUPACT-11). The Waste Isolation Pilot Plant (WIPP) is being developed by the DOE as a repository for TRU waste. With the Waste Isolation Pilot Plant (WIPP) opening in 1999, these sites are faced with a need to develop waste management practices that will enable the transportation of Pu-238 TRU waste to WIPP for disposal. This paper describes a decision analysis that provided a logical framework for addressing the Pu-238 TRU waste issue. The insights that can be gained by performing a formalized decision analysis are multifold. First and foremost, the very process. of formulating a decision tree forces the decision maker into structured, logical thinking where alternatives can be evaluated one against the other using a uniform set of criteria. In the process of developing the decision tree for transportation of Pu-238 TRU waste, several alternatives were eliminated and the logical order for decision making was discovered. Moreover, the key areas of uncertainty for proposed alternatives were identified and quantified. The decision analysis showed that the DOE can employ a combination approach where they will (1) use headspace gas analyses to show that a fraction of the Pu-238 TRU waste drums are no longer generating hydrogen gas and can be shipped to WIPP ''as-is'', (2) use drums and bags with advanced filter systems to repackage Pu-238 TRU waste drums that are still generating hydrogen, and (3) add hydrogen getter materials to the inner containment vessel of the TRUPACT-11to relieve the build-up of hydrogen gas during transportation of the Pu-238 TRU waste drums.

  5. FEMAXI-V benchmarking study on peak temperature and fission gas release prediction of PWR rod fuel

    SciTech Connect (OSTI)

    Suwardi; Dewayatna, W.; Briyatmoko, B.

    2012-06-06

    The present paper reports a study of FEMAXI-V code and related report on code benchmarking. Capabilities of the FEMAXI-V code to predict the thermal and fission gas release have been tested on MOX fuels in LWRs which has been done in SCK{center_dot}CEN and Belgonucleaire by using PRIMO MOX rod BD8 irradiation experiment after V Sobolev as reported O. J. Ott. Base irradiation in the BR3 reactor, the BD8 rod was transported to CEA-Saclay for irradiation in the OSIRIS reactor (ramp power excursion). The irradiation device used for the PRIMO ramps was the ISABELLE 1 loop, installed on a movable structure of the core periphery. The power variations were obtained by inwards/backwards movements of the loop in the core water. The preconditioning phase for rod BD8 occurred at a peak power level of 189 W/cm with a hold time of 27 hours. The subsequent power excursion rate amounted to 77 W/ (cm.min), reaching a terminal peak power level of 395 W/cm that lasted for 20 hours.

  6. Two-stage epitaxial growth of vertically-aligned SnO2 nano-rods on(001) ceria

    SciTech Connect (OSTI)

    Solovyov, Vyacheslav F.; Wu, Li-jun; Rupich, Martin W.; Sathyamurthy, Srivatsan; Li, Xiaoping; Li, Qiang

    2014-09-20

    Growth of high-aspect ratio oriented tin oxide, SnO2, nano-rods is complicated by a limited choice of matching substrates. We show that a (001) cerium oxide, CeO2, surface uniquely enables epitaxial growth of tin-oxide nano-rods via a two-stage process. First, (100) oriented nano-wires coat the ceria surface by lateral growth, forming a uniaxially-textured SnO2 deposit. Second, vertical SnO2nano-rods nucleate on the deposit by homoepitaxy. We demonstrate growth of vertically oriented 1-2 ?m long nano-rods with an average diameter of ?20 nm.

  7. PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report. NRC/EPRI/Westinghouse Report No. 11. Appendices K-P

    SciTech Connect (OSTI)

    Loftus, M.J.; Hochreiter, L.E.; Lee, N.; McGuire, M.F.; Wenzel, A.H.; Valkovic, M.M.

    1982-09-01

    This report presents data and limited analysis from the 21-Rod Bundle Flow Blockage Task of the Full-Length Emergency Cooling Heat Transfer Separate Effects and Systems Effects Test Program (FLECHT SEASET). The tests consisted of forced and gravity reflooding tests utilizing electrical heater rods with a cosine axial power profile to simulate PWR nuclear core fuel rod arrays. Steam cooling and hydraulic characteristics tests were also conducted. These tests were utilized to determine effects of various flow blockage configurations (shapes and distributions) on reflooding behavior, to aid in development/assessment of computational models in predicting reflooding behavior of flow blockage configurations, and to screen flow blockage configurations for future 163-rod flow blockage bundle tests.

  8. A Multiple Objective Decision Support Tool (MODS)

    Energy Science and Technology Software Center (OSTI)

    2003-12-14

    The Multiple Objective Decision Support (MODS) tool is an automated tool used to assist decision makers and policy analysts with multiple-objective decision problems. The classes of problems that this decision support tool addresses have both multiple objectives and multiple stakeholders. Decision problems, which have multiple objectives that in general cannot be maximized simultaneously, and multiple stakeholders, who have different perspectives about the relative importance of the objectives, require analytic approaches and tools that can providemore » flexible support to decision makers. This tool provides capabilities for the management, analysis, and graphical display for these types of decision problems drawn from diverse problem domains. The MODS tool is a unique integration of analysis algorithms, an information database, and a graphical user interface. This collection of algorithms, the combination of an information database with the analysis into a single tool, and the graphical user interface provides a technically advanced tool to decision makers and policy analysts. There are two main issues when addressing problems of this type: what set of attributes should be used to characterize the tokens in the domain of interest, and how should the values of these attributes and their weights be determined and combined to provide a relative ordering to the tokens. This tool addresses both of these issues. This decision support tool provides a flexible way to derive and use a chosen set of attributes. For example, the tool could be used to first perform a paired comparison of a large set of attributes and from this evaluation select those attributes that have the highest weights. The flexibility of the tool allows experimentation with various attribute sets and this capability, along with domain expertise, addresses the first issue. To address the second issue, several algorithms have been implemented. For example, two algorithms that have been implemented are

  9. Summary of Decisions- December 23, 2013 – December 27, 2013

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  10. Summary of Decisions- June 16, 2014 – June 20, 2014

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  11. Summary of Decisions- December 16, 2013 – December 20, 2013

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  12. Summary of Decisions- October 27, 2014 – October 31, 2014

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Personnel Security (10 CFR Part 710) - Freedom of Information Act Appeal

  13. Summary of Decisions- July 29, 2013- August 2, 2013

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Personnel Security (10 CFR Part 710) - Whistleblower Appeal (10 CFR Part 708)

  14. Summary of Decisions- August 26, 2013- August 30, 2013

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  15. Summary of Decisions- September 24, 2012 – September 28, 2012

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  16. Summary of Decisions- December 10, 2012 – December 14, 2012

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  17. Summary of Decisions- March 3, 2014 – March 7, 2014

    Office of Energy Efficiency and Renewable Energy (EERE)

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  18. Summary of Decisions- November 24, 2014 – November 28, 2014

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Personnel Security (10 CFR Part 710) - Freedom of Information Act Appeal

  19. Summary of Decisions- September 9, 2013 – September 13, 2013

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)

  20. Summary of Decisions- July 15, 2013- July 19, 2013

    Broader source: Energy.gov [DOE]

    Decisions were issued on: - Freedom of Information Act Appeal - Personnel Security (10 CFR Part 710)