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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

    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...

  11. 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...

  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-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. ...

  17. 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...

  18. 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...

  19. 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...

  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-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...

  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. 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...

  5. 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.

  6. 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.

  7. 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.

  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. 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....

  19. 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 ...

  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. 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...

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

    Office of Legacy Management (LM)

  4. 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...

  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. 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 ...

  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. 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...

  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. 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

  4. 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.

  5. 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.

  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

    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...

  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

    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

  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. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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.

  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 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...

  7. 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...

  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. 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.

  18. 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.

  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. 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

  5. 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

  6. 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

  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. 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.

  11. 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

  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. 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.

  19. 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.

  20. 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.

  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. 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%.

  5. 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. ...

  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. 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.

  8. 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.

  9. 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.

  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-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

  12. 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

  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. 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.

  3. 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.

  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. 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.

  9. 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

  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. 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.

  15. 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.

  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. 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; ...

  18. 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 ...

  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. 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. ...

  1. 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 ...

  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. 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

  4. 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.

  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. 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

  18. 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

  19. 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

  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. 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.

  2. 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

  3. 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)

  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.