Sample records for defueled naval reactor

  1. EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington

    Broader source: Energy.gov [DOE]

    This EA, prepared by the Department of the Navy, evaluates the environmental impacts of the disposal of decommissioned, defueled, naval reactor plants from the USS Enterprise at DOE’s Hanford Site, Richland, Washington. DOE participated as a cooperating agency in the preparation of this EA. The Department of the Navy issued its FONSI on August 23, 2012.

  2. EIS-0259: Disposal of Decommissioned, Defueled Cruiser, Ohio Class and Los Angeles Class Naval Reactor Plants, Hanford Site, Richland (adopted from Navy)

    Broader source: Energy.gov [DOE]

    This EIS analyzes the alternate ways for disposing of decommissioned, defieled reactor compliments from U.S. Navy nuclear-powered cruisers, (Bainbridge, Truxtun, Long Beach, California Class and Virginia Class) and Los Angeles Class, and Ohio Class submarines.

  3. EIS-0275: Disposal of the S1C Prototype Reactor Plant, Hanford Site, Richland, WA (Navy Document)

    Broader source: Energy.gov [DOE]

    This EIS analyzes the Office of Naval Reactors (Naval Reactors) proposed action to dismantle the defueled S1C Prototype reactor plant.

  4. Characterization of solids in the Three Mile Island Unit 2 reactor defueling water

    SciTech Connect (OSTI)

    Campbell, D. O.

    1987-12-01T23:59:59.000Z

    Because of the impact of poor water clarity on defueling operations at the Three Mile Island Unit 2 Nuclear Power Station, a study was undertaken to characterize suspended particulates in the reactor defueling water. The examination included cascade filtration through Nuclepore filters of progressively smaller pore sizes, using three water samples obtained at different times and after varying degrees of clarification. The solids collected on the filters were examined with a scanning electron microscope and analyzed with energy-dispersive x-ray fluorescence. A wide variety of solids was observed, and 26 elements were detected. These included all the materials expected from the reactor system (uranium, zirconium, silver, cadmium, indium, iron, chromium, and nickel), chemicals and zeolites used to decontaminate the water (aluminum, silicon, sodium), common impurities (potassium, chlorine, sulfur, magnesium, calcium, and others), as well as some unexpected metals (molybdenum, manganese, bromine, and lead). There was also evidence for the presence of organic material. A diverse assortment of particles with widely varying surface properties was found to be present.

  5. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    SciTech Connect (OSTI)

    P. Delmolino

    2005-05-06T23:59:59.000Z

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

  6. NA 30 - Deputy Administrator for Naval Reactors | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Us Our Operations Management and Budget Office of Civil Rights Workforce Statistics NA 30 - Deputy Administrator for Naval Reactors NA 30 - Deputy Administrator for...

  7. Naval Reactors | Y-12 National Security Complex

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

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  8. LCEs for Naval Reactor Benchmark Calculations

    SciTech Connect (OSTI)

    W.J. Anderson

    1999-07-19T23:59:59.000Z

    The purpose of this engineering calculation is to document the MCNP4B2LV evaluations of Laboratory Critical Experiments (LCEs) performed as part of the Disposal Criticality Analysis Methodology program. LCE evaluations documented in this report were performed for 22 different cases with varied design parameters. Some of these LCEs (10) are documented in existing references (Ref. 7.1 and 7.2), but were re-run for this calculation file using more neutron histories. The objective of this analysis is to quantify the MCNP4B2LV code system's ability to accurately calculate the effective neutron multiplication factor (k{sub eff}) for various critical configurations. These LCE evaluations support the development and validation of the neutronics methodology used for criticality analyses involving Naval reactor spent nuclear fuel in a geologic repository.

  9. 1996 environmental monitoring report for the Naval Reactors Facility

    SciTech Connect (OSTI)

    NONE

    1996-12-31T23:59:59.000Z

    The results of the radiological and nonradiological environmental monitoring programs for 1996 at the Naval Reactors Facility (NRF) are presented in this report. The NRF is located on the Idaho National Engineering and Environmental Laboratory and contains three naval reactor prototypes and the Expended Core Facility, which examines developmental nuclear fuel material samples, spent naval fuel, and irradiated reactor plant components/materials. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency (EPA) and the Department of Energy (DOE).

  10. Naval Reactors Facility environmental monitoring report, calendar year 2001

    SciTech Connect (OSTI)

    NONE

    2002-12-31T23:59:59.000Z

    The results of the radiological and nonradiological environmental monitoring programs for 2001 at the Naval Reactors Facility are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U. S. Environmental Protection Agency and the U. S. Department of Energy.

  11. Naval Reactors Facility Environmental Monitoring Report, Calendar Year 2003

    SciTech Connect (OSTI)

    None

    2003-12-31T23:59:59.000Z

    The results of the radiological and nonradiological environmental monitoring programs for 2003 at the Naval Reactors Facility are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with Federal and State regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the U.S. Environmental Protection Agency and the U.S. Department of Energy.

  12. 1997 environmental monitoring report for the Naval Reactors Facility

    SciTech Connect (OSTI)

    NONE

    1997-12-31T23:59:59.000Z

    The results of the radiological and nonradiological environmental monitoring programs for 1997 at the Naval Reactors Facility (NRF) are presented in this report. The results obtained from the environmental monitoring programs verify that releases to the environment from operations at NRF were in accordance with state and federal regulations. Evaluation of the environmental data confirms that the operation of NRF continues to have no adverse effect on the quality of the environment or the health and safety of the general public. Furthermore, a conservative assessment of radiation exposure to the general public as a result of NRF operations demonstrated that the dose received by any member of the public was well below the most restrictive dose limits prescribed by the Environmental Protection Agency (EPA) and the Department of Energy (DOE).

  13. EIS-0259: Final Environmental Impact Statement

    Broader source: Energy.gov [DOE]

    Disposal of Decommissioned, Defueled Cruiser, Ohio Class, Los Angeles and Class Naval Reactor Plants

  14. 2012 Annual Planning Summary for Naval Reactors | Department of Energy

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

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  15. Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

    SciTech Connect (OSTI)

    Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro [Japan Atomic Energy Agency 4-33 Muramatsu, Tokaimura, Nakagun, Ibaraki 319-1194 (Japan)

    2013-07-01T23:59:59.000Z

    For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

  16. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.

  17. naval reactors

    National Nuclear Security Administration (NNSA)

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  18. EA-1889: Final Environmental Assessment and Finding of No Significant...

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

    of No Significant Impact (FONSI) on the Disposal of Decommissioned, Defueled, Naval Reactor Plants from the USS Enterprise. Because the preferred alternative is to dispose of...

  19. Naval Reactors Prime Contractor Team (NRPCT) Experiences and Considerations With Irradiation Test Performance in an International Environment

    SciTech Connect (OSTI)

    MH Lane

    2006-02-15T23:59:59.000Z

    This letter forwards a compilation of knowledge gained regarding international interactions and issues associated with Project Prometheus. The following topics are discussed herein: (1) Assessment of international fast reactor capability and availability; (2) Japanese fast reactor (JOYO) contracting strategy; (3) NRPCT/Program Office international contract follow; (4) Completion of the Japan Atomic Energy Agency (JAEA)/Pacific Northwest National Laboratory (PNNL) contract for manufacture of reactor test components; (5) US/Japanese Departmental interactions and required Treaties and Agreements; and (6) Non-technical details--interactions and considerations.

  20. Nuclear Naval Propulsion: A Feasible Proliferation Pathway?

    SciTech Connect (OSTI)

    Swift, Alicia L.

    2014-01-31T23:59:59.000Z

    There is no better time than now to close the loophole in Article IV of the Nuclear Non-proliferation Treaty (NPT) that excludes military uses of fissile material from nuclear safeguards. Several countries have declared their intention to pursue and develop naval reactor technology, including Argentina, Brazil, Iran, and Pakistan, while other countries such as China, India, Russia, and the United States are expanding their capabilities. With only a minority of countries using low enriched uranium (LEU) fuel in their naval reactors, it is possible that a state could produce highly enriched uranium (HEU) under the guise of a nuclear navy while actually stockpiling the material for a nuclear weapon program. This paper examines the likelihood that non-nuclear weapon states exploit the loophole to break out from the NPT and also the regional ramifications of deterrence and regional stability of expanding naval forces. Possible solutions to close the loophole are discussed, including expanding the scope of the Fissile Material Cut-off Treaty, employing LEU fuel instead of HEU fuel in naval reactors, amending the NPT, creating an export control regime for naval nuclear reactors, and forming individual naval reactor safeguards agreements.

  1. Multiple Irradiation Capsule Experiment (MICE)-3B Irradiation Test of Space Fuel Specimens in the Advanced Test Reactor (ATR) - Close Out Documentation for Naval Reactors (NR) Information

    SciTech Connect (OSTI)

    M. Chen; CM Regan; D. Noe

    2006-01-09T23:59:59.000Z

    Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (low fission rate, high temperature, long duration). As such, basic testing is required to validate predictions (and in some cases determine) performance aspects of these fuels. Therefore, the MICE-3B test of UO{sub 2} pellets was designed to provide data on gas release, unrestrained swelling, and restrained swelling at the upper range of fission rates expected for a space reactor. These data would be compared with model predictions and used to determine adequacy of a space reactor design basis relative to fission gas release and swelling of UO{sub 2} fuel and to assess potential pellet-clad interactions. A primary goal of an irradiation test for UN fuel was to assess performance issues currently associated with this fuel type such as gas release, swelling and transient performance. Information learned from this effort may have enabled use of UN fuel for future applications.

  2. Naval Civil Engineering Laboratory

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

    Naval Civil Engineering Laboratory Personnel from the Power Systems Department have participated in numerous distribution equipment research, development, demonstration, testing,...

  3. Naval Engineering A National Naval Obligation

    E-Print Network [OSTI]

    Chryssostomidis, Chryssostomos

    2000-05-16T23:59:59.000Z

    As part of its national obligations, ONR must ensure US world leadership in those unique technology areas that insure naval superiority. ONR accomplishes this mission through research, recruitment and education, maintaining ...

  4. Naval petroleum reserves

    SciTech Connect (OSTI)

    Not Available

    1981-01-01T23:59:59.000Z

    A hearing to consider two bills (S. 1744 and H.R. 3023) authorizing appropriations to operate the Naval Petroleum Reserve during fiscal 1982 brought testimony from officials of the Departments of Energy and Defense; from Chevron, USA; and from the Independent Refiners Association. Both bills authorize $228,463,000, of which $2.56 million will be available for the naval oil shale reserves and the remainder for the naval petroleum reserves. Chevron spokesmen noted that 8-11 months were required to reach full production at the Elk Hills site rather than the 60-90 days estimated by DOE, although both Chevron and the Independent Refiners Association of the west coast support the President's decision that it is in the national interest to continue the production of crude from naval petroleum reserves for the next three years.

  5. NPS Research supports Naval

    E-Print Network [OSTI]

    · Management Stanley Arthur Chair of Logistics· RADM George F. Wagner Chair in· Public Management Chair WAYNE E. MEYER INSTITUTE OF SYSTEMS ENGINEERING FY08 Naval Sponsored Program Research and Education: $36

  6. Annular core liquid-salt cooled reactor with multiple fuel and blanket zones

    DOE Patents [OSTI]

    Peterson, Per F.

    2013-05-14T23:59:59.000Z

    A liquid fluoride salt cooled, high temperature reactor having a reactor vessel with a pebble-bed reactor core. The reactor core comprises a pebble injection inlet located at a bottom end of the reactor core and a pebble defueling outlet located at a top end of the reactor core, an inner reflector, outer reflector, and an annular pebble-bed region disposed in between the inner reflector and outer reflector. The annular pebble-bed region comprises an annular channel configured for receiving pebble fuel at the pebble injection inlet, the pebble fuel comprising a combination of seed and blanket pebbles having a density lower than the coolant such that the pebbles have positive buoyancy and migrate upward in said annular pebble-bed region toward the defueling outlet. The annular pebble-bed region comprises alternating radial layers of seed pebbles and blanket pebbles.

  7. Naval Architecture and Marine Engineering

    E-Print Network [OSTI]

    Eustice, Ryan

    knowledge of mathematics, science, and engineering within naval architecture and marine engineering and marine engineering problems; an ability to apply basic knowledge in fluid mechanics, dynamicsNaval Architecture and Marine Engineering Undergraduate Program The University of Michigan #12

  8. BOARD OF ADVISORS TO THE PRESIDENTS OF THE NAVAL POSTGRADUATE SCHOOL & NAVAL WAR COLLEGE

    E-Print Network [OSTI]

    BOARD OF ADVISORS TO THE PRESIDENTS OF THE NAVAL POSTGRADUATE SCHOOL & NAVAL WAR COLLEGE October 17 attendance (choose all that apply): Naval Postgraduate School Subcommittee, 17 October 2012 Naval War College

  9. Naval Civil Engineering Laboratory

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

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  10. Shippingport operations with the Light Water Breeder Reactor core. (LWBR Development Program)

    SciTech Connect (OSTI)

    Budd, W.A. (ed.)

    1986-03-01T23:59:59.000Z

    This report describes the operation of the Shippingport Atomic Power Station during the LWBR (Light Water Breeder Reactor) Core lifetime. It also summarizes the plant-oriented operations during the period preceding LWBR startup, which include the defueling of The Pressurized Water Reactor Core 2 (PWR-2) and the installation of the LWBR Core, and the operations associated with the defueling of LWBR. The intent of this report is to examine LWBR experience in retrospect and present pertinent and significant aspects of LWBR operations that relate primarily to the nuclear portion of the Station. The nonnuclear portion of the Station is discussed only as it relates to overall plant operation or to unusual problems which result from the use of conventional equipment in radioactive environments. 30 refs., 69 figs., 27 tabs.

  11. naval reactors | National Nuclear Security Administration

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

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  12. About Naval Reactors | National Nuclear Security Administration

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisiting the TWP TWP Related LinksATHENA could reduceCustomerEIA's 2015questionsNNSA

  13. Fracture of aluminum naval structures

    E-Print Network [OSTI]

    Galanis, Konstantinos, 1970-

    2007-01-01T23:59:59.000Z

    Structural catastrophic failure of naval vessels due to extreme loads such as underwater or air explosion, high velocity impact (torpedoes), or hydrodynamic loads (high speed vessels) is primarily caused by fracture. ...

  14. James P. Mosquera Director, Reactor Plant Components

    E-Print Network [OSTI]

    of the application of nuclear reactor power to capital ships of the U.S. Navy, and other assigned projects. Mr for steam generator technology (within the Nuclear Components Division); and power plant systems engineer working for the U.S. Naval Nuclear Propulsion Program (a.k.a. Naval Reactors). This program is a joint

  15. Distributed energy resources at naval base ventura county building 1512

    E-Print Network [OSTI]

    Bailey, Owen C.; Marnay, Chris

    2004-01-01T23:59:59.000Z

    Resources at Naval Base Ventura Country Building 1512 7.August 2001. “Naval Base Ventura County Standby GeneratorEnergy Resources at Naval Base Ventura Country Building 1512

  16. Naval Petroleum Reserves | Department of Energy

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

    Naval Petroleum Reserves For much of the 20th century, the Naval Petroleum and Oil Shale Reserves served as a contingency source of fuel for the Nation's military. All that...

  17. Naval Petroleum Reserve No. 1

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    For several years, the administration has proposed selling the government's ownership interest in the Naval Petroleum Reserves, arguing that it would help reduce the federal budget deficit. The administration's latest proposal calls for the sale of reserves in fiscal year 1990. DOE estimates that if the reserves are sold in 1990, proceeds would amount to about $3.4 billion. The Naval Petroleum Reserve at Elk Hills, California, is the largest of the reserves. This report has reviewed and analyzed the new reserve data and found that DOE's reserve estimates for Elk Hills are still neither accurate nor up-to-date.

  18. NAVAL POSTGRADUAm SCHOOL Monterey, California

    E-Print Network [OSTI]

    NAVAL POSTGRADUAm SCHOOL Monterey, California A WHOLESALE LEVEL CONSUMABLE ITEM DEMAND PATI TYPE AND DATES COVERED Master's Thesis 4. TITLE AND SUBTITLE A WHOLESALE LEVEL CONSUMABLE DEMAND is unlimited. A Wholesale Level Consumable Item Inventory Model for Non-Stationary Demand Patterns Glenn C

  19. The form, function, and interrelationships of naval rams: a study of naval rams from antiquity

    E-Print Network [OSTI]

    Pridemore, Matthew Garnett

    1996-01-01T23:59:59.000Z

    The discovery of several naval rams from sites around the Mediterranean has given scholars a brief glimpse of one of the most widely used naval weapons of the ancient world. Examining these physical examples provides information that is unavailable...

  20. andreyev bay naval: Topics by E-print Network

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

    led by my Marine Corps staff and battalion New Mexico, University of 2 Naval Architecture Marine Engineering Engineering Websites Summary: Naval Architecture Marine...

  1. Naval Petroleum Reserve No. 3 Disposition Decision Analysis and...

    Energy Savers [EERE]

    Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline Naval Petroleum Reserve No. 3 Disposition Decision Analysis and Timeline This Report to Congress provides a...

  2. Naval Research Laboratory Stennis Space Center

    E-Print Network [OSTI]

    Naval Research Laboratory Stennis Space Center Mississippi 39529 www7320.nrlssc.navy.mil/ Ocean Ocean prediction technology The Naval Research Laboratory (NRL) is the US Navy corporate laboratory, dedicated to addressing Navy unique problems and enabling the Navy to operate efficiently and safely. Unique

  3. Comparative naval architecture analysis of diesel submarines

    E-Print Network [OSTI]

    Torkelson, Kai Oscar

    2005-01-01T23:59:59.000Z

    Many comparative naval architecture analyses of surface ships have been performed, but few published comparative analyses of submarines exist. Of the several design concept papers, reports and studies that have been written ...

  4. U.S. NAVAL ACADEMY COMPUTER SCIENCE DEPARTMENT

    E-Print Network [OSTI]

    Crabbe, Frederick

    U.S. NAVAL ACADEMY COMPUTER SCIENCE DEPARTMENT TECHNICAL REPORT Mobile Vehicle Teleoperated Over Akin and Frederick L. Crabbe U.S. Naval Academy Computer Science Department 572M Holloway Rd, Stop 9F

  5. EFFECTS OF NAVAL ORDNANCE TESTS ON THE PATUXENT RIVER FISHERY

    E-Print Network [OSTI]

    EFFECTS OF NAVAL ORDNANCE TESTS ON THE PATUXENT RIVER FISHERY Marine Biological Laboratory t, T "B and Wildlife Service, John L. Farley, Director EFFECTS OF NAVAL ORDNANCE TESTS ON THE PATUXENT RIVER FISHERY of Medicine, Univ. of Puerto Rico. #12;#12;EFFECTS OF NAVAL ORDNANCE TESTS ON THE PATUXENT RIVER FISHERY

  6. DEPARTMENT OF THE NAVY NAVAL POSTGRADUATE SCHOOL

    E-Print Network [OSTI]

    DEPARTMENT OF THE NAVY NAVAL POSTGRADUATE SCHOOL 1 UNIVERSITY CIR MONTEREY, CA 93943-5000 IN REPLY FOR ADMINISTRATION AND MANAGEMENT OF NAVY FULLY-FUNDED GRADUATE EDUCATION PROGRAMS AT CIVILIAN INSTITUTIONS guidance for the U.S. Navy's fully funded graduate education programs at Civilian Institutions (CIVINS

  7. Yangtze Patrol: American Naval Forces in China

    E-Print Network [OSTI]

    Yangtze Patrol: American Naval Forces in China A Selected, Partially-Annotated Bibliography literature of the United States Navy in China. mvh #12;"Like Chimneys in Summer" The thousands of men who served on the China Station before World War II have been all but forgotten, except in the mythology

  8. Congressional Delegation visits Naval Reactors Facility | National Nuclear

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  9. Statement on Defense Nuclear Nonproliferation and Naval Reactors Activities

    National Nuclear Security Administration (NNSA)

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  10. Management of Naval Reactors' Cyber Security Program, OIG-0884

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't YourTransport(FactDepartment ofLetterEconomyDr.Energy University ofOverviewManagement of

  11. NA 30 - Deputy Administrator for Naval Reactors | National Nuclear Security

    National Nuclear Security Administration (NNSA)

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  12. More About NNSA's Naval Reactors Office | National Nuclear Security

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

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  13. More About NNSA's Naval Reactors Office | National Nuclear Security

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your1 SECTIONES2008-54174 ThisBackgroundAdministration

  14. Russian naval bases due commercial development

    SciTech Connect (OSTI)

    Not Available

    1992-04-27T23:59:59.000Z

    Tecnogrid Group, New York, has signed a joint venture with the Russian Navy for commercial development of a wide range of sea dn land based assets owned by the former Soviet Navy. This paper reports that among other things, the venture aims for projects that will allow greater volumes of oil exports by revamping several naval bases. Tecnogrid's partner in the joint venture is AO Navicon, A Russian stock holding company that is the commercial arm of the Navy. Navicon has the sole right to commercially develop and deploy the Navy's assets. The Navy can no longer depend on the state for support, and Adm. Ig. Malhonin. With that in mind, the Navy is looking to become the leading force in moving toward a free market economy. Mahonin is Russia's second ranking naval official.

  15. The case for naval arms control

    SciTech Connect (OSTI)

    Fieldhouse, R. (Natural Resources Defense Council in Washington, DC (USA))

    1990-02-01T23:59:59.000Z

    Resurfacing at the Malta summit, the issue of naval arms control has once again become prominent as START and other potential treaties near completion. The time has come when we should begin discussing naval forces, said Soviet leader Mikhail Gorbachev, arguing that limiting only ground and air forces would not be equitable. The United States has opposed naval arms control - although some prominent U.S. officials, such as former chairman of the Joint Chiefs of Staff, Admiral William J. Crowe, Jr., have advocated some type of limitations. The official US position is that as a maritime power, the United States requires an unrestrained navy to fulfill its defense obligations. This issue of Arms Control Today presents here two views on this controversy. In the article, Richard Fieldhouse, senior research associate with the Nuclear Weapons Data Project, argues that there are indeed areas, such as controlling nuclear weapons on ships and confidence-building measures, that will enhance, not diminish, U.S. security. Following this, James R. Blaker, a former deputy assistant secretary of defense, presents a counter argument.

  16. DESIGN ANALYSIS FOR THE NAVAL SNF WASTE PACKAGE

    SciTech Connect (OSTI)

    T.L. Mitchell

    2000-05-31T23:59:59.000Z

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

  17. Distributed energy resources at naval base ventura county building 1512

    E-Print Network [OSTI]

    Bailey, Owen C.; Marnay, Chris

    2004-01-01T23:59:59.000Z

    by a DER system. Distributed Energy Resources at Naval BaseFebruary 2003. “Distributed Energy Resources in Practice: A2004. “Distributed Energy Resources Customer Adoption Model

  18. Naval Construction Battalion Center Gulfport- Mississippi Power Partnership Success Story

    Broader source: Energy.gov [DOE]

    Presentation covers the Naval Construction Battalion Center Gulfport - Mississippi Power Partnership success story given at the Spring 2009 Federal Utility Partnership Working Group (FUPWG) meeting...

  19. Distributed energy resources at naval base ventura county building 1512

    E-Print Network [OSTI]

    Bailey, Owen C.; Marnay, Chris

    2004-01-01T23:59:59.000Z

    system. Distributed Energy Resources at Naval Base Ventura2003. “Distributed Energy Resources in Practice: A Case2004. “Distributed Energy Resources Customer Adoption Model

  20. 13.400 Introduction to Naval Architecture, Fall 2004

    E-Print Network [OSTI]

    Herbein, David

    Introduction to principles of naval architecture, ship geometry, hydrostatics, calculation and drawing of curves of form, intact and damaged stability, hull structure strength calculations and ship resistance. Projects ...

  1. Department of Energy, Office of Naval Petroleum & Oil Shale Reserves

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

    Items that may be marked "disposrtron not Office of Naval Petroleum & Oil Shale Reserves approved" or "withdrawn" In column 10 4 Nameof Personwith whom to confer 5...

  2. THE NAVAL RESEARCH ENTERPRISE AND PLASMA PHYSICS RESEARCH AT THE NAVAL RESEARCH LAB

    E-Print Network [OSTI]

    Shyy, Wei

    , to create Xray simulators for testing nuclear weapons effects, and to understand high altitude nuclear ex and space plasmas, intense electron and ion beams and photon sources, atomic physics, pulsed power also participates in two Innovative Naval Prototype programs: the electromagnetic railgun and the free

  3. Naval Research Laboratory Technology Marketing Summaries - Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire Solar541,9337, 2011 at 2:00 P.M.Innovation Portal Naval

  4. Distributed Energy Resources at Naval Base Ventura County Building 1512: A Sensitivity Analysis

    E-Print Network [OSTI]

    Bailey, Owen C.; Marnay, Chris

    2005-01-01T23:59:59.000Z

    Resources at Naval Base Ventura Country Building 1512 6.Resources at Navy Base Ventura County Building 1512. ”August 2001. “Naval Base Ventura County Standby Generator

  5. Peter C. Chu Naval Ocean Analysis and Prediction Laboratory,

    E-Print Network [OSTI]

    Chu, Peter C.

    , such as using the wind tunnel, we present a new efficient and low cost method to determine the drag, liftPeter C. Chu Chenwu Fan Naval Ocean Analysis and Prediction Laboratory, Naval Postgraduate School, and no fin and no-tail section) conducted at the SRI test site. The cost of this method is much lower than

  6. Radiological survey of the Mare Island Naval Shipyard, Alameda Naval Air Station, and Hunters Point Shipyard

    SciTech Connect (OSTI)

    Semler, M.O.; Blanchard, R.L. (Environmental Protection Agency, Montgomery, AL (USA). Eastern Environmental Radiation Facility)

    1989-06-01T23:59:59.000Z

    Since 1963, the Eastern Environmental Radiation Facility (EERF), US Environmental Protection Agency (USEPA), in cooperation with the US Naval Sea Systems Command (NAVSEA) has surveyed facilities serving nuclear-powered warships on the Atlantic and Pacific coasts and the Gulf of Mexico. These surveys assess whether the operation of nuclear-powered warships, during construction, maintenance, overhaul, or refueling, have created elevated levels of radioactivity. The surveys emphasize sampling those areas and pathways that could expose the public. In 1984, NAVSEA requested that EPA survey all active facilities serving nuclear-powered warships over the next three years. This report contains the results of surveys conducted at Naval facilities located at Mare Island, Alameda, and Hunters Point in the San Francisco region. The locations of these facilities are shown. 3 refs., 4 figs., 3 tabs.

  7. Sandia National Laboratories: Carderock Naval Surface War-fare...

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

    Carderock Naval Surface War-fare Center Inter-Agency Agreement Signed between DOE's Wind and Water Power Program and Carderock On December 3, 2014, in Energy, News, News & Events,...

  8. Radiological surveys of Naval facilities on Puget Sound. Final report

    SciTech Connect (OSTI)

    Lloyd, V.D.; Blanchard, R.L.

    1989-06-01T23:59:59.000Z

    This report presents results of surveys conducted to assess levels of environmental radioactivity resulting from maintenance and operation of nuclear-powered warships at Puget Sound Naval Shipyard, Naval Submarine Base, Bangor, and the proposed Carrier Battle Group Homeporting Site in northwestern Washington. The purpose of the survey was to determine if activities related to nuclear-powered warships resulted in release of radionuclides that may contribute to significant population exposure or contamination of the environment.

  9. Tiger Team Assessment of the Naval Petroleum Reserves in California

    SciTech Connect (OSTI)

    Not Available

    1991-12-01T23:59:59.000Z

    This report documents the Tiger Team Assessment of the Naval Petroleum Reserves in California (NPRC) which consists of Naval Petroleum Reserve Number 1 (NPR-1), referred to as the Elk Hills oil field and Naval Petroleum Reserve Number 2 (NPR-2), referred to as the Buena Vista oil field, each located near Bakersfield, California. The Tiger Team Assessment was conducted from November 12 to December 13, 1991, under the auspices of DOE's Office of Special Projects (OSP) under the Assistant Secretary for Environment, Safety and Health (EH). The assessment was comprehensive, encompassing environmental, safety, and health (ES H), and quality assurance (OA) disciplines; site remediation; facilities management; and waste management operations. Compliance with applicable Federal, State of California, and local regulations; applicable DOE Orders; best management practices; and internal NPRC requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of DOE/NPRC, CUSA, and BPOI management of the ES H/QA programs was conducted.

  10. Tiger Team Assessment of the Naval Petroleum Reserves in California

    SciTech Connect (OSTI)

    Not Available

    1991-12-01T23:59:59.000Z

    This report documents the Tiger Team Assessment of the Naval Petroleum Reserves in California (NPRC) which consists of Naval Petroleum Reserve Number 1 (NPR-1), referred to as the Elk Hills oil field and Naval Petroleum Reserve Number 2 (NPR-2), referred to as the Buena Vista oil field, each located near Bakersfield, California. The Tiger Team Assessment was conducted from November 12 to December 13, 1991, under the auspices of DOE`s Office of Special Projects (OSP) under the Assistant Secretary for Environment, Safety and Health (EH). The assessment was comprehensive, encompassing environmental, safety, and health (ES&H), and quality assurance (OA) disciplines; site remediation; facilities management; and waste management operations. Compliance with applicable Federal, State of California, and local regulations; applicable DOE Orders; best management practices; and internal NPRC requirements was assessed. In addition, an evaluation of the adequacy and effectiveness of DOE/NPRC, CUSA, and BPOI management of the ES&H/QA programs was conducted.

  11. Carl Vinson and pre-war naval legislation 1932-1940

    E-Print Network [OSTI]

    Svonavec, Stephen Charles

    1994-01-01T23:59:59.000Z

    , House and Senate debates, and behind the scenes conferences between Vinson and officials of the Navy Department and Roosevelt Administration which helped decide the course of naval expansion. It shows that while many people contributed passing naval...

  12. Page 1 of 16 Naval Power and Globalization

    E-Print Network [OSTI]

    Aronov, Boris

    years China has followed the same path as its predecessor modernizing Asian neighbors. It has committed size and the scale, China is affecting both the regional and worldwide economic balances of power and India are influenced by the potential for China's increasing role as both an economic and naval power

  13. Colleagues and Friends of NPS: Recently the Naval Postgraduate

    E-Print Network [OSTI]

    @nps.edu Journalists Barbara Honegger MC2 (SW) Corey Truax MC3 Kellie Arakawa Photographers Javier Chagoya MC2 (SW) Corey Truax MC2 Kellie Arakawa Naval Postgraduate School President Daniel T. Oliver Provost Executive. Full versions of all articles are available at www.nps.edu #12;July 2008 Contents 7 New GSEAS Dean Dr

  14. Energy use baselining study for the National Naval Medical Center

    SciTech Connect (OSTI)

    Parker, G.B.; Halverson, M.A.

    1992-04-01T23:59:59.000Z

    This report provides an energy consumption profile for fourteen buildings at the National Naval Medical Center (NNMC) in Bethesda, Maryland. Recommendations are also made for viable energy efficiency projects funded with assistance from the servicing utility (Potomic Electric Power Company) in the form of rebates and incentives available in their Demand Side Management (DSM) program and through Shared Energy Savings (SES) projects. This report also provides estimates of costs and potential energy savings of the recommended projects.

  15. Naval Petroleum and Oil Shale Reserves annual report of operations for fiscal year 1996

    SciTech Connect (OSTI)

    NONE

    1996-12-31T23:59:59.000Z

    During fiscal year 1996, the Department of Energy continued to operate Naval Petroleum Reserve No. 1 in California and Naval Petroleum Reserve No. 3 in Wyoming through its contractors. In addition, natural gas operations were conducted at Naval Petroleum Reserve No. 3. All productive acreage owned by the Government at Naval Petroleum Reserve No. 2 in California was produced under lease to private companies. The locations of all six Naval Petroleum and Oil Shale Reserves are shown in a figure. Under the Naval Petroleum Reserves Production Act of 1976, production was originally authorized for six years, and based on findings of national interest, the President was authorized to extend production in three-year increments. President Reagan exercised this authority three times (in 1981, 1984, and 1987) and President Bush authorized extended production once (in 1990). President Clinton exercised this authority in 1993 and again in October 1996; production is presently authorized through April 5, 2000. 4 figs. 30 tabs.

  16. DOE - Office of Legacy Management -- Westinghouse Naval Ordnance - MI 02

    Office of Legacy Management (LM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOn AprilA group currentBradleyTableSelling Corp -KWatertown Arsenal - MAWesternPlantNaval

  17. Naval Academy, Maryland: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer PlantMunhall, Pennsylvania: EnergyEnergy InformationNatura Bio FuelsNautilusNaval

  18. United States Naval Surface Warfare Center | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty Edit withTianlin BaxinUmwelt Management AG UMaAG JumpEuropeUnitedUnitedLSC JumpNaval

  19. The 2006 Naval S&T Partnership Conference is presented by NDIA with technical support from ONR The Naval Postgraduate School's Role

    E-Print Network [OSTI]

    · Directed Energy Systems · Software Engineering · Combat System Physics · Electronic Warfare · SIGINT 1 Kenya 1 Nigeria 1 Rwanda 1 Senegal 1 Tanzania 1 Tunisia 4 11 #12;The 2006 Naval S&T Partnership

  20. a contaminant in decline: long-term tbt monitoring at a naval base in Western australia

    E-Print Network [OSTI]

    Burgman, Mark

    a contaminant in decline: long-term tbt monitoring at a naval base in Western australia john a planulatus) in and around the RAN naval base in Cockburn Sound, WesternAustralia, was initiated and continued, Australia. 2 Current address: ES Link Services Pty Ltd, PO Box 10, Castlemaine, VIC 3450, Australia. 3

  1. DEPARTMENT OF THE NAVY OFfiCE OF THE CHIEF OF NAVAL OPERATIONS

    E-Print Network [OSTI]

    DEPARTMENT OF THE NAVY OFfiCE OF THE CHIEF OF NAVAL OPERATIONS 2000 NAVY PENTAGON WASHINGTON, DC: Chief of Naval Operations Subj , NAVY PASSENGER TRAVEL Ref: (al 000 Di rective 5154.29 of 9 Marc h 1993 on the management , execution, and funding of passenger travel for Navy personne l . This i n struction

  2. Naval Petroleum and Oil Shale Reserves. Annual report of operations, Fiscal year 1992

    SciTech Connect (OSTI)

    Not Available

    1992-12-31T23:59:59.000Z

    During fiscal year 1992, the reserves generated $473 million in revenues, a $181 million decrease from the fiscal year 1991 revenues, primarily due to significant decreases in oil and natural gas prices. Total costs were $200 million, resulting in net cash flow of $273 million, compared with $454 million in fiscal year 1991. From 1976 through fiscal year 1992, the Naval Petroleum and Oil Shale Reserves generated more than $15 billion in revenues and a net operating income after costs of $12.5 billion. In fiscal year 1992, production at the Naval Petroleum Reserves at maximum efficient rates yielded 26 million barrels of crude oil, 119 billion cubic feet of natural gas, and 164 million gallons of natural gas liquids. From April to November 1992, senior managers from the Naval Petroleum and Oil Shale Reserves held a series of three workshops in Boulder, Colorado, in order to build a comprehensive Strategic Plan as required by Secretary of Energy Notice 25A-91. Other highlights are presented for the following: Naval Petroleum Reserve No. 1--production achievements, crude oil shipments to the strategic petroleum reserve, horizontal drilling, shallow oil zone gas injection project, environment and safety, and vanpool program; Naval Petroleum Reserve No. 2--new management and operating contractor and exploration drilling; Naval Petroleum Reserve No. 3--steamflood; Naval Oil Shale Reserves--protection program; and Tiger Team environmental assessment of the Naval Petroleum and Oil Shale Reserves in Colorado, Utah, and Wyoming.

  3. Coastal Inundation due to Tide, Surge, Waves, and Sea Level Rise at Naval Station Norfolk

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Coastal Inundation due to Tide, Surge, Waves, and Sea Level Rise at Naval Station Norfolk Honghai of future sea level rise (SLR) scenarios and to evaluate the potential coastal inundation at Naval Station and sea level rise threats to coastal residents and coastal military facilities, the US Strategic

  4. Vitrification of contaminated soils from the Charleston Naval Complex

    SciTech Connect (OSTI)

    O'Connor, William K.; Turner, Paul C.; Brosnan, D.A. (CECM, CLemson Univ.); Mussro, R. (CECM, Clemson Univ.); Addison, G.W. (AJT Enterprises, Inc.); Jackson, V.B. (AJT Enterprises, Inc.); Teaster, G.F. (AJT Enterprises, Inc.)

    1998-05-01T23:59:59.000Z

    Demonstration melting tests for vitrifying chrome- and lead-bearing wastes from the Charleston Naval Complex, and organic-contaminated dredging spoils from the Ashley River (part of the greater Charleston Harbor), were conducted in a 3-phase AC, graphite electrode arc furnace located at the Albany Research Center (ALRC) of the U.S. Department of Energy (DOE). These tests were conducted in cooperation with the Center for Engineering Ceramic Manufacturing (CECM) of Clemson University, and AJT Enterprises, Inc., of Charleston, South Carolina, and were funded by the DOE Office of Environmental Restoration. The two waste streams were composited into separate furance feed mixtures by blending and agglomeration with readily available industrial minerals. Over 11,340 kg (25,000 lb) of feed was processed during the demonstration melting test, at feed rates up to 523 kg/h (1,150 lb/h). Continuous feeding and glass tapping was achieved for both the dredging spoils feed mixture and the naval complex mixture. Roughly 85% of all feed reported to the glass products, which readily passed the Environmental Protection Agency (EPA) Toxicity Characteristic Leaching Procedure (TCLP). ASTM aggregate tests using the vitrified aggregate in concrete and asphaltic cements indicated a potential for utilization of these materials in concentrations from 5-15% of the total aggregate, without negative impact on the mix. Toxicological tests performed on the galss products found that this material appears to be nonhazardous and its use is not likely to result in a public health risk.

  5. Habitat restoration on naval petroleum reserves in Kern County, California

    SciTech Connect (OSTI)

    Anderson, D.C. [EG& G Energy Measurements, Inc., Tupman, CA (United States)

    1990-12-31T23:59:59.000Z

    One of several task performed under contract to the Department of Energy (DOE) by EG & G Energy Measurements as part of the endangered species program is the restoration of abandoned well pads, roads, pipelines and soil borrow sites resulting from oil and gas production activities on Naval Petroleum Reserves in California (NPRC). Naval Petroleum Reserves in California is located in the Elk Hills approximately 30 miles southwest of Bakersfield in the rain shadow of the coastal range. Annual precipitation is approximately five inches. Reclamation of disturbed habitat on NPRC began with research plots and test trials in the early 1980s. Full scale reclamation began in 1985 and has continued through the 1989 planting season. Almost 700 acres have been revegetated, which represents over 1,200 sites distributed over the 47,250 acres of NPRC and averaging less than .75 acre in size. Monitoring of the sites began in 1987 to establish reclamation success and evaluate reclamation techniques. Reclamation objectives include the improvement of wildlife habitat for four endangered species living on NPRC, and the protection of the soils from wind and water erosion on the disturbed sites.

  6. Naval Petroleum Reserve No. 1 (Elk Hills): Supplemental environmental impact statement. Record of decision

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    Pursuant to the Council on Environmental Quality regulations, which implement the procedural provisions of the National Environmental Policy Act, and the US Department of Energy National Environmental Policy Act regulations, the Department of Energy, Office of Fossil Energy, is issuing a Record of Decision on the continued operation of Naval Petroleum Reserve No. 1, Kern County, California. The Department of Energy has decided to continue current operations at Naval Petroleum Reserve No. 1 and implement additional well drilling, facility development projects and other activities necessary for continued production of Naval Petroleum Reserve No. 1 in accordance with the requirements of the Naval Petroleum Reserves Production Act of 1976. The final Supplemental Environmental Impact Statement, entitled ``Petroleum Production at Maximum Efficient Rate, Naval Petroleum Reserve No. 1 (Elk Hills), Kern County, California (DOE/SEIS-0158),`` was released on September 3, 1993.

  7. 2014 Annual Planning Summary for the NNSA Naval Reactors | Department of

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China 2015ofDepartment ofCBFO-13-3322(EE) |2DepartmentNaturalDepartment of Energy

  8. Audit Report - Naval Reactors Information Technology System Development Efforts, IG-0879

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: The FutureComments from TarasaName Affiliation Ahern,5 AuditImplementation of

  9. Naval Petroleum Reserves: assessment of alternative operating strategies beyond 1982

    SciTech Connect (OSTI)

    Gsellman, L.R.; Mendis, M.S.; Rosenberg, J.I.

    1981-08-01T23:59:59.000Z

    Legislation authorizing production from two Naval Petroleum Reserves, i.e., NPR-1 (Elk Hills, California) and NPR-3 (Teapot Dome, Wyoming), expires in 1982. This paper presents an assessment of the trade-offs of extending production or returning to a shut-in status. Strategic, economic, and energy factors at the national, regional, and local levels are considered. The results of the study indicate that the only major local impact of shut-in will be on small refineries near NPR-1. At the national level, shut-in increases the size of the national petroleum reserve system. However, economic losses as measured by changes in the present value of real GNP also occur. The estimate of the increase in the size of the national petroleum reserve with shut-in of the NPRs was found to be most sensitive to the assumed length of future import interruptions.

  10. Naval Petroleum Reserve No. 1: an assessment of production alternatives

    SciTech Connect (OSTI)

    Not Available

    1984-07-30T23:59:59.000Z

    Under existing legislation, every 3 years the President must decide whether to shut-in or continue production of the Naval Petroleum Reserve No. 1 (NPR-1) oil field at Elk Hills, California. The current authorization for production expires on April 5, 1985. GAO discusses the geologic, budgetary, local economic, and national security implications of three production alternatives for NPR-1: continued production, shut-in, and partial shut in. In addition, GAO discusses the advantages and disadvantages of establishing a Defense Petroleum Reserve, a crude oil reserve for the military, using part of the revenues from continued production at NPR-1 to fund it. During the course of its review, GAO found that production rates at Elk Hills may be too high, causing problems within the reserve that could decrease ultimate recovery of oil by about 139 million barrels. The Department of Energy plans to analyze this situation and, if need be, adjust the rate. 2 figures, 2 tables.

  11. Annual report of operations. [Naval Petroleum Reserves No. 1, 2, 3; oil shale reserves

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    The Naval Petroleum and Oil Shale Reserves during FY 1980 deliver 59,993,213 bbl of crude oil and substantial quantities of natural gas, butane, propane and natural gasoline to the United States market. During September, Naval Petroleum Reserve oil was utilized to resume filling the Strategic Petroleum Reserve. During FY 1980, Naval Petroleum Reserve No. 1, Elk Hills, became the largest producing oil field in California and the second largest producing field in the United States. Production at the end of September was 165,000 bbl/d; production is expected to peak at about 190,000 bbl/d early in calender year 1982. Production from Naval Petroleum Reserves Nos. 2 and 3 in California and Wyoming, contributed 1,101,582 and 1,603,477 bbl of crude oil to the market, respectively. Enhanced oil recovery work has been inititated at Naval Petroleum Reserve no. 3. Total revenues from the Naval Petroleum Reserves during FY 1980 were 1.6 billion. The three Naval Oil Shale Reserves in Colorado and Utah have substantial potential. In addition to containing approximately 2.5 billion bbl recoverable shale oil. They probably contain significant quantities of conventional oil and gas.

  12. BDDR, a new CEA technological and operating reactor database

    SciTech Connect (OSTI)

    Soldevilla, M.; Salmons, S.; Espinosa, B. [CEA-Saclay, CEA/DEN/DANS/DM2S/SERMA, 91191 Gif-sur-Yvette (France); Clanet, M.; Boudin, X. [CEA-Bruyeres-le-Chatel, 91297 Arpajon (France)

    2013-07-01T23:59:59.000Z

    The new application BDDR (Reactor database) has been developed at CEA in order to manage nuclear reactors technological and operating data. This application is a knowledge management tool which meets several internal needs: -) to facilitate scenario studies for any set of reactors, e.g. non-proliferation assessments; -) to make core physics studies easier, whatever the reactor design (PWR-Pressurized Water Reactor-, BWR-Boiling Water Reactor-, MAGNOX- Magnesium Oxide reactor-, CANDU - CANada Deuterium Uranium-, FBR - Fast Breeder Reactor -, etc.); -) to preserve the technological data of all reactors (past and present, power generating or experimental, naval propulsion,...) in a unique repository. Within the application database are enclosed location data and operating history data as well as a tree-like structure containing numerous technological data. These data address all kinds of reactors features and components. A few neutronics data are also included (neutrons fluxes). The BDDR application is based on open-source technologies and thin client/server architecture. The software architecture has been made flexible enough to allow for any change. (authors)

  13. Rise and fall of a tactic: the ram in nineteenth century naval doctrine

    E-Print Network [OSTI]

    Johnson, Robert Leroy

    1989-01-01T23:59:59.000Z

    . , 158; "A Royal Navy Officer", "Tactical Results of Recent Naval Construction, " Naval Science, Vol. 2 No. 2 (AP '1, 1873), 1397 Ed d J 2 d, ~0 ~ld 88 ((. o d: JoR M 9, 1869), 20. Baxter, Introduction of the Ironclad Warshi , 100. U. S. , Department...? son ( ~&ember) J. Richard St (Member) L rry D. Hill (He d of Department) December 1989 ABSTRACT Rise and Fall of a Tactic: The Ram in Nineteenth Century Naval Doctrine. (December 1989) Robert Leroy Johnson II, B. A. , Kansas State University...

  14. Naval petroleum reserves: Sales procedures and prices received for Elk Hills oil

    SciTech Connect (OSTI)

    Not Available

    1986-01-01T23:59:59.000Z

    The Congress expressed concern about the Department of Energy's actions in selling oil from the Elk Hills Naval Petroleum Reserve at what appeared to be unreasonably low prices. DOE officials believe that Naval Petroleum Reserve oil has been and is currently being produced at the appropriate rate and that no recoverable oil has been lost. This fact sheet provides information on the basis for the procedures followed by DOE in selling Naval Petroleum Reserve oil and sales data for the period extending from October 1985 through April 1986.

  15. Light-weight materials selection for high-speed naval craft

    E-Print Network [OSTI]

    Torrez, Joseph B. (Joseph Benjamin)

    2007-01-01T23:59:59.000Z

    A decision analysis study was conducted on the process of materials selection for high-speed naval craft using the Modified Digital Logic (MDL) method proposed by B. Dehgham-Manshadi et al in ref [17]. The purpose is to ...

  16. EA-1236: Preparation for Transfer of Ownership of Naval Petroleum Reserve No. 3, Natrona County, WY

    Broader source: Energy.gov [DOE]

    Final Sitewide Environmental Assessment (EA) This Sitewide EA evaluates activities that DOE would conduct in anticipation of possible transfer of Naval Petroleum Reserve No. 3 (NPR-3) out of Federal operation.

  17. Naval ship propulsion and electric power systems selection for optimal fuel consumption

    E-Print Network [OSTI]

    Sarris, Emmanouil

    2011-01-01T23:59:59.000Z

    Although propulsion and electric power systems selection is an important part of naval ship design, respective decisions often have to be made without detailed ship knowledge (resistance, propulsors, etc.). Propulsion and ...

  18. Modular machinery arrangement and its impact in early-stage naval electric ship design

    E-Print Network [OSTI]

    Jurkiewicz, David J. (David James)

    2012-01-01T23:59:59.000Z

    Electrical power demands for naval surface combatants are projected to rise with the development of increasingly complex and power intensive combat systems. This trend also coincides with the need of achieving maximum fuel ...

  19. Analyzing the effects of component reliability on naval Integrated Power System quality of service

    E-Print Network [OSTI]

    Hawbaker, Benjamin F. (Benjamin Forrest)

    2008-01-01T23:59:59.000Z

    The Integrated Power System (IPS) is a key enabling technology for future naval vessels and their advanced weapon systems. While conventional warship designs utilize separate power systems for propulsion and shipboard ...

  20. Design and analysis of a permanent magnet generator for naval applications

    E-Print Network [OSTI]

    Rucker, Jonathan E. (Jonathan Estill)

    2005-01-01T23:59:59.000Z

    This paper discusses the electrical and magnetic design and analysis of a permanent magnet generation module for naval applications. Numerous design issues are addressed and several issues are raised about the potential ...

  1. US Department of Energy Naval petroleum reserve number 1. Financial statement audit

    SciTech Connect (OSTI)

    NONE

    1997-03-01T23:59:59.000Z

    The Naval Petroleum and Oil Shale Reserves (NPOSR) produces crude oil and associated hydrocarbons from the Naval Petroleum Reserves (NPR) numbered 1, 2, and 3, and the Naval Oil Shale Reserves numbered 1, 2, and 3 in a manner to achieve the greatest value and benefits to the United States taxpayer. NPOSR was established by a series of Executive Orders in the early 1900s as a future source of liquid fuels for the military. NPOSR remained largely inactive until Congress, responding to the Arab oil embargo of 1973-74, passed the Naval Petroleum Reserves Production Act of 1976. The law authorized production for six years. Thereafter, NPOSR production could be reauthorized by the President in three-year increments. Since enactment of the law, every President has determined that continuing NPOSR production is in the nation`s best interest. NPOSR currently is authorized to continue production through April 5, 2000.

  2. A study of the Naval Construction Force project material supply chain

    E-Print Network [OSTI]

    Stasick, Steven J. (Steven James), 1970-

    2004-01-01T23:59:59.000Z

    The Naval Construction Force (NCF) performs construction projects in all areas of the world during both peacetime and war. While some of these projects occur in populated areas where project materials are readily available, ...

  3. Application and analysis of stiffened side shell panel failure for naval patrol craft

    E-Print Network [OSTI]

    Mothander, Matthew K. A., Lieutenant (Matthew Kristian Alden)

    2009-01-01T23:59:59.000Z

    Over their lifetime, naval patrol craft are subjected to many different types of loading scenarios, most of which are perfectly safe. In rare instances, through a variety of different reasons, these craft are loaded beyond ...

  4. EIS-0158: Sale of the Naval Petroleum Reserve No. 1 at Elk Hills, California (1997)

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this EIS to assess the potential environmental impacts of the continued operation of the Naval Petroleum Reserve No. 1 at the Maximum Efficient Rate authorized by Public Law 94-258.

  5. EIS-0068: Development Policy Options for the Naval Oil Shale Reserves in Colorado

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy Office of Naval Petroleum and Oil Shale Reserves prepared this programmatic statement to examine the environmental and socioeconomic impacts of development projects on the Naval Oil Shale Reserve 1, and examine select alternatives, such as encouraging production from other liquid fuel resources (coal liquefaction, biomass, offshore oil and enhanced oil recovery) or conserving petroleum in lieu of shale oil production.

  6. Naval Undersea Warfare Center Division Newport utilities metering, Phase 1

    SciTech Connect (OSTI)

    Carroll, D.M.

    1992-11-01T23:59:59.000Z

    Pacific Northwest Laboratory developed this report for the US Navy's Naval Undersea Warfare Center Division Newport, Rhode Island (NUWC). The purpose of the report was to review options for metering electricity and steam used in the NUWC compound, and to make recommendations to NUWC for implementation under a follow-on project. An additional NUWC concern is a proposed rate change by the servicing utility, Newport Electric, which would make a significant shift from consumption to demand billing, and what effect that rate change would have on the NUWC utility budget. Automated, remote reading meters are available which would allow NUWC to monitor its actual utility consumption and demand for both the entire NUWC compound and by end-use in individual buildings. Technology is available to perform the meter reads and manipulate the data using a personal computer with minimal staff requirement. This is not meant to mislead the reader into assuming that there is no requirement for routine preventive maintenance. All equipment requires routine maintenance to maintain its accuracy. While PNL reviewed the data collected during the site visit, however, it became obvious that significant opportunities exist for reducing the utility costs other than accounting for actual consumption and demand. Unit costs for both steam and electricity are unnecessarily high, and options are presented in this report for reducing them. Additionally, NUWC has an opportunity to undertake a comprehensive energy resource management program to significantly reduce its energy demand, consumption, and costs.

  7. Naval Undersea Warfare Center Division Newport utilities metering, Phase 1

    SciTech Connect (OSTI)

    Carroll, D.M.

    1992-11-01T23:59:59.000Z

    Pacific Northwest Laboratory developed this report for the US Navy`s Naval Undersea Warfare Center Division Newport, Rhode Island (NUWC). The purpose of the report was to review options for metering electricity and steam used in the NUWC compound, and to make recommendations to NUWC for implementation under a follow-on project. An additional NUWC concern is a proposed rate change by the servicing utility, Newport Electric, which would make a significant shift from consumption to demand billing, and what effect that rate change would have on the NUWC utility budget. Automated, remote reading meters are available which would allow NUWC to monitor its actual utility consumption and demand for both the entire NUWC compound and by end-use in individual buildings. Technology is available to perform the meter reads and manipulate the data using a personal computer with minimal staff requirement. This is not meant to mislead the reader into assuming that there is no requirement for routine preventive maintenance. All equipment requires routine maintenance to maintain its accuracy. While PNL reviewed the data collected during the site visit, however, it became obvious that significant opportunities exist for reducing the utility costs other than accounting for actual consumption and demand. Unit costs for both steam and electricity are unnecessarily high, and options are presented in this report for reducing them. Additionally, NUWC has an opportunity to undertake a comprehensive energy resource management program to significantly reduce its energy demand, consumption, and costs.

  8. NALDA (Naval Aviation Logistics Data Analysis) CAI (computer aided instruction)

    SciTech Connect (OSTI)

    Handler, B.H. (Oak Ridge K-25 Site, TN (USA)); France, P.A.; Frey, S.C.; Gaubas, N.F.; Hyland, K.J.; Lindsey, A.M.; Manley, D.O. (Oak Ridge Associated Universities, Inc., TN (USA)); Hunnum, W.H. (North Carolina Univ., Chapel Hill, NC (USA)); Smith, D.L. (Memphis State Univ., TN (USA))

    1990-07-01T23:59:59.000Z

    Data Systems Engineering Organization (DSEO) personnel developed a prototype computer aided instruction CAI system for the Naval Aviation Logistics Data Analysis (NALDA) system. The objective of this project was to provide a CAI prototype that could be used as an enhancement to existing NALDA training. The CAI prototype project was performed in phases. The task undertaken in Phase I was to analyze the problem and the alternative solutions and to develop a set of recommendations on how best to proceed. The findings from Phase I are documented in Recommended CAI Approach for the NALDA System (Duncan et al., 1987). In Phase II, a structured design and specifications were developed, and a prototype CAI system was created. A report, NALDA CAI Prototype: Phase II Final Report, was written to record the findings and results of Phase II. NALDA CAI: Recommendations for an Advanced Instructional Model, is comprised of related papers encompassing research on computer aided instruction CAI, newly developing training technologies, instructional systems development, and an Advanced Instructional Model. These topics were selected because of their relevancy to the CAI needs of NALDA. These papers provide general background information on various aspects of CAI and give a broad overview of new technologies and their impact on the future design and development of training programs. The paper within have been index separately elsewhere.

  9. Renewable Energy Optimization Report for Naval Station Newport

    SciTech Connect (OSTI)

    Robichaud, R.; Mosey, G.; Olis, D.

    2012-02-01T23:59:59.000Z

    In 2008, the U.S. Environmental Protection Agency (EPA) launched the RE-Powering America's Land initiative to encourage the development of renewable energy (RE) on potentially contaminated land and mine sites. As part of this effort, EPA is collaborating with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to evaluate RE options at Naval Station (NAVSTA) Newport in Newport, Rhode Island. NREL's Renewable Energy Optimization (REO) tool was utilized to identify RE technologies that present the best opportunity for life-cycle cost-effective implementation while also serving to reduce energy-related carbon dioxide emissions and increase the percentage of RE used at NAVSTA Newport. The technologies included in REO are daylighting, wind, solar ventilation preheating (SVP), solar water heating, photovoltaics (PV), solar thermal (heating and electric), and biomass (gasification and cogeneration). The optimal mix of RE technologies depends on several factors including RE resources; technology cost and performance; state, utility, and federal incentives; and economic parameters (discount and inflation rates). Each of these factors was considered in this analysis. Technologies not included in REO that were investigated separately per NAVSTA Newport request include biofuels from algae, tidal power, and ground source heat pumps (GSHP).

  10. Distributed energy resources at naval base ventura county building 1512

    SciTech Connect (OSTI)

    Bailey, Owen C.; Marnay, Chris

    2004-10-01T23:59:59.000Z

    This paper reports the findings of a preliminary assessment of the cost effectiveness of distributed energy resources at Naval Base Ventura County (NBVC) Building 1512. This study was conducted in response to the base's request for design assistance to the Federal Energy Management Program. Given the current tariff structure there are two main decisions facing NBVC: whether to install distributed energy resources (DER), or whether to continue the direct access energy supply contract. At the current effective rate, given assumptions about the performance and structure of building energy loads and available generating technology characteristics, the results of this study indicate that if the building installed a 600 kW DER system with absorption cooling and heat capabilities chosen by cost minimization, the energy cost savings would be about 14 percent, or $55,000 per year. However, under current conditions, this study also suggests that significant savings could be obtained if Building 1 512 changed from the direct access contract to a SCE TOU-8 (Southern California Edison time of use tariff number 8) rate without installing a DER system. At current SCE TOU-8 tariffs, the potential savings from installation of a DER system would be about 4 percent, or $15,000 per year.

  11. ONR Symposium on Naval Hydrodynamics, Val de Reuil, France, 17-22 September. Forces, Moment and Wave Pattern for Naval Combatant

    E-Print Network [OSTI]

    Gui, Lichuan

    ABSTRACT A model-scale naval surface combatant, DTMB 5512, is studied experimentally in steady forward and Stern (1996) applied traditional 5-hole pitot probes to measure the time mean velocities. Laser Ohkusu (1990) described two methods, i.e. with wave probes installed on the towing carriage for acquiring

  12. Fuel Summary Report: Shippingport Light Water Breeder Reactor

    SciTech Connect (OSTI)

    Illum, D.B.; Olson, G.L.; McCardell, R.K.

    1999-01-01T23:59:59.000Z

    The Shippingport Light Water Breeder Reactor (LWBR) was a small water cooled, U-233/Th-232 cycle breeder reactor developed by the Pittsburgh Naval Reactors to improve utilization of the nation's nuclear fuel resources in light water reactors. The LWBR was operated at Shippingport Atomic Power Station (APS), which was a Department of Energy (DOE) (formerly Atomic Energy Commission)-owned reactor plant. Shippingport APS was the first large-scale, central-station nuclear power plant in the United States and the first plant of such size in the world operated solely to produce electric power. The Shippingport LWBR was operated successfully from 1977 to 1982 at the APS. During the five years of operation, the LWBR generated more than 29,000 effective full power hours (EFPH) of energy. After final shutdown, the 39 core modules of the LWBR were shipped to the Expended Core Facility (ECF) at Naval Reactors Facility at the Idaho National Engineering and Environmental Laboratory (INEEL). At ECF, 12 of the 39 modules were dismantled and about 1000 of more than 17,000 rods were removed from the modules of proof-of-breeding and fuel performance testing. Some of the removed rods were kept at ECF, some were sent to Argonne National Laboratory-West (ANL-W) in Idaho and some to ANL-East in Chicago for a variety of physical, chemical and radiological examinations. All rods and rod sections remaining after the experiments were shipped back to ECF, where modules and loose rods were repackaged in liners for dry storage. In a series of shipments, the liners were transported from ECF to Idaho Nuclear Technology Engineering Center (INTEC), formerly the Idaho Chemical Processing Plant (ICPP). The 47 liners containing the fully-rodded and partially-derodded core modules, the loose rods, and the rod scraps, are now stored in underground dry wells at CPP-749.

  13. Nuclear reactor engineering

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1981-01-01T23:59:59.000Z

    Chapters are presented concerning energy from nuclear fission; nuclear reactions and radiations; diffusion and slowing-down of neutrons; principles of reactor analysis; nuclear reactor kinetics and control; energy removal; non-fuel reactor materials; the reactor fuel system; radiation protection and environmental effects; nuclear reactor shielding; nuclear reactor safety; and power reactor systems.

  14. This document was downloaded on May 22, 2013 at 14:37:52 Author(s) Naval Postgraduate School (U.S.)

    E-Print Network [OSTI]

    Officer in Charge Naval Engineering J. E. Fradd D. R. Frakes J. P. Craft Capt. USN Cmdr. USN Cmdr. USN

  15. Potential geothermal energy use at the Naval Air Rework Facilities, Norfolk, Virginia and Jacksonville, Florida, and at the naval shipyard, Charleston, South Carolina

    SciTech Connect (OSTI)

    Costain, J.K.; Glover, L. III; Newman, R.W.

    1984-05-01T23:59:59.000Z

    The feasibility of geothermal energy use at naval installations in Norfolk, VA, Jacksonville, FL, and Charleston, SC was assessed. Geophysical and geological studies of the above areas were performed. Engineering and economic factors, affecting potential energy use, were evaluated. The Norfolk and Jacksonville facilities are identified as candidates for geothermal systems. System costs are predicted. Economic benefits of the proposed geothermal systems are forecast, using the net present value method of predicting future income.

  16. FY 2012 Budget Hearing Testimony on Nuclear Nonproliferation and Naval

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) Environmental Assessments (EA) /EmailMolecularGE,OzoneContacts&51Reactor Programs

  17. Modeling of Coastal Inundation, Storm Surge, and Relative Sea-Level Rise at Naval Station Norfolk, Norfolk, Virginia, U.S.A.

    E-Print Network [OSTI]

    US Army Corps of Engineers

    Modeling of Coastal Inundation, Storm Surge, and Relative Sea- Level Rise at Naval Station Norfolk. Modeling of coastal inundation, storm surge, and relative sea-level rise at Naval Station Norfolk, Norfolk, and relative sea-level-rise (RSLR) scenarios were examined at the U.S. Naval Station, Norfolk, Virginia

  18. Bioconversion reactor

    DOE Patents [OSTI]

    McCarty, Perry L. (Stanford, CA); Bachmann, Andre (Palo Alto, CA)

    1992-01-01T23:59:59.000Z

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  19. Catalytic reactor

    DOE Patents [OSTI]

    Aaron, Timothy Mark (East Amherst, NY); Shah, Minish Mahendra (East Amherst, NY); Jibb, Richard John (Amherst, NY)

    2009-03-10T23:59:59.000Z

    A catalytic reactor is provided with one or more reaction zones each formed of set(s) of reaction tubes containing a catalyst to promote chemical reaction within a feed stream. The reaction tubes are of helical configuration and are arranged in a substantially coaxial relationship to form a coil-like structure. Heat exchangers and steam generators can be formed by similar tube arrangements. In such manner, the reaction zone(s) and hence, the reactor is compact and the pressure drop through components is minimized. The resultant compact form has improved heat transfer characteristics and is far easier to thermally insulate than prior art compact reactor designs. Various chemical reactions are contemplated within such coil-like structures such that as steam methane reforming followed by water-gas shift. The coil-like structures can be housed within annular chambers of a cylindrical housing that also provide flow paths for various heat exchange fluids to heat and cool components.

  20. Naval Research Laboratory Memorandum Report, 2003 Perceptual and Ergonomic Issues in

    E-Print Network [OSTI]

    Swan II, J. Edward

    Naval Research Laboratory Memorandum Report, 2003 1 Perceptual and Ergonomic Issues in Mobile paradigm, the field needs a much better understanding of the fundamental perceptual and ergonomic issues aimed at both understanding the fundamental perceptual and ergonomic issues in AR display

  1. Importance of Nuclear DataImportance of Nuclear Data to the Naval Nuclear Propulsion Program

    E-Print Network [OSTI]

    Danon, Yaron

    Importance of Nuclear DataImportance of Nuclear Data to the Naval Nuclear Propulsion Program Don Cores · Project Prometheus · Some Very Recent Criticality Analyses #12;Use of Early RPI Measurements · Criticality Analyses of Under-moderated Systemsy y y · Most Reactive Condition ­ Highest Water Density

  2. Karen Swider-Lyons, Peter Bouwman, Norma Ugarte Naval Research Laboratory

    E-Print Network [OSTI]

    supported on MOx·H2O supported on carbon Pt MOx e- carbon H+ OO H+ H+ Nafion H+ O2 O H2O Catalyst development via electrochemical and structural analysis #12;Naval Research Lab DOE review 19May2003 Pt-MOx

  3. Zircaloy performance in light water reactors

    SciTech Connect (OSTI)

    Adamson, R.B.; Cheng, B.C.; Kruger, R.M. [GE Nuclear Energy, Pleasanton, CA (United States)

    1992-12-31T23:59:59.000Z

    Zircaloy has been successfully used as the primary light water reactor (LWR) core structural material since its introduction in the early days of the US naval nuclear program. Its unique combination of low neutron absorption cross section, fabricability, mechanical strength, and corrosion resistance in water and steam near 300{degrees}C has resulted in remarkable reliability of operation of pressurized and boiling water reactor (PWR, BWR) fuel through the years. At present time, BWRs use Zircaloy-2 and PWRs use Zircaloy-4 for fuel cladding. In BWRs, both Zircaloy-2 and -4 have been successfully used for spacer grids and channels, and in PWRs Zircaloy-4 is used for spacer grids and control rod guide tubes. Performance of fuel rods has been excellent thus far. The current trend for utilities worldwide is to expect both higher fuel reliability in the future. Fuel suppliers have already achieved extended exposures in lead use assemblies, and have demonstrated excellent performance in all areas; therefore unsuspected problems are not likely to arise. However, as exposure and expectations continue to increase, Zircaloy is being taken toward the limits of its known capabilities. This paper reviews Zircaloy performance capabilities in areas related to environmentally affected microstructure, mechanical properties, corrosion resistance, and dimensional stability. The effects of radiation and reactor environment on each property is illustrated with data, micrographs, and analysis.

  4. Mitigation action plan sale of Naval Petroleum Reserve No. 1 (Elk Hills) Kern County, California

    SciTech Connect (OSTI)

    NONE

    1998-01-01T23:59:59.000Z

    Naval Petroleum Reserve No. 1 (NPR-1, also called {open_quotes}Elk Hills{close_quotes}), a Federally-owned oil and gas production field in Kern County, California, was created by an Executive Order issued by President Taft on September 2, 1912. He signed another Executive Order on December 13, 1912, to establish Naval Petroleum Reserve No. 2 (NPR-2), located immediately south of NPR-1 and containing portions of the town of Taft, California. NPR-1 was not developed until the 1973-74 oil embargo demonstrated the nation`s vulnerability to oil supply interruptions. Following the embargo, Congress passed the Naval Petroleum Reserves Production Act of 1976 which directed that the reserve be explored and developed to its fall economic potential at the {open_quotes}maximum efficient rate{close_quotes} (MER) of production. Since Elk Hills began full production in 1976, it has functioned as a commercial operation, with total revenues to the Federal government through FY 1996 of $16.4 billion, compared to total exploration, development and production costs of $3.1 billion. In February 1996, Title 34 of the National Defense Authorization Act for Fiscal Year 1996 (P.L. 104-106), referred to as the Elk Hills Sales Statute, directed the Secretary of Energy to sell NPR-1 by February 10, 1998.The Secretary was also directed to study options for enhancing the value of the other Naval Petroleum and Oil Shale Reserve properties such as NPR-2, located adjacent to NPR-1 in Kern County- Naval Petroleum Reserve No. 3 (NPR-3) located in Natrona County, Wyoming; Naval Oil Shale Reserves No. 1 and No. 3 (NOSR-1 and NOSR-3) located in Garfield County, Colorado; and Naval Oil Shale Reserve No. 2 (NOSR-2) located in Uintah and Carbon Counties, Utah. The purpose of these actions was to remove the Federal government from the inherently non-Federal function of operating commercial oil fields while making sure that the public would obtain the maximum value from the reserves.

  5. Neutronic reactor

    DOE Patents [OSTI]

    Wende, Charles W. J. (Augusta, GA); Babcock, Dale F. (Wilmington, DE); Menegus, Robert L. (Wilmington, DE)

    1983-01-01T23:59:59.000Z

    A nuclear reactor includes an active portion with fissionable fuel and neutron moderating material surrounded by neutron reflecting material. A control element in the active portion includes a group of movable rods constructed of neutron-absorbing material. Each rod is movable with respect to the other rods to vary the absorption of neutrons and effect control over neutron flux.

  6. "The Fourth Dimension of Naval Tactics": The U.S. Navy and Public Relations, 1919-1939 

    E-Print Network [OSTI]

    Wadle, Ryan David

    2012-07-16T23:59:59.000Z

    Prior to 1917, the United States Navy only utilized public relations techniques during times of war or to attract recruits into naval service. Following World I, the Navy confronted several daunting problems, including the ...

  7. EA-0531: Proposed Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3, Garfield County, Colorado

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of a proposal for a Natural Gas Protection Program for Naval Oil Shale Reserves Nos. 1 and 3 which would be implemented over a five-year period that...

  8. Technical Safety Appraisal of the Naval Petroleum Reserve No. 1, Elk Hills, California

    SciTech Connect (OSTI)

    Not Available

    1990-02-01T23:59:59.000Z

    This report presents the results of a focused Technical Safety Appraisal (TSA) of the Naval Petroleum Reserve No. 1 (NPR-1), Elk Hills, California, conducted during November 27 through December 8, 1989. The Department of Energy (DOE) program organization responsible for NPR-1 is the Assistant Secretary for Fossil Energy (FE); the responsible Field Office is the Naval Petroleum Reserves California (NPRC) Office. This appraisal is an application of the program that was initiated in 1985 to strengthen the DOE Environment, Safety and Health Program. The appraisal was conducted by the staff of the DOE Assistant Secretary for Environment, Safety and Health (EH), Office of Safety Appraisals, with support from experts in specific appraisal areas, including a number from the petroleum industry, and a liaison representative from FE. The Senior EH Manager for the appraisal was Mr. Robert Barber, Acting Director, Office of Compliance Programs; the Team Leader was Dr. Owen Thompson, Office of Safety Appraisals.

  9. Investigation on the continued production of the Naval Petroleum Reserves beyond April 5, 1991

    SciTech Connect (OSTI)

    Not Available

    1990-09-01T23:59:59.000Z

    The authority to produce the Naval Petroleum Reserves (NPRs) is due to expire in April 1991, unless extended by Presidential finding. As provided in the Naval Petroleum Reserves Production act of 1976 (Public Law 94-258), the President may continue production of the NPRs for a period of up to three years following the submission to Congress, at least 180 days prior to the expiration of the current production period, of a report that determines that continued production of the NPRs is necessary and a finding by the President that continued production is in the national interest. This report assesses the need to continue production of the NPRs, including analyzing the benefits and costs of extending production or returning to the shut-in status that existed prior to 1976. This continued production study considers strategic, economic, and energy issues at the local, regional, and national levels. 15 figs., 13 tabs.

  10. Structure of processes in flow reactor and closed reactor: Flow reactor

    E-Print Network [OSTI]

    Greifswald, Ernst-Moritz-Arndt-Universität

    Structure of processes in flow reactor and closed reactor: Flow reactor Closed reactor Active Zone -- chemical quasi- equilibria, similarity principles and macroscopic kinetics", in: Lectures on Plasma Physics

  11. U.S. Department of Energy Naval Petroleum and Oil Shale Reserves combined financial statements, September 30, 1996 and 1995

    SciTech Connect (OSTI)

    NONE

    1997-03-01T23:59:59.000Z

    The Naval Petroleum and Oil Shale Reserves (NPOSR) produces crude oil and associated hydrocarbons from the Naval Petroleum Reserves (NPR) numbered 1, 2, and 3, and the Naval Oil Shale Reserves (NOSR) numbered 1, 2, and 3 in a manner to achieve the greatest value and benefits to the US taxpayer. NPOSR consists of the Naval Petroleum Reserve in California (NPRC or Elk Hills), which is responsible for operations of NPR-1 and NPR-2; the Naval Petroleum Oil Shale Reserve in Colorado, Utah, and Wyoming (NPOSR-CUW), which is responsible for operations of NPR-3, NOSR-1, 2, and 3 and the Rocky Mountain Oilfield Testing Center (RMOTC); and NPOSR Headquarters in Washington, DC, which is responsible for overall program direction. Each participant shares in the unit costs and production of hydrocarbons in proportion to the weighted acre-feet of commercially productive oil and gas formations (zones) underlying the respective surface lands as of 1942. The participating shares of NPR-1 as of September 30, 1996 for the US Government and Chevron USA, Inc., are listed. This report presents the results of the independent certified public accountants` audit of the Department of Energy`s (Department) Naval Petroleum and Oil Shale Reserves (NPOSR) financial statements as of September 30, 1996.

  12. Hybrid adsorptive membrane reactor

    DOE Patents [OSTI]

    Tsotsis, Theodore T. (Huntington Beach, CA); Sahimi, Muhammad (Altadena, CA); Fayyaz-Najafi, Babak (Richmond, CA); Harale, Aadesh (Los Angeles, CA); Park, Byoung-Gi (Yeosu, KR); Liu, Paul K. T. (Lafayette Hill, PA)

    2011-03-01T23:59:59.000Z

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  13. Nuclear reactor engineering

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1982-07-01T23:59:59.000Z

    A book is reviewed which emphasizes topics directly related to the light water reactor power plant and the fast reactor power system. Current real-world problems are addressed throughout the text, and a chapter on safety includes much of the postThree Mile Island impact on operating systems. Topics covered include Doppler broadening, neutron resonances, multigroup diffusion theory, reactor kinetics, reactor control, energy removal, nonfuel materials, reactor fuel, radiation protection, environmental effects, and reactor safety.

  14. Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2

    SciTech Connect (OSTI)

    Cummins, G.D.

    1994-06-01T23:59:59.000Z

    This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy`s (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS.

  15. EIS-0251: Department of the Navy Final Environmental Impact Statement for a Container System for the Management of Naval Spent Nuclear Fuel (November 1996)

    Broader source: Energy.gov [DOE]

    This Final Environmental Impact Statement addresses six general alternative systems for the loading, storage, transport, and possible disposal of naval spent nuclear fuel following examination.

  16. SRS Small Modular Reactors

    SciTech Connect (OSTI)

    None

    2012-04-27T23:59:59.000Z

    The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

  17. SRS Small Modular Reactors

    ScienceCinema (OSTI)

    None

    2014-05-21T23:59:59.000Z

    The small modular reactor program at the Savannah River Site and the Savannah River National Laboratory.

  18. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J. (Clairton, PA)

    1980-03-11T23:59:59.000Z

    This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature.

  19. Naval Petroleum and Oil Shale Reserves. Annual report of operations, Fiscal year 1993

    SciTech Connect (OSTI)

    Not Available

    1993-12-31T23:59:59.000Z

    During fiscal year 1993, the reserves generated $440 million in revenues, a $33 million decrease from the fiscal year 1992 revenues, primarily due to significant decreases in oil and natural gas prices. Total costs were $207 million, resulting in net cash flow of $233 million, compared with $273 million in fiscal year 1992. From 1976 through fiscal year 1993, the Naval Petroleum and Oil Shale Reserves generated $15.7 billion in revenues for the US Treasury, with expenses of $2.9 billion. The net revenues of $12.8 billion represent a return on costs of 441 percent. See figures 2, 3, and 4. In fiscal year 1993, production at the Naval Petroleum and Oil Shale Reserves at maximum efficient rates yielded 25 million barrels of crude oil, 123 billion cubic feet of natural gas, and 158 million gallons of natural gas liquids. The Naval Petroleum and Oil Shale Reserves has embarked on an effort to identify additional hydrocarbon resources on the reserves for future production. In 1993, in cooperation with the US Geological Survey, the Department initiated a project to assess the oil and gas potential of the program`s oil shale reserves, which remain largely unexplored. These reserves, which total a land area of more than 145,000 acres and are located in Colorado and Utah, are favorably situated in oil and gas producing regions and are likely to contain significant hydrocarbon deposits. Alternatively the producing assets may be sold or leased if that will produce the most value. This task will continue through the first quarter of fiscal year 1994.

  20. Nuclear reactor

    DOE Patents [OSTI]

    Thomson, Wallace B. (Severna Park, MD)

    2004-03-16T23:59:59.000Z

    A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

  1. Rise and fall of a tactic: the ram in nineteenth century naval doctrine 

    E-Print Network [OSTI]

    Johnson, Robert Leroy

    1989-01-01T23:59:59.000Z

    collision between a steamer and another vessel at anchor which resulted in the sinking of the latter. In 1846, George L. Schuyler proposed a ram to Congress, supporting his concept with the evidence of two maritime accidents. The first occurred when... THE EMERGENCE OF THE RAM IN THE 1860'S About 1860, two important events happened that mark a new phase in the history of the ram, as well as naval history in general. In 1858, the French laid down the first ocean-going ironclad warship, the Gloire, to which...

  2. Influence of physiography and vegetation on small mammals at the Naval Petroleum Reserves, California

    SciTech Connect (OSTI)

    Cypher, B.L.

    1995-02-13T23:59:59.000Z

    Influence of physiography and vegetation on small mammal abundance and species Composition was investigated at Naval Petroleum Reserve No. 1 in California to assess prey abundance for Federally endangered San Joaquin kit foxes (Vulpes macrotis mutica) and to assess the distribution of two Federal candidate species, San Joaquin antelope squirrels (Ammospermophilus nelsoni) and short-nosed kangaroo rats (Dinodomys nitratoides brevinasus). The specific objectives of this investigation were to determine whether small mammal abundance and community composition varied with north-south orientation, terrain, ground cover, and Cypher shrub density, and whether these factors influenced the distribution and abundance of San Joaquin antelope squirrels and short-nosed kangaroo rats.

  3. U.S. Naval Station, Guantanamo Bay, Cuba | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergyIssuesEnergyTransportation&Department of Energy U.S.Naval

  4. Atmospheric Pressure Reactor System | EMSL

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

    Atmospheric Pressure Reactor System Atmospheric Pressure Reactor System The atmospheric pressure reactor system is designed for testing the efficiency of various catalysts for the...

  5. Critical experiments at Sandia National Laboratories : technical meeting on low-power critical facilities and small reactors.

    SciTech Connect (OSTI)

    Harms, Gary A.; Ford, John T.; Barber, Allison Delo

    2010-11-01T23:59:59.000Z

    Sandia National Laboratories (SNL) has conducted radiation effects testing for the Department of Energy (DOE) and other contractors supporting the DOE since the 1960's. Over this period, the research reactor facilities at Sandia have had a primary mission to provide appropriate nuclear radiation environments for radiation testing and qualification of electronic components and other devices. The current generation of reactors includes the Annular Core Research Reactor (ACRR), a water-moderated pool-type reactor, fueled by elements constructed from UO2-BeO ceramic fuel pellets, and the Sandia Pulse Reactor III (SPR-III), a bare metal fast burst reactor utilizing a uranium-molybdenum alloy fuel. The SPR-III is currently defueled. The SPR Facility (SPRF) has hosted a series of critical experiments. A purpose-built critical experiment was first operated at the SPRF in the late 1980's. This experiment, called the Space Nuclear Thermal Propulsion Critical Experiment (CX), was designed to explore the reactor physics of a nuclear thermal rocket motor. This experiment was fueled with highly-enriched uranium carbide fuel in annular water-moderated fuel elements. The experiment program was completed and the fuel for the experiment was moved off-site. A second critical experiment, the Burnup Credit Critical Experiment (BUCCX) was operated at Sandia in 2002. The critical assembly for this experiment was based on the assembly used in the CX modified to accommodate low-enriched pin-type fuel in water moderator. This experiment was designed as a platform in which the reactivity effects of specific fission product poisons could be measured. Experiments were carried out on rhodium, an important fission product poison. The fuel and assembly hardware for the BUCCX remains at Sandia and is available for future experimentation. The critical experiment currently in operation at the SPRF is the Seven Percent Critical Experiment (7uPCX). This experiment is designed to provide benchmark reactor physics data to support validation of the reactor physics codes used to design commercial reactor fuel elements in an enrichment range above the current 5% enrichment cap. A first set of critical experiments in the 7uPCX has been completed. More experiments are planned in the 7uPCX series. The critical experiments at Sandia National Laboratories are currently funded by the US Department of Energy Nuclear Criticality Safety Program (NCSP). The NCSP has committed to maintain the critical experiment capability at Sandia and to support the development of a critical experiments training course at the facility. The training course is intended to provide hands-on experiment experience for the training of new and re-training of practicing Nuclear Criticality Safety Engineers. The current plans are for the development of the course to continue through the first part of fiscal year 2011 with the development culminating is the delivery of a prototype of the course in the latter part of the fiscal year. The course will be available in fiscal year 2012.

  6. Environmental assessment, aircraft chemical warfare survivability test program, Naval Air Warfare Center, Aircraft Division, Patuxent River, Maryland

    SciTech Connect (OSTI)

    NONE

    1992-02-01T23:59:59.000Z

    The proposed project, the Aircraft Chemical Warfare Survivability Test Program at Patuxent River Naval Air Station, involves the testing and development of aircraft systems and operating procedures for use in an environment contaminated with chemical/biological warfare agents. The tests will be performed in accordance with a directive from the chief of Naval Operations to obtain and maintain the capability to operate in a chemically-contaminated environment. These tests will be performed under outdoor, warm-weather conditions on a dredge disposal area and adjacent runways to simulate the conditions under which a real-life threat would be encountered.

  7. Endangered Species Program, Naval Petroleum Reserves in California. Annual report FY93

    SciTech Connect (OSTI)

    NONE

    1995-02-01T23:59:59.000Z

    The Naval Petroleum Reserves in California (NPRC) are operated by the US Department of Energy (DOE) and Chevron USA. Production Company (CPDN). Four federally-listed endangered animal species and one federally-threatened plant species are known to occur on NPRC: San Joaquin kit fox, blunt-nosed leopard lizard, giant kangaroo rat, Tipton kangaroo rat, and Hoover`s wooly-star. All five are protected under the Endangered Species Act of 1973, which declares that it is ``...the policy of Congress that all Federal departments and agencies shall seek to conserve endangered species and threatened species and shall utilize their authorities in furtherance of the purposes of the Act.`` DOE is also obliged to determine whether actions taken by their lessees on Naval Petroleum Reserve No. 2 will have any effects on endangered species or their habitats. The major objective of the EG&G Energy Measurements, Inc. Endangered Species Program on NPRC is to provide DOE with the scientific expertise necessary for compliance with the Endangered Species Act. The specific objective of this report is to summarize progress and results of the Endangered Species Program made during fiscal year 1993.

  8. Endangered species and cultural resources program, Naval Petroleum Reserves in California, annual report FY97

    SciTech Connect (OSTI)

    NONE

    1998-05-01T23:59:59.000Z

    The Naval Petroleum Reserves in California (NPRC) are oil fields administered by the DOE in the southern San Joaquin Valley of California. Four federally endangered animal species and one federally threatened plant species are known to occur on NPRC: San Joaquin kit fox (Vulpes macrotis mutica), blunt-nosed leopard lizard (Gambelia silus), giant kangaroo rat (Dipodomys ingens), Tipton kangaroo rat (Dipodomys nitratoides), and Hoover`s wooly-star (Eriastrum hooveri). All five are protected under the Endangered Species Act (ESA) of 1973. The DOE/NPRC is obliged to determine whether actions taken by their lessees on Naval Petroleum Reserve No. 2 (NPR-2) will have any effects on endangered species or their habitats. The primary objective of the Endangered Species and Cultural Resources Program is to provide NPRC with the scientific expertise necessary for compliance with the ESA, the National Environmental Policy Act (NEPA), and the National Historic Preservation Act (NHPA). The specific objective of this report is to summarize progress, results, and accomplishments of the program during fiscal year 1997 (FY97).

  9. JOB DESCRIPTION: E06, Senior Principal Naval Architect with a minimum of 10 + years experience in the design and construction of naval and/or commercial vessels, with a

    E-Print Network [OSTI]

    Eustice, Ryan

    + Years Naval Architecture experience International Experience Experience with Earned Value Management Demonstrated team management, task management and capture/proposal experience Desired Qualifications: 15 Program and/or Subcontract Management Experience To Apply On line, go to Raytheon.com under the careers

  10. Reactor Sharing Program

    SciTech Connect (OSTI)

    Vernetson, W.G.

    1993-01-01T23:59:59.000Z

    Progress achieved at the University of Florida Training Reactor (UFTR) facility through the US Department of Energy's University Reactor Sharing Program is reported for the period of 1991--1992.

  11. Undergraduate reactor control experiment

    SciTech Connect (OSTI)

    Edwards, R.M.; Power, M.A.; Bryan, M. (Pennsylvania State Univ., University Park (United States))

    1992-01-01T23:59:59.000Z

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise.

  12. Attrition reactor system

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN); Davison, Brian H. (Knoxvile, TN)

    1993-01-01T23:59:59.000Z

    A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur.

  13. Attrition reactor system

    DOE Patents [OSTI]

    Scott, C.D.; Davison, B.H.

    1993-09-28T23:59:59.000Z

    A reactor vessel for reacting a solid particulate with a liquid reactant has a centrifugal pump in circulatory flow communication with the reactor vessel for providing particulate attrition, resulting in additional fresh surface where the reaction can occur. 2 figures.

  14. Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility, a Prototypic Liquid Metal Fast Breeder Reactor

    SciTech Connect (OSTI)

    John D. Bess

    2010-03-01T23:59:59.000Z

    The Fast Flux Test Facility (FFTF) was a 400-MWt, sodium-cooled, low-pressure, high-temperature, fast-neutron flux, nuclear fission reactor plant designed for the irradiation testing of nuclear reactor fuels and materials for the development of liquid metal fast breeder reactors (LMFBRs). The FFTF was fueled with plutonium-uranium mixed oxide (MOX) and reflected by Inconel-600. Westinghouse Hanford Company operated the FFTF as part of the Hanford Engineering Development Laboratory (HEDL) for the U.S. Department of Energy on the Hanford Site near Richland, Washington. Although the FFTF was a testing facility not specifically designed to breed fuel or produce electricity, it did provide valuable information for LMFBR projects and base technology programs in the areas of plant system and component design, component fabrication, prototype testing, and site construction. The major objectives of the FFTF were to provide a strong, disciplined engineering base for the LMFBR program, provide fast flux testing for other U.S. programs, and contribute to the development of a viable self-sustaining competitive U.S. LMFBR industry. During its ten years of operation, the FFTF acted as a national research facility to test advanced nuclear fuels, materials, components, systems, nuclear power plant operating and maintenance procedures, and active and passive reactor safety technologies; it also produced a large number of isotopes for medical and industrial users, generated tritium for the U.S. fusion research program, and participated in cooperative, international research work. Prior to the implementation of the reactor characterization program, a series of isothermal physics measurements were performed; this acceptance testing program consisted of a series of control rod worths, critical rod positions, subcriticality measurements, maximum reactivity addition rates, shutdown margins, excess reactivity, and isothermal temperature coefficient reactivity. The results of these experiments were of particular importance because they provide extensive information which can be directly applied to the design of large LMFBR’s. It should be recognized that the data presented in the initial report were evaluated only to the extent necessary to ensure that adequate data were obtained. Later reports provided further interpretation and detailed comparisons with prediction techniques. The conclusion of the isothermal physics measurements was that the FFTF nuclear characteristics were essentially as designed and all safety requirements were satisfied. From a nuclear point of view, the FFTF was qualified to proceed into power operation mode. The FFTF was completed in 1978 and first achieved criticality on February 9, 1980. Upon completion of the isothermal physics and reactor characterization programs, the FFTF operated for ten years from April 1982 to April 1992. Reactor operations of the FFTF were terminated and the reactor facility was then defueled, deactivated, and placed into cold standby condition. Deactivation of the reactor was put on hold from 1996 to 2000 while the U.S. Department of Energy examined alternative uses for the FFTF but then announced the permanent deactivation of the FFTF in December 2001. Its core support basket was later drilled in May 2005, so as to remove all remaining sodium coolant. On April 17, 2006, the American Nuclear Society designated the FFTF as a “National Nuclear Historic Landmark”.

  15. Advanced Test Reactor Tour

    SciTech Connect (OSTI)

    Miley, Don

    2011-01-01T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  16. High solids fermentation reactor

    DOE Patents [OSTI]

    Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.

    1993-03-02T23:59:59.000Z

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  17. High solids fermentation reactor

    DOE Patents [OSTI]

    Wyman, Charles E. (Lakewood, CO); Grohmann, Karel (Littleton, CO); Himmel, Michael E. (Littleton, CO); Richard, Christopher J. (Lakewood, CO)

    1993-01-01T23:59:59.000Z

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  18. Improved vortex reactor system

    DOE Patents [OSTI]

    Diebold, James P. (Lakewood, CO); Scahill, John W. (Evergreen, CO)

    1995-01-01T23:59:59.000Z

    An improved vortex reactor system for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor.

  19. Advanced Test Reactor Tour

    ScienceCinema (OSTI)

    Miley, Don

    2013-05-28T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  20. The Immortal Fausto: The Life, Works, and Ships of the Venetian Humanist and Naval Architect Vettor Fausto (1490-1546)

    E-Print Network [OSTI]

    Campana, Lilia

    2014-06-11T23:59:59.000Z

    in the Mediterranean, the Republic of Venice strongly encouraged Venetian shipwrights to submit new designs for war galleys. The undisputed founder and champion of this naval program was not a skilled shipwright but a young professor of Greek in the School of Saint...

  1. EIS-0158-S2: Supplemental Environmental Impact Statement Naval Petroleum Reserve No. 1 (Elk Hills), Kern County, California

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement, the supplement to DOE/EIS-0158, to analyze the environmental and socioeconomic impacts of the sale of Naval Petroleum Reserve No. 1 in Kern County, California to Occidental Petroleum Corporation.

  2. Superfund record of decision (EPA Region 3): Naval Weapons Station, operable unit 2, Yorktown, VA, September 29, 1995

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    This decision document presents a determination that the No Further Remedial Action Decision with Institutional Controls is sufficient to protect human health and the environment for Operable Unit No. II (OU II), Site 16, the West Road Landfill and Site Screening Area (SSA) 16, the Building 402 Metal Disposal Area at the Naval Weapons Station (WPNSTA) Yorktown (Site 16/SSA 16).

  3. Neutron behavior, reactor control, and reactor heat transfer. Volume four

    SciTech Connect (OSTI)

    Not Available

    1986-01-01T23:59:59.000Z

    Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant).

  4. Reactor vessel support system

    DOE Patents [OSTI]

    Golden, Martin P. (Trafford, PA); Holley, John C. (McKeesport, PA)

    1982-01-01T23:59:59.000Z

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  5. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix D, Part B: Naval spent nuclear fuel management

    SciTech Connect (OSTI)

    Not Available

    1994-06-01T23:59:59.000Z

    This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement.

  6. Naval petroleum reserves: Preliminary analysis of future net revenues from Elk Hills production

    SciTech Connect (OSTI)

    Not Available

    1986-01-01T23:59:59.000Z

    This is an interim report on the present value of the net revenues from Elk Hills Naval Petroleum Reserve. GAO calculated alternative present values of the net revenues applying (1) low, medium, and high forecasts of future crude oil prices and (2) alternative interest rates for discounting the future net revenues to their present values. The calculations are sensitive to both the oil price forecasts and discount rates used; they are preliminary and should be used with caution. They do not take into account possible added tax revenues collected by the government if Elk Hills were sold nor varying production levels and practices, which could either increase or decrease the total amount of oil that can be extracted.

  7. Naval Petroleum Reserves: assessment of alternative operating strategies beyond 1982. Analysis and supporting data

    SciTech Connect (OSTI)

    Gsellman, L.R.; Mendis, M.S.; Rosenberg, J.I.

    1981-06-01T23:59:59.000Z

    Legislation authorizing production from two of the Naval Petroleum Reserves, i.e., NPR-1 (Elk Hills, California) and NPR-3 (Teapot Dome, Wyoming), expires in 1982. This paper presents analyses and supporting data concerning the trade-offs of extending production or returning to a shut-in status in order to provide the Department of Energy with information needed to formulate a recommendation. The primary objective of the study is to evaluate a range of possible futures (through 1990) to determine technical, economic, energy, strategic and political trade-offs between the two options. A secondary objective is to develop a data base for use by DOE to respond to questions and issues raised by interested parties during executive branch and Congressional reviews.

  8. Naval petroleum reserves: Oil sales procedures and prices at Elk Hills, April through December 1986

    SciTech Connect (OSTI)

    Not Available

    1987-01-01T23:59:59.000Z

    The Elk Hills Naval Petroleum Reserve is located near Bakersfield, California and ranks seventh among domestic producing oil fields. In Feb. 1986 the Department of Energy awarded contracts to 16 companies for the sale of about 82,000 barrels per day of NPR crude oil between April and September 1986. These companies bid a record high average discount of $4.49 from DOE's base price. The discounts ranged from $0.87 to $6.98 per barrel. These contracts resulted in DOE selling Elk Hills oil as low as $3.91 per barrel. Energy stated that the process for selling from NPR had gotten out of step with today's marketplace. Doe subsequently revised its sales procedures which requires bidders to submit a specific price for the oil rather than a discount to a base price. DOE also initiated other efforts designed to avoid future NPR oil sales at less than fair market value.

  9. Environmental Survey preliminary report, Naval Petroleum Reserves in California (NPRC), Tupman, California

    SciTech Connect (OSTI)

    Not Available

    1989-02-01T23:59:59.000Z

    This report presents the preliminary environmental findings from the first phase of the Environmental Survey of the US Department of Energy (DOE) Naval Petroleum Reserves 1 (NPR-1) and 2 (NPR-2) in California (NPRC), conducted May 9--20, 1988. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment Safety and Health's Office of Environmental Audit. Individual team specialists are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with NPRC. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involved the review of existing site environmental data, observations of the operations carried on at NPRC, and interviews with site personnel. 120 refs., 28 figs., 40 tabs.

  10. Reactor water cleanup system

    DOE Patents [OSTI]

    Gluntz, D.M.; Taft, W.E.

    1994-12-20T23:59:59.000Z

    A reactor water cleanup system includes a reactor pressure vessel containing a reactor core submerged in reactor water. First and second parallel cleanup trains are provided for extracting portions of the reactor water from the pressure vessel, cleaning the extracted water, and returning the cleaned water to the pressure vessel. Each of the cleanup trains includes a heat exchanger for cooling the reactor water, and a cleaner for cleaning the cooled reactor water. A return line is disposed between the cleaner and the pressure vessel for channeling the cleaned water thereto in a first mode of operation. A portion of the cooled water is bypassed around the cleaner during a second mode of operation and returned through the pressure vessel for shutdown cooling. 1 figure.

  11. Spinning fluids reactor

    SciTech Connect (OSTI)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20T23:59:59.000Z

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  12. Determining Reactor Neutrino Flux

    E-Print Network [OSTI]

    Jun Cao

    2012-03-08T23:59:59.000Z

    Flux is an important source of uncertainties for a reactor neutrino experiment. It is determined from thermal power measurements, reactor core simulation, and knowledge of neutrino spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle $\\theta_{13}$ by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding of the correlation of uncertainties is required for $\\theta_{13}$ experiments. Precise determination of reactor neutrino flux will also improve the sensitivity of the non-proliferation monitoring and future reactor experiments. We will discuss the flux calculation and recent progresses.

  13. Occurrence and distribution of special status plant species on the Naval Petroleum Reserves in California

    SciTech Connect (OSTI)

    Anderson, D.C.; Cypher, B.L.; Holmstead, G.L.; Hammer, K.L.; Frost, N.

    1994-10-01T23:59:59.000Z

    Several special status plant species occur or potentially occur at the Naval Petroleum Reserves in California (NPRC). Special status species are defined as those species that are either federally listed as endangered or threatened, or candidate taxa. Candidate species are classified as Category 1 or Category 2. Category 1 taxa are those species for which there is sufficient evidence to support listing, while Category 2 taxa are those species for which listing may possibly be appropriate, but for which sufficient data are lacking to warrant immediate listing. Determining the presence and distribution of these species on NPRC is necessary so that appropriate conservation or protection measures can be implemented. In the spring of 1988, a survey of Naval Petroleum Reserve No. 1 (NPR-1) was conducted to determine the occurrence of Hoover`s wooly-star (Eriastrum hooveri), Kern Mallow (Eremalche kemensis), San Joaquin wooly-threads (Lembertia congdonii), and California jewelflower (Caulanthus califonicus), all listed by the US Fish and Wildlife Service (FWS) as Category 2 species at that time. Of the four species, only Hoover`s wooly-star was found. It was concluded that Kern mallow and San Joaquin wooly-threads could potentially be found on NPR-1, but habitat for California jewelflower did not occur on NPR-1 and its occurrence was unlikely. As part of an ongoing effort to document the presence or absence of sensitive plant species on NPRC, surveys for species other than Hoover`s wooly-star were conducted in the spring of 1993. Abundant spring rains in 1993 created favorable growing conditions for annual forbs. Surveys in 1993 focused on potential habitat of several endangered and candidate species. The results of those surveys are presented in this report.

  14. Wildlife management plan, Naval Petroleum Reserve No. 1, Kern County, California

    SciTech Connect (OSTI)

    O'Farrell, T.P.; Scrivner, J.H.

    1987-01-01T23:59:59.000Z

    Under the Naval Petroleum Act of 1976, Congress directed the Secretary of the Navy and subsequently the Secretary of Energy, to produce petroleum products from Naval Petroleum Reserve No. 1 (NPR-1) in Kern County, California, at the maximum efficient rate consistent with sound engineering practices. Because of the presence of two endangered species and the quality, quantity, and contiguous nature of habitat on NPR-1, the area is unique and management of its resources deserves special attention. The purpose of this wildlife management plan is to: (1) draw together specific information on NPR-1 wildlife resources; (2) suggest management goals that could be implemented, which if achieved, would result in diverse, healthy wildlife populations; and (3) reinitiate cooperative agreements between the US Department of Energy (DOE) and other conservation organizations regarding the management of wildlife on NPR-1. NPR-1 supports an abundant and diverse vertebrate fauna. Twenty-five mammalian, 92 avian, eight reptilian, and two amphibian species have been observed on Elk Hills. Of these, three are endangered (San Joaquin kit fox, Vulpes macrotis mutica; giant kangaroo rat, Dipodomys ingens; blunt-nosed leopard lizard, Gambelia silus). Nine vertebrates, six invertebrates, and four plant species known to occur or suspected of occurring on Elk Hills are potential candidates for listing. A major objective of this management plan is to minimize the impact of petroleum development activities on the San Joaquin kit fox, giant kangaroo rat, blunt-nosed leopard lizard, and their essential habitats. This will mainly be achieved by monitoring the status of these species and their habitat and by restoring disturbed habitats. In general, management policies designed to benefit the above three species and other species of concern will also benefit other wildlife inhabiting NPR-1.

  15. Improved vortex reactor system

    DOE Patents [OSTI]

    Diebold, J.P.; Scahill, J.W.

    1995-05-09T23:59:59.000Z

    An improved vortex reactor system is described for affecting fast pyrolysis of biomass and Refuse Derived Fuel (RDF) feed materials comprising: a vortex reactor having its axis vertically disposed in relation to a jet of a horizontally disposed steam ejector that impels feed materials from a feeder and solids from a recycle loop along with a motive gas into a top part of said reactor. 12 figs.

  16. EA-1956: Site-Wide Environmental Assessment for the Divestiture of Rocky Mountain Oilfield Testing Center and Naval Petroleum Reserve No. 3, Natrona County, Wyoming

    Broader source: Energy.gov [DOE]

    DOE prepared an EA that assesses the potential environmental impacts of the proposed discontinuation of DOE operations at the Rocky Mountain Oilfield Testing Center (RMOTC) and the proposed divestiture of Naval Petroleum Reserve Number 3 (NPR-3)

  17. This document was downloaded on May 22, 2013 at 14:24:38 Author(s) Naval Postgraduate School (U.S.)

    E-Print Network [OSTI]

    state-of- the-art laboratories, numerous academic buildings, a library, government housing and impressive recreational facilities. The Students Nearly 2,000 students attend the Naval Postgraduate School Engineering, Applied Mathematics, Astronautical Engineering, Computer Science, Electrical Engineering

  18. Disruptive innovation and naval power : strategic and financial implications of unmanned underwater vehicles (UUVs) and long-term underwater power sources

    E-Print Network [OSTI]

    Larson, Richard Winston

    2014-01-01T23:59:59.000Z

    The naval warfare environment is rapidly changing. The U.S. Navy is adapting by continuing its blue-water dominance while simultaneously building brown-water capabilities. Unmanned systems, such as unmanned airborne drones, ...

  19. Tokamak reactor first wall

    DOE Patents [OSTI]

    Creedon, R.L.; Levine, H.E.; Wong, C.; Battaglia, J.

    1984-11-20T23:59:59.000Z

    This invention relates to an improved first wall construction for a tokamak fusion reactor vessel, or other vessels subjected to similar pressure and thermal stresses.

  20. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, Juhani (Karhula, FI)

    1996-01-01T23:59:59.000Z

    A pressurized fluid bed reactor power plant includes a fluidized bed reactor contained within a pressure vessel with a pressurized gas volume between the reactor and the vessel. A first conduit supplies primary gas from the gas volume to the reactor, passing outside the pressure vessel and then returning through the pressure vessel to the reactor, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the reactor, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the reactor at a substantially continuously controlled rate as the primary gas to the reactor. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the reactor is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine.

  1. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, J.

    1996-03-19T23:59:59.000Z

    A pressurized fluid bed reactor power plant includes a fluidized bed reactor contained within a pressure vessel with a pressurized gas volume between the reactor and the vessel. A first conduit supplies primary gas from the gas volume to the reactor, passing outside the pressure vessel and then returning through the pressure vessel to the reactor, and pressurized gas is supplied from a compressor through a second conduit to the gas volume. A third conduit, comprising a hot gas discharge, carries gases from the reactor, through a filter, and ultimately to a turbine. During normal operation of the plant, pressurized gas is withdrawn from the gas volume through the first conduit and introduced into the reactor at a substantially continuously controlled rate as the primary gas to the reactor. In response to an operational disturbance of the plant, the flow of gas in the first, second, and third conduits is terminated, and thereafter the pressure in the gas volume and in the reactor is substantially simultaneously reduced by opening pressure relief valves in the first and third conduits, and optionally by passing air directly from the second conduit to the turbine. 1 fig.

  2. Using Net-Zero Energy Projects to Enable Sustainable Economic Redevelopment at the Former Brunswick Air Naval Base

    SciTech Connect (OSTI)

    Huffman, S.

    2011-10-01T23:59:59.000Z

    A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites. The Brunswick Naval Air Station is a naval air facility and Environmental Protection Agency (EPA) Super Fund site that is being cleaned up, and closed down. The objective of this report is not only to look at the economics of individual renewable energy technologies, but also to look at the systemic benefits that can be gained when cost-effective renewable energy technologies are integrated with other systems and businesses in a community; thus multiplying the total monetary, employment, and quality-of-life benefits they can provide to a community.

  3. Improvement of operational safety of dual-purpose transport packaging set for naval SNF in storage

    SciTech Connect (OSTI)

    Guskov, Vladimir; Korotkov, Gennady [JSC 'KBSM' (Russian Federation); Barnes, Ella [US Environmental Protection Agency - EPA (United States); Snipes, Randy [Oak Ridge National Laboratory - ORNL, 1 Bethel Valley Rd, Oak Ridge, TN 37830 (United States)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: In recent ten years a new technology of management of irradiated nuclear fuel (SNF) at the final stage of fuel cycle has been intensely developing on a basis of a new type of casks used for interim storage of SNF and subsequent transportation therein to the place of processing, further storage or final disposal. This technology stems from the concept of a protective cask which provides preservation of its content (SNF) and fulfillment of all other safety requirements for storage and transportation of SNF. Radiation protection against emissions and non-distribution of activity outside the cask is ensured by physical barriers, i.e. all-metal or composite body, shells, inner cavities for irradiated fuel assemblies (SFA), lids with sealing systems. Residual heat release of SFA is discharged to the environment by natural way: through emission and convection of surrounding air. By now more than 100 dual purpose packaging sets TUK-108/1 are in operation in the mode of interim storage and transportation of SNF from decommissioned nuclear powered submarines (NPS). In accordance with certificate, spent fuel is stored in TUK-108/1 on the premises of plants involved in NPS dismantlement for 2 years, whereupon it is transported for processing to PO Mayak. At one Far Eastern plant Zvezda involved in NPS dismantlement there arose a complicated situation due to necessity to extend period of storage of SNF in TUK- 108/1. To ensure safety over a longer period of storage of SNF in TUK-108/1 it is essential to modify conditions of storage by removing of residual water and filling the inner cavity of the cask with an inert gas. Within implementation of the international 1.1- 2 project Development of drying technology for the cask TUK-108/1 intended for naval SNF under the Program, there has been developed the technology of preparation of the cask for long-term storage of SNF in TUK-108/1, the design of a mobile TUK-108/1 drying facility; a pilot facility has been manufactured. This report describes key issues of cask drying technology, justification of terms of dry storage of naval SNF in no-108/1, design features of the mobile drying facility, results of tests of the pilot facility at the Far Eastern plant Zvezda. (authors)

  4. Environmental Survey preliminary report, Naval Petroleum and Oil Shale Reserves in Colorado, Utah, and Wyoming, Casper, Wyoming

    SciTech Connect (OSTI)

    Not Available

    1989-02-01T23:59:59.000Z

    This report presents the preliminary environmental findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Naval Petroleum and Oil Shale Reserves in Colorado, Utah, and Wyoming (NPOSR-CUW) conducted June 6 through 17, 1988. NPOSR consists of the Naval Petroleum Reserve No. 3 (NPR-3) in Wyoming, the Naval Oil Shale Reserves No. 1 and 3 (NOSR-1 and NOSR-3) in Colorado and the Naval Oil Shale Reserve No. 2 (NOSR-2) in Utah. NOSR-2 was not included in the Survey because it had not been actively exploited at the time of the on-site Survey. The Survey is being conducted by an interdisciplinary team of environmental specialists, lead and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team specialists are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with NPOSR. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at NPOSR and interviews with site personnel. The Survey team has developed a Sampling and Analysis Plan to assist in further assessing specific environmental problems identified at NOSR-3 during the on-site Survey. There were no findings associated with either NPR-3 or NOSR-1 that required Survey-related sampling and Analysis. The Sampling and Analysis Plan will be executed by Idaho National Engineering Laboratory. When completed, the results will be incorporated into the Environmental Survey Summary report. The Summary Report will reflect the final determinations of the NPOSR-CUW Survey and the other DOE site-specific Surveys. 110 refs., 38 figs., 24 tabs.

  5. Report to the President on agreements and programs relating to the Naval Petroleum and Oil Shale Reserves

    SciTech Connect (OSTI)

    Not Available

    1994-08-01T23:59:59.000Z

    The Department of Energy monitors commercial natural gas production activities along the boundaries of Naval Oil Shale Reserve No. 1 and Naval Oil Shale Reserve No. 3, which are located in Garfield County, Colorado, and were created in the early part of this century to provide a future source of shale oil for the military. In response to the private sector`s drilling of natural gas wells along the south and southwest boundaries of the Reserves, which began in the early 1980`s, the Department developed a Natural Gas Protection Program to protect the Government`s resources from drainage due to the increasing number of commercial gas wells contiguous to Naval Oil Shale Reserve No. 3. This report provides an update of the Gas Protection Program being implemented and the agreements that have been placed in effect since December 19, 1991, and also includes the one communitized well containing Naval Petroleum Reserve No. 3 lands. The Protection Program employs two methods to protect the Government`s resources: (1) sharing with the private sector in the costs and production of wells by entering into ``communitization`` agreements; and (2) drilling wholly-owned Government wells to ``offset`` commercial wells that threaten to drain natural gas from the Reserves. The methods designed to protect the Government`s resources are achieving their objective of abating gas drainage and migration. As a result of the Protection Program, the Department of Energy is able to produce natural gas and either sell its share on the open market or transfer it for use at Government facilities. The Natural Gas Protection Program is a reactive, ongoing program that is continually revised as natural gas transportation constraints, market conditions, and nearby commercial production activities change.

  6. Brookhaven Graphite Research Reactor Workshop

    Broader source: Energy.gov [DOE]

    The Brookhaven Graphite Research Reactor (BGRR) was the first reactor built in the U.S. for peacetime atomic research following World War II.  Construction began in 1947 and the reactor started...

  7. United States-Russian laboratory-to-laboratory cooperation on protection, control, and accounting for naval nuclear materials

    SciTech Connect (OSTI)

    Sukhoruchkin, V. [Kurchatov Inst., Moscow (Russian Federation); Yurasov, N.; Goncharenko, Y. [Russian Navy, Moscow (Russian Federation); Mullen, M. [Los Alamos National Lab., NM (United States); McConnell, D. [Sandia National Labs., Albuquerque, NM (United States)

    1996-12-31T23:59:59.000Z

    In March 1995, the Russian Navy contacted safeguards experts at the Kurchatov Institute (KI) and proposed the initiation of work to enhance nuclear materials protection, control, and accounting (MPC and A) at Russian Navy facilities. Because of KI`s successful experience in laboratory-to-laboratory MPC and A cooperation with US Department of Energy Laboratories, the possibility of US participation in the work with the Russian Navy was explored. Several months later, approval was received from the US Government and the Russian Navy to proceed with this work on a laboratory-to-laboratory basis through Kurchatov Institute. As a first step in the cooperation, a planning meeting occurred at KI in September, 1995. Representatives from the US Department of Energy (DOE), the US Department of Defense (DOD), the Russian Navy, and KI discussed several areas for near-term cooperative work, including a vulnerability assessment workshop and a planning study to identify and prioritize near-term MPC and A enhancements that might be implemented at Russian facilities which store or handle unirradiated highly enriched uranium fuel for naval propulsion applications. In subsequent meetings, these early proposals have been further refined and extended. This MPC and A cooperation will now include enhanced protection and control features for storage facilities and refueling service ships, computerized accounting systems for naval fuel, methods and equipment for rapid inventories, improved security of fresh fuel during truck transportation, and training. This paper describes the current status and future plans for MPC and A cooperation for naval nuclear materials.

  8. Naval Petroleum Reserve Number 1 financial statements September 30, 1997 and 1996 (with independent auditors` report thereon)

    SciTech Connect (OSTI)

    NONE

    1997-12-31T23:59:59.000Z

    The Naval Petroleum and Oil Shale Reserves (NPOSR) produces crude oil and associated hydrocarbons from the Naval Petroleum Reserve No. 1 (NPR-1) in a manner to achieve the greatest value and benefits to the US taxpayer. As required by the 1996 National Defense Authorization Act, the Department of Energy offered NPR-1 for sale during FY 1997. DOE structured the sale so as to offer two types of ownership segments: one operatorship segment, consisting of 74% of the US interest in NPR-1, and 13 nonoperating segments, each consisting of 2% of the US interest. Potential purchasers could bid on one, some, or all of the segments. If a single purchaser wanted to buy all of the Government`s interest, then its bid would have to exceed the total of the highest bids for all of the individual segments. Bids were due October 1, 1997, at which time DOE received 22 bids from 15 parties acting alone or in concert. The report and management letter present the results of the independent certified public accountants` audits of the Department of Energy`s Naval Petroleum Reserve Number 1 (NPR-1) financial statements as of, and for the years ended, September 30, 1997 and 1996.

  9. Final sitewide environmental assessment for continued development of Naval Petroleum Reserve No. 3 (NPR-3), Natrona County, Wyoming

    SciTech Connect (OSTI)

    NONE

    1995-07-01T23:59:59.000Z

    The Secretary of Energy is required by law to explore, prospect, conserve, develop, use, and operate the Naval Petroleum and Oil Shale Reserves. The Naval Petroleum Reserves Production Act of 1976 (Public Law 94-258), requires that the Naval Petroleum Reserves be produced at their maximum efficient rate (MER), consistent with sound engineering practices, for a period of six years. To fulfill this mission, DOE is proposing continued development activities which would include the drilling of approximately 250 oil production and injection (gas, water, and steam) wells, the construction of between 25 and 30 miles of associated gas, water, and steam pipelines, the installation of several production and support facilities, and the construction of between 15 and 20 miles of access roads. These drilling and construction estimates include any necessary activities related to the operation of the Rocky Mountain Oilfield Testing Center (RMOTC). The purpose of RMOTC will be to provide facilities and necessary support to government and private industry for testing and evaluating new oilfield and environmental technologies, and to transfer these results to the petroleum industry through seminars and publications. Continued development activities either have no potential to result in adverse environmental impacts or would only result in adverse impacts that could be readily mitigated. The small amounts of disturbed surface area will be reclaimed to its original natural state when production operations terminate. The preparation of an environmental impact statement is not required, and the DOE is issuing this Finding of No Significant Impact (FONSI). 73 refs.

  10. REACTOR OPERATIONS AND CONTROL

    E-Print Network [OSTI]

    Pázsit, Imre

    REACTOR OPERATIONS AND CONTROL KEYWORDS: core calculations, neural networks, control rod elevation of a control rod, or a group of control rods, is an important parameter from the viewpoint of reactor control DETERMINATION OF PWR CONTROL ROD POSITION BY CORE PHYSICS AND NEURAL NETWORK METHODS NINOS S. GARIS* and IMRE

  11. Reed Reactor Facility. Final report

    SciTech Connect (OSTI)

    Frantz, S.G.

    1994-12-31T23:59:59.000Z

    This report discusses the operation and maintenance of the Reed Reactor Facility. The Reed reactor is mostly used for education and train purposes.

  12. Reactor & Nuclear Systems Publications | ORNL

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

    Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications The...

  13. Naval Petroleum Reserves in California site environmental report for calendar year 1989

    SciTech Connect (OSTI)

    Not Available

    1989-01-01T23:59:59.000Z

    This summary for Naval Petroleum Reserves in California (NPRC) is divided into NPR-1 and NPR-2. Monitoring efforts at NPR-1 include handling and disposal of oilfield wastes; environmental preactivity surveys for the protection of endangered species and archaeological resources; inspections of topsoil stockpiling; monitoring of revegetated sites; surveillance of production facilities for hydrocarbons and oxides of nitrogen (NO{sub x}) emissions; monitoring of oil spill prevention and cleanup; and monitoring of wastewater injection. No major compliance issues existed for NPR-1 during 1989. Oil spills are recorded, reviewed for corrective action, and reported. Environmental preactivity surveys for proposed projects which may disturb or contaminate the land are conducted to prevent damage to the federally protected San Joaquin kit fox, blunt-nosed leopard lizard, Tipton kangaroo rat and the giant kangaroo rat. Projects are adjusted or relocated as necessary to avoid impact to dens, burrows, or flat-bottomed drainages. A major revegetation program was accomplished in 1989 for erosion control enhancement of endangered species habitat. The main compliance issue on NPR-2 was oil and produced water discharges into drainages by lessees. An additional compliance issue on NPR-2 is surface refuse from past oilfield operations. 17 refs.

  14. Endangered species and cultural resources program Naval petroleum Reserves in California. Annual report FY96

    SciTech Connect (OSTI)

    NONE

    1997-07-01T23:59:59.000Z

    In FY96, Enterprise Advisory Services, Inc. (EASI) continued to support efforts to protect endangered species and cultural resources at the Naval Petroleum Reserves in California (NPRC). These efforts are conducted to ensure NPRC compliance with regulations regarding the protection of listed species and cultural resources on federal properties. Population monitoring activities were conducted for San Joaquin kit foxes, giant kangaroo rats, blunt-nosed leopard lizards, and Hoover`s wooly-star. Kit fox abundance and distribution was assessed by live-trapping over a 329-km{sup 2} area. Kit fox reproduction and mortality were assessed by radiocollaring and monitoring 22 adults and two pups. Reproductive success and litter size were determined through live-trapping and den observations. Rates and sources of kit fox mortality were assessed by recovering dead radiocollared kit foxes and conducting necropsies to determine cause of death. Abundance of coyotes and bobcats, which compete with kit foxes, was determined by conducting scent station surveys. Kit fox diet was assessed through analysis of fecal samples collected from live-trapped foxes. Abundance of potential prey for kit foxes was determined by conducting transect surveys for lagornorphs and live-trapping small mammals.

  15. Distributed Energy Resources at Naval Base Ventura County Building1512: A Sensitivity Analysis

    SciTech Connect (OSTI)

    Bailey, Owen C.; Marnay, Chris

    2005-06-05T23:59:59.000Z

    This report is the second of a two-part study by BerkeleyLab of a DER (distributed energy resources) system at Navy Base VenturaCounty (NBVC). First, a preliminary assessment ofthe cost effectivenessof distributed energy resources at Naval Base Ventura County (NBVC)Building 1512 was conducted in response to the base s request for designassistance to the Federal Energy Management Program (Bailey and Marnay,2004). That report contains a detailed description of the site and theDER-CAM (Consumer Adoption Model) parameters used. This second reportcontains sensitivity analyses of key parameters in the DER system modelof Building 1512 at NBVC and additionally considers the potential forabsorption-powered refrigeration.The prior analysis found that under thecurrent tariffs, and given assumptions about the performance andstructure of building energy loads and available generating technologycharacteristics, installing a 600 kW DER system with absorption coolingand recovery heat capabilities could deliver cost savings of about 14percent, worth $55,000 per year. However, under current conditions, thisstudy also suggested that significant savings could be obtained ifBuilding 1512 changed from its current direct access contract to a SCETOU-8 (Southern California Edison time of use tariff number 8) ratewithout installing a DER system. Evaluated on this tariff, the potentialsavings from installation of a DER system would be about 4 percent of thetotal bill, or $16,000 per year.

  16. Material unaccounted for at the Southwest Experimental Fast Oxide Reactor: The SEFOR MUF

    SciTech Connect (OSTI)

    Higinbotham, W.A.

    1994-11-07T23:59:59.000Z

    The U.S. Atomic Energy Commission contracted with the General Electric Company to design, construct, and operate the Southwest Experimental Fast Oxide Reactor (SEFOR) to measure the Doppler effect for fast neutron breeder reactors. It contracted with Nuclear Fuel Services to fabricate the fuel rods for the reactor. When the reactor went critical in May, 1969, it appeared that some of the mixed uranium-plutonium oxide (MOX) fuel rods did not contain the specified quantity of plutonium. The SEFOR operators soon found several fuel rods which appeared to be low in plutonium. The safeguards group at Brookhaven was asked to look into the problem and, if possible, determine how much plutonium was missing from the unirradiated rods and from the larger number which had been slightly irradiated in the reactor. It was decided that the plutonium content of the unirradiated and irradiated rods could be measured relative to a reference rod using a high resolution gamma-ray detector and also by neutron measurements using an auto-correlation circuit recently developed at the Naval Research Laboratory (NRL). During the next two years, Brookhaven personnel and C.V. Strain of NRL made several trips to the SEFOR reactor. About 250 of the 775 rods were measured by two or more methods, using a sodium-iodide detector, a high-resolution germanium detector, a neutron detector, or the reactor (to measure reactivity). The research team concluded that 4.6 {+-} 0.46 kg of plutonium was missing out of the 433 kg that the rods should have contained. This report describes the SEFOR experiment and the procedures used to determine the material unaccounted for, or MUF.

  17. Nuclear reactor control column

    SciTech Connect (OSTI)

    Bachovchin, D.M.

    1982-08-10T23:59:59.000Z

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

  18. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1981, for the Division of Reactor Safety Research within the U.S. Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipeto- pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities. These programs include loss-ofcoolant accident (LOCA) simulation tests at the NRU reactor, Chalk River, Canada; fuel rod deformation, severe fuel damage, and postaccident coolability tests for the ESSOR reactor Super Sara Test Program, Ispra, Italy; the instrumented fuel assembly irradiation program at Halden, Norway; and experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory (INEL). These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  19. Nuclear reactor control column

    DOE Patents [OSTI]

    Bachovchin, Dennis M. (Plum Borough, PA)

    1982-01-01T23:59:59.000Z

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

  20. Fast Breeder Reactor studies

    SciTech Connect (OSTI)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01T23:59:59.000Z

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

  1. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Martin Peng, Y.K.M.

    1985-10-03T23:59:59.000Z

    The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

  2. Nuclear reactor reflector

    DOE Patents [OSTI]

    Hopkins, Ronald J. (Pensacola, FL); Land, John T. (Pensacola, FL); Misvel, Michael C. (Pensacola, FL)

    1994-01-01T23:59:59.000Z

    A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled.

  3. Nuclear reactor reflector

    DOE Patents [OSTI]

    Hopkins, R.J.; Land, J.T.; Misvel, M.C.

    1994-06-07T23:59:59.000Z

    A nuclear reactor reflector is disclosed that comprises a stack of reflector blocks with vertical water flow passages to cool the reflector. The interface between blocks is opposite support points for reactor fuel rods. Water flows between the reflector and the reactor barrel from passages in a bottom block. The top block contains a flange to limit this flow and the flange has a slot to receive an alignment pin that is welded to the barrel. The pin is held in the slot by two removable shims. Alignment bars extend the length of the stack in slots machined in each block when the stack is assembled. 12 figs.

  4. Microfluidic electrochemical reactors

    DOE Patents [OSTI]

    Nuzzo, Ralph G. (Champaign, IL); Mitrovski, Svetlana M. (Urbana, IL)

    2011-03-22T23:59:59.000Z

    A microfluidic electrochemical reactor includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical reactor can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical reactors can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.

  5. Endangered species program Naval Petroleum Reserves in California. Annual report FY94

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    In FY94, EG and G Energy Measurements, Inc. (EG and G/EM) continued to support efforts to conserve endangered species and cultural resources at the Naval Petroleum Reserves in California (NPRC). These efforts are conducted to ensure NPRC compliance with regulations regarding the protection of listed species and cultural resources on Federal properties. Population monitoring activities are conducted annually for San Joaquin kit foxes, giant kangaroo rats, blunt-nosed leopard lizards, and Hoover`s wooly star. To mitigate impacts of oil field activities on listed species, 400 preactivity surveys covering approximately 315 acres were conducted in FY94. Mitigation measures implemented as a result of survey findings resulted in avoidance of incidental takes of listed species during construction activities. EG and G/EM also assisted with mitigating effects from third-party projects, primarily by conducting biological and cultural resource consultations with regulatory agencies. Third-party projects in FY94 included three pipeline projects and two well abandonment/clean-up projects. Cultural resource support provided to NPRC consisted primarily of conducting preliminary surveys for cultural resources, and preparing a Cultural Resource Management Plan and Programmatic Agreement for NPR-1. These two documents will be finalized in FY95. EG and G/EM has conducted an applied habitat reclamation program at NPRC since 1985. In FY94, an evaluation of revegetation rates on reclaimed and non-reclaimed disturbed lands was initiated to assess reclamation efficacy. Results will be used to direct future habitat reclamation efforts at NPRC. In addition to this effort, 347 reclaimed sites were assessed to evaluate reclamation success.

  6. Conservation plan for protected species on Naval Petroleum Reserve No. 1, Kern County, California

    SciTech Connect (OSTI)

    Otten, M.R.M.; Cypher, B.L.

    1997-07-01T23:59:59.000Z

    Habitats in and around Naval Petroleum Reserve No. 1 (NPR-1) support populations of various vertebrates and plants, including a number of threatened and endangered species. Adequate conservation of habitats and species, particularly protected species, can be facilitated through development and implementation of management plans. This document provides a comprehensive plan for the conservation of protected species on NPR-1, through compliance with terms and conditions expressed in Biological Opinions rendered by the U.S. Fish and Wildlife Service for NPR-1 activities. Six conservation strategies by which threatened and endangered species have been, and will be, protected are described: population monitoring, mitigation strategies, special studies, operating guidelines and policies, information transfer and outreach, and the endangered species conservation area. Population monitoring programs are essential for determining population densities and for assessing the effects of oil field developments and environmental factors on protected species. Mitigation strategies (preactivity surveys and habitat reclamation) are employed to minimize the loss of important habitats components and to restore previously disturbed lands to conditions more suitable for species` use. A number of special studies were undertaken between 1985 and 1995 to investigate the effectiveness of a variety of population and habitat management techniques with the goal of increasing the density of protected species. Operating guidelines and policies governing routine oil field activities continue to be implemented to minimize the potential for the incidental take of protected species and minimize damage to wildlife habitats. Information transfer and outreach activities are important means by which technical and nontechnical information concerning protected species conservation on NPR-1 is shared with both the scientific and non-scientific public.

  7. Endangered species and cultural resources program, Naval Petroleum Reserves in California: Annual report FY95

    SciTech Connect (OSTI)

    NONE

    1996-04-01T23:59:59.000Z

    In FY95, EG and G Energy Measurements, Inc. (EG and G/EM) continued to support efforts to protect endangered species and cultural resources at the Naval Petroleum Reserves in California (NPRC). These efforts are conducted to ensure NPRC compliance with regulations regarding the protection of listed species and cultural resources on Federal properties. Population monitoring activities are conducted annually for San Joaquin kit foxes, giant kangaroo rats, blunt-nosed leopard lizards, and Hoover`s wooly-star. To mitigate impacts of oil field activities on listed species, 674 preactivity surveys covering approximately 211 hectares (521 acres) were conducted in FY95. EG and G/EM also assisted with mitigating effects from third-party projects, primarily by conducting biological and cultural resource consultations with regulatory agencies. EG and G/EM has conducted an applied habitat reclamation program at NPRC since 1985. In FY95, an evaluation of revegetation rates on reclaimed and non-reclaimed disturbed lands was completed, and the results will be used to direct future habitat reclamation efforts at NPRC. In FY95, reclamation success was monitored on 50 sites reclaimed in 1985. An investigation of factors influencing the distribution and abundance of kit foxes at NPRC was initiated in FY94. Factors being examined include habitat disturbance, topography, grazing, coyote abundance, lagomorph abundance, and shrub density. This investigation continued in FY95 and a manuscript on this topic will be completed in FY96. Also, Eg and G/EM completed collection of field data to evaluate the effects of a well blow-out on plant and animal populations. A final report will be prepared in FY96. Finally, EG and G/EM completed a life table analysis on San Joaquin kit foxes at NPRC.

  8. Hypothetical Reactor Accident Study

    E-Print Network [OSTI]

    POPULATIONS; IODINE 131; MELTDOWN; METEOROLOGY; NUCLEAR POWER PLANTS; P CODES; PWR TYPE REACTORS; RADIATION in a Typical BWR and in a typical PWR. Comparison with WASH-1400 by C F . Højerup 202 APPENDIX 3. Calculation

  9. P Reactor Grouting

    SciTech Connect (OSTI)

    None

    2010-01-01T23:59:59.000Z

    Filling the P Reactor with grout. This seals the radioactive material and reduces the environmental footprint left from the Cold War. Project sponsored by the Recovery Act at the Savannah River Site.

  10. Nuclear reactor control

    SciTech Connect (OSTI)

    Ingham, R.V.

    1980-01-01T23:59:59.000Z

    A liquid metal cooled fast breeder nuclear reactor has power setback means for use in an emergency. On initiation of a trip-signal a control rod is injected into the core in two stages, firstly, by free fall to effect an immediate power-set back to a safe level and, secondly, by controlled insertion. Total shut-down of the reactor under all emergencies is avoided. 4 claims.

  11. Polymerization reactor control

    SciTech Connect (OSTI)

    Ray, W.H.

    1985-01-01T23:59:59.000Z

    The principal difficulties in achieving good control of polymerization reactors are related to inadequate on-line measurement, a lack of understanding of the dynamics of the process, the highly sensitive and nonlinear behavior of these reactors, and the lack of well-developed techniques for the control of nonlinear processes. Some illustrations of these problems and a discussion of potential techniques for overcoming some of these difficulties is provided.

  12. Molten metal reactors

    DOE Patents [OSTI]

    Bingham, Dennis N; Klingler, Kerry M; Turner, Terry D; Wilding, Bruce M

    2013-11-05T23:59:59.000Z

    A molten metal reactor for converting a carbon material and steam into a gas comprising hydrogen, carbon monoxide, and carbon dioxide is disclosed. The reactor includes an interior crucible having a portion contained within an exterior crucible. The interior crucible includes an inlet and an outlet; the outlet leads to the exterior crucible and may comprise a diffuser. The exterior crucible may contain a molten alkaline metal compound. Contained between the exterior crucible and the interior crucible is at least one baffle.

  13. Reactor- Nuclear Science Center 

    E-Print Network [OSTI]

    Unknown

    2011-08-17T23:59:59.000Z

    A COMPARISON OF NUCLEAR REACTOR CONTROL ROOM DISPLAY PANELS A Thesis by FRANCES RENAE BOWERS Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 1988... Major Subject: Industrial Engineering A COMPARISON OF NUCLEAR REACTOR CONTROL ROOM DISPLAY PANELS A Thesis by FRANCES RENAE BOWERS Approved as to style and content by: Rod er . oppa (Cha' of 'ttee) R. Quinn Brackett (Member) rome . Co gleton...

  14. Power Burst Facility (PBF) Reactor Reactor Decommissioning

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah Project Office PressPostdoctoraldecadal7Powder DropperReactor

  15. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Dotson, CW

    1980-08-01T23:59:59.000Z

    This document summarizes the work performed by Pacific Northwest laboratory from October 1 through December 31, 1979, for the Division of Reactor Safety Research within the Nuclear Regulatory Commission. Evaluation of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibilty of determining structural graphite strength, evaluating the feasibilty of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the remaining integrity of pressurized water reactor steam generator tubes where service-induced degradation has been indicated. Test assemblies and analytical support are being provided for experimental programs at other facilities. These programs include the loss-of-coolant accident simulation tests at the NRU reactor, Chalk River, Canada; the fuel rod deformation and post-accident coolability tests for the ESSOR Test Reactor Program, lspra, Italy; the blowdown and reflood tests in the test facility at Cadarache, France; the instrumented fuel assembly irradiation program at Halden, Norway; and the experimental programs at the Power Burst Facility, Idaho National Engineering Laboratory. These programs will provide data for computer modeling of reactor system and fuel performance during various abnormal operating conditions.

  16. F Reactor Inspection

    SciTech Connect (OSTI)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-10-29T23:59:59.000Z

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  17. F Reactor Inspection

    ScienceCinema (OSTI)

    Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

    2014-11-24T23:59:59.000Z

    Workers from Mission Support Alliance, LLC., removed the welds around the steel door of the F Reactor before stepping inside the reactor to complete its periodic inspection. This is the first time the Department of Energy (DOE) has had the reactor open since 2008. The F Reactor is one of nine reactors along the Columbia River at the Department's Hanford Site in southeastern Washington State, where environmental cleanup has been ongoing since 1989. As part of the Tri-Party Agreement, the Department completes surveillance and maintenance activities of cocooned reactors periodically to evaluate the structural integrity of the safe storage enclosure and to ensure confinement of any remaining hazardous materials. "This entry marks a transition of sorts because the Hanford Long-Term Stewardship Program, for the first time, was responsible for conducting the entry and surveillance and maintenance activities," said Keith Grindstaff, Energy Department Long-Term Stewardship Program Manager. "As the River Corridor cleanup work is completed and transitioned to long-term stewardship, our program will manage any on-going requirements."

  18. Technical Feasibility Study for Deployment of Ground-Source Heat Pump Systems: Portsmouth Naval Shipyard -- Kittery, Maine

    SciTech Connect (OSTI)

    Hillesheim, M.; Mosey, G.

    2014-11-01T23:59:59.000Z

    The U.S. Environmental Protection Agency (EPA) Office of Solid Waste and Emergency Response, in accordance with the RE-Powering America's Lands initiative, engaged the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to conduct feasibility studies to assess the viability of developing renewable energy generating facilities on contaminated sites. Portsmouth Naval Shipyard (PNSY) is a United States Navy facility located on a series of conjoined islands in the Piscataqua River between Kittery, ME and Portsmouth, NH. EPA engaged NREL to conduct a study to determine technical feasibility of deploying ground-source heat pump systems to help PNSY achieve energy reduction goals.

  19. Zero Power Reactor simulation | Argonne National Laboratory

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

    Zero Power Reactor simulation Share Description Ever wanted to see a nuclear reactor core in action? Here's a detailed simulation of the Zero Power Reactor experiment, run by...

  20. Naval Research Laboratory`s programs in advanced indium phosphide solar cell development

    SciTech Connect (OSTI)

    Summers, G.P.

    1995-10-01T23:59:59.000Z

    The Naval Research Laboratory has been involved in developing InP solar cell technology since 1988. The purpose of these programs was to produce advanced cells for use in very high radiation environments, either as a result of operating satellites in the Van Allen belts or for very long duration missions in other orbits. Richard Statler was technical representative on the first program, with Spire Corporation as the contractor, which eventually produced several hundred, high efficiency 2 x 2 sq cm single crystal InP cells. The shallow homojunction technology which was developed in this program enabled cells to be made with AMO, one sun efficiencies greater than 19%. Many of these cells have been flown on space experiments, including PASP Plus, which have confirmed the high radiation resistance of InP cells. NRL has also published widely on the radiation response of these cells and also on radiation-induced defect levels detected by DLTS, especially the work of Rob Walters and Scott Messenger. In 1990 NRL began another Navy-sponsored program with Tim Coutts and Mark Wanlass at the National Renewable Energy Laboratory (NREL), to develop a one sun, two terminal space version of the InP-InGaAs tandem junction cell being investigated at NREL for terrestrial applications. These cells were grown on InP substrates. Several cells with AMO, one sun efficiencies greater than 22% were produced. Two 2 x 2 sq cm cells were incorporated on the STRV lA/B solar cell experiment. These were the only two junction, tandem cells on the STRV experiment. The high cost and relative brittleness of InP wafers meant that if InP cell technology were to become a viable space power source, the superior radiation resistance of InP would have to be combined with a cheaper and more robust substrate. The main technical challenge was to overcome the effect of the dislocations produced by the lattice mismatch at the interface of the two materials.

  1. Methanation assembly using multiple reactors

    DOE Patents [OSTI]

    Jahnke, Fred C.; Parab, Sanjay C.

    2007-07-24T23:59:59.000Z

    A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a reactor assembly has a plurality of methanation reactors each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation reactors and to combine water from the water supply with the output of each methanation reactor being conveyed to a next methanation reactor and carry the mixture to such next methanation reactor.

  2. A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...

    Office of Scientific and Technical Information (OSTI)

    A reactor and associated power plant designed to produce 1.05 Mwh and 3.535 Mwh of steam for heating purposes are described. The total thermal output of the reactor is 10 Mwh....

  3. EIS-0020: Crude Oil Transport Alternate From Naval Petroleum Reserve No. 1 Elk Hills/SOHIO Pipeline Connection Conveyance System, Terminal Tank Farm Relocation to Rialto, California

    Broader source: Energy.gov [DOE]

    The Office of Naval Petroleum and Oil Shale Reserves developed this supplemental statement to evaluate the environmental impacts associated with a modified design of a proposed 250,000 barrels per day crude oil conveyance system from Navel Petroleum Reserve No. 1 to connect to the proposed SOHIO West Coast to Midcontinent Pipeline at Rialto, California. This SEIS is a supplement to DOE/EIS-0020, Crude Oil Transport Alternate From Naval Petroleum Reserve No. 1 Elk Hills/SOHIO Pipeline Connection Conveyance System, Terminal Tank Farm Relocation to Rialto, California.

  4. Public health assessment for Treasure Island Naval Station, Hunters Point Annex, San Francisco, San Francisco County, California, Region 9. Cerclis No. CA1170090087. Final report

    SciTech Connect (OSTI)

    Not Available

    1994-09-30T23:59:59.000Z

    Naval Station Treasure Island, Hunters Point Annex (HPA), an inactive Naval shipyard located on a peninsula in the San Francisco Bay, San Francisco, California, was listed for base closure in 1990. Metals, pesticides, radium-226, polychlorinated biphenyls (PCBs), polycyclic aromatic hydrocarbons (PAHs), volatile organic compounds, semivolatile organic compounds, petroleum products, and asbestos have been found in various media such as soil, groundwater, surface water, air, and sediments. Navy contractors have identified 58 HPA areas where there may be contamination; investigations at these areas are ongoing.

  5. Reactor for exothermic reactions

    DOE Patents [OSTI]

    Smith, Jr., Lawrence A. (Bellaire, TX); Hearn, Dennis (Houston, TX); Jones, Jr., Edward M. (Friendswood, TX)

    1993-01-01T23:59:59.000Z

    A liquid phase process for oligomerization of C.sub.4 and C.sub.5 isoolefins or the etherification thereof with C.sub.1 to C.sub.6 alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120.degree. to 300.degree. F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

  6. Thermionic Reactor Design Studies

    SciTech Connect (OSTI)

    Schock, Alfred

    1994-08-01T23:59:59.000Z

    Paper presented at the 29th IECEC in Monterey, CA in August 1994. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their (thermionic reactor) performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling.

  7. Reactor for exothermic reactions

    DOE Patents [OSTI]

    Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.

    1993-03-02T23:59:59.000Z

    A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

  8. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, Ernest (Wilmette, IL)

    1986-01-01T23:59:59.000Z

    A safety device is disclosed for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of an upward thermal excursion. Such safety device comprises a laminated helical ribbon configured as a tube-like helical coil having contiguous helical turns with slidably abutting edges. The helical coil is disclosed as a portion of a drive member connected axially to the control rod. The laminated ribbon is formed of outer and inner laminae. The material of the outer lamina has a greater thermal coefficient of expansion than the material of the inner lamina. In the event of an upward thermal excursion, the laminated helical coil curls inwardly to a smaller diameter. Such inward curling causes the total length of the helical coil to increase by a substantial increment, so that the control rod is axially repositioned by a corresponding amount to reduce the power output of the reactor.

  9. Fusion reactor control

    SciTech Connect (OSTI)

    Plummer, D.A.

    1995-12-31T23:59:59.000Z

    The plasma kinetic temperature and density changes, each per an injected fuel density rate increment, control the energy supplied by a thermonuclear fusion reactor in a power production cycle. This could include simultaneously coupled control objectives for plasma current, horizontal and vertical position, shape and burn control. The minimum number of measurements required, use of indirect (not plasma parameters) system measurements, and distributed control procedures for burn control are to be verifiable in a time dependent systems code. The International Thermonuclear Experimental Reactor (ITER) has the need to feedback control both the fusion output power and the driven plasma current, while avoiding damage to diverter plates. The system engineering of fusion reactors must be performed to assure their development expeditiously and effectively by considering reliability, availability, maintainability, environmental impact, health and safety, and cost.

  10. Heat dissipating nuclear reactor

    DOE Patents [OSTI]

    Hunsbedt, Anstein (Los Gatos, CA); Lazarus, Jonathan D. (Sunnyvale, CA)

    1987-01-01T23:59:59.000Z

    Disclosed is a nuclear reactor containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the reactor vessel. The reactor vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extends from the metal base plate downwardly and outwardly into the earth.

  11. Heat dissipating nuclear reactor

    DOE Patents [OSTI]

    Hunsbedt, A.; Lazarus, J.D.

    1985-11-21T23:59:59.000Z

    Disclosed is a nuclear reactor containment adapted to retain and cool core debris in the unlikely event of a core meltdown and subsequent breach in the reactor vessel. The reactor vessel is seated in a cavity which has a thick metal sidewall that is integral with a thick metal basemat at the bottom of the cavity. The basemat extends beyond the perimeter of the cavity sidewall. Underneath the basemat is a porous bed with water pipes and steam pipes running into it. Water is introduced into the bed and converted into steam which is vented to the atmosphere. A plurality of metal pilings in the form of H-beams extend from the metal base plate downwardly and outwardly into the earth.

  12. Fast quench reactor method

    DOE Patents [OSTI]

    Detering, Brent A. (Idaho Falls, ID); Donaldson, Alan D. (Idaho Falls, ID); Fincke, James R. (Idaho Falls, ID); Kong, Peter C. (Idaho Falls, ID); Berry, Ray A. (Idaho Falls, ID)

    1999-01-01T23:59:59.000Z

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream.

  13. Fast quench reactor method

    DOE Patents [OSTI]

    Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.; Berry, R.A.

    1999-08-10T23:59:59.000Z

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream. 8 figs.

  14. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, Daniel L. (Princeton, NJ)

    1988-01-01T23:59:59.000Z

    A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam.

  15. Reactor Neutrino Experiments

    E-Print Network [OSTI]

    Jun Cao

    2007-12-06T23:59:59.000Z

    Precisely measuring $\\theta_{13}$ is one of the highest priority in neutrino oscillation study. Reactor experiments can cleanly determine $\\theta_{13}$. Past reactor neutrino experiments are reviewed and status of next precision $\\theta_{13}$ experiments are presented. Daya Bay is designed to measure $\\sin^22\\theta_{13}$ to better than 0.01 and Double Chooz and RENO are designed to measure it to 0.02-0.03. All are heading to full operation in 2010. Recent improvements in neutrino moment measurement are also briefed.

  16. Perspectives on reactor safety

    SciTech Connect (OSTI)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01T23:59:59.000Z

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  17. THE MATERIALS OF FAST BREEDER REACTORS

    E-Print Network [OSTI]

    Olander, Donald R.

    2013-01-01T23:59:59.000Z

    times larger in a fast reactor than in a thermal reactor,structural metals in a fast reactor will be subject to farof fuel ele- ments in fast reactors which are roughly one

  18. Innovative design of uranium startup fast reactors

    E-Print Network [OSTI]

    Fei, Tingzhou

    2012-01-01T23:59:59.000Z

    Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic ...

  19. Reactor operation environmental information document

    SciTech Connect (OSTI)

    Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

    1989-12-01T23:59:59.000Z

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

  20. Power calibrations for TRIGA reactors

    SciTech Connect (OSTI)

    Whittemore, W.L.; Razvi, J.; Shoptaugh, J.R. Jr. [General Atomics, San Diego, CA (United States)

    1988-07-01T23:59:59.000Z

    The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than {+-} 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to {+-} 1.5%. The procedures are equally applicable to the Mark I, Mark II and Mark III reactors as well as to reactors having much larger reactor tanks and to TRIGA reactors capable of forced cooling up to 3 MW in some cases and 15 MW in another case. In the case of forced cooled TRIGA reactors, the calorimetric power calibration is applicable in the natural convection mode for these reactors using exactly the same procedures as are discussed below for the smaller TRIGA reactors (< 2 MW)

  1. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01T23:59:59.000Z

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  2. Reed Reactor Facility Annual Report

    SciTech Connect (OSTI)

    Frantz, Stephen G.

    2000-09-01T23:59:59.000Z

    This is the report of the operations, experiments, modifications, and other aspects of the Reed Reactor Facility for the year.

  3. Nuclear Reactors and Technology

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01T23:59:59.000Z

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  4. NETL - Chemical Looping Reactor

    ScienceCinema (OSTI)

    None

    2014-06-26T23:59:59.000Z

    NETL's Chemical Looping Reactor unit is a high-temperature integrated CLC process with extensive instrumentation to improve computational simulations. A non-reacting test unit is also used to study solids flow at ambient temperature. The CLR unit circulates approximately 1,000 pounds per hour at temperatures around 1,800 degrees Fahrenheit.

  5. Thermal Reactor Safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01T23:59:59.000Z

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  6. Nuclear reactor building

    DOE Patents [OSTI]

    Gou, Perng-Fei (Saratoga, CA); Townsend, Harold E. (Campbell, CA); Barbanti, Giancarlo (Sirtori, IT)

    1994-01-01T23:59:59.000Z

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.

  7. Nuclear reactor building

    DOE Patents [OSTI]

    Gou, P.F.; Townsend, H.E.; Barbanti, G.

    1994-04-05T23:59:59.000Z

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed there above. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define there between an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin. 4 figures.

  8. Fossil fuel furnace reactor

    DOE Patents [OSTI]

    Parkinson, William J. (Los Alamos, NM)

    1987-01-01T23:59:59.000Z

    A fossil fuel furnace reactor is provided for simulating a continuous processing plant with a batch reactor. An internal reaction vessel contains a batch of shale oil, with the vessel having a relatively thin wall thickness for a heat transfer rate effective to simulate a process temperature history in the selected continuous processing plant. A heater jacket is disposed about the reactor vessel and defines a number of independent controllable temperature zones axially spaced along the reaction vessel. Each temperature zone can be energized to simulate a time-temperature history of process material through the continuous plant. A pressure vessel contains both the heater jacket and the reaction vessel at an operating pressure functionally selected to simulate the continuous processing plant. The process yield from the oil shale may be used as feedback information to software simulating operation of the continuous plant to provide operating parameters, i.e., temperature profiles, ambient atmosphere, operating pressure, material feed rates, etc., for simulation in the batch reactor.

  9. NETL - Chemical Looping Reactor

    SciTech Connect (OSTI)

    None

    2013-07-24T23:59:59.000Z

    NETL's Chemical Looping Reactor unit is a high-temperature integrated CLC process with extensive instrumentation to improve computational simulations. A non-reacting test unit is also used to study solids flow at ambient temperature. The CLR unit circulates approximately 1,000 pounds per hour at temperatures around 1,800 degrees Fahrenheit.

  10. Reactor Monitoring with Neutrinos

    E-Print Network [OSTI]

    M. Cribier

    2007-04-06T23:59:59.000Z

    The fundamental knowledge on neutrinos acquired in the recent years open the possibility of applied neutrino physics. Among it the automatic and non intrusive monitoring of nuclear reactor by its antineutrino signal could be very valuable to IAEA in charge of the control of nuclear power plants. Several efforts worldwide have already started.

  11. The naval Research Laboratory has been actively involved in research in unmanned and autonomous systems since its opening in 1923. From one of the first unmanned

    E-Print Network [OSTI]

    systems since its opening in 1923. From one of the first unmanned ground vehicles to the developmentThe naval Research Laboratory has been actively involved in research in unmanned and autonomous of more than 200 prototype air, ground, underwater, and space platforms, and from smart sensors to smart

  12. US Department of Energy Naval Petroleum and Oil Shale Reserves combined financial statements and management overview and supplemental financial and management information, September 30, 1995 and 1994

    SciTech Connect (OSTI)

    NONE

    1996-02-15T23:59:59.000Z

    This report presents the results of the independent certified public accountant`s audit of the Department of Energy`s (Department) Naval Petroleum and Oil Shale Reserves (NPOSR) financial statements as of September 30, 1995. The auditors have expressed an unqualified opinion on the 1995 statements. Their reports on the NPOSR internal control structure and compliance with laws and regulations are also provided.

  13. Phase II - final report study of alternatives for future operations of the naval petroleum and oil shale reserves NPR-3, Wyoming

    SciTech Connect (OSTI)

    NONE

    1996-12-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has asked Gustavson Associates, Inc. to serve as an Independent Petroleum Appraiser under contract DE-AC01-96FE64202. This authorizes a study and recommendations regarding future development of Naval Petroleum Reserve No. 3 (NPR-3) in Natrona County, Wyoming. The report that follows is the Phase II Final Report for that study.

  14. Reactor vessel support system. [LMFBR

    DOE Patents [OSTI]

    Golden, M.P.; Holley, J.C.

    1980-05-09T23:59:59.000Z

    A reactor vessel support system includes a support ring at the reactor top supported through a box ring on a ledge of the reactor containment. The box ring includes an annular space in the center of its cross-section to reduce heat flow and is keyed to the support ledge to transmit seismic forces from the reactor vessel to the containment structure. A coolant channel is provided at the outside circumference of the support ring to supply coolant gas through the keyways to channels between the reactor vessel and support ledge into the containment space.

  15. Nuclear reactor construction with bottom supported reactor vessel

    DOE Patents [OSTI]

    Sharbaugh, John E. (Bullskin Township, Fayette County, PA)

    1987-01-01T23:59:59.000Z

    An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core within the pool. The reactor vessel has an open top end, a closed flat bottom end wall and a continuous cylindrical closed side wall interconnecting the top end and bottom end wall. The reactor also has a generally cylindrical concrete containment structure surrounding the reactor vessel and being formed by a cylindrical side wall spaced outwardly from the reactor vessel side wall and a flat base mat spaced below the reactor vessel bottom end wall. A central support pedestal is anchored to the containment structure base mat and extends upwardly therefrom to the reactor vessel and upwardly therefrom to the reactor core so as to support the bottom end wall of the reactor vessel and the lower end of the reactor core in spaced apart relationship above the containment structure base mat. Also, an annular reinforced support structure is disposed in the reactor vessel on the bottom end wall thereof and extends about the lower end of the core so as to support the periphery thereof. In addition, an annular support ring having a plurality of inward radially extending linear members is disposed between the containment structure base mat and the bottom end of the reactor vessel wall and is connected to and supports the reactor vessel at its bottom end on the containment structure base mat so as to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event. The reactor construction also includes a bed of insulating material in sand-like granular form, preferably being high density magnesium oxide particles, disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall on the containment structure base mat so as to insulate the reactor vessel bottom end wall from the containment structure base mat and allow the reactor vessel bottom end wall to freely expand as it heats up while providing continuous support thereof. Further, a deck is supported upon the side wall of the containment structure above the top open end of the reactor vessel, and a plurality of serially connected extendible and retractable annular bellows extend between the deck and the top open end of the reactor vessel and flexibly and sealably interconnect the reactor vessel at its top end to the deck. An annular guide ring is disposed on the containment structure and extends between its side wall and the top open end of the reactor vessel for providing lateral support of the reactor vessel top open end by limiting imposition of lateral loads on the annular bellows by the occurrence of a lateral seismic event.

  16. Reservoir analysis study, Naval Petroleum Reserve No. 1, Elk Hills Field, Kern County, California: Phase 2 report, Volume 1

    SciTech Connect (OSTI)

    Not Available

    1988-06-01T23:59:59.000Z

    Jerry R. Bergeso and Associates, Inc. (Bergeson) has completed Phase II of the Reservoir Analysis, Naval Petroleum Reserve Number 1, Elk Hills Oilfield, California. The objectives for this phase of the study included the establishment of revised estimates of the original oil and gas-in-place for each of the zones/reservoirs, estimation of the remaining proved developed, proved undeveloped, probable and possible reserves, and assessment of the effects of historical development and production operations and practices on recoverable reserves. Volume one contains the following: summary; introduction; and reservoir studies for tulare, dry gas zone, eastern shallow oil zone, western shallow oil zone, and Stevens --MBB/W31S, 31S NA/D.

  17. Five-year resurvey for endangered species on Naval Petroleum Reserve No. 1 (Elk Hills), Kern County, California

    SciTech Connect (OSTI)

    O'Farrell, T.P.; Mathews, N.E.

    1987-09-01T23:59:59.000Z

    A transect survey of Naval Petroleum Reserve No. 1 (NPR-1), Kern County, California, was conducted in 1984 to determine the distribution and relative abundance of endangered species and other wildlife. A total of 589.8 miles of transects were walked through approximately 47,235 acres in all or parts of 81 sections. A total of 16,401 observations of 58 species of wildlife were made which demonstrated the richness and abundance of wildlife on NPR-1 in spite of the intensity of recent petroleum developments. Although most construction activities associated with increased petroleum production took place between the first transect survey in 1979 and this resurvey, no adverse changes in relative densities of kit fox dens, prey base, or other wildlife were observed. NPR-1 should be resurveyed again in 1989. 33 refs., 5 figs., 13 tabs.

  18. Performance and evaluation of gas-engine-driven split-system cooling equipment at the Willow Grove Naval Air Station

    SciTech Connect (OSTI)

    Armstrong, P.R.; Schmelzer, J.R.

    1997-01-01T23:59:59.000Z

    DOE`s Federal Energy Management Program supports efforts to reduce energy use and associated expenditures within the federal sector; one such effort, the New Technology Demonstration Program (NTDP)(formerly the Test Bed Demonstration program), seeks to evaluate new energy saving US technologies and secure their more timely adoption by the federal government. This report describes the field evaluation conducted to examine the performance of a 15-ton natural-gas-engine- driven, split-system, air-conditioning unit. The unit was installed at a multiple-use building at Willow Grove Naval Air Station, a regular and reserve training facility north of Philadelphia, and its performance was monitored under the NTDP.

  19. Reservoir analysis study, Naval Petroleum Reserve No. 1, Elk Hills Field, Kern County, California: Phase 2 report, Executive summary

    SciTech Connect (OSTI)

    Not Available

    1988-07-01T23:59:59.000Z

    The Naval Petroleum Reserve No. 1 (Elk Hills) is located in Kern County, California, and is jointly owned by the US Department of Energy and Chevron USA Inc. The Elk Hills Field is presently producing oil and gas from five geologic zones. These zones contain a number of separate and geologically complex reservoirs. Considerable field development and production of oil and gas have occurred since initial estimates of reserves were made. Total cumulative field production through December 1987 is 850 MMBbls of oil, 1.2 Tcf of gas and 648.2 MMBbls of water. In December 1987, field producing rates expressed on a calendar day basis amounted to 110,364 BOPD, 350,946 Mcfd and 230,179 BWPD from 1157 producers. In addition, a total of two reservoirs have gas injection in progress and four reservoirs have water injection in progress and four reservoirs have water injection in progress. Cumulative gas and water injection amounted to 586 Bcf of gas and 330 MMB of water. December 1987 gas and water injection rates amounted to 174 MMcfd and 234 MBWPD, into 129 injectors. In addition, a steamflood pilot program is currently active in the Eastern Shallow Oil Zone. Jerry R. Bergeson and Associates, Inc. (Bergeson) has completed Phase II of the Reservoir Analysis, Naval Petroleum Reserve Number 1, Elk Hills Oilfield, California. The objectives for this phase of the study included the establishment of revised estimates of the original oil and gas-in-place for each of the zones/reservoirs, estimation of the remaining proved developed, proved undeveloped, probable and possible reserves, and assessment of the effects of historical development and production operations and practices on recoverable reserves. 28 figs., 37 tabs.

  20. Performance and evaluation of gas engine driven rooftop air conditioning equipment at the Willow Grove (PA) Naval Air Station

    SciTech Connect (OSTI)

    Armstrong, P.R.; Conover, D.R.

    1993-05-01T23:59:59.000Z

    In a field evaluation conducted for the US Department of Energy (DOE) Office of Federal Energy Management Program (FEMP), the Pacific Northwest Laboratory (PNL) examined the performance of a new US energy-related technology under the FEMP Test Bed Demonstration Program. The technology was a 15-ton natural gas engine driven roof top air conditioning unit. Two such units were installed on a naval retail building to provide space conditioning to the building. Under the Test Bed Demonstration Program, private and public sector interests are focused to support the installation and evaluation of new US technologies in the federal sector. Participating in this effort under a Cooperative Research and Development Agreement (CRADA) with DOE were the American Gas Cooling Center, Philadelphia Electric Company, Thermo King Corporation, and the US Naval Air Station at Willow Grove, Pennsylvania. Equipment operating and service data as well as building interior and exterior conditions were secured for the 1992 cooling season. Based on a computer assessment of the building using standard weather data, a comparison was made with the energy and operating costs associated with the previous space conditioning system. Based on performance during the 1992 cooling season and adjusted to a normal weather year, the technology will save the site $6,000/yr in purchased energy costs. An additional $9,000 in savings due to electricity demand ratchet charge reductions will also be realized. Detailed information on the technology, the installation, and the results of the technology test are provided to illustrate the advantages to the federal sector of using this technology. A history of the CRADA development process is also reported.

  1. Nuclear reactor safety device

    DOE Patents [OSTI]

    Hutter, E.

    1983-08-15T23:59:59.000Z

    A safety device is described for use in a nuclear reactor for axially repositioning a control rod with respect to the reactor core in the event of a thermal excursion. It comprises a laminated strip helically configured to form a tube, said tube being in operative relation to said control rod. The laminated strip is formed of at least two materials having different thermal coefficients of expansion, and is helically configured such that the material forming the outer lamina of the tube has a greater thermal coefficient of expansion than the material forming the inner lamina of said tube. In the event of a thermal excursion the laminated strip will tend to curl inwardly so that said tube will increase in length, whereby as said tube increases in length it exerts a force on said control rod to axially reposition said control rod with respect to said core.

  2. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, D.L.

    1987-09-04T23:59:59.000Z

    A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.

  3. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Peng, Yueng-Kay M. (Oak Ridge, TN)

    1989-01-01T23:59:59.000Z

    A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

  4. Nuclear reactor sealing system

    DOE Patents [OSTI]

    McEdwards, James A. (Calabasas, CA)

    1983-01-01T23:59:59.000Z

    A liquid metal-cooled nuclear reactor sealing system. The nuclear reactor includes a vessel sealed at its upper end by a closure head. The closure head comprises at least two components, one of which is rotatable; and the two components define an annulus therebetween. The sealing system includes at least a first and second inflatable seal disposed in series in an upper portion of the annulus. The system further includes a dip seal extending into a body of insulation located adjacent a bottom portion of the closure head. The dip seal comprises a trough formed by a lower portion of one of the components, and a seal blade pendently supported from the other component and extending downwardly into the trough. A body of liquid metal is contained in the trough which submerges a portion of the seal blade. The seal blade is provided with at least one aperture located above the body of liquid metal for providing fluid communication between the annulus intermediate the dip seal and the inflatable seals, and a body of cover gas located inside the vessel. There also is provided means for introducing a purge gas into the annulus intermediate the inflatable seals and the seal blade. The purge gas is introduced in an amount sufficient to substantially reduce diffusion of radioactive cover gas or sodium vapor up to the inflatable seals. The purge gas mixes with the cover gas in the reactor vessel where it can be withdrawn from the vessel for treatment and recycle to the vessel.

  5. Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1994-12-31T23:59:59.000Z

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future.

  6. Modular Pebble Bed Reactor High Temperature Gas Reactor

    E-Print Network [OSTI]

    Built · Site Assembled · On--line Refueling · Modules added to meet demand. · No Reprocessing · High Experiments · Non-Proliferation · Safeguards · Waste Disposal · Reactor Research/ Demonstration Facility

  7. Thermionic Reactor Design Studies

    SciTech Connect (OSTI)

    Schock, Alfred

    1994-06-01T23:59:59.000Z

    During the 1960's and early 70's the author performed extensive design studies, analyses, and tests aimed at thermionic reactor concepts that differed significantly from those pursued by other investigators. Those studies, like most others under Atomic Energy Commission (AEC and DOE) and the National Aeronautics and Space Administration (NASA) sponsorship, were terminated in the early 1970's. Some of this work was previously published, but much of it was never made available in the open literature. U.S. interest in thermionic reactors resumed in the early 80's, and was greatly intensified by reports about Soviet ground and flight tests in the late 80's. This recent interest resulted in renewed U.S. thermionic reactor development programs, primarily under Department of Defense (DOD) and Department of Energy (DOE) sponsorship. Since most current investigators have not had an opportunity to study all of the author's previous work, a review of the highlights of that work may be of value to them. The present paper describes some of the author's conceptual designs and their rationale, and the special analytical techniques developed to analyze their performance. The basic designs, first published in 1963, are based on single-cell converters, either double-ended diodes extending over the full height of the reactor core or single-ended diodes extending over half the core height. In that respect they are similar to the thermionic fuel elements employed in the Topaz-2 reactor subsequently developed in the Soviet Union, copies of which were recently imported by the U.S. As in the Topaz-2 case, electrically heated steady-state performance tests of the converters are possible before fueling. Where the author's concepts differed from the later Topaz-2 design was in the relative location of the emitter and the collector. Placing the fueled emitter on the outside of the cylindrical diodes permits much higher axial conductances to reduce ohmic losses in the electrodes of full-core-height diodes. Moreover, placing the fuel on the outside of the diode makes possible reactors with much higher fuel volume fractions, which enable power-flattened fast reactors scalable to very low power levels without the need for life-limiting hydride moderators or the use of efficiency-limiting driver fuel. In addition, with the fuel on the outside its swelling does not increase the emitter diameter or reduce the interelectrode gap. This should permit long lifetimes even with closer spacings, which can significantly improve the system efficiences. This was confirmed by coupled neutronic, thermal, thermionic, and electrical system analyses - some of which are presented in this paper - and by subsequent experiments. A companion paper presented next describes the fabrication and testing of full-scale converter elements, both fueled and unfueled, and summarizes the test results obtained. There is a duplicate copy in the file.

  8. Designing Reactors to Facilitate Decommissioning

    SciTech Connect (OSTI)

    Richard H. Meservey

    2006-06-01T23:59:59.000Z

    Critics of nuclear power often cite issues with tail-end-of-the-fuel-cycle activities as reasons to oppose the building of new reactors. In fact, waste disposal and the decommissioning of large nuclear reactors have proven more challenging than anticipated. In the early days of the nuclear power industry the design and operation of various reactor systems was given a great deal of attention. Little effort, however, was expended on end-of-the-cycle activities, such as decommissioning and disposal of wastes. As early power and test reactors have been decommissioned difficulties with end-of-the-fuel-cycle activities have become evident. Even the small test reactors common at the INEEL were not designed to facilitate their eventual decontamination, decommissioning, and dismantlement. The results are that decommissioning of these facilities is expensive, time consuming, relatively hazardous, and generates large volumes of waste. This situation clearly supports critics concerns about building a new generation of power reactors.

  9. Evaluation of Concepts for Mulitiple Application Thermal Reactor for Irradiation eXperiments (MATRIX)

    SciTech Connect (OSTI)

    Michael A. Pope; Hans D. Gougar; John M. Ryskamp

    2013-09-01T23:59:59.000Z

    The Advanced Test Reactor (ATR) is a high power density test reactor specializing in fuel and materials irradiation. For more than 45 years, the ATR has provided irradiations of materials and fuels testing along with radioisotope production. Originally operated primarily in support of the Offcie of Naval Reactors (NR), the mission has gradually expanded to cater to other customers, such as the DOE Office of Nuclear Energy (NE), private industry, and universities. Unforeseen circumstances may lead to the decommissioning of ATR, thus leaving the U.S. Government without a large-scale materials irradiation capability to meet the needs of its nuclear energy and naval reactor missions. In anticipation of this possibility, work was performed under the Laboratory Directed Research and Development (LDRD) program to investigate test reactor concepts that could satisfy the current missions of the ATR along with an expanded set of secondary missions. This work can be viewed as an update to a project from the 1990’s called the Broad Application Test Reactor (BATR). In FY 2012, a survey of anticipated customer needs was performed, followed by analysis of the original BATR concepts with fuel changed to low-enriched uranium. Departing from these original BATR designs, four concepts were identified for further analysis in FY2013. The project informally adopted the acronym MATRIX (Multiple-Application Thermal Reactor for Irradiation eXperiments). This report discusses analysis of the four MATRIX concepts along with a number of variations on these main concepts. Designs were evaluated based on their satisfaction of anticipated customer requirements and the “Cylindrical” variant was selected for further analysis of options. This downselection should be considered preliminary and the backup alternatives should include the other three main designs. The baseline Cylindrical MATRIX design is expected to be capable of higher burnup than the ATR (or longer cycle length given a particular batch scheme). The volume of test space in IPTs is larger in MATRIX than in ATR with comparable magnitude of neutron flux. In addition to the IPTs, the Cylindrical MATRIX concept features test spaces at the centers of fuel assemblies where very high fast flux can be achieved. This magnitude of fast flux is similar to that achieved in the ATR A-positions, however, the available volume having these conditions is greater in the MATRIX design than in the ATR. From the analyses performed in this work, it appears that the Cylindrical MATRIX design can be designed to meet the anticipated needs of the ATR replacement reactor. However, this statement must be qualified by acknowledging that this design is quite immature, and therefore any requirements currently met must be re-evaluated as the design matures. Also, some of the requirements were not strictly met, but are believed to be achievable once features to be added later are designed.

  10. Fast quench reactor and method

    DOE Patents [OSTI]

    Detering, B.A.; Donaldson, A.D.; Fincke, J.R.; Kong, P.C.

    1998-05-12T23:59:59.000Z

    A fast quench reactor includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the reactor chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This ``freezes`` the desired end product(s) in the heated equilibrium reaction stage. 7 figs.

  11. Neutrino Oscillation Studies with Reactors

    E-Print Network [OSTI]

    Petr Vogel; Liangjian Wen; Chao Zhang

    2015-03-03T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavors are quantum mechanical mixtures. Over the past several decades reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle $\\theta_{13}$. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  12. Neutrino Oscillation Studies with Reactors

    E-Print Network [OSTI]

    Petr Vogel; Liangjian Wen; Chao Zhang

    2015-04-27T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavors are quantum mechanical mixtures. Over the past several decades reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle $\\theta_{13}$. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  13. Neutrino Oscillation Studies with Reactors

    E-Print Network [OSTI]

    Vogel, Petr; Zhang, Chao

    2015-01-01T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective, and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavors are quantum mechanical mixtures. Over the past several decades reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle $\\theta_{13}$. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  14. Progress Update: Reactor Disassembly Grouting

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14T23:59:59.000Z

    Grouting the P&R reactors in order to remove these basins as an environmental threat. This will end the Cold War legacy and end the environmental footprint.

  15. Progress Update: Reactor Disassembly Grouting

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01T23:59:59.000Z

    Grouting the P&R reactors in order to remove these basins as an environmental threat. This will end the Cold War legacy and end the environmental footprint.

  16. Neutrino oscillation studies with reactors

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

    Vogel, P. [California Inst. of Technology (CalTech), Pasadena, CA (United States). Kellog Radiation Lab.; Wen, L.J. [Chinese Academy of Sciences (CAS), Beijing (China). Inst. of High Energy Physics (IHEP); Zhang, C. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-04-27T23:59:59.000Z

    Nuclear reactors are one of the most intense, pure, controllable, cost-effective and well-understood sources of neutrinos. Reactors have played a major role in the study of neutrino oscillations, a phenomenon that indicates that neutrinos have mass and that neutrino flavours are quantum mechanical mixtures. Over the past several decades, reactors were used in the discovery of neutrinos, were crucial in solving the solar neutrino puzzle, and allowed the determination of the smallest mixing angle ?13. In the near future, reactors will help to determine the neutrino mass hierarchy and to solve the puzzling issue of sterile neutrinos.

  17. Thermonuclear Reflect AB-Reactor

    E-Print Network [OSTI]

    Alexander Bolonkin

    2008-03-26T23:59:59.000Z

    The author offers a new kind of thermonuclear reflect reactor. The remarkable feature of this new reactor is a three net AB reflector, which confines the high temperature plasma. The plasma loses part of its energy when it contacts with the net but this loss can be compensated by an additional permanent plasma heating. When the plasma is rarefied (has a small density), the heat flow to the AB reflector is not large and the temperature in the triple reflector net is lower than 2000 - 3000 K. This offered AB-reactor has significantly less power then the currently contemplated power reactors with magnetic or inertial confinement (hundreds-thousands of kW, not millions of kW). But it is enough for many vehicles and ships and particularly valuable for tunnelers, subs and space apparatus, where air to burn chemical fuel is at a premium or simply not available. The author has made a number of innovations in this reactor, researched its theory, developed methods of computation, made a sample computation of typical project. The main point of preference for the offered reactor is its likely cheapness as a power source. Key words: Micro-thermonuclear reactor, Multi-reflex AB-thermonuclear reactor, Self-magnetic AB-thermonuclear reactor, aerospace thermonuclear engine.

  18. Reactor coolant pump flywheel

    DOE Patents [OSTI]

    Finegan, John Raymond; Kreke, Francis Joseph; Casamassa, John Joseph

    2013-11-26T23:59:59.000Z

    A flywheel for a pump, and in particular a flywheel having a number of high density segments for use in a nuclear reactor coolant pump. The flywheel includes an inner member and an outer member. A number of high density segments are provided between the inner and outer members. The high density segments may be formed from a tungsten based alloy. A preselected gap is provided between each of the number of high density segments. The gap accommodates thermal expansion of each of the number of segments and resists the hoop stress effect/keystoning of the segments.

  19. Reactor refueling containment system

    DOE Patents [OSTI]

    Gillett, J.E.; Meuschke, R.E.

    1995-05-02T23:59:59.000Z

    A method of refueling a nuclear reactor is disclosed whereby the drive mechanism is disengaged and removed by activating a jacking mechanism that raises the closure head. The area between the barrier plate and closure head is exhausted through the closure head penetrations. The closure head, upper drive mechanism, and bellows seal are lifted away and transported to a safe area. The barrier plate acts as the primary boundary and each drive and control rod penetration has an elastomer seal preventing excessive tritium gases from escaping. The individual instrumentation plugs are disengaged allowing the corresponding fuel assembly to be sealed and replaced. 2 figs.

  20. Nuclear reactor control assembly

    SciTech Connect (OSTI)

    Negron, S.B.

    1991-06-11T23:59:59.000Z

    This patent describes an assembly for providing global power control in a nuclear reactor having the core split into two halves. It comprises a disk assembly formed from at least two disks each machined with an identical surface hole pattern such that rotation of one disk relative to the other causes the hole pattern to open or close, the disk assembly being positioned substantially at the longitudinal center of and coaxial with the core halves; and means for rotating at least one of the disks relative to the other.

  1. Nuclear reactor control apparatus

    SciTech Connect (OSTI)

    Sridhar, B.N.

    1981-08-28T23:59:59.000Z

    Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additonal magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

  2. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, C.D.; Marasco, J.A.

    1996-02-27T23:59:59.000Z

    A fluidized bed reactor system is described which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary and tertiary particulate phases, continuously introduced and removed simultaneously in the cocurrent and countercurrent mode, act in a role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Means for introducing and removing the sorbent phases include feed screw mechanisms and multivane slurry valves. 3 figs.

  3. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN)

    1993-01-01T23:59:59.000Z

    A fluidized bed reactor system which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves.

  4. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN); Marasco, Joseph A. (Kingston, TN)

    1995-01-01T23:59:59.000Z

    A fluidized bed reactor system utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves.

  5. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, Charles D. (Oak Ridge, TN); Marasco, Joseph A. (Kingston, TN)

    1996-01-01T23:59:59.000Z

    A fluidized bed reactor system which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary and tertiary particulate phases, continuously introduced and removed simultaneously in the cocurrent and countercurrent mode, act in a role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Means for introducing and removing the sorbent phases include feed screw mechanisms and multivane slurry valves.

  6. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, C.D.

    1993-12-14T23:59:59.000Z

    A fluidized bed reactor system which utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase is described. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves. 3 figures.

  7. Reactor refueling containment system

    DOE Patents [OSTI]

    Gillett, James E. (Greensburg, PA); Meuschke, Robert E. (Pittsburgh, PA)

    1995-01-01T23:59:59.000Z

    A method of refueling a nuclear reactor whereby the drive mechanism is disengaged and removed by activating a jacking mechanism that raises the closure head. The area between the barrier plate and closure head is exhausted through the closure head penetrations. The closure head, upper drive mechanism, and bellows seal are lifted away and transported to a safe area. The barrier plate acts as the primary boundary and each drive and control rod penetration has an elastomer seal preventing excessive tritium gases from escaping. The individual instrumentation plugs are disengaged allowing the corresponding fuel assembly to be sealed and replaced.

  8. Biparticle fluidized bed reactor

    DOE Patents [OSTI]

    Scott, C.D.; Marasco, J.A.

    1995-04-25T23:59:59.000Z

    A fluidized bed reactor system utilizes a fluid phase, a retained fluidized primary particulate phase, and a migratory second particulate phase. The primary particulate phase is a particle such as a gel bead containing an immobilized biocatalyst. The secondary particulate phase, continuously introduced and removed in either cocurrent or countercurrent mode, acts in a secondary role such as a sorbent to continuously remove a product or by-product constituent from the fluid phase. Introduction and removal of the sorbent phase is accomplished through the use of feed screw mechanisms and multivane slurry valves. 3 figs.

  9. Nuclear reactor control apparatus

    DOE Patents [OSTI]

    Sridhar, Bettadapur N. (Cupertino, CA)

    1983-11-01T23:59:59.000Z

    Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additional magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

  10. N Reactor - Hanford Site

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)Integrated Codes |IsLove Your1 SECTIONES2008-54174MoreMuseum Day atMyNERSCVanN Reactor

  11. Vettor Fausto (1490-1546), Professor of Greek and a Naval Architect: A New Light on the 16th-century Manuscript Misure di vascelli etc. di…proto dell’Arsenale di Venetia 

    E-Print Network [OSTI]

    Campana, Lilia 1975-

    2010-12-06T23:59:59.000Z

    This thesis investigates the significant role that the Venetian humanist Vettor Fausto (1490-1546), professor of Greek at the School of Saint Mark, played during the first half of the 16th century in Venetian naval ...

  12. EA-0962: Construction and Routine Operation of a 12-kilovolt Overhead Powerline and Formal Authorization for a 10-inch and 8-inch Fresh Water Pipeline Right-of-Way at Naval Petroleum Reserve No. 1, Kern County, California

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to install an overhead powerline extension from the U.S. Department of Energy's Naval Petroleum Reserve No. 1 (NPR-1) power source to the...

  13. Fast Reactor Fuel Type and Reactor Safety Performance

    SciTech Connect (OSTI)

    R. Wigeland; J. Cahalan

    2009-09-01T23:59:59.000Z

    Fast Reactor Fuel Type and Reactor Safety Performance R. Wigeland , Idaho National Laboratory J. Cahalan, Argonne National Laboratory The sodium-cooled fast neutron reactor is currently being evaluated for the efficient transmutation of the highly-hazardous, long-lived, transuranic elements that are present in spent nuclear fuel. One of the fundamental choices that will be made is the selection of the fuel type for the fast reactor, whether oxide, metal, carbide, nitride, etc. It is likely that a decision on the fuel type will need to be made before many of the related technologies and facilities can be selected, from fuel fabrication to spent fuel reprocessing. A decision on fuel type should consider all impacts on the fast reactor system, including safety. Past work has demonstrated that the choice of fuel type may have a significant impact on the severity of consequences arising from accidents, especially for severe accidents of low probability. In this paper, the response of sodium-cooled fast reactors is discussed for both oxide and metal fuel types, highlighting the similarities and differences in reactor response and accident consequences. Any fast reactor facility must be designed to be able to successfully prevent, mitigate, or accommodate all consequences of potential events, including accidents. This is typically accomplished by using multiple barriers to the release of radiation, including the cladding on the fuel, the intact primary cooling system, and most visibly the reactor containment building. More recently, this has also included the use of ‘inherent safety’ concepts to reduce or eliminate the potential for serious damage in some cases. Past experience with oxide and metal fuel has demonstrated that both fuel types are suitable for use as fuel in a sodium-cooled fast reactor. However, safety analyses for these two fuel types have also shown that there can be substantial differences in accident consequences due to the neutronic and thermophysical properties of the fuel and their compatibility with the reactor coolant, with corresponding differences in the challenges presented to the reactor developers. Accident phenomena are discussed for the sodium-cooled fast reactor based on the mechanistic progression of conditions from accident initiation to accident termination, whether a benign state is achieved or more severe consequences are expected. General principles connecting accident phenomena and fuel properties are developed from the oxide and metal fuel safety analyses, providing guidelines that can be used as part of the evaluation for selection of fuel type for the sodium-cooled fast reactor.

  14. Granular Dynamics in Pebble Bed Reactor Cores

    E-Print Network [OSTI]

    Laufer, Michael Robert

    2013-01-01T23:59:59.000Z

    in a pebble-bed nuclear reactor,” Phys. Rev. E, vol. 74, no.cycles of the pebble bed reactor,” Nuclear Engineering andoptimization of pebble-bed reactors,” Annals of Nuclear

  15. Gaseous reactor control system

    SciTech Connect (OSTI)

    Abdel-Khalik, S.

    1991-09-03T23:59:59.000Z

    This paper describes a nuclear reactor control system for controlling the reactivity of the core of a nuclear reactor. It includes a control gas having a high neutron cross-section; a first tank containing a first supply of the control gas; a first conduit providing a first fluid passage extending into the core, the first conduit being operatively connected to communicate with the first tank; a first valve operatively connected to regulate the flow of the control gas between the first tank and the first conduit; a second conduit concentrically disposed around the first conduit such that a second fluid passage is defined between the outer surface of the first conduit and the inner surface of the second conduit; a second tank containing a second supply of the control gas, the second tank being operatively connected to communicate with the second fluid passage; a second supply valve operatively connected to regulate the flow of the control gas between the second tank and the second fluid passage.

  16. Solvent refined coal reactor quench system

    DOE Patents [OSTI]

    Thorogood, R.M.

    1983-11-08T23:59:59.000Z

    There is described an improved SRC reactor quench system using a condensed product which is recycled to the reactor and provides cooling by evaporation. In the process, the second and subsequent reactors of a series of reactors are cooled by the addition of a light oil fraction which provides cooling by evaporation in the reactor. The vaporized quench liquid is recondensed from the reactor outlet vapor stream. 1 fig.

  17. Reactor Neutrino Physics -- An Update

    E-Print Network [OSTI]

    Felix Boehm

    1999-06-18T23:59:59.000Z

    We review the status and the results of reactor neutrino experiments. Long baseline oscillation experiments at Palo Verde and Chooz have provided limits for the oscillation parameters while the recently proposed Kamland experiment at a baseline of more than 100km is now in the planning stage. We also describe the status of neutrino magnetic moment experiments at reactors.

  18. Radiation Shielding for Fusion Reactors

    SciTech Connect (OSTI)

    Santoro, R.T.

    1999-10-01T23:59:59.000Z

    Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel. Radiation shielding requirements for fusion reactors present different problems than those for fission reactors and accelerators. Fusion devices, particularly tokamak reactors, are complicated by geometry constraints that complicate disposition of fully effective shielding. This paper reviews some of these shielding issues and suggested solutions for optimizing the machine and biological shielding. Radiation transport calculations are essential for predicting and confirming the nuclear performance of the reactor and, as such, must be an essential part of the reactor design process. Development and optimization of reactor components from the first wall and primary shielding to the penetrations and containment shielding must be carried out in a sensible progression. Initial results from one-dimensional transport calculations are used for scoping studies and are followed by detailed two- and three-dimensional analyses to effectively characterize the overall radiation environment. These detail model calculations are essential for accounting for the radiation leakage through ports and other penetrations in the bulk shield. Careful analysis of component activation and radiation damage is cardinal for defining remote handling requirements, in-situ replacement of components, and personnel access at specific locations inside the reactor containment vessel.

  19. Granular Dynamics in Pebble Bed Reactor Cores

    E-Print Network [OSTI]

    Laufer, Michael Robert

    2013-01-01T23:59:59.000Z

    gas reactors with the effective heat transfer of a molten salt coolant and the passive natural circulation safety systems of sodium fast reactors.

  20. MOOSE simulating nuclear reactor CRUD buildup

    ScienceCinema (OSTI)

    None

    2014-07-21T23:59:59.000Z

    This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

  1. MOOSE simulating nuclear reactor CRUD buildup

    SciTech Connect (OSTI)

    None

    2014-02-06T23:59:59.000Z

    This simulation uses multiple physical models to show how the buildup of boron deposits on reactor fuel can affect performance and the reactor's power profile.

  2. The Endurance Bioenergy Reactor | Argonne National Laboratory

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

    The Endurance Bioenergy Reactor Share Description Argonne biophysicist Dr. Philip Laible and Air Force Major Matt Michaud talks about he endurance bioenergy reactor-a device that...

  3. Fast reactors and nuclear nonproliferation

    SciTech Connect (OSTI)

    Avrorin, E.N. [Russian Federal Nuclear Center - Zababakhin Institute of Applied Physics, Snezhinsk (Russian Federation); Rachkov, V.I.; Chebeskov, A.N. [State Scientific Center of the Russian Federation - Institute for Physics and Power Engineering, Bondarenko Square, 1, Obninsk, Kaluga region, 249033 (Russian Federation)

    2013-07-01T23:59:59.000Z

    Problems are discussed with regard to nuclear fuel cycle resistance in fast reactors to nuclear proliferation risk due to the potential for use in military programs of the knowledge, technologies and materials gained from peaceful nuclear power applications. Advantages are addressed for fast reactors in the creation of a more reliable mode of nonproliferation in the closed nuclear fuel cycle in comparison with the existing fully open and partially closed fuel cycles of thermal reactors. Advantages and shortcomings are also discussed from the point of view of nonproliferation from the start with fast reactors using plutonium of thermal reactor spent fuel and enriched uranium fuel to the gradual transition using their own plutonium as fuel. (authors)

  4. Automatic reactor power control for a pressurized water reactor

    SciTech Connect (OSTI)

    Jungin Choi (Kyungwon Univ. (Korea, Republic of)); Yungjoon Hah (Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)); Unchul Lee (Seoul National Univ. (Korea, Republic of))

    1993-05-01T23:59:59.000Z

    An automatic reactor power control system is presented for a pressurized water reactor (PWR). The associated reactor control strategy is called mode K.' The new system implements a heavy-worth bank dedicated to axial shape control, independent of the existing regulating banks. The heavy bank provides a monotonic relationship between its motion and the axial shape change, which allows automatic control of the axial power distribution. Thus, the mode K enables precise regulation of both the reactivity and the power distribution, by using double closed-loop control of the reactor coolant temperature and the axial power difference. Automatic reactor power control permits the nuclear power plant to accommodate the load-follow operations, including frequency control, to respond to the grid requirements. The mode K reactor control concepts were tested using simulation responses of a Korean standardized 1,000-MW (electric) PWR. The simulation results illustrate that the mode K would be a practical reactor power control strategy for the increased automation of nuclear plants.

  5. Proposed natural gas protection program for Naval Oil Shale Reserves Nos. 1 and 3, Garfield County, Colorado

    SciTech Connect (OSTI)

    Not Available

    1991-08-01T23:59:59.000Z

    As a result of US Department of Energy (DOE) monitoring activities, it was determined in 1983 that the potential existed for natural gas resources underlying the Naval Oil Shales Reserves Nos. 1 and 3 (NOSrs-1 3) to be drained by privately-owned gas wells that were being drilled along the Reserves borders. In 1985, DOE initiated a limited number of projects to protect the Government's interest in the gas resources by drilling its own offset production'' wells just inside the boundaries, and by formally sharing in the production, revenues and costs of private wells that are drilled near the boundaries ( communitize'' the privately-drilled wells). The scope of these protection efforts must be expanded. DOE is therefore proposing a Natural Gas Protection Program for NOSRs-1 3 which would be implemented over a five-year period that would encompass a total of 200 wells (including the wells drilled and/or communitized since 1985). Of these, 111 would be offset wells drilled by DOE on Government land inside the NOSRs' boundaries and would be owned either entirely by the Government or communitized with adjacent private land owners or lessees. The remainder would be wells drilled by private operators in an area one half-mile wide extending around the NOSRs boundaries and communitized with the Government. 23 refs., 2 figs., 6 tabs.

  6. Empirical, probabilistic, and modelling approaches to assess cross-media impacts to marine sediments at Puget Sound Naval Shipyard

    SciTech Connect (OSTI)

    Rohrer, W.L.; Vita, C.L. [URS Consultants, Inc., Seattle, WA (United States); Schrock, W. [Navy, Poulsbo, WA (United States). Engineering Field Activity Northwest; Leicht, G. [Navy, Bremerton, WA (United States)

    1996-12-31T23:59:59.000Z

    Dredge spoils, industrial fill, and liquid wastes from the 1940s to 1970s have resulted in inorganic and organic contamination of soils, groundwater, and marine sediments near the U.S.S. Missouri and Charleston Beach parking lots at Puget Sound Naval Shipyard (PSNS), in Bremerton, Washington. Extensive collection of environmental data from several studies including the recently completed Remedial Investigation conducted under CERCLA have confirmed contaminant levels above federal risk screening levels and state regulatory criteria for several heavy metals and organic compounds, including pesticides and PCBs. Although the correlation between contamination in marine sediments and those in on-shore fill appears to be strong, there is little evidence that a viable transport pathway currently exists from soils to groundwater and thence to sediments. Several methods used to estimate chemical mass flux from soil to groundwater to sediments and marine waters of Sinclair Inlet are corroborative in this regard. Nonetheless, this result is vexing because present groundwater concentrations exceed ARARs, yet are below levels of concern in terms of mass flux to marine waters. Despite the marginal risks posed by groundwater, various remedial alternatives, including perimeter containment using a subsurface waste-stabilized containment wall, were evaluated to determine whether chemical flux could be reduced to levels below those observed at the present time. Three-dimensional flow modelling and transport modelling also confirmed that chemical fluxes were limited in magnitude and could be addressed with more conventional remedial approaches.

  7. Summary and evaluation of the coyote control program on Naval Petroleum Reserve No. 1, Kern County, California, 1987

    SciTech Connect (OSTI)

    Scrivner, J.H.

    1987-09-01T23:59:59.000Z

    For the third consecutive year (1987) the US Department of Energy (DOE) funded a coyote (Canis latrans) control program in an attempt to reduce coyote predation on the endangered San Joaquin kit fox (Vulpes macrotis mutica) on Naval Petroleum Reserve No. 1 (NPR-1, Elk Hills) in Kern County, California. During approximately 8 weeks of control activities, personnel from the US Department of Agriculture, Division of Animal Damage Control (ADC), removed 16 adult coyotes: 14 were trapped, 2 were shot. Data were gathered on standard measurements, weights, ages, and reproductive condition. No kit foxes were accidently trapped. Based on the results of canid scent-station surveys, the coyote population on NPR-1 declined and the kit fox population was relatively stable. Recommendations were made to conduct the 1987/1988 coyote control program between December 1987 and February 1988, use helicopters for aerial gunning and locating coyote dens, and develop a cooperative agreement between DOE, ADC, US Fish and Wildlife Service, Bureau of Land Management, and the California Department of Fish and Game to conduct the coyote control program on lands surrounding NPR-1 owned by DOE and others. 8 refs., 2 figs., 2 tabs.

  8. U.S. Department of Energy Naval Petroleum Reserve Number 1 quarterly financial statements, December 31, 1996 and 1995

    SciTech Connect (OSTI)

    NONE

    1997-03-18T23:59:59.000Z

    The report presents the results of the independent certified public accountants` review of the Department of Energy`s Naval Petroleum Reserve Number 1 interim financial statements as of December 31, 1996 and 1995. The review was done in accordance with Statements on Standards for Accounting and Review Services issued by the American Institute of Certified Public Accountants. A review of interim financial statements consists principally of inquiries of NPR-1 personnel and analytical procedures applied to financial data. It is substantially less in scope than an audit in accordance with generally accepted auditing standards, the objective of which is the expression of an opinion regarding the financial statements take as a whole. Accordingly, the certified public accountants do not express such an opinion. The auditors have stated that, except for the omission of certain disclosures, they are not aware of any material modifications that should be made to the financial statements in order for them to be in conformity with the other comprehensive basis of accounting described in Note 1 to the financial statements.

  9. U.S. Department of Energy Naval Petroleum Reserve Number 1 quarterly financial statements, March 31, 1997 and 1996

    SciTech Connect (OSTI)

    NONE

    1997-04-17T23:59:59.000Z

    The report presents the results of the independent certified public accountants` review of the Department of Energy`s Naval Petroleum Reserve Number 1 interim financial statements as of March 31, 1997 and 1996. The review was done in accordance with Statements on Standards for Accounting and Review Services issued by the American Institute of Certified Public Accountants. A review of interim financial statements consist principally of inquires of NPR-1 personnel and analytical procedures applied to financial data. It is substantially less in scope than an audit in accordance with generally accepted auditing standards, the objective of which is the expression of an opinion regarding the financial statements taken as a whole. Accordingly, the certified public accountants do not express such an opinion. The auditors have stated that, except for the omission of certain disclosures, they are not aware of any material modifications that should be made to the financial statements in order for them to be in conformity with the other comprehensive basis of accounting described in Note 1 to the financial statements.

  10. Nuclear reactor engineering: Reactor design basics. Fourth edition, Volume One

    SciTech Connect (OSTI)

    Glasstone, S.; Sesonske, A.

    1994-12-31T23:59:59.000Z

    This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in design and operation of nuclear power plants. Extensively updated, the fourth edition includes new material on reactor safety and risk analysis, regulation, fuel management, waste management, and operational aspects of nuclear power. This volume contains the following: energy from nuclear fission; nuclear reactions and radiations; neutron transport; nuclear design basics; nuclear reactor kinetics and control; radiation protection and shielding; and reactor materials.

  11. University Reactor Conversion Lessons Learned Workshop for Purdue University Reactor

    SciTech Connect (OSTI)

    Eric C. Woolstenhulme; Dana M. Hewit

    2008-09-01T23:59:59.000Z

    The Department of Energy’s Idaho National Laboratory, under its programmatic responsibility for managing the University Research Reactor Conversions, has completed the conversion of the reactor at Purdue University Reactor. With this work completed and in anticipation of other impending conversion projects, the INL convened and engaged the project participants in a structured discussion to capture the lessons learned. The lessons learned process has allowed us to capture gaps, opportunities, and good practices, drawing from the project team’s experiences. These lessons will be used to raise the standard of excellence, effectiveness, and efficiency in all future conversion projects.

  12. Nuclear reactor control

    DOE Patents [OSTI]

    Cawley, William E. (Phoenix, AZ); Warnick, Robert F. (Pasco, WA)

    1982-01-01T23:59:59.000Z

    1. In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

  13. Nuclear reactor control apparatus

    DOE Patents [OSTI]

    Sridhar, Bettadapur N. (Cupertino, CA)

    1983-10-25T23:59:59.000Z

    Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

  14. Nuclear reactor control

    SciTech Connect (OSTI)

    Cawley, W.E.; Warnick, R.F.

    1982-03-30T23:59:59.000Z

    In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

  15. United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support

    SciTech Connect (OSTI)

    Douglas Morrell

    2011-03-01T23:59:59.000Z

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  16. Reactor protection system design alternatives for sodium fast reactors

    E-Print Network [OSTI]

    DeWitte, Jacob D. (Jacob Dominic)

    2011-01-01T23:59:59.000Z

    Historically, unprotected transients have been viewed as design basis events that can significantly challenge sodium-cooled fast reactors. The perceived potential consequences of a severe unprotected transient in a ...

  17. Reactor physics design of supercritical CO?-cooled fast reactors

    E-Print Network [OSTI]

    Pope, Michael A. (Michael Alexander)

    2004-01-01T23:59:59.000Z

    Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO? (S-CO?) as a Brayton cycle working fluid in a direct ...

  18. Nuclear reactor downcomer flow deflector

    DOE Patents [OSTI]

    Gilmore, Charles B. (Greensburg, PA); Altman, David A. (Pittsburgh, PA); Singleton, Norman R. (Murrysville, PA)

    2011-02-15T23:59:59.000Z

    A nuclear reactor having a coolant flow deflector secured to a reactor core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the reactor vessel. The deflector has a main body with a front side facing the fluid inlet nozzle and a rear side facing the core barrel. The rear side of the main body has at least one protrusion secured to the core barrel so that a gap exists between the rear side of the main body adjacent the protrusion and the core barrel. Preferably, the protrusion is a relief that circumscribes the rear side of the main body.

  19. 2012 Annual Report Research Reactor Infrastructure Program

    SciTech Connect (OSTI)

    Douglas Morrell

    2012-11-01T23:59:59.000Z

    The content of this report is the 2012 Annual Report for the Research Reactor Infrastructure Program.

  20. How far is a Fusion Power Reactor from an Experimental Reactor?

    E-Print Network [OSTI]

    1 How far is a Fusion Power Reactor from an Experimental Reactor? R. Toschi(1) , P. Barabaschi(2 September 2000 Madrid, Spain #12;2 How far is a fusion power reactor from an experimental reactor? R. Toschi To support a request of very substantial resources to build and operate an experimental reactor such as ITER

  1. Distribution ICategory: General Reactor Technology

    E-Print Network [OSTI]

    Shlyakhter, Ilya

    --- Distribution ICategory: General Reactor Technology (UC-520) ANl-92/23 AR(;ONNE NATIONAL, progressively by Huygens, Maxwell and Roentgen, mankind has learned to observe it, measure it, control it

  2. Spectral shift reactor control method

    SciTech Connect (OSTI)

    Impink, A.J. Jr.

    1987-08-18T23:59:59.000Z

    The method is described of closely controlling the reactor water coolant temperature of an operating spectral-shift nuclear reactor, the reactor comprising a core formed of fuel assemblies through which the reactor water coolant flows; different types of elongated elements operable to be controllably moved into and out of the core; one type of the elongated elements comprising control rods formed of neutron absorbing material and operable to decrease reactivity through neutron absorption when inserted into the core; another of the types of elongated elements comprising displacer rods formed of material which has a low absorption for neutrons and which have overall neutron-absorbing and moderating characteristics essentially not exceeding those of hollow tubular Zircaloy members with a filling zirconium oxide or aluminum oxide, the displacer rods operating to displace an equivalent volume of water coolant fluid from the core when inserted therein to decrease reactivity and to increase reactivity when moved from the core.

  3. University Reactor Matching Grants Program

    SciTech Connect (OSTI)

    John Valentine; Farzad Rahnema; Said Abdel-Khalik

    2003-02-14T23:59:59.000Z

    During the 2002 Fiscal year, funds from the DOE matching grant program, along with matching funds from the industrial sponsors, have been used to support research in the area of thermal-hydraulics. Both experimental and numerical research projects have been performed. Experimental research focused on two areas: (1) Identification of the root cause mechanism for axial offset anomaly in pressurized water reactors under prototypical reactor conditions, and (2) Fluid dynamic aspects of thin liquid film protection schemes for inertial fusion reactor chambers. Numerical research focused on two areas: (1) Multi-fluid modeling of both two-phase and two-component flows for steam conditioning and mist cooling applications, and (2) Modeling of bounded Rayleigh-Taylor instability with interfacial mass transfer and fluid injection through a porous wall simulating the ''wetted wall'' protection scheme in inertial fusion reactor chambers. Details of activities in these areas are given.

  4. Reactor physics project final report

    E-Print Network [OSTI]

    Driscoll, Michael J.

    1970-01-01T23:59:59.000Z

    This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...

  5. Combustion synthesis continuous flow reactor

    DOE Patents [OSTI]

    Maupin, G.D.; Chick, L.A.; Kurosky, R.P.

    1998-01-06T23:59:59.000Z

    The present invention is a reactor for combustion synthesis of inorganic powders. The reactor includes a reaction vessel having a length and a first end and a second end. The reaction vessel further has a solution inlet and a carrier gas inlet. The reactor further has a heater for heating both the solution and the carrier gas. In a preferred embodiment, the reaction vessel is heated and the solution is in contact with the heated reaction vessel. It is further preferred that the reaction vessel be cylindrical and that the carrier gas is introduced tangentially into the reaction vessel so that the solution flows helically along the interior wall of the reaction vessel. As the solution evaporates and combustion produces inorganic material powder, the carrier gas entrains the powder and carries it out of the reactor. 10 figs.

  6. Advanced Catalytic Hydrogenation Retrofit Reactor

    SciTech Connect (OSTI)

    Reinaldo M. Machado

    2002-08-15T23:59:59.000Z

    Industrial hydrogenation is often performed using a slurry catalyst in large stirred-tank reactors. These systems are inherently problematic in a number of areas, including industrial hygiene, process safety, environmental contamination, waste production, process operability and productivity. This program proposed the development of a practical replacement for the slurry catalysts using a novel fixed-bed monolith catalyst reactor, which could be retrofitted onto an existing stirred-tank reactor and would mitigate many of the minitations and problems associated with slurry catalysts. The full retrofit monolith system, consisting of a recirculation pump, gas/liquid ejector and monolith catalyst, is described as a monolith loop reactor or MLR. The MLR technology can reduce waste and increase raw material efficiency, which reduces the overall energy required to produce specialty and fine chemicals.

  7. Teaching About Nature's Nuclear Reactors

    E-Print Network [OSTI]

    Herndon, J M

    2005-01-01T23:59:59.000Z

    Naturally occurring nuclear reactors existed in uranium deposits on Earth long before Enrico Fermi built the first man-made nuclear reactor beneath Staggs Field in 1942. In the story of their discovery, there are important lessons to be learned about scientific inquiry and scientific discovery. Now, there is evidence to suggest that the Earth's magnetic field and Jupiter's atmospheric turbulence are driven by planetary-scale nuclear reactors. The subject of planetocentric nuclear fission reactors can be a jumping off point for stimulating classroom discussions about the nature and implications of planetary energy sources and about the geomagnetic field. But more importantly, the subject can help to bring into focus the importance of discussing, debating, and challenging current thinking in a variety of areas.

  8. Nuclear Reactors and Technology; (USA)

    SciTech Connect (OSTI)

    Cason, D.L.; Hicks, S.C. (eds.)

    1991-01-01T23:59:59.000Z

    Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  9. Reactor core isolation cooling system

    DOE Patents [OSTI]

    Cooke, Franklin E. (San Jose, CA)

    1992-01-01T23:59:59.000Z

    A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom.

  10. Reactor core isolation cooling system

    DOE Patents [OSTI]

    Cooke, F.E.

    1992-12-08T23:59:59.000Z

    A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom. 1 figure.

  11. Interfacial effects in fast reactors

    E-Print Network [OSTI]

    Saidi, Mohammad Said

    1979-01-01T23:59:59.000Z

    The problem of increased resonance capture rates near zone interfaces in fast reactor media has been examined both theoretically and experimentally. An interface traversing assembly was designed, constructed and employed ...

  12. Solid State Reactor Final Report

    SciTech Connect (OSTI)

    Mays, G.T.

    2004-03-10T23:59:59.000Z

    The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas of research were undertaken: (1) establishing the design and safety-related basis via neutronic and reactor control assessments with the graphite foam as heat transfer medium; (2) evaluating the thermal performance of the graphite foam for heat removal, reactor stability, reactor operations, and overall core thermal characteristics; (3) characterizing the physical properties of the graphite foam under normal and irradiated conditions to determine any effects on structure, dimensional stability, thermal conductivity, and thermal expansion; and (4) developing a power conversion system design to match the reactor operating parameters.

  13. Alternate-fuel reactor studies

    SciTech Connect (OSTI)

    Evans, K. Jr.; Ehst, D.A.; Gohar, Y.; Jung, J.; Mattas, R.F.; Turner, L.R.

    1983-02-01T23:59:59.000Z

    A number of studies related to improvements and/or greater understanding of alternate-fueled reactors is presented. These studies cover the areas of non-Maxwellian distributions, materials and lifetime analysis, a /sup 3/He-breeding blanket, tritium-rich startup effects, high field magnet support, and reactor operation spanning the range from full D-T operation to operation with no tritium breeding.

  14. Automatic safety rod for reactors

    DOE Patents [OSTI]

    Germer, John H. (San Jose, CA)

    1988-01-01T23:59:59.000Z

    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.

  15. Fast quench reactor and method

    DOE Patents [OSTI]

    Detering, Brent A. (Idaho Falls, ID); Donaldson, Alan D. (Idaho Falls, ID); Fincke, James R. (Idaho Falls, ID); Kong, Peter C. (Idaho Falls, ID)

    1998-01-01T23:59:59.000Z

    A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a restrictive convergent-divergent nozzle at its outlet end. Reactants are injected into the reactor chamber. The resulting heated gaseous stream is then rapidly cooled by passage through the nozzle. This "freezes" the desired end product(s) in the heated equilibrium reaction stage.

  16. Propellant actuated nuclear reactor steam depressurization valve

    DOE Patents [OSTI]

    Ehrke, Alan C. (San Jose, CA); Knepp, John B. (San Jose, CA); Skoda, George I. (Santa Clara, CA)

    1992-01-01T23:59:59.000Z

    A nuclear fission reactor combined with a propellant actuated depressurization and/or water injection valve is disclosed. The depressurization valve releases pressure from a water cooled, steam producing nuclear reactor when required to insure the safety of the reactor. Depressurization of the reactor pressure vessel enables gravity feeding of supplementary coolant water through the water injection valve to the reactor pressure vessel to prevent damage to the fuel core.

  17. When Do Commercial Reactors Permanently Shut Down?

    Reports and Publications (EIA)

    2011-01-01T23:59:59.000Z

    For those wishing to obtain current data, the following resources are available: U.S. reactors, go to the Energy Information Administration's nuclear reactor shutdown list. (Note: As of April 30, 2010, the last U.S. reactor to permanently shut down was Big Rock Point in 1997.) Foreign Reactors, go to the Power Reactor Information System (PRIS) on the International Atomic Energy Agency's website.

  18. Nuclear reactor control rod

    SciTech Connect (OSTI)

    Cearley, J.E.; Izzo, K.R.

    1987-06-30T23:59:59.000Z

    This patent describes a vertically oriented bottom entry control rod from a nuclear reactor: a frame including an elongated central spine of cruciform cross section connected between an upper support member and a lower support member both of cruciform shape having four laterally extending arms. The arms are in alignment with the arms of the lower support member and each aligned upper and lower support members has a sheath extending between; absorber plates of neutron absorber material, different from the material of the frame, one of the absorber plates is positioned within a sheath beneath each of the arms; attachment means suspends the absorber plates from the arms of the upper support member within a sheath; elongated absorber members positioned within a sheath between each of the suspended absorber plates and an arm of the lower support member; and joint means between the upper ends of the absorber members and the lower ends of the suspended absorber plates for minimizing gaps; the sheath means encloses the suspended absorber plates and the absorber members extending between aligned arms of the upper and lower support members and secured.

  19. Reactor pressure vessel nozzle

    DOE Patents [OSTI]

    Challberg, R.C.; Upton, H.A.

    1994-10-04T23:59:59.000Z

    A nozzle for joining a pool of water to a nuclear reactor pressure vessel includes a tubular body having a proximal end joinable to the pressure vessel and a distal end joinable in flow communication with the pool. The body includes a flow passage therethrough having in serial flow communication a first port at the distal end, a throat spaced axially from the first port, a conical channel extending axially from the throat, and a second port at the proximal end which is joinable in flow communication with the pressure vessel. The inner diameter of the flow passage decreases from the first port to the throat and then increases along the conical channel to the second port. In this way, the conical channel acts as a diverging channel or diffuser in the forward flow direction from the first port to the second port for recovering pressure due to the flow restriction provided by the throat. In the backflow direction from the second port to the first port, the conical channel is a converging channel and with the abrupt increase in flow area from the throat to the first port collectively increase resistance to flow therethrough. 2 figs.

  20. Reactor shroud joint

    DOE Patents [OSTI]

    Ballas, G.J.; Fife, A.B.; Ganz, I.

    1998-04-07T23:59:59.000Z

    A shroud for a nuclear reactor is described. In one embodiment, the shroud includes first and second shroud sections, and each shroud section includes a substantially cylindrical main body having a first end and a second end. With respect to each shroud section, a flange is located at the main body first end, and the flange has a plurality of bolt openings therein and a plurality of scalloped regions. The first shroud section is welded to the second shroud section, and at least some of the bolt openings in the first shroud section flange align with respective bolt openings in the second shroud section flange. In the event that the onset of inter-granular stress corrosion cracking is ever detected in the weld between the shroud section, bolts are inserted through bolt openings in the first shroud section flange and through aligned bolt openings the second shroud section flange. Each bolt, in one embodiment, has a shank section and first and second threaded end sections. Nuts are threadedly engaged to the threaded end sections and tightened against the respective flanges. 4 figs.

  1. Solar solids reactor

    DOE Patents [OSTI]

    Yudow, B.D.

    1986-02-24T23:59:59.000Z

    A solar powered kiln is provided, that is of relatively simple design and which efficiently uses solar energy. The kiln or solids reactor includes a stationary chamber with a rearward end which receives solid material to be reacted and a forward end through which reacted material is disposed of, and a screw conveyor extending along the bottom of the chamber for slowly advancing the material between the chamber ends. Concentrated solar energy is directed to an aperture at the forward end of the chamber to heat the solid material moving along the bottom of the chamber. The solar energy can be reflected from a mirror facing at an upward incline, through the aperture and against a heat-absorbing material near the top of the chamber, which moves towards the rear of the chamber to distribute heat throughout the chamber. Pumps at the forward and rearward ends of the chamber pump heated sweep gas through the length of the chamber, while minimizing the flow of gas through an open aperture through which concentrated sunlight is received.

  2. Solar solids reactor

    DOE Patents [OSTI]

    Yudow, Bernard D. (Chicago, IL)

    1987-01-01T23:59:59.000Z

    A solar powered kiln is provided, that is of relatively simple design and which efficiently uses solar energy. The kiln or solids reactor includes a stationary chamber with a rearward end which receives solid material to be reacted and a forward end through which reacted material is disposed of, and a screw conveyor extending along the bottom of the chamber for slowly advancing the material between the chamber ends. Concentrated solar energy is directed to an aperture at the forward end of the chamber to heat the solid material moving along the bottom of the chamber. The solar energy can be reflected from a mirror facing at an upward incline, through the aperture and against a heat-absorbing material near the top of the chamber, which moves towards the rear of the chamber to distribute heat throughout the chamber. Pumps at the forward and rearward ends of the chamber pump heated sweep gas through the length of the chamber, while minimizing the flow of gas through an open aperture through which concentrated sunlight is received.

  3. Novel Catalytic Membrane Reactors

    SciTech Connect (OSTI)

    Stuart Nemser, PhD

    2010-10-01T23:59:59.000Z

    There are many industrial catalytic organic reversible reactions with amines or alcohols that have water as one of the products. Many of these reactions are homogeneously catalyzed. In all cases removal of water facilitates the reaction and produces more of the desired chemical product. By shifting the reaction to right we produce more chemical product with little or no additional capital investment. Many of these reactions can also relate to bioprocesses. Given the large number of water-organic compound separations achievable and the ability of the Compact Membrane Systems, Inc. (CMS) perfluoro membranes to withstand these harsh operating conditions, this is an ideal demonstration system for the water-of-reaction removal using a membrane reactor. Enhanced reaction synthesis is consistent with the DOE objective to lower the energy intensity of U.S. industry 25% by 2017 in accord with the Energy Policy Act of 2005 and to improve the United States manufacturing competitiveness. The objective of this program is to develop the platform technology for enhancing homogeneous catalytic chemical syntheses.

  4. Reproduction of the San Joaquin kit fox on Naval Petroleum Reserve No. 1, Elk Hills, California: 1980-1985

    SciTech Connect (OSTI)

    Zoellick, B.W.; O'Farrell, T.P.; McCue, P.M.; Harris, C.E.; Kato, T.T.

    1987-01-01T23:59:59.000Z

    Reproduction of the San Joaquin kit fox (Vulpes macrotis mutica) was studied in areas of petroleum development and areas relatively undisturbed by development on and adjacent to Elk Hills Naval Petroleum Reserve No. 1 (NPR-1), California from 1980-1985. Pregnancy rates of adults did not differ between habitats (93 to 100%), but the yearling pregnancy rate in developed habitat (56%) was lower than the adult rates and the yearling rate for undeveloped habitat (100%). Mean corpora lutea and placental scar counts did not differ between undeveloped and developed habitats, but adults had greater corpora lutea and placental scar counts than yearlings. Litter sizes averaged 4.1 and 4.4 for undeveloped and developed habitats respectively from 1980-1985 and did not differ between years or habitats. Mean number of litters observed per square mile during 1980-1985 did not differ between undeveloped (0.34) and developed habitats (0.29). The percentage of all females successfully raising pups in developed habitat declined significantly from 1980-1985 in comparison with the percent success of females in undeveloped habitat. Numbers of litters per square mile in developed habitat also declined significantly after 1981. The sex ratio of pups trapped in developed habitat was skewed towards males during the decline in litters produced per square mile from 1982-1985, but the ratio of males to females in undeveloped habitat did not differ from 1:1 during this time. The decline in some measures of reproductive success in developed habitat after 1981 coincided with a decrease in black-tailed jackrabbit and desert cottontail numbers on the NPR-1 study area. The decreased reproductive success of foxes in developed habitat after 1981 may have resulted from habitat degradation caused by oil field production activities, declining lagomorph numbers, or other unknown causes. 49 refs., 7 figs., 8 tabs.

  5. Joint environmental assessment for western NPR-1 3-dimensional seismic project at Naval Petroleum Reserve No. 1, Kern County, California

    SciTech Connect (OSTI)

    NONE

    1996-05-01T23:59:59.000Z

    The Department of Energy (DOE), in conjunction with the Bureau of Land Management (BLM), has prepared an Environmental Assessment (DOE/EA-1124) to identify and evaluate the potential environmental impacts of the proposed geophysical seismic survey on and adjacent to the Naval Petroleum Reserve No.1 (NPR-1), located approximately 35 miles west of Bakersfield, California. NPR-1 is jointly owned and operated by the federal government and Chevron U.S.A. Production Company. The federal government owns about 78 percent of NPR-1, while Chevron owns the remaining 22 percent. The government`s interest is under the jurisdiction of DOE, which has contracted with Bechtel Petroleum Operations, Inc. (BPOI) for the operation and management of the reserve. The 3-dimensional seismic survey would take place on NPR-1 lands and on public and private lands adjacent to NPR-1. This project would involve lands owned by BLM, California Department of Fish and Game (CDFG), California Energy Commission (CEC), The Nature Conservancy, the Center for Natural Lands Management, oil companies (Chevron, Texaco, and Mobil), and several private individuals. The proposed action is designed to provide seismic data for the analysis of the subsurface geology extant in western NPR-1 with the goal of better defining the commercial limits of a currently producing reservoir (Northwest Stevens) and three prospective hydrocarbon bearing zones: the {open_quotes}A Fan{close_quotes} in Section 7R, the 19R Structure in Section 19R, and the 13Z Structure in Section 13Z. Interpreting the data is expected to provide NPR-1 owners with more accurate locations of structural highs, faults, and pinchouts to maximize the recovery of the available hydrocarbon resources in western NPR-1. Completion of this project is expected to increase NPR-1 recoverable reserves, and reduce the risks and costs associated with further exploration and development in the area.

  6. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation

    E-Print Network [OSTI]

    Heidet, Florent

    2010-01-01T23:59:59.000Z

    selected as part of the Generation IV reactors .. - 4 -The development of Generation IV fast reactors can make aconcepts selected for the Generation IV reactors, three,

  7. Uncertainties in the Anti-neutrino Production at Nuclear Reactors

    E-Print Network [OSTI]

    Djurcic, Zelimir

    2009-01-01T23:59:59.000Z

    neutrino Production at Nuclear Reactors Z. Djurcic 1 , ?emission rates from nuclear reactors are determined fromlarge commercial nuclear reactors are playing an important

  8. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors

    E-Print Network [OSTI]

    Terrani, Kurt Amir

    2010-01-01T23:59:59.000Z

    Fundamental aspects of nuclear reactor fuel elements.Unlike permanent nuclear reactor core components, nuclearof the first nuclear reactors, commercial nuclear fuel still

  9. PIA - Advanced Test Reactor National Scientific User Facility...

    Energy Savers [EERE]

    Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor National Scientific User Facility Users Week 2009 PIA - Advanced Test Reactor...

  10. acid immunoaffinity reactor: Topics by E-print Network

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

    sludge blanket reactors (more) Ning, Zuojun. 2009-01-01 8 Inexpensive Mini Thermonuclear Reactor CiteSeer Summary: This proposed design for a mini thermonuclear reactor...

  11. MULTIPHASE REACTOR MODELING FOR ZINC CHLORIDE CATALYZED COAL LIQUEFACTION

    E-Print Network [OSTI]

    Joyce, Peter James

    2011-01-01T23:59:59.000Z

    II. c. High Yield Batch Reactor Results. . . • .Objectives •. Slurry Reactors . . . . . . .A. StudiesSystems. D. Slurry Reactor Theory. General. . Application to

  12. Superfund record of decision (EPA Region 3): Patuxent River Naval Air Station, St. Mary`s County, MD, July 29, 1996

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    The decision document presents the selected interim remedial action for Operable Unit 1 (OU1) of the Former Sanitary Landfill site, at the U.S. Naval Air Station Patuxent River, MD. The interim remedy will reduce the potential of human exposure to wastes remaining at the landfill, precipitation filtering through landfill waste, and the potential risk posed by inhalation and ingestion of contaminated surficial soil at the landfill. The interim action will allow for the continued investigation of the landfill while evaluating final remedial options for groundwater, surface water, and sediment at the site.

  13. Naval Station Newport Wind Resource Assessment. A Study Prepared in Partnership with the Environmental Protection Agency for the RE-Powering America's Land Initiative: Siting Renewable Energy on Potentially Contaminated Land and Mine Sites, and The Naval Facilities Engineering Service Center

    SciTech Connect (OSTI)

    Robichaud, R.; Fields, J.; Roberts, J. O.

    2012-02-01T23:59:59.000Z

    The U.S. Environmental Protection Agency (EPA) launched the RE-Powering America's Land initiative to encourage development of renewable energy (RE) on potentially contaminated land and mine sites. EPA is collaborating with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to evaluate RE options at Naval Station (NAVSTA) Newport in Newport, Rhode Island where multiple contaminated areas pose a threat to human health and the environment. Designated a superfund site on the National Priorities List in 1989, the base is committed to working toward reducing the its dependency on fossil fuels, decreasing its carbon footprint, and implementing RE projects where feasible. The Naval Facilities Engineering Service Center (NFESC) partnered with NREL in February 2009 to investigate the potential for wind energy generation at a number of Naval and Marine bases on the East Coast. NAVSTA Newport was one of several bases chosen for a detailed, site-specific wind resource investigation. NAVSTA Newport, in conjunction with NREL and NFESC, has been actively engaged in assessing the wind resource through several ongoing efforts. This report focuses on the wind resource assessment, the estimated energy production of wind turbines, and a survey of potential wind turbine options based upon the site-specific wind resource.

  14. International Research Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Leopando, Leonardo [Philippine Nuclear Research Institute, Quezon City (Philippines); Warnecke, Ernst [International Atomic Energy Agency, Vienna (Austria)

    2008-01-15T23:59:59.000Z

    Many research reactors have been or will be shut down and are candidates for decommissioning. Most of the respective countries neither have a decommissioning policy nor the required expertise and funds to effectively implement a decommissioning project. The IAEA established the Research Reactor Decommissioning Demonstration Project (R{sup 2}D{sup 2}P) to help answer this need. It was agreed to involve the Philippine Research Reactor (PRR-1) as model reactor to demonstrate 'hands-on' experience as it is just starting the decommissioning process. Other facilities may be included in the project as they fit into the scope of R{sup 2}D{sup 2}P and complement to the PRR-1 decommissioning activities. The key outcome of the R{sup 2}D{sup 2}P will be the decommissioning of the PRR-1 reactor. On the way to this final goal the preparation of safety related documents (i.e., decommissioning plan, environmental impact assessment, safety analysis report, health and safety plan, cost estimate, etc.) and the licensing process as well as the actual dismantling activities could provide a model to other countries involved in the project. It is expected that the R{sup 2}D{sup 2}P would initiate activities related to planning and funding of decommissioning activities in the participating countries if that has not yet been done.

  15. Rapid starting methanol reactor system

    DOE Patents [OSTI]

    Chludzinski, Paul J. (38 Berkshire St., Swampscott, MA 01907); Dantowitz, Philip (39 Nancy Ave., Peabody, MA 01960); McElroy, James F. (12 Old Cart Rd., Hamilton, MA 01936)

    1984-01-01T23:59:59.000Z

    The invention relates to a methanol-to-hydrogen cracking reactor for use with a fuel cell vehicular power plant. The system is particularly designed for rapid start-up of the catalytic methanol cracking reactor after an extended shut-down period, i.e., after the vehicular fuel cell power plant has been inoperative overnight. Rapid system start-up is accomplished by a combination of direct and indirect heating of the cracking catalyst. Initially, liquid methanol is burned with a stoichiometric or slightly lean air mixture in the combustion chamber of the reactor assembly. The hot combustion gas travels down a flue gas chamber in heat exchange relationship with the catalytic cracking chamber transferring heat across the catalyst chamber wall to heat the catalyst indirectly. The combustion gas is then diverted back through the catalyst bed to heat the catalyst pellets directly. When the cracking reactor temperature reaches operating temperature, methanol combustion is stopped and a hot gas valve is switched to route the flue gas overboard, with methanol being fed directly to the catalytic cracking reactor. Thereafter, the burner operates on excess hydrogen from the fuel cells.

  16. Imaging Fukushima Daiichi reactors with muons

    SciTech Connect (OSTI)

    Miyadera, Haruo; Borozdin, Konstantin N.; Greene, Steve J.; Milner, Edward C.; Morris, Christopher L. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Lukic, Zarija [Computational Cosmology Center, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States); Masuda, Koji [University of New Mexico, Albuquerque, NM 87131 (United States); Perry, John O. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); University of New Mexico, Albuquerque, NM 87131 (United States)

    2013-05-15T23:59:59.000Z

    A study of imaging the Fukushima Daiichi reactors with cosmic-ray muons to assess the damage to the reactors is presented. Muon scattering imaging has high sensitivity for detecting uranium fuel and debris even through thick concrete walls and a reactor pressure vessel. Technical demonstrations using a reactor mockup, detector radiation test at Fukushima Daiichi, and simulation studies have been carried out. These studies establish feasibility for the reactor imaging. A few months of measurement will reveal the spatial distribution of the reactor fuel. The muon scattering technique would be the best and probably the only way for Fukushima Daiichi to make this determination in the near future.

  17. Speciation and Fate of Trace Metals in Estuarine Sediments Under Reduced and Oxidized Conditions, Seaplane Lagoon, Alameda Naval Air Station

    SciTech Connect (OSTI)

    Carroll, S A; Day, P A; Esser, B; Randall, S

    2002-10-18T23:59:59.000Z

    We have identified important chemical reactions that control the fate of metal-contaminated estuarine sediments if they are left undisturbed (in situ) or if they are dredged. We combined information on the molecular bonding of metals in solids from X-ray absorption spectroscopy (XAS) with thermodynamic and kinetic driving forces obtained from dissolved metal concentrations to deduce the dominant reactions under reduced and oxidized conditions. We evaluated the in situ geochemistry of metals (cadmium, chromium, iron, lead, manganese and zinc) as a function of sediment depth (to 100 cm) from a 60-year record of contamination at the Alameda Naval Air Station, California. Results from XAS and thermodynamic modeling of porewaters show that cadmium and most of the zinc form stable sulfide phases, and that lead and chromium are associated with stable carbonate, phosphate, phyllosilicate, or oxide minerals. Therefore, there is minimal risk associated with the release of these trace metals from the deeper sediments contaminated prior to the Clean Water Act (1975) as long as reducing conditions are maintained. Increased concentrations of dissolved metals with depth were indicative of the formation of metal HS- complexes. The sediments also contain zinc, chromium, and manganese associated with detrital iron-rich phyllosilicates and/or oxides. These phases are recalcitrant at near-neutral pH and do not undergo reductive dissolution within the 60-year depositional history of sediments at this site. The fate of these metals during dredging was evaluated by comparing in situ geochemistry with that of sediments oxidized by seawater in laboratory experiments. Cadmium and zinc pose the greatest hazard from dredging because their sulfides were highly reactive in seawater. However, their dissolved concentrations under oxic conditions were limited eventually by sorption to or co-precipitation with an iron (oxy)hydroxide. About 50% of the reacted CdS and 80% of the reacted ZnS were bonded to an oxide-substrate at the end of the 90-day oxidation experiment. Lead and chromium pose a minimal hazard from dredging because they are bonded to relatively insoluble carbonate, phosphate, phyllosilicate, or oxide minerals that are stable in seawater. These results point out the specific chemical behavior of individual metals in estuarine sediments, and the need for direct confirmation of metal speciation in order to constrain predictive models that realistically assess the fate of metals in urban harbors and coastal sediments.

  18. Five-year resurvey for endangered species on Naval Petroleum Reserve No. 1, (Elk Hills), Kern County, California

    SciTech Connect (OSTI)

    Otten, M.R.M.; O`Farrell, T.P.; Briden, L.E.

    1992-06-01T23:59:59.000Z

    A transect survey of Naval Petroleum Reserve No. 1 (NPR-1), Kern County, California, was conducted between July 3 and August 5, 1989 to determine the distribution and relative density of endangered species and other wildlife. Results were compared with other reported results, particularly the 1979 and 1984 surveys of NPR-1. A total of 589.8 miles of transects were walked through approximately 47,235 acres in all or parts of 81 sections. Of the 516 San Joaquin kit fox dens observed, 496 were typical subterranean dens and 20 were atypical dens in man-made structures. Estimated den density was 36.7 {plus_minus} 4.1 per square mile; and relative den density was 10.5/1,000 acres for all of NPR-1. Characteristics of typical kit fox dens were comparable to characteristics reported for other studies, except mean number of entrances per den, which was lower. Observers counted a total of 300 dens previously marked with an identification sign, 191 of which contained at least one complete entrance and would have been observed without a sign. Relative densities of preferred kit fox prey, black-toiled jackrabbits (40.1/1,000 acres) and desert cottontails (14.1/1,000 acres), were lower than previously recorded. Five blunt-nosed leopard lizards were observed along the southwest and northeast perimeter of the Reserve. Most of the 59 giant kangaroo rat burrow systems were observed in the flat terrain along the northeast and south perimeters of the Reserve. San Joaquin antelope squirrels were observed in the central and western parts of NPR- 1. A total of 73 antelope squirrels were observed, and the relative density was 1.511,000 acres. A total.of 30 possible environmental hazards were observed during transect surveys. Most of these were oil and water leaks of small size and appeared to pose little risk to endangered species. Results of this survey indicate that NPR-1 is supporting less wildlife than it did during either the 1979 or 1984 surveys.

  19. Five-year resurvey for endangered species on Naval Petroleum Reserve No. 1, (Elk Hills), Kern County, California

    SciTech Connect (OSTI)

    Otten, M.R.M.; O'Farrell, T.P.; Briden, L.E.

    1992-06-01T23:59:59.000Z

    A transect survey of Naval Petroleum Reserve No. 1 (NPR-1), Kern County, California, was conducted between July 3 and August 5, 1989 to determine the distribution and relative density of endangered species and other wildlife. Results were compared with other reported results, particularly the 1979 and 1984 surveys of NPR-1. A total of 589.8 miles of transects were walked through approximately 47,235 acres in all or parts of 81 sections. Of the 516 San Joaquin kit fox dens observed, 496 were typical subterranean dens and 20 were atypical dens in man-made structures. Estimated den density was 36.7 [plus minus] 4.1 per square mile; and relative den density was 10.5/1,000 acres for all of NPR-1. Characteristics of typical kit fox dens were comparable to characteristics reported for other studies, except mean number of entrances per den, which was lower. Observers counted a total of 300 dens previously marked with an identification sign, 191 of which contained at least one complete entrance and would have been observed without a sign. Relative densities of preferred kit fox prey, black-toiled jackrabbits (40.1/1,000 acres) and desert cottontails (14.1/1,000 acres), were lower than previously recorded. Five blunt-nosed leopard lizards were observed along the southwest and northeast perimeter of the Reserve. Most of the 59 giant kangaroo rat burrow systems were observed in the flat terrain along the northeast and south perimeters of the Reserve. San Joaquin antelope squirrels were observed in the central and western parts of NPR- 1. A total of 73 antelope squirrels were observed, and the relative density was 1.511,000 acres. A total.of 30 possible environmental hazards were observed during transect surveys. Most of these were oil and water leaks of small size and appeared to pose little risk to endangered species. Results of this survey indicate that NPR-1 is supporting less wildlife than it did during either the 1979 or 1984 surveys.

  20. Reactor control rod timing system

    DOE Patents [OSTI]

    Wu, Peter T. K. (Clifton Park, NY)

    1982-01-01T23:59:59.000Z

    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.

  1. Reactor control rod timing system

    SciTech Connect (OSTI)

    Wu, P.T.

    1982-02-09T23:59:59.000Z

    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.

  2. Integral fast reactor safety features

    SciTech Connect (OSTI)

    Cahalan, J.E.; Kramer, J.M.; Marchaterre, J.F.; Mueller, C.J.; Pedersen, D.R.; Sevy, R.H.; Wade, D.C.; Wei, T.Y.C.

    1988-01-01T23:59:59.000Z

    The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on the technical aspects of the improved safety margins available in the IFR concept. This increased level of safety is made possible by (1) the liquid metal (sodium) coolant and pool-type primary system layout, which together facilitate passive decay heat removal, and (2) a sodium-bonded metallic fuel pin design with thermal and neutronic properties that provide passive core responses which control and mitigate the consequences of reactor accidents.

  3. DOE's way-out reactors

    SciTech Connect (OSTI)

    Marshall, E.

    1986-03-21T23:59:59.000Z

    The SP-100 reactor, envisioned long before Star Wars, was to power civilian structures such as the space station and orbiting commercial labs. According to the SDI Organization, it will be the cornerstone for SDI, used as a no-maintenance, general source of energy for the military's infrastructure - weapons scale power will come later. DOE wants to spend $72 in FY 1977 to design and build these reactors. Funding problems with Congress, as well as some of the technology and timetables are discussed here.

  4. Nuclear reactor safety heat transfer

    SciTech Connect (OSTI)

    Jones, O.C.

    1982-07-01T23:59:59.000Z

    Reviewed is a book which has 5 parts: Overview, Fundamental Concepts, Design Basis Accident-Light Water Reactors (LWRs), Design Basis Accident-Liquid-Metal Fast Breeder Reactors (LMFBRs), and Special Topics. It combines a historical overview, textbook material, handbook information, and the editor's personal philosophy on safety of nuclear power plants. Topics include thermal-hydraulic considerations; transient response of LWRs and LMFBRs following initiating events; various accident scenarios; single- and two-phase flow; single- and two-phase heat transfer; nuclear systems safety modeling; startup and shutdown; transient response during normal and upset conditions; vapor explosions, natural convection cooling; blockages in LMFBR subassemblies; sodium boiling; and Three Mile Island.

  5. Uncertainties in the Anti-neutrino Production at Nuclear Reactors

    E-Print Network [OSTI]

    Djurcic, Zelimir

    2009-01-01T23:59:59.000Z

    reactors are determined from thermal power measure- ments and ?ssion rate calculations.of a reactor’s ther- mal power is given by a calculation ofCALCULATIONS During the power cycle of a nuclear reactor,

  6. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation

    E-Print Network [OSTI]

    Heidet, Florent

    2010-01-01T23:59:59.000Z

    Gas Expansion Module Gas-cooled Fast Reactor High Enrichedfast reactors: gas-cooled fast reactor (GFR), sodium-cooledderived from the Gas cooled Fast Reactor (GFR). This core

  7. Computational Analysis of Fluid Flow in Pebble Bed Modular Reactor

    E-Print Network [OSTI]

    Gandhir, Akshay

    2012-10-19T23:59:59.000Z

    High Temperature Gas-cooled Reactor (HTGR) is a Generation IV reactor under consideration by Department of Energy and in the nuclear industry. There are two categories of HTGRs, namely, Pebble Bed Modular Reactor (PBMR) and Prismatic reactor. Pebble...

  8. Reactor Operations informal monthly report September 1994

    SciTech Connect (OSTI)

    Junker, L.

    1994-09-01T23:59:59.000Z

    This paper presents operations at the MRR and HFBR reactors at Brookhaven National Laboratory for September 1994. Reactor run-times, instrumentation, mechanical maintenance, occurrence reports and safety information are listed. Irradiation summaries are included.

  9. Reactivity control assembly for nuclear reactor

    DOE Patents [OSTI]

    Bollinger, Lawrence R. (Schenectady, NY)

    1984-01-01T23:59:59.000Z

    Reactivity control assembly for nuclear reactor comprises supports stacked above reactor core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.

  10. Microfluidic reactors for the synthesis of nanocrystals

    E-Print Network [OSTI]

    Yen, Brian K. H

    2007-01-01T23:59:59.000Z

    Several microfluidic reactors were designed and applied to the synthesis of colloidal semiconductor nanocrystals (NCs). Initially, a simple single-phase capillary reactor was used for the synthesis of CdSe NCs. Precursors ...

  11. Stability analysis of supercritical water cooled reactors

    E-Print Network [OSTI]

    Zhao, Jiyun, Ph. D. Massachusetts Institute of Technology

    2005-01-01T23:59:59.000Z

    The Supercritical Water-Cooled Reactor (SCWR) is a concept for an advanced reactor that will operate at high pressure (25MPa) and high temperature (500°C average core exit). The high coolant temperature as it leaves the ...

  12. Auxiliary reactor for a hydrocarbon reforming system

    DOE Patents [OSTI]

    Clawson, Lawrence G.; Dorson, Matthew H.; Mitchell, William L.; Nowicki, Brian J.; Bentley, Jeffrey M.; Davis, Robert; Rumsey, Jennifer W.

    2006-01-17T23:59:59.000Z

    An auxiliary reactor for use with a reformer reactor having at least one reaction zone, and including a burner for burning fuel and creating a heated auxiliary reactor gas stream, and heat exchanger for transferring heat from auxiliary reactor gas stream and heat transfer medium, preferably two-phase water, to reformer reaction zone. Auxiliary reactor may include first cylindrical wall defining a chamber for burning fuel and creating a heated auxiliary reactor gas stream, the chamber having an inlet end, an outlet end, a second cylindrical wall surrounding first wall and a second annular chamber there between. The reactor being configured so heated auxiliary reactor gas flows out the outlet end and into and through second annular chamber and conduit which is disposed in second annular chamber, the conduit adapted to carry heat transfer medium and being connectable to reformer reaction zone for additional heat exchange.

  13. Challenges in the Development of Advanced Reactors

    SciTech Connect (OSTI)

    P. Sabharwall; M.C. Teague; S.M. Bragg-Sitton; M.W. Patterson

    2012-08-01T23:59:59.000Z

    Past generations of nuclear reactors have been successively developed and the next generation is currently being developed, demonstrating the constant progress and technical and industrial vitality of nuclear energy. In 2000 US Department of Energy launched Generation IV International Forum (GIF) which is one of the main international frameworks for the development of future nuclear systems. The six systems that were selected were: sodium cooled fast reactor, lead cooled fast reactor, supercritical water cooled reactor, very high temperature gas cooled reactor (VHTR), gas cooled fast reactor and molten salt reactor. This paper discusses some of the proposed advanced reactor concepts that are currently being researched to varying degrees in the United States, and highlights some of the major challenges these concepts must overcome to establish their feasibility and to satisfy licensing requirements.

  14. Annual Report: 2010-2011 Storm Season Sampling For NON-DRY DOCK STORMWATER MONITORING FOR PUGET SOUND NAVAL SHIPYARD, BREMERTON, WA

    SciTech Connect (OSTI)

    Brandenberger, Jill M.; Metallo, David; Johnston, Robert K.; Gebhardt, Christine; Hsu, Larry

    2012-09-01T23:59:59.000Z

    This interim report summarizes the stormwater monitoring conducted for non-dry dock outfalls in both the confined industrial area and the residential areas of Naval Base Kitsap within the Puget Sound Naval Shipyard (referred to as the Shipyard). This includes the collection, analyses, and descriptive statistics for stormwater sampling conducted from November 2010 through April 2011. Seven stormwater basins within the Shipyard were sampled during at least three storm events to characterize non-dry dock stormwater discharges at selected stormwater drains located within the facility. This serves as the Phase I component of the project and Phase II is planned for the 2011-2012 storm season. These data will assist the Navy, USEPA, Ecology and other stakeholders in understanding the nature and condition of stormwater discharges from the Shipyard and inform the permitting process for new outfall discharges. The data from Phase I was compiled with current stormwater data available from the Shipyard, Sinclair/Dyes Inlet watershed, and Puget Sound in order to support technical investigations for the Draft NPDES permit. The permit would require storm event sampling at selected stormwater drains located within the Shipyard. However, the data must be considered on multiple scales to truly understand potential impairments to beneficial uses within Sinclair and Dyes Inlets.

  15. Petroleum production at maximum efficient rate, Naval Petroleum Reserve No. 1 (Elk Hills), Kern County, California. Draft Supplement to the 1979 Final Environmental Impact Statement

    SciTech Connect (OSTI)

    Not Available

    1992-05-01T23:59:59.000Z

    The proposed action involves the continued operation of the Naval Petroleum Reserve No. 1 (NPR-1) at the Maximum Efficiency Rate (MER) through the year approximately 2025 in accordance with the requirements of the Naval Petroleum Reserves Production Act of 1976 (P.L. 94-258). NPR-1 is a large oil and gas field comprising 74 square miles. MER production primarily includes continued operation and maintenance of existing facilities; a well drilling and abandonment program; construction and operation of future gas processing, gas compression, and steamflood, waterflood, cogeneration, and butane isomerization facilities; and continued implementation of a comprehensive environmental protection program. The basis for the draft environment impact statement (DSEIS) proposed action is the April 1989 NPR-1 Long Range Plan which describes a myriad of planned operational, maintenance, and development activities over the next 25--30 years. These activities include the continued operation of existing facilities; additional well drilling; expanded steamflood operations; expanded waterflood programs; expanded gas compression, gas lift, gas processing and gas injection; construction of a new cogeneration facility; construction of a new isobutane facility; and a comprehensive environmental program designed to minimize environmental impacts.

  16. Petroleum production at Maximum Efficient Rate Naval Petroleum Reserve No. 1 (Elk Hills), Kern County, California. Final Supplemental Environmental Impact Statement

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    This document provides an analysis of the potential impacts associated with the proposed action, which is continued operation of Naval Petroleum Reserve No. I (NPR-1) at the Maximum Efficient Rate (MER) as authorized by Public law 94-258, the Naval Petroleum Reserves Production Act of 1976 (Act). The document also provides a similar analysis of alternatives to the proposed action, which also involve continued operations, but under lower development scenarios and lower rates of production. NPR-1 is a large oil and gas field jointly owned and operated by the federal government and Chevron U.SA Inc. (CUSA) pursuant to a Unit Plan Contract that became effective in 1944; the government`s interest is approximately 78% and CUSA`s interest is approximately 22%. The government`s interest is under the jurisdiction of the United States Department of Energy (DOE). The facility is approximately 17,409 acres (74 square miles), and it is located in Kern County, California, about 25 miles southwest of Bakersfield and 100 miles north of Los Angeles in the south central portion of the state. The environmental analysis presented herein is a supplement to the NPR-1 Final Environmental Impact Statement of that was issued by DOE in 1979 (1979 EIS). As such, this document is a Supplemental Environmental Impact Statement (SEIS).

  17. MULTIPHASE REACTOR MODELING FOR ZINC CHLORIDE CATALYZED COAL LIQUEFACTION

    E-Print Network [OSTI]

    Joyce, Peter James

    2011-01-01T23:59:59.000Z

    for the Coal Slurry Reactor Calculations are shown here for= Total reactor pressure, psi. The calculation is iterative,

  18. Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors

    E-Print Network [OSTI]

    Terrani, Kurt Amir

    2010-01-01T23:59:59.000Z

    target subassemblies in a fast reactor core for effectiveof minor actinides in fast reactors [79]. In order to

  19. Granular Dynamics in Pebble Bed Reactor Cores

    E-Print Network [OSTI]

    Laufer, Michael Robert

    2013-01-01T23:59:59.000Z

    a simulant fluid to match the dynamics of fuel pebbles andfuel pebbles through reactor cores with and without coupled fluid

  20. Digital computer operation of a nuclear reactor

    DOE Patents [OSTI]

    Colley, Robert W. (Richland, WA)

    1984-01-01T23:59:59.000Z

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

  1. Digital computer operation of a nuclear reactor

    DOE Patents [OSTI]

    Colley, R.W.

    1982-06-29T23:59:59.000Z

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

  2. Liquid metal cooled nuclear reactor plant system

    DOE Patents [OSTI]

    Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

    1993-01-01T23:59:59.000Z

    A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

  3. Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories

    Office of Legacy Management (LM)

    Radiological Condition of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories Cheswick, Pennsylvania -. -, -- AGENCY: Office of Operational Safety, Department...

  4. Naval electrochemical corrosion reducer

    DOE Patents [OSTI]

    Clark, Howard L. (Ballston Lake, NY)

    1991-10-01T23:59:59.000Z

    A corrosion reducer for use with ships having a hull, a propeller mounted a propeller shaft and extending through the hull, bearings supporting the shaft, at least one thrust bearing and one seal. The improvement includes a current collector and a current reduction assembly for reducing the voltage between the hull and shaft in order to reduce corrosion due to electrolytic action. The current reduction assembly includes an electrical contact, the current collector, and the hull. The current reduction assembly further includes a device for sensing and measuring the voltage between the hull and the shaft and a device for applying a reverse voltage between the hull and the shaft so that the resulting voltage differential is from 0 to 0.05 volts. The current reduction assembly further includes a differential amplifier having a voltage differential between the hull and the shaft. The current reduction assembly further includes an amplifier and a power output circuit receiving signals from the differential amplifier and being supplied by at least one current supply. The current selector includes a brush assembly in contact with a slip ring over the shaft so that its potential may be applied to the differential amplifier.

  5. Naval Nuclear Propulsion

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for Renewable Energy:Nanowire Solar541,9337, 2011 at 2:00 P.M. Next8,NatureNauruEnergy

  6. Interdisciplinary Institute for Innovation Nuclear reactors' construction

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Interdisciplinary Institute for Innovation Nuclear reactors' construction costs: The role of lead@mines-paristech.fr hal-00956292,version1-6Mar2014 #12;hal-00956292,version1-6Mar2014 #12;Nuclear reactors' construction reactor construction costs in France and the United States. Studying the cost of nuclear power has often

  7. Laminar Entrained Flow Reactor (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2014-02-01T23:59:59.000Z

    The Laminar Entrained Flow Reactor (LEFR) is a modular, lab scale, single-user reactor for the study of catalytic fast pyrolysis (CFP). This system can be employed to study a variety of reactor conditions for both in situ and ex situ CFP.

  8. BROOKHAVEN NATIONAL LABORATORY'S HIGH FLUX BEAM REACTOR

    E-Print Network [OSTI]

    Ohta, Shigemi

    1 BROOKHAVEN NATIONAL LABORATORY'S HIGH FLUX BEAM REACTOR Compiled by S. M. Shapiro I. PICTORIAL with fiberglass insulation and a protective aluminum skin. The reactor vessel is shaped somewhat like a very large at the spherical end. It is located at the center of the reactor building and is surrounded by a lead and steel

  9. The Reactor An ObjectOriented Framework

    E-Print Network [OSTI]

    Schmidt, Douglas C.

    The Reactor An Object­Oriented Framework for Event Demultiplexing and Event Handler Dispatching Douglas C. Schmidt 1 Overview ffl The Reactor is an object­oriented frame­ work that encapsulates OS event demul­ tiplexing mechanisms -- e.g., the Reactor API runs transparently atop both Wait

  10. REACTOR SAFETY KEYWORDS: best estimate plus

    E-Print Network [OSTI]

    Hoppe, Fred M.

    REACTOR SAFETY KEYWORDS: best estimate plus uncertainty analysis, epistemic error and aleatory phe- nomena that underlie the safety analyses. The use of BE codes within the reactor technology in advance and that result from a variety of operating conditions or states. These arise because the reactor

  11. Chemical Reactor Analysis and Optimal Digestion

    E-Print Network [OSTI]

    Jumars, Pete

    J 310 Chemical Reactor Analysis and Optimal Digestion An optimal digestion theory can be readily derived from basic principles o f chemical reactor analysis and design Deborah L. Penry and Peter a reactor and an operating strategy that maximize the yield or yield rate of desired reaction products

  12. BioElectrochemically Assisted Microbial Reactor

    E-Print Network [OSTI]

    Lee, Dongwon

    BioElectrochemically Assisted Microbial Reactor (BEAMR) The BEAMR reactor uses only >0.2 V needed of combustion) >85% based on energy in electricity + acetate, at a rate of 1 m3 -H2 /m3 -reactor volume/d (100 A

  13. Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina)

    E-Print Network [OSTI]

    Gratta, Giorgio

    Nuclear reactor safeguards and monitoring with antineutrino detectors A. Bernsteina) Sandia of nuclear reactor types, including power reactors, research reactors, and plutonium production reactors-understood principles that govern the core's evolution in time, can be used to determine whether the reactor is being

  14. Integrated reformer and shift reactor

    DOE Patents [OSTI]

    Bentley, Jeffrey M.; Clawson, Lawrence G.; Mitchell, William L.; Dorson, Matthew H.

    2006-06-27T23:59:59.000Z

    A hydrocarbon fuel reformer for producing diatomic hydrogen gas is disclosed. The reformer includes a first reaction vessel, a shift reactor vessel annularly disposed about the first reaction vessel, including a first shift reactor zone, and a first helical tube disposed within the first shift reactor zone having an inlet end communicating with a water supply source. The water supply source is preferably adapted to supply liquid-phase water to the first helical tube at flow conditions sufficient to ensure discharge of liquid-phase and steam-phase water from an outlet end of the first helical tube. The reformer may further include a first catalyst bed disposed in the first shift reactor zone, having a low-temperature shift catalyst in contact with the first helical tube. The catalyst bed includes a plurality of coil sections disposed in coaxial relation to other coil sections and to the central longitudinal axis of the reformer, each coil section extending between the first and second ends, and each coil section being in direct fluid communication with at least one other coil section.

  15. Starfire - a commercial tokamak reactor

    SciTech Connect (OSTI)

    Baker, C.C.; Abdou, M.A.; DeFreece, D.A.; Trachsel, C.A.; Kokoszenski, J.; Graumann, D.

    1981-01-01T23:59:59.000Z

    The basic objective of the STARFIRE Project is to develop a design concept for a commercial tokamak fusion electric power plant based on the deuterium/tritium/lithium fuel cycle. The key technical objective is to develop the best embodiment of the tokamak as a power reactor consistent with credible engineering solutions to design problems. 10 refs.

  16. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, W.G.; Harris, M.T.; Scott, T.C.; Basaran, O.A.

    1996-04-02T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 5 figs.

  17. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Basaran, Osman A. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN)

    1995-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  18. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN); Scott, Timothy C. (Knoxville, TN); Basaran, Osman A. (Oak Ridge, TN)

    1998-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  19. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Basaran, Osman A. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN)

    1998-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  20. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, Warren G. (Oak Ridge, TN); Harris, Michael T. (Knoxville, TN); Scott, Timothy C. (Knoxville, TN); Basaran, Osman A. (Oak Ridge, TN)

    1996-01-01T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode.

  1. Nuclear Reactions and Reactor Safety

    E-Print Network [OSTI]

    Onuchic, José

    Nuclear Reactions and Reactor Safety DO NOT LICK We haven't entirely nailed down what element nuclear chain reaction, 1938 #12;Nuclear Chain Reactions Do nuclear chain reactions lead to runaway explosions? or ? -Controlled nuclear chain reactions possible: control energy release/sec -> More

  2. MCZ 050411 1 Stellarator Reactors

    E-Print Network [OSTI]

    designs => Motivated development of more compact designs · SPPS projected cost of electricity similar Average Major Radius (m) ASRA-6C 20 m HSR-G 18 m SPPS 14 m FFHR-J 10 m ARIES-ST Spherical Torus 3.2 m to tokamaks, but higher initial capital cost · Stellarator reactors expected to operate in true ignition

  3. Nuclear Reactor Safety Design Criteria

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

    1993-01-19T23:59:59.000Z

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

  4. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, W.G.; Harris, M.T.; Scott, T.C.; Basaran, O.A.

    1998-06-02T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two coaxial cylindrical bodies, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 5 figs.

  5. Nozzle for electric dispersion reactor

    DOE Patents [OSTI]

    Sisson, W.G.; Basaran, O.A.; Harris, M.T.

    1998-04-14T23:59:59.000Z

    A nozzle for an electric dispersion reactor includes two concentric electrodes, the inner one of the two delivering disperse phase fluid into a continuous phase fluid. A potential difference generated by a voltage source creates a dispersing electric field at the end of the inner electrode. 4 figs.

  6. Control of reactor coolant flow path during reactor decay heat removal

    DOE Patents [OSTI]

    Hunsbedt, Anstein N. (Los Gatos, CA)

    1988-01-01T23:59:59.000Z

    An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

  7. Spectral shift reactor control method

    SciTech Connect (OSTI)

    Impink, A.J. Jr.

    1987-12-29T23:59:59.000Z

    This patent describes the method of operating a pressurized-water fissile-material-fueled spectral-shift nuclear reactor in such manner that short-term reactivity requirement variations can be satisfied without making control rod or chemical shim changes. The reactor includes a pressure vessel enclosing a reactor core and having an inlet and an outlet for circulating a water coolant moderator in heat transfer relationship with the core. The core comprises fuel assemblies disposed therein for generating heat by nuclear fission. The reactor provided with neutron-absorbing control rods which are vertically movable into and out of the core so that movement of the control rods into the core will substantially decrease reactivity and withdrawal of the control rods from the core will substantially increase reactivity. The control rods when inserted into the core displace an equivalent volume of the water coolant moderator. The reactor also provides neutron-spectral-shift rods which have a lower absorptivity for neutrons than the control rods, the neutron-spectral shift rods when inserted into the core displacing an equaivalent volume of the water coolant moderator. The neutron-spectral-shift rods comprises two different types of rods, a first of the different types of the neutron-spectral-shift rods comprising displacer rods which have a low absorptivity for neutrons, the remainder of the neutron-spectral-shift rods comprising gray rods which have an absorption for neutrons which is intermediate the neutron absorption of the control rods and the low neutron absorption of the displacer rods. Each neutron-spectral-shift displacer rod comprises a hollow thin-walled Zircaloy member containing a filling of solid or annular zirconium- or aluminum-containing material for providing internal support and mass for the thin-walled tubular member.

  8. Heterogeneous Recycling in Fast Reactors

    SciTech Connect (OSTI)

    Forget, Benoit; Pope, Michael; Piet, Steven J.; Driscoll, Michael

    2012-07-30T23:59:59.000Z

    Current sodium fast reactor (SFR) designs have avoided the use of depleted uranium blankets over concerns of creating weapons grade plutonium. While reducing proliferation risks, this restrains the reactor design space considerably. This project will analyze various blanket and transmutation target configurations that could broaden the design space while still addressing the non-proliferation issues. The blanket designs will be assessed based on the transmutation efficiency of key minor actinide (MA) isotopes and also on mitigation of associated proliferation risks. This study will also evaluate SFR core performance under different scenarios in which depleted uranium blankets are modified to include minor actinides with or without moderators (e.g. BeO, MgO, B4C, and hydrides). This will be done in an effort to increase the sustainability of the reactor and increase its power density while still offering a proliferation resistant design with the capability of burning MA waste produced from light water reactors (LWRs). Researchers will also analyze the use of recycled (as opposed to depleted) uranium in the blankets. The various designs will compare MA transmutation efficiency, plutonium breeding characteristics, proliferation risk, shutdown margins and reactivity coefficients with a current reference sodium fast reactor design employing homogeneous recycling. The team will also evaluate the out-of-core accumulation and/or burn-down rates of MAs and plutonium isotopes on a cycle-by-cycle basis. This cycle-by-cycle information will be produced in a format readily usable by the fuel cycle systems analysis code, VISION, for assessment of the sustainability of the deployment scenarios.

  9. Fast-acting nuclear reactor control device

    DOE Patents [OSTI]

    Kotlyar, Oleg M. (Idaho Falls, ID); West, Phillip B. (Idaho Falls, ID)

    1993-01-01T23:59:59.000Z

    A fast-acting nuclear reactor control device for moving and positioning a fety control rod to desired positions within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump/motor, an electric gear motor, and solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

  10. Shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Groh, E.F.; Olson, A.P.; Wade, D.C.; Robinson, B.W.

    1984-06-05T23:59:59.000Z

    An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion. 8 figs.

  11. Shutdown system for a nuclear reactor

    DOE Patents [OSTI]

    Groh, Edward F. (Naperville, IL); Olson, Arne P. (Western Springs, IL); Wade, David C. (Naperville, IL); Robinson, Bryan W. (Oak Lawn, IL)

    1984-01-01T23:59:59.000Z

    An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains are capable of horizontal movement, so as to flow around obstructions in the reactor during their downward motion.

  12. Reactor monitoring and safeguards using antineutrino detectors

    E-Print Network [OSTI]

    N. S. Bowden

    2008-09-15T23:59:59.000Z

    Nuclear reactors have served as the antineutrino source for many fundamental physics experiments. The techniques developed by these experiments make it possible to use these very weakly interacting particles for a practical purpose. The large flux of antineutrinos that leaves a reactor carries information about two quantities of interest for safeguards: the reactor power and fissile inventory. Measurements made with antineutrino detectors could therefore offer an alternative means for verifying the power history and fissile inventory of a reactors, as part of International Atomic Energy Agency (IAEA) and other reactor safeguards regimes. Several efforts to develop this monitoring technique are underway across the globe.

  13. Self isolating high frequency saturable reactor

    DOE Patents [OSTI]

    Moore, James A. (Powell, TN)

    1998-06-23T23:59:59.000Z

    The present invention discloses a saturable reactor and a method for decoupling the interwinding capacitance from the frequency limitations of the reactor so that the equivalent electrical circuit of the saturable reactor comprises a variable inductor. The saturable reactor comprises a plurality of physically symmetrical magnetic cores with closed loop magnetic paths and a novel method of wiring a control winding and a RF winding. The present invention additionally discloses a matching network and method for matching the impedances of a RF generator to a load. The matching network comprises a matching transformer and a saturable reactor.

  14. Reactor assessments of advanced bumpy torus configurations

    SciTech Connect (OSTI)

    Uckan, N.A.; Owen, L.W.; Spong, D.A.; Miller, R.L.; Ard, W.B.; Pipkins, J.F.; Schmitt, R.J.

    1983-01-01T23:59:59.000Z

    Recently, several configurational approaches and concept improvement schemes were introduced for enhancing the performance of the basic ELMO Bumpy Torus (EBT) concept and for improving its reactor potential. These configurations include planar racetrack and square geometries, Andreoletti coil systems, and bumpy torus-stellarator hybrids (which include twisted racetrack and helical axis stellarator-snakey torus). Preliminary evaluations of reactor implications of each of these configurations have been carried out based on magnetics (vacuum) calculations, transport and scaling relationships, and stability properties. Results indicate favorable reactor projections with a significant reduction in reactor physical size as compared to conventional EBT reactor designs carried out in the past.

  15. Savannah River Site production reactor technical specifications. K Production Reactor

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    These technical specifications are explicit restrictions on the operation of the Savannah River Site K Production Reactor. They are designed to preserve the validity of the plant safety analysis by ensuring that the plant is operated within the required conditions bounded by the analysis, and with the operable equipment that is assumed to mitigate the consequences of an accident. Technical specifications preserve the primary success path relied upon to detect and respond to accidents. This report describes requirements on thermal-hydraulic limits; limiting conditions for operation and surveillance for the reactor, power distribution control, instrumentation, process water system, emergency cooling and emergency shutdown systems, confinement systems, plant systems, electrical systems, components handling, and special test exceptions; design features; and administrative controls.

  16. Nuclear reactor vessel fuel thermal insulating barrier

    DOE Patents [OSTI]

    Keegan, C. Patrick; Scobel, James H.; Wright, Richard F.

    2013-03-19T23:59:59.000Z

    The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

  17. Safety control circuit for a neutronic reactor

    DOE Patents [OSTI]

    Ellsworth, Howard C. (Richland, WA)

    2004-04-27T23:59:59.000Z

    A neutronic reactor comprising an active portion containing material fissionable by neutrons of thermal energy, means to control a neutronic chain reaction within the reactor comprising a safety device and a regulating device, a safety device including means defining a vertical channel extending into the reactor from an aperture in the upper surface of the reactor, a rod containing neutron-absorbing materials slidably disposed within the channel, means for maintaining the safety rod in a withdrawn position relative to the active portion of the reactor including means for releasing said rod on actuation thereof, a hopper mounted above the active portion of the reactor having a door disposed at the bottom of the hopper opening into the vertical channel, a plurality of bodies of neutron-absorbing materials disposed within the hopper, and means responsive to the failure of the safety rod on actuation thereof to enter the active portion of the reactor for opening the door in the hopper.

  18. Directions to the River's Edge Catering & Conference Center, Naval Air Station Patuxent River For mapping GPS program reference, Lexington Park, MD is the town just outside the base gates. Physical

    E-Print Network [OSTI]

    Yener, Aylin

    Rev 0310 Directions to the River's Edge Catering & Conference Center, Naval Air Station Patuxent. Physical address is 46870 Tate Road ­ Bldg 2815, Patuxent River, MD. 20670. REC&C (301) 342-6210. From River For mapping GPS program reference, Lexington Park, MD is the town just outside the base gates

  19. Fast-acting nuclear reactor control device

    SciTech Connect (OSTI)

    Kotlyar, O.M.; West, P.B.

    1993-08-03T23:59:59.000Z

    A fast-acting nuclear reactor control device is described for controlling a safety control rod within the core of a nuclear reactor, the reactor controlled by a reactor control system, the device comprising: a safety control rod drive shaft and an electromagnetic clutch co-axial with the drive shaft operatively connected to the safety control rod for driving and positioning the safety control rod within or without the reactor core during reactor operation, the safety rod being oriented in a substantially vertical position to allow the rod to fall into the reactor core under the influence of gravity during shutdown of the reactor; the safety control rod drive shaft further operatively connected to a hydraulic pump such that operation of the drive shaft simultaneously drives and positions the safety control rod and operates the hydraulic pump such that a hydraulic fluid is forced into an accumulator, filling the accumulator with oil for the storage and supply of primary potential energy for safety control rod insertion such that the release of potential energy in the accumulator causes hydraulic fluid to flow through the hydraulic pump, converting the hydraulic pump to a hydraulic motor having speed and power capable of full length insertion and high speed driving of the safety control rod into the reactor core; a solenoid valve interposed between the hydraulic pump and the accumulator, said solenoid valve being a normally open valve, actuated to close when the safety control rod is out of the reactor during reactor operation; and further wherein said solenoid opens in response to a signal from the reactor control system calling for shutdown of the reactor and rapid insertion of the safety control rod into the reactor core, such that the opening of the solenoid releases the potential energy in the accumulator to place the safety control rod in a safe shutdown position.

  20. Nuclear reactor alignment plate configuration

    DOE Patents [OSTI]

    Altman, David A; Forsyth, David R; Smith, Richard E; Singleton, Norman R

    2014-01-28T23:59:59.000Z

    An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accomodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through with the dowel pins pass.

  1. Spectral shift reactor control method

    SciTech Connect (OSTI)

    Impink, A.J. Jr.

    1984-02-21T23:59:59.000Z

    A method of operating a pressurized water nuclear reactor is described which comprises the determining of the present core power and reactivity levels and predicting the change in such levels due to displacer rod movements. Groups or single clusters of displacer rods can be inserted or withdrawn based on the predicted core power and reactivity levels to change the core power level and power distribution thereby providing load follow capability, without changing control rod positions or coolant boron concentrations.

  2. Review of mineral estate of the United States at Naval Petroleum Reserve No. 2, Buena Vista Hills Field, Kern County, California

    SciTech Connect (OSTI)

    NONE

    1996-08-09T23:59:59.000Z

    The purpose of this report is to present this Consultant`s findings regarding the nature and extent of the mineral estate of the United States at National Petroleum Reserve No. 2 (NPR-2), Buena Vista Hills Field, Kern County, California. Determination of the mineral estate is a necessary prerequisite to this Consultant`s calculation of estimated future cash flows attributable to said estate, which calculations are presented in the accompanying report entitled ``Phase II Final Report, Study of Alternatives for Future Operations of the Naval Petroleum and Oil Shale Reserves, NPR-2, California.`` This Report contains a discussion of the leases in effect at NPR-2 and subsequent contracts affecting such leases. This Report also summarizes discrepancies found between the current royalty calculation procedures utilized at NPR-2 and those procedures required under applicable agreements and regulations. Recommendations for maximizing the government`s income stream at NPR-2 are discussed in the concluding section of this Report.

  3. Assessment of impacts and evaluation of restoration methods on areas affected by a well blowout, Naval Petroleum Reserve No. 1, California

    SciTech Connect (OSTI)

    Warrick, G.D.; Kato, T.T.; Phillips, M.V. [and others

    1996-12-01T23:59:59.000Z

    In June 1994, an oil well on Naval Petroleum Reserve No. 1 blew-out and crude oil was deposited downwind. After the well was capped, information was collected to characterize the release and to assess effects to wildlife and plants. Oil residue was found up to 13.7 km from the well site, but deposition was relatively light and the oil quickly dried to form a thin crust on the soil surface. Elevated levels of hydrocarbons were found in livers collected from Heermann`s kangaroo rats (Dipodomys heermanni) from the oiled area but polycyclic aromatic hydrocarbons (known carcinogens or mutagens) were not detected in the livers. Restoration techniques (surface modification and bioremediation) and natural recovery were evaluated within three portions of the oiled area. Herbaceous cover and production, and survival and vigor of desert saltbush (Atriplex polycarpa) were also monitored within each trapping grid.

  4. Operating and maintenance experience with a 6-kW wind energy conversion system at Naval Station, Treasure Island, California. Technical note Sep 79-Jun 81

    SciTech Connect (OSTI)

    Pal, D.

    1982-07-01T23:59:59.000Z

    The experience gained and lessons learned from the 6-kW grid-integrated Wind Energy Conversion System (WECS) demonstration at Naval Station, Treasure Island, San Francisco Bay are detailed. The objective of this demonstration was to develop operating experience and maintenance information on the 6-kW WECS using a combination of permanent magnet alternator with a line commutated synchronous inverter. The on-site measurements conducted during the demonstation indicate that the WECS site has annual average windspeeds of about 8 to 10 mph. The test results to data indicate a satisfactory performance of the WECS except for two failures involving arcing at the electrical terminals located on the yaw shaft. Due to wind characteristics encountered at the site, the performance data collected to date are at windspeeds of 20 mph or lower. For evaluating the WECS performance at all windspeeds, location at a windier site with annual average windspeeds of 14 mph or higher is recommended.

  5. The ARIES tokamak reactor study

    SciTech Connect (OSTI)

    Not Available

    1989-10-01T23:59:59.000Z

    The ARIES study is a community effort to develop several visions of tokamaks as fusion power reactors. The aims are to determine the potential economics, safety, and environmental features of a range of possible tokamak reactors, and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. Three ARIES visions are planned, each having a different degree of extrapolation from the present data base in physics and technology. The ARIES-I design assumes a minimum extrapolation from current tokamak physics (e.g., 1st stability) and incorporates technological advances that can be available in the next 20 to 30 years. ARIES-II is a DT-burning tokamak which would operate at a higher beta in the 2nd MHD stability regime. It employs both potential advances in the physics and expected advances in technology and engineering. ARIES-II will examine the potential of the tokamak and the D{sup 3}He fuel cycle. This report is a collection of 14 papers on the results of the ARIES study which were presented at the IEEE 13th Symposium on Fusion Engineering (October 2-6, 1989, Knoxville, TN). This collection describes the ARIES research effort, with emphasis on the ARIES-I design, summarizing the major results, the key technical issues, and the central conclusions.

  6. Reference worldwide model for antineutrinos from reactors

    E-Print Network [OSTI]

    Marica Baldoncini; Ivan Callegari; Giovanni Fiorentini; Fabio Mantovani; Barbara Ricci; Virginia Strati; Gerti Xhixha

    2015-02-16T23:59:59.000Z

    Antineutrinos produced at nuclear reactors constitute a severe source of background for the detection of geoneutrinos, which bring to the Earth's surface information about natural radioactivity in the whole planet. In this framework we provide a reference worldwide model for antineutrinos from reactors, in view of reactors operational records yearly published by the International Atomic Energy Agency (IAEA). We evaluate the expected signal from commercial reactors for ongoing (KamLAND and Borexino), planned (SNO+) and proposed (Juno, RENO-50, LENA and Hanohano) experimental sites. Uncertainties related to reactor antineutrino production, propagation and detection processes are estimated using a Monte Carlo based approach, which provides an overall site dependent uncertainty on the signal in the geoneutrino energy window on the order of 3%. We also implement the off-equilibrium correction to the reference reactor spectra associated with the long-lived isotopes and we estimate a 2.4% increase of the unoscillated event rate in the geoneutrino energy window due to the storage of spent nuclear fuels in the cooling pools. We predict that the research reactors contribute to less than 0.2% to the commercial reactor signal in the investigated 14 sites. We perform a multitemporal analysis of the expected reactor signal over a time lapse of 10 years using reactor operational records collected in a comprehensive database published at www.fe.infn.it/antineutrino.

  7. Updating reactor control: mini-computers

    SciTech Connect (OSTI)

    Crawford, K.C.; Sandquist, G.M. [University of Utah, Salt Lake City, UT (United States)

    1984-07-01T23:59:59.000Z

    An aging reactor control console and a limited operating budget have impeded many research projects in the TRIGA reactor facility at the University of Utah. The, University's present console is Circa 1959 vintage and repairs to the console are frequently required which present many electronic problems to a staff with little electronic training. As an alternative to a single function control console we are developing a TRIGA control system based upon a mini-computer. The system hardware has been specified and the hardware is currently being acquired. The software will be programmed by the staff to customize the system to the reactor's physical systems and technical specifications. The software will be designed to monitor and control all reactor functions, control a pneumatic sample transfer system, acquire and analyze neutron activation data, provide reactor facility security surveillance, provide reactor documentation including online logging of physical parameters, and record regularly scheduled reactor calibrations and laboratory accounting procedures. The problem of hardware rewiring and changing technical specifications and changing safety system characteristics can be easily handled in the software. Our TRIGA reactor also functions as a major educational resource using available reactor based software. The computer control system can be employed to provide on-line training in reactor physics and kinetics. (author)

  8. Advanced Safeguards Approaches for New Fast Reactors

    SciTech Connect (OSTI)

    Durst, Philip C.; Therios, Ike; Bean, Robert; Dougan, A.; Boyer, Brian; Wallace, Rick L.; Ehinger, Michael H.; Kovacic, Don N.; Tolk, K.

    2007-12-15T23:59:59.000Z

    This third report in the series reviews possible safeguards approaches for new fast reactors in general, and the ABR in particular. Fast-neutron spectrum reactors have been used since the early 1960s on an experimental and developmental level, generally with fertile blanket fuels to “breed” nuclear fuel such as plutonium. Whether the reactor is designed to breed plutonium, or transmute and “burn” actinides depends mainly on the design of the reactor neutron reflector and the whether the blanket fuel is “fertile” or suitable for transmutation. However, the safeguards issues are very similar, since they pertain mainly to the receipt, shipment and storage of fresh and spent plutonium and actinide-bearing “TRU”-fuel. For these reasons, the design of existing fast reactors and details concerning how they have been safeguarded were studied in developing advanced safeguards approaches for the new fast reactors. In this regard, the design of the Experimental Breeder Reactor-II “EBR-II” at the Idaho National Laboratory (INL) was of interest, because it was designed as a collocated fast reactor with a pyrometallurgical reprocessing and fuel fabrication line – a design option being considered for the ABR. Similarly, the design of the Fast Flux Facility (FFTF) on the Hanford Site was studied, because it was a successful prototype fast reactor that ran for two decades to evaluate fuels and the design for commercial-scale fast reactors.

  9. Performance and evaluation of gas engine driven rooftop air conditioning equipment at the Willow Grove (PA) Naval Air Station. Interim report, 1992 cooling season

    SciTech Connect (OSTI)

    Armstrong, P.R.; Conover, D.R.

    1993-05-01T23:59:59.000Z

    In a field evaluation conducted for the US Department of Energy (DOE) Office of Federal Energy Management Program (FEMP), the Pacific Northwest Laboratory (PNL) examined the performance of a new US energy-related technology under the FEMP Test Bed Demonstration Program. The technology was a 15-ton natural gas engine driven roof top air conditioning unit. Two such units were installed on a naval retail building to provide space conditioning to the building. Under the Test Bed Demonstration Program, private and public sector interests are focused to support the installation and evaluation of new US technologies in the federal sector. Participating in this effort under a Cooperative Research and Development Agreement (CRADA) with DOE were the American Gas Cooling Center, Philadelphia Electric Company, Thermo King Corporation, and the US Naval Air Station at Willow Grove, Pennsylvania. Equipment operating and service data as well as building interior and exterior conditions were secured for the 1992 cooling season. Based on a computer assessment of the building using standard weather data, a comparison was made with the energy and operating costs associated with the previous space conditioning system. Based on performance during the 1992 cooling season and adjusted to a normal weather year, the technology will save the site $6,000/yr in purchased energy costs. An additional $9,000 in savings due to electricity demand ratchet charge reductions will also be realized. Detailed information on the technology, the installation, and the results of the technology test are provided to illustrate the advantages to the federal sector of using this technology. A history of the CRADA development process is also reported.

  10. Evaluation of in-vessel corium retention through external reactor vessel cooling for integral reactor

    SciTech Connect (OSTI)

    Park, R. J.; Lee, J. R.; Kim, S. B.; Jin, Y.; Kim, H. Y. [Korea Atomic Energy Research Inst., 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2012-07-01T23:59:59.000Z

    In-vessel corium retention through external reactor vessel cooling (IVR-ERVC) for a small integral reactor has been evaluated to determine the thermal margin for the prevention of a reactor vessel failure. A thermal load analysis from the corium pool to the outer reactor vessel wall in the lower plenum of the reactor vessel has been performed to determine the heat flux distribution. The critical heat flux (CHF) on the outer reactor vessel wall has been determined to fix the maximum heat removal rate through the external coolant between the outer reactor vessel and the insulation of the reactor vessel. Finally, the thermal margin has been evaluated by comparison of the thermal load with the maximum heat removal rate of the CHF on the outer reactor vessel wall. The maximum heat flux from the corium pool to the outer reactor vessel is estimated at approximately 0.25 MW/m{sup 2} in the metallic layer because of the focusing effect. The CHF of the outer reactor vessel is approximately 1.1 MW/m{sup 2} because of a two phase natural circulation mass flow. Since the thermal margin for the IVR-ERVC is sufficient, the reactor vessel integrity is maintained during a severe accident of a small integral reactor. (authors)

  11. Molten-Salt Depleted-Uranium Reactor

    E-Print Network [OSTI]

    Dong, Bao-Guo; Gu, Ji-Yuan

    2015-01-01T23:59:59.000Z

    The supercritical, reactor core melting and nuclear fuel leaking accidents have troubled fission reactors for decades, and greatly limit their extensive applications. Now these troubles are still open. Here we first show a possible perfect reactor, Molten-Salt Depleted-Uranium Reactor which is no above accident trouble. We found this reactor could be realized in practical applications in terms of all of the scientific principle, principle of operation, technology, and engineering. Our results demonstrate how these reactors can possess and realize extraordinary excellent characteristics, no prompt critical, long-term safe and stable operation with negative feedback, closed uranium-plutonium cycle chain within the vessel, normal operation only with depleted-uranium, and depleted-uranium high burnup in reality, to realize with fission nuclear energy sufficiently satisfying humanity long-term energy resource needs, as well as thoroughly solve the challenges of nuclear criticality safety, uranium resource insuffic...

  12. PID Control Effectiveness for Surface Reactor Concepts

    SciTech Connect (OSTI)

    Dixon, David D. [North Carolina State University, Raleigh, NC (United States); Los Alamos National Laboratory, Los Alamos, NM (United States); Marsh, Christopher L. [United States Naval Academy, Annapolis, MD (United States); Los Alamos National Laboratory, Los Alamos, NM (United States); Poston, David I. [Los Alamos National Laboratory, Los Alamos, NM (United States)

    2007-01-30T23:59:59.000Z

    Control of space and surface fission reactors should be kept as simple as possible, because of the need for high reliability and the difficulty to diagnose and adapt to control system failures. Fortunately, compact, fast-spectrum, externally controlled reactors are very simple in operation. In fact, for some applications it may be possible to design low-power surface reactors without the need for any reactor control after startup; however, a simple proportional, integral, derivative (PID) controller can allow a higher performance concept and add more flexibility to system operation. This paper investigates the effectiveness of a PID control scheme for several anticipated transients that a surface reactor might experience. To perform these analyses, the surface reactor transient code FRINK was modified to simulate control drum movements based on bulk coolant temperature.

  13. D-D tokamak reactor studies

    SciTech Connect (OSTI)

    Evans, K.E. Jr.; Baker, C.C.; Brooks, J.N.; Ehst, D.A.; Finn, P.A.; Jung, J.; Mattas, R.F.; Misra, B.; Smith, D.L.; Stevens, H.C.

    1980-11-01T23:59:59.000Z

    A tokamak D-D reactor design, utilizing the advantages of a deuterium-fueled reactor but with parameters not unnecessarily extended from existing D-T designs, is presented. Studies leading to the choice of a design and initial studies of the design are described. The studies are in the areas of plasma engineering, first-wall/blanket/shield design, magnet design, and tritium/fuel/vacuum requirements. Conclusions concerning D-D tokamak reactors are stated.

  14. Review of light water reactor safety

    SciTech Connect (OSTI)

    Cheng, H.S.

    1980-12-01T23:59:59.000Z

    A review of the present status of light water reactor (LWR) safety is presented. The review starts with a brief discussion of the outstanding accident scenarios concerning LWRs. Where possible the areas of present technological uncertainties are stressed. To provide a better perspective of reactor safety, it then reviews the probabilistic assessment of the outstanding LWR accidents considered in the Reactor Safety Study (WASH-1400) and discusses the potential impact of the present technological uncertainties on WASH-1400.

  15. Solid tags for identifying failed reactor components

    DOE Patents [OSTI]

    Bunch, Wilbur L. (Richland, WA); Schenter, Robert E. (Richland, WA)

    1987-01-01T23:59:59.000Z

    A solid tag material which generates stable detectable, identifiable, and measurable isotopic gases on exposure to a neutron flux to be placed in a nuclear reactor component, particularly a fuel element, in order to identify the reactor component in event of its failure. Several tag materials consisting of salts which generate a multiplicity of gaseous isotopes in predetermined ratios are used to identify different reactor components.

  16. Neutron shielding panels for reactor pressure vessels

    DOE Patents [OSTI]

    Singleton, Norman R. (Murrysville, PA)

    2011-11-22T23:59:59.000Z

    In a nuclear reactor neutron panels varying in thickness in the circumferential direction are disposed at spaced circumferential locations around the reactor core so that the greatest radial thickness is at the point of highest fluence with lesser thicknesses at adjacent locations where the fluence level is lower. The neutron panels are disposed between the core barrel and the interior of the reactor vessel to maintain radiation exposure to the vessel within acceptable limits.

  17. Small Reactor for Deep Space Exploration

    SciTech Connect (OSTI)

    None

    2012-11-29T23:59:59.000Z

    This is the first demonstration of a space nuclear reactor system to produce electricity in the United States since 1965, and an experiment demonstrated the first use of a heat pipe to cool a small nuclear reactor and then harvest the heat to power a Stirling engine at the Nevada National Security Site's Device Assembly Facility confirms basic nuclear reactor physics and heat transfer for a simple, reliable space power system.

  18. Small Reactor for Deep Space Exploration

    ScienceCinema (OSTI)

    None

    2014-05-30T23:59:59.000Z

    This is the first demonstration of a space nuclear reactor system to produce electricity in the United States since 1965, and an experiment demonstrated the first use of a heat pipe to cool a small nuclear reactor and then harvest the heat to power a Stirling engine at the Nevada National Security Site's Device Assembly Facility confirms basic nuclear reactor physics and heat transfer for a simple, reliable space power system.

  19. Precision Reactor e Spectrum Measurements: Recent Results and PROSPECTs

    E-Print Network [OSTI]

    Precision Reactor e Spectrum Measurements: Recent Results and PROSPECTs Bryce Littlejohn Illinois;Outline · Intro: Reactor e Flux and Spectrum Predictions · Reactor Anomaly and recent flux for PROSPECT 2 #12;Outline · Intro: Reactor e Flux and Spectrum Predictions · Reactor Anomaly and recent flux

  20. Electron cyclotron heating in a tokamak reactor

    SciTech Connect (OSTI)

    Hsuan, H.C.S.

    1984-01-01T23:59:59.000Z

    The role of electron cyclotron heating (ECH) in a tokamak reactor is discussed, various aspects of physics and engineering issues are reviewed.

  1. Mass Hierarchy via Mossbauer and Reactor Neutrinos

    E-Print Network [OSTI]

    Stephen Parke; Hisakazu Minakata; Hiroshi Nunokawa; Renata Zukanovich Funchal

    2008-12-10T23:59:59.000Z

    We show how one could determine the neutrino mass hierarchy with Mossbauer neutrinos and also revisit the question of whether the hierarchy can be determined with reactor neutrinos.

  2. Mass Hierarchy via Mossbauer and Reactor Neutrinos

    E-Print Network [OSTI]

    Parke, Stephen; Nunokawa, Hiroshi; Funchal, Renata Zukanovich

    2008-01-01T23:59:59.000Z

    We show how one could determine the neutrino mass hierarchy with Mossbauer neutrinos and also revisit the question of whether the hierarchy can be determined with reactor neutrinos.

  3. Sandia National Laboratories: Small Modular Reactors

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

    advanced computing capabilities that serve as a virtual version of existing, operating nuclear reactors-to enable nuclear energy to continue to provide dependable, afford-able...

  4. Recovery Act Progress Update: Reactor Closure Feature

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01T23:59:59.000Z

    A Recovery Act Progress Update. Decommissioning of two nuclear reactor sites at the Department of Energy's facilities has been approved and is underway.

  5. Plasma instrumentation for fusion power reactor control

    SciTech Connect (OSTI)

    Sager, G.T.; Bauer, J.F.; Maya, I.; Miley, G.H.

    1985-07-01T23:59:59.000Z

    Feedback control will be implemented in fusion power reactors to guard against unpredicted behavior of the plant and to assure desirable operation. In this study, plasma state feedback requirements for plasma control by systems strongly coupled to the plasma (magnet sets, RF, and neutral beam heating systems, and refueling systems) are estimated. Generic considerations regarding the impact of the power reactor environment on plasma instrumentation are outlined. Solutions are proposed to minimize the impact of the power reactor environment on plasma instrumentation. Key plasma diagnostics are evaluated with respect to their potential for upgrade and implementation as power reactor instruments.

  6. Progress Update: P-Reactor Grout

    SciTech Connect (OSTI)

    Cody, Tom

    2010-01-01T23:59:59.000Z

    A progress update, the Recovery Act at work at the Savannah River Site. The new phase of work on the permanent closure of two cold war nuclear reactors.

  7. Recovery Act Progress Update: Reactor Closure Feature

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14T23:59:59.000Z

    A Recovery Act Progress Update. Decommissioning of two nuclear reactor sites at the Department of Energy's facilities has been approved and is underway.

  8. Progress Update: P-Reactor Grout

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14T23:59:59.000Z

    A progress update, the Recovery Act at work at the Savannah River Site. The new phase of work on the permanent closure of two cold war nuclear reactors.

  9. Heat dissipating nuclear reactor with metal liner

    DOE Patents [OSTI]

    Gluekler, E.L.; Hunsbedt, A.; Lazarus, J.D.

    1985-11-21T23:59:59.000Z

    A nuclear reactor containment including a reactor vessel disposed within a cavity with capability for complete inherent decay heat removal in the earth and surrounded by a cast steel containment member which surrounds the vessel is described in this disclosure. The member has a thick basemat in contact with metal pilings. The basemat rests on a bed of porous particulate material, into which water is fed to produce steam which is vented to the atmosphere. There is a gap between the reactor vessel and the steel containment member. The containment member holds any sodium or core debris escaping from the reactor vessel if the core melts and breaches the vessel.

  10. Heat dissipating nuclear reactor with metal liner

    DOE Patents [OSTI]

    Gluekler, Emil L. (San Jose, CA); Hunsbedt, Anstein (Los Gatos, CA); Lazarus, Jonathan D. (Sunnyvale, CA)

    1987-01-01T23:59:59.000Z

    Disclosed is a nuclear reactor containment including a reactor vessel disposed within a cavity with capability for complete inherent decay heat removal in the earth and surrounded by a cast steel containment member which surrounds the vessel. The member has a thick basemat in contact with metal pilings. The basemat rests on a bed of porous particulate material, into which water is fed to produce steam which is vented to the atmosphere. There is a gap between the reactor vessel and the steel containment member. The containment member holds any sodium or core debris escaping from the reactor vessel if the core melts and breaches the vessel.

  11. Plant maintenance and advanced reactors, 2006

    SciTech Connect (OSTI)

    Agnihotri, Newal (ed.)

    2006-09-15T23:59:59.000Z

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Advanced plants to meet rising expectations, by John Cleveland, International Atomic Energy Agency, Vienna; A flexible and economic small reactor, by Mario D. Carelli and Bojan Petrovic, Westinghouse Electric Company; A simple and passively safe reactor, by Yury N. Kuznetsov, Research and Development Institute of Power Engineering (NIKIET), Russia; Gas-cooled reactors, by Jeffrey S. Merrifield, U.S. Nuclear Regulatory Commission; ISI project managment in the PRC, by Chen Chanbing, RINPO, China; and, Fort Calhoun refurbishment, by Sudesh Cambhir, Omaha Public Power District.

  12. Search for sterile neutrinos at reactors

    E-Print Network [OSTI]

    Yasuda, Osamu

    2011-01-01T23:59:59.000Z

    The sensitivity to the sterile neutrino mixing at very short baseline reactor neutrino experiments is investigated. In the case of conventional (thermal neutron) reactors it is found that the sensitivity is lost for $\\Delta m^2 \\gtrsim$ 1 eV$^2$ due to smearing of the reactor core size. On the other hand, in the case of an experimental fast neutron reactor Joyo, because of its small size, sensitivity to $\\sin^22\\theta_{14}$ can be as good as 0.03 for $\\Delta m^2 \\sim$ several eV$^2$ with the Bugey-like detector setup.

  13. TA-2 Water Boiler Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Durbin, M.E. (ed.); Montoya, G.M.

    1991-06-01T23:59:59.000Z

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m{sup 3} of low-level solid radioactive waste and 35 m{sup 3} of mixed waste. 15 refs., 25 figs., 3 tabs.

  14. Thermomechanical analysis of fast-burst reactors

    SciTech Connect (OSTI)

    Miller, J.D.

    1994-08-01T23:59:59.000Z

    Fast-burst reactors are designed to provide intense, short-duration pulses of neutrons. The fission reaction also produces extreme time-dependent heating of the nuclear fuel. An existing transient-dynamic finite element code was modified specifically to compute the time-dependent stresses and displacements due to thermal shock loads of reactors. Thermomechanical analysis was then applied to determine structural feasibility of various concepts for an EDNA-type reactor and to optimize the mechanical design of the new SPR III-M reactor.

  15. Advanced Reactor Thermal Hydraulic Modeling | Argonne Leadership...

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

    Advanced Reactor Thermal Hydraulic Modeling PI Name: Paul Fischer PI Email: fischer@mcs.anl.gov Institution: Argonne National Laboratory Allocation Program: INCITE Allocation Hours...

  16. Advanced Reactor Thermal Hydraulic Modeling | Argonne Leadership...

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

    Fischer (ANL), Aleks Obabko (ANL), and Hank Childs (LBNL) Advanced Reactor Thermal Hydraulic Modeling PI Name: Paul Fischer PI Email: fischer@mcs.anl.gov Institution: Argonne...

  17. Nuclear reactor multiphysics via bond graph formalism

    E-Print Network [OSTI]

    Sosnovsky, Eugeny

    2014-01-01T23:59:59.000Z

    This work proposes a simple and effective approach to modeling nuclear reactor multiphysics problems using bond graphs. Conventional multiphysics simulation paradigms normally use operator splitting, which treats the ...

  18. Advanced Reactor Research and Development Funding Opportunity...

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

    of research, development, and demonstration related to advanced non-light water reactor concepts. A goal of the program is to facilitate greater engagement between DOE and...

  19. NEW OPTIMIZATION-BASED APPROACH TO CHEMICAL REACTOR SYNTHESIS TOWARDS THE FULL INTEGRATION OF REACTOR

    E-Print Network [OSTI]

    Van den Hof, Paul

    NEW OPTIMIZATION-BASED APPROACH TO CHEMICAL REACTOR SYNTHESIS ­ TOWARDS THE FULL INTEGRATION OF REACTOR DESIGN, OPERATION AND CONTROL Nikola Nikacevi1 , Adrie Huesman1 , Paul Van den Hof1 , Andrzej, Leeghwaterstraat 44, 2628 CA Delft, The Netherlands Conceptual chemical reactor design still follows traditional

  20. Pollution prevention through reactor design

    SciTech Connect (OSTI)

    Hopper, J.R. [Lamar Univ., Beaumont, TX (United States)

    1995-09-01T23:59:59.000Z

    Generation of waste in the chemical processing industries has its beginning in the heart of the process--the reaction system. Pollution prevention will have the greatest impact in minimizing the generation of waste through the design and operation of chemical reactors by reducing generation at the source--source reduction. Pollution prevention by modification of reaction parameters is defined as changing the selectivity of the reaction so that undesirable reactions which produce waste products are minimized while at the same time producing the desirable products.

  1. Reactor pressure vessel vented head

    DOE Patents [OSTI]

    Sawabe, James K. (San Jose, CA)

    1994-01-11T23:59:59.000Z

    A head for closing a nuclear reactor pressure vessel shell includes an arcuate dome having an integral head flange which includes a mating surface for sealingly mating with the shell upon assembly therewith. The head flange includes an internal passage extending therethrough with a first port being disposed on the head mating surface. A vent line includes a proximal end disposed in flow communication with the head internal passage, and a distal end disposed in flow communication with the inside of the dome for channeling a fluid therethrough. The vent line is fixedly joined to the dome and is carried therewith when the head is assembled to and disassembled from the shell.

  2. Spheromak reactor-design study

    SciTech Connect (OSTI)

    Les, J.M.

    1981-06-30T23:59:59.000Z

    A general overview of spheromak reactor characteristics, such as MHD stability, start up, and plasma geometry is presented. In addition, comparisons are made between spheromaks, tokamaks and field reversed mirrors. The computer code Sphero is also discussed. Sphero is a zero dimensional time independent transport code that uses particle confinement times and profile parameters as input since they are not known with certainty at the present time. More specifically, Sphero numerically solves a given set of transport equations whose solutions include such variables as fuel ion (deuterium and tritium) density, electron density, alpha particle density and ion, electron temperatures.

  3. Fast pulse nonthermal plasma reactor

    DOE Patents [OSTI]

    Rosocha, Louis A.

    2005-06-14T23:59:59.000Z

    A fast pulsed nonthermal plasma reactor includes a discharge cell and a charging assembly electrically connected thereto. The charging assembly provides plural high voltage pulses to the discharge cell. Each pulse has a rise time between one and ten nanoseconds and a duration of three to twenty nanoseconds. The pulses create nonthermal plasma discharge within the discharge cell. Accordingly, the nonthermal plasma discharge can be used to remove pollutants from gases or break the gases into smaller molecules so that they can be more efficiently combusted.

  4. Graphite Reactor | ornl.gov

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) Environmental AssessmentsGeoffrey(SC)Graphite Reactor 'In the early, desperate

  5. Coupled Reactor Kinetics and Heat Transfer Model for Heat Pipe Cooled Reactors

    SciTech Connect (OSTI)

    WRIGHT,STEVEN A.; HOUTS,MICHAEL

    2000-11-22T23:59:59.000Z

    Heat pipes are often proposed as cooling system components for small fission reactors. SAFE-300 and STAR-C are two reactor concepts that use heat pipes as an integral part of the cooling system. Heat pipes have been used in reactors to cool components within radiation tests (Deverall, 1973); however, no reactor has been built or tested that uses heat pipes solely as the primary cooling system. Heat pipe cooled reactors will likely require the development of a test reactor to determine the main differences in operational behavior from forced cooled reactors. The purpose of this paper is to describe the results of a systems code capable of modeling the coupling between the reactor kinetics and heat pipe controlled heat transport. Heat transport in heat pipe reactors is complex and highly system dependent. Nevertheless, in general terms it relies on heat flowing from the fuel pins through the heat pipe, to the heat exchanger, and then ultimately into the power conversion system and heat sink. A system model is described that is capable of modeling coupled reactor kinetics phenomena, heat transfer dynamics within the fuel pins, and the transient behavior of heat pipes (including the melting of the working fluid). The paper focuses primarily on the coupling effects caused by reactor feedback and compares the observations with forced cooled reactors. A number of reactor startup transients have been modeled, and issues such as power peaking, and power-to-flow mismatches, and loading transients were examined, including the possibility of heat flow from the heat exchanger back into the reactor. This system model is envisioned as a tool to be used for screening various heat pipe cooled reactor concepts, for designing and developing test facility requirements, for use in safety evaluations, and for developing test criteria for in-pile and out-of-pile test facilities.

  6. 22.312 Engineering of Nuclear Reactors, Fall 2002

    E-Print Network [OSTI]

    Todreas, Neil E.

    Engineering principles of nuclear reactors, emphasizing power reactors. Power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural ...

  7. 22.312 Engineering of Nuclear Reactors, Fall 2004

    E-Print Network [OSTI]

    Buongiorno, Jacopo, 1971-

    Engineering principles of nuclear reactors, emphasizing power reactors. Power plant thermodynamics, reactor heat generation and removal (single-phase as well as two-phase coolant flow and heat transfer), and structural ...

  8. STATEMENT OF CONSIDERATIONS Advance Test Reactor Class Waiver

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

    Advance Test Reactor Class Waiver W(C)-2008-004 The Advanced Test Reactor (A TR) is a pressurized water test reactor at the Idaho National Laboratory (INL) that operates at low...

  9. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation

    E-Print Network [OSTI]

    Heidet, Florent

    2010-01-01T23:59:59.000Z

    Fuels for sodium-cooled fast reactors: US perspective.Pitch to Diameter Sodium-cooled Fast Reactor Simple Movingreactor (GFR), sodium-cooled fast reactor (SFR) and lead-

  10. Maximum Fuel Utilization in Advanced Fast Reactors without Actinides Separation

    E-Print Network [OSTI]

    Heidet, Florent

    2010-01-01T23:59:59.000Z

    Reports. 1999. IAEA, Fast Reactor Database 2006 Update, inof the Breed/Burn Fast Reactor Concept, in Department ofof Ultra-long Life Fast Reactor Core Concept, in Physor

  11. argentine reactor ra-6: Topics by E-print Network

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

    materials is much smaller in a fast reactor than in a thermal reactor. Consequently, metals that in a thermal reactor would severely impair neutron economy are acceptable in a...

  12. APPLICATION OF DATA ANALYSIS TECHNIQUES TO NUCLEAR REACTOR

    E-Print Network [OSTI]

    Kunz, Robert Francis

    1 APPLICATION OF DATA ANALYSIS TECHNIQUES TO NUCLEAR REACTOR SYSTEMS CODE ACCURACY ASSESSMENT) has been developed by the authors to provide quantitative comparisons between nuclear reactor systems. 1. INTRODUCTION In recent years, the commercial nuclear reactor industry has focused significant

  13. Simulated nuclear reactor fuel assembly

    DOE Patents [OSTI]

    Berta, Victor T. (Idaho Falls, ID)

    1993-01-01T23:59:59.000Z

    An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end.

  14. Simulated nuclear reactor fuel assembly

    DOE Patents [OSTI]

    Berta, V.T.

    1993-04-06T23:59:59.000Z

    An apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inner target tube is surrounded by and radially spaced from the heater tubes and outer target tube. The top of the assembly is generally open to allow for the electrical power connection to the heater tubes, and the bottom of the assembly includes means for completing the electrical circuitry in the heater tubes to provide electrical resistance heating to simulate the power profile in a nuclear reactor. The embedded conductor elements in each heater tube is split into two halves for a substantial portion of its length and provided with electrical isolation such that each half of the conductor is joined at one end and is not joined at the other end.

  15. New Production Reactors Program Plan

    SciTech Connect (OSTI)

    Not Available

    1990-12-01T23:59:59.000Z

    Part I of this New Production Reactors (NPR) Program Plan: describes the policy basis of the NPR Program; describes the mission and objectives of the NPR Program; identifies the requirements that must be met in order to achieve the mission and objectives; and describes and assesses the technology and siting options that were considered, the Program's preferred strategy, and its rationale. The implementation strategy for the New Production Reactors Program has three functions: Linking the design, construction, operation, and maintenance of facilities to policies requirements, and the process for selecting options. The development of an implementation strategy ensures that activities and procedures are consistent with the rationale and analysis underlying the Program. Organization of the Program. The strategy establishes plans, organizational structure, procedures, a budget, and a schedule for carrying out the Program. By doing so, the strategy ensures the clear assignment of responsibility and accountability. Management and monitoring of the Program. Finally, the strategy provides a basis for monitoring the Program so that technological, cost, and scheduling issues can be addressed when they arise as the Program proceeds. Like the rest of the Program Plan, the Implementation Strategy is a living document and will be periodically revised to reflect both progress made in the Program and adjustments in plans and policies as they are made. 21 figs., 5 tabs.

  16. FISSION REACTORS KEYWORDS: high-temperature

    E-Print Network [OSTI]

    Yildiz, Bilge

    that is directly cou- pled to an advanced gas-cooled reactor (AGR) is pro- posed in this paper. The system features conversion system, and the progress in the electrolysis cell materials field can help the econom- ical by a supercritical CO2 ~SCO2! power conversion system that is directly coupled to an advanced gas-cooled reactor

  17. FISSION REACTORS KEYWORDS: core-barrel vibra-

    E-Print Network [OSTI]

    Demazière, Christophe

    FISSION REACTORS KEYWORDS: core-barrel vibra- tions, in-core neutron noise, shell- mode vibrations CALCULATION OF THE NEUTRON NOISE INDUCED BY SHELL-MODE CORE-BARREL VIBRATIONS IN A 1-D, TWO-GROUP, TWO-REGION SLAB REACTOR MODEL CARL SUNDE,* CHRISTOPHE DEMAZI�RE, and IMRE PÁZSIT Chalmers University of Technology

  18. Chemical Reactor Models of Digestion Modulation

    E-Print Network [OSTI]

    Logan, David

    Chemical Reactor Models of Digestion Modulation William Wolesensky & J. David Logan Department give an overview of the application of chemical reactor theory to models of digestion processes and indicate how those models extend to eco-physiological questions of modulation of digestion and feeding

  19. Standard Operating Procedure (Polypropylene Reactor System)

    E-Print Network [OSTI]

    Choi, Kyu Yong

    are closed. 3. Open the valves in the propylene gas line except for the last valve before the connection in the high temperature bath and connect the propylene gas line. #12;3 6. Start the reaction by opening the valve on the reactor top to let the propylene gas into the reactor. 7. After the reaction is complete

  20. Reactor monitoring with Neutrinos Michel Cribier

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    it the automatic and non intrusive monitoring of nuclear reactor by its antineutrino signal could be very valuable, but also book keeping of the fuel element composition before and after their use in the nuclear powerReactor monitoring with Neutrinos Michel Cribier Astroparticule & Cosmologie 10, rue Alice Domon et

  1. Topaz-II reactor control unit development

    SciTech Connect (OSTI)

    Wyant, F.J.; Jensen, D.; Logothetis, J.

    1994-12-31T23:59:59.000Z

    The development for a new digital reactor control unit for the Topaz-II reactor is described. The unit is expected to provide the means for automated control during a possible Topaz flight experiment. The breadboard design and development is discussed.

  2. University of Virginia Reactor Facility Decommissioning Results

    SciTech Connect (OSTI)

    Ervin, P. F.; Lundberg, L. A.; Benneche, P. E.; Mulder, R. U.; Steva, D. P.

    2003-02-24T23:59:59.000Z

    The University of Virginia Reactor Facility started accelerated decommissioning in 2002. The facility consists of two licensed reactors, the CAVALIER and the UVAR. This paper will describe the progress in 2002, remaining efforts and the unique organizational structure of the project team.

  3. High Temperature Gas Reactors The Next Generation ?

    E-Print Network [OSTI]

    -Proof Advanced Reactor and Gas Turbine #12;Flow through Power Conversion Vessel 8 #12;9 TRISO Fuel Particle1 High Temperature Gas Reactors The Next Generation ? Professor Andrew C Kadak Massachusetts of Brayton vs. Rankine Cycle · High Temperature Helium Gas (900 C) · Direct or Indirect Cycle · Originally

  4. High Temperature Gas Reactors Briefing to

    E-Print Network [OSTI]

    Meltdown-Proof Advanced Reactor and Gas Turbine #12;TRISO Fuel Particle -- "Microsphere" · 0.9mm diameter · Utilizes gas turbine technology · Lower Power Density · Less Complicated Design (No ECCS) #12;AdvantagesHigh Temperature Gas Reactors Briefing to by Andrew C. Kadak, Ph.D. Professor of the Practice

  5. Pebble Flow Experiments For Pebble Bed Reactors

    E-Print Network [OSTI]

    Bazant, Martin Z.

    of Technology 2nd International Topical Meeting on High Temperature Reactor Technology Institute of NuclearPebble Flow Experiments For Pebble Bed Reactors Andrew C. Kadak1 Department of Nuclear Engineering Massachusetts Institute of Technology Martin Z. Bazant Department of Mathematics Massachusetts Institute

  6. The First Reactor, 40th Anniversary (rev.)

    SciTech Connect (OSTI)

    Allardice, Corbin; Trapnell, Edward R.; Fermi, Enrico; Fermi, Laura; Williams, Robert C.

    1982-12-01T23:59:59.000Z

    This booklet, an updated version of the original booklet describing the first nuclear reactor, was written in honor of the 40th anniversary of the first reactor or "pile". It is based on firsthand accounts told to Corbin Allardice and Edward R. Trapnell, and includes recollections of Enrico and Laura Fermi.

  7. Safety Issues for High Temperature Gas Reactors

    E-Print Network [OSTI]

    Risk Informed Safety Profile #12;LEVELS OF DEFENCE IN DEPTH (From INSAG-10) Control, limiting (reactivity insertion) ­ Loss of Load ­ Rod Ejection (more significant in block reactors) ­ Failure of reactor effects and chemical attack on graphite · Blow down loads and timing of accident event sequences

  8. Hydrogasification reactor and method of operating same

    DOE Patents [OSTI]

    Hobbs, Raymond; Karner, Donald; Sun, Xiaolei; Boyle, John; Noguchi, Fuyuki

    2013-09-10T23:59:59.000Z

    The present invention provides a system and method for evaluating effects of process parameters on hydrogasification processes. The system includes a hydrogasification reactor, a pressurized feed system, a hopper system, a hydrogen gas source, and a carrier gas source. Pressurized carbonaceous material, such as coal, is fed to the reactor using the carrier gas and reacted with hydrogen to produce natural gas.

  9. CASCADE OPTIMIZATION AND CONTROL OF BATCH REACTORS

    E-Print Network [OSTI]

    Jutan, Arthur

    CASCADE OPTIMIZATION AND CONTROL OF BATCH REACTORS Xiangming Hua, Sohrab Rohani and Arthur Jutan ajutan@uwo.ca Abstract: In this study, a cascade closed-loop optimization and control strategy for batch reactor. Using model reduction a cascade system is developed, which can effectively combine optimization

  10. Selective purge for hydrogenation reactor recycle loop

    DOE Patents [OSTI]

    Baker, Richard W. (Palo Alto, CA); Lokhandwala, Kaaeid A. (Union City, CA)

    2001-01-01T23:59:59.000Z

    Processes and apparatus for providing improved contaminant removal and hydrogen recovery in hydrogenation reactors, particularly in refineries and petrochemical plants. The improved contaminant removal is achieved by selective purging, by passing gases in the hydrogenation reactor recycle loop or purge stream across membranes selective in favor of the contaminant over hydrogen.

  11. Explosive demolition of K East Reactor Stack

    ScienceCinema (OSTI)

    None

    2010-09-02T23:59:59.000Z

    Using $420,000 in Recovery Act funds, the Department of Energy and contractor CH2M HILL Plateau Remediation Company topped off four months of preparations when they safely demolished the exhaust stack at the K East Reactor and equipment inside the reactor building on July 23, 2010.

  12. State space modeling of reactor core in a pressurized water reactor

    SciTech Connect (OSTI)

    Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

    2014-07-10T23:59:59.000Z

    The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

  13. SciTech Connect: Nuclear power reactor instrumentation systems...

    Office of Scientific and Technical Information (OSTI)

    of Publication: United States Language: English Subject: N79400* --Reactors--Reactor Control Systems; N46110 -- Instrumentation--Radiation Detection Instruments--General...

  14. Physics-based multiscale coupling for full core nuclear reactor...

    Office of Scientific and Technical Information (OSTI)

    multiscale coupling for full core nuclear reactor simulation Numerical simulation of nuclear reactors is a key technology in the quest for improvements in efficiency, safety,...

  15. Development of Light Water Reactor Fuels with Enhanced Accident...

    Energy Savers [EERE]

    Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to Congress Development of Light Water Reactor Fuels with Enhanced Accident Tolerance - Report to...

  16. anammox biofilm reactors: Topics by E-print Network

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

    theta13 by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding...

  17. argonaut type reactors: Topics by E-print Network

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

    theta13 by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding...

  18. agr type reactors: Topics by E-print Network

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

    theta13 by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding...

  19. argonne thermal source reactor: Topics by E-print Network

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

    theta13 by reactor neutrino experiments in the coming years will use near-far detector configurations. Most uncertainties from reactor will be canceled out. Understanding...

  20. aerated biofilm reactor: Topics by E-print Network

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

    spectra of fuel isotopes. Past reactor neutrino experiments have determined the flux to (2-3)% precision. Precision measurements of mixing angle theta13 by reactor...