Sample records for vessel bunkering military

  1. The bunkering industry and its effect on shipping tanker operations

    E-Print Network [OSTI]

    Boutsikas, Angelos

    2004-01-01T23:59:59.000Z

    The bunkering industry provides the shipping industry with the fuel oil that the vessels consume. The quality of the fuel oil provided will ensure the safe operation of vessels. Shipping companies under their fuel oil ...

  2. Coal bunkers in underground mines

    SciTech Connect (OSTI)

    Polak, J.; Zegzulka, J. [VSB-Technical Univ., Ostrava (Czech Republic)

    1996-12-31T23:59:59.000Z

    In spite of the technical progress in the application of face technological equipment, the fluctuation of its output has been still considerable. A coal clearance system can be on one hand overloaded by production peaks and on the other hand its stoppages unfavorably influence production of faces. It has been proved that the most effective coal conveying system incorporates surge bunkers to eliminate the above mentioned problems. The surge bunkers have been used in the Czech mines since the middle of the sixties. There were 17 bunkers with an average capacity of 200 m{sup 3} in the biggest Czech coal mine basin OKD in 1967. Presently the number of bunkers has increased to 66 with a total capacity of 40,000 m{sup 3}. It represents the possibility of storing 56% of the daily OKD running of mine output. Two thirds of the number are gate bunkers with an average capacity of 540 m{sup 3} and the rest are skip ones with an average capacity of 740 m{sup 3}, situated at the shaft side.

  3. Residual Fuel Oil Sales for Vessel Bunkering Use

    U.S. Energy Information Administration (EIA) 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghurajiConventionalMississippi"site.1 Relative Standard Errors forA2. For9,250 14,609 9,8515,257,810

  4. Distillate Fuel Oil Sales for Vessel Bunkering Use

    Annual Energy Outlook 2013 [U.S. Energy Information Administration (EIA)]

    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 33 111 1,613 122 40Coal Stocks at1,066,688 760,877 951,322 1,381,127 1,710,513

  5. Bunker Fuel Market | OpenEI Community

    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 beingZealand Jump to:EzfeedflagBiomassSustainable andBucoda, Washington: Energy(B2G) (SmartBullittBuncombeBunker

  6. Bunker Hill Village, Texas: 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 You are beingZealand Jump to:EzfeedflagBiomassSustainable andBucoda, Washington: Energy(B2G)Bunker Hill Village, Texas:

  7. Sandia Energy - Military

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

    Military Home Stationary Power Grid Modernization Resilient Electric Infrastructures Military Militaryashoter2015-04-07T21:59:39+00:00 The DoD is pursuing a number of initiatives...

  8. China's Civil-Military Integration

    E-Print Network [OSTI]

    LAFFERTY, Brian; SHRABERG, Aaron; CLEMENS, Morgan

    2013-01-01T23:59:59.000Z

    China’s civil-military integration, and China’s high tech2013 China’s Civil-Military Integration Brian LAFFERTY Aarons pursuit of civil-military integration (CMI) intensified in

  9. Partnering with the Military

    E-Print Network [OSTI]

    Wythe, Kathy

    2006-01-01T23:59:59.000Z

    Partnering with the Military Story by Kathy Wythe Texas Agricultural Experiment Stationresearchers have partnered with Fort Hoodpersonnel to identify a natural ?weapon? to restore the facility?s tank training areas?land and soils seriously eroded... Center (BREC) in Temple have determined that composted dairy manure can increase soil fertility and vegetation cover on some of the Fort?s 200,000 acres of training areas and stabilize eroded soils without excessive nutrients entering the streams...

  10. Vehicle Technologies Office: AVTA - Evaluating Military Bases...

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

    Military Bases and Fleet Readiness for Electric Vehicles Vehicle Technologies Office: AVTA - Evaluating Military Bases and Fleet Readiness for Electric Vehicles The Vehicle...

  11. From Cold War to cold vessels

    SciTech Connect (OSTI)

    Melrath, C.

    1996-09-01T23:59:59.000Z

    This article describes a former Soviet weapons plant which is converted to produce cryogenic vessels and other peaceful cylinders. In 1995, Byelocorp Scientific Inc. (BSI), a New York-based firm that specializes in transferring technologies developed in the former Soviet Union, began converting a huge military defense plant in Kazakhstan into civilian-industrial use. The nearly 750,000-square-foot factory in Almaty, the capital of the former Soviet republic, was previously used to manufacture torpedo shells and ballistic rocket casings. The old defense plant, which was known as Gidromash, will now manufacture cylinders of a kinder, gentler variety--cryogenic vessels. The Kazakhstan operation is being managed jointly with Supco Srl., an Italian manufacturing, engineering, and construction company. With financing from the US Department of Defense, BSI, Supco, and the Kazakhstan government, a new joint venture called Byelkamit (a combination of Byelocorp, Kazakhstan, America, and Italy) was established.

  12. MILITARY TECHNICAL ACADEMY Vol. XXII, No. 4

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    #12;MILITARY TECHNICAL ACADEMY Vol. XXII, No. 4 © Military Technical Academy Publishing House Technical Academy of Bucharest, Romania Col. Prof. Eng. IOAN NICOLAESCU, Ph.D. The Military Technical Academy of Bucharest, Romania Prof. Eng. VICTOR-VALERIU PATRICIU, Ph.D. The Military Technical Academy

  13. Superfund Record of Decision (EPA Region 10): Bunker Hill Mining and Metallurgical Complex, Shoshone County, ID. (First remedial action), August 1991

    SciTech Connect (OSTI)

    Not Available

    1991-08-30T23:59:59.000Z

    The Bunker Hill Mining and Metallurgical Complex site is a 21 square-mile area centered around an inactive industrial mining and smelting site, and includes the cities of Kellogg, Smelterville, Wardner, Pinehurst, and Page, in Shoshone County, Idaho. The inactive industrial complex includes the Bunker Hill mine and mill, a lead smelter, a zinc smelter and a phosphoric acid fertilizer plant, all totalling several hundred acres. Initially, most of the solid and liquid residue from the complex was discharged into the river. When the river flooded, these materials were deposited onto the valley floor, and have leached into onsite soil and ground water. The selected remedial action for the site includes soil sampling; excavating contaminated soil and sod exceeding 1,000 mg/kg lead on approximately 1,800 residential properties, and replacing it with clean soil and sod; disposing of the contaminated soil and sod at an onsite repository; and capping the repository.

  14. Vacuum Vessel Remote Handling

    E-Print Network [OSTI]

    and Remote Handling 4 Vacuum vessel functions · Plasma vacuum environment · Primary tritium confinement, incl ports 65 tonnes - Weight of torus shielding 100 tonnes · Coolant - Normal Operation Water, Handling 12 Vessel octant subassembly fab. (3) · Octant-to-octant splice joint requires double wall weld

  15. Neutrino Factory Target Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    by UT-Battelle for the U.S. Department of Energy Target Vessel Update 26 June 2012 Cooling Channel in both walls for draining · Downstream end can be shortened, assuming the window cooling is adequate #12;11 Managed by UT-Battelle for the U.S. Department of Energy Target Vessel Update 26 June 2012 Remote Handling

  16. Dual shell pressure balanced vessel

    DOE Patents [OSTI]

    Fassbender, Alexander G. (West Richland, WA)

    1992-01-01T23:59:59.000Z

    A dual-wall pressure balanced vessel for processing high viscosity slurries at high temperatures and pressures having an outer pressure vessel and an inner vessel with an annular space between the vessels pressurized at a pressure slightly less than or equivalent to the pressure within the inner vessel.

  17. Armed forces, states and threats : civil-military institutions and military power in modern democracies

    E-Print Network [OSTI]

    DeVore, Marc Ronald

    2009-01-01T23:59:59.000Z

    Two longstanding questions preoccupying political scientists, military officers and policymakers alike are how should and how do political leaders interact with military professionals? This thesis argues that historic ...

  18. HEART AND BLOOD VESSELS CARDIOVASCULARCARDIOVASCULAR

    E-Print Network [OSTI]

    Cochran-Stafira, D. Liane

    HEART AND BLOOD VESSELS CARDIOVASCULARCARDIOVASCULAR SYSTEMSYSTEM SYSTEM COMPONENTS · Heart pumps blood though blood vessels where exchanges can take place with the interstitial fluid (between cells) · Heart and blood vessels regulate blood flow according to the needs of the body

  19. 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.

  20. A Bibliography of Professional Military Education

    E-Print Network [OSTI]

    Independent Study of Joint Officer Management and Joint Professional Military Education. McLean, VA: Booz, Allen & Hamilton, 2003. Israel, Steve. Report of the Proceedings: Conference on Military Education

  1. Reactor vessel annealing system

    DOE Patents [OSTI]

    Miller, Phillip E. (Greensburg, PA); Katz, Leonoard R. (Pittsburgh, PA); Nath, Raymond J. (Murrysville, PA); Blaushild, Ronald M. (Export, PA); Tatch, Michael D. (Randolph, NJ); Kordalski, Frank J. (White Oak, PA); Wykstra, Donald T. (Pittsburgh, PA); Kavalkovich, William M. (Monroeville, PA)

    1991-01-01T23:59:59.000Z

    A system for annealing a vessel (14) in situ by heating the vessel (14) to a defined temperature, composed of: an electrically operated heater assembly (10) insertable into the vessel (14) for heating the vessel (14) to the defined temperature; temperature monitoring components positioned relative to the heater assembly (10) for monitoring the temperature of the vessel (14); a controllable electric power supply unit (32-60) for supplying electric power required by the heater assembly (10); a control unit (80-86) for controlling the power supplied by the power supply unit (32-60); a first vehicle (2) containing the power supply unit (32-60); a second vehicle (4) containing the control unit (80-86); power conductors (18,22) connectable between the power supply unit (32-60) and the heater unit (10) for delivering the power supplied by the power supply unit (32-60) to the heater assembly (10); signal conductors (20,24) connectable between the temperature monitoring components and the control unit (80-86) for delivering temperature indicating signals from the temperature monitoring components to the control unit (80-86); and control conductors (8) connectable between the control unit (80-86) and the power supply unit (32-60) for delivering to the power supply unit (32-60) control signals for controlling the level of power supplied by the power supply unit (32-60) to the heater assembly (10).

  2. Neutrino Factory Mercury Vessel

    E-Print Network [OSTI]

    McDonald, Kirk

    Neutrino Factory Mercury Vessel: Initial Cooling Calculations V. Graves Target Studies Nov 15, 2012 #12;2 Managed by UT-Battelle for the U.S. Department of Energy Cooling Calculations 15 Nov 2012 Target · Separates functionality, provides double mercury containment, simplifies design and remote handling · Each

  3. CIVIL-MILITARY GAP AND MILITARY EFFECTIVENESS: THE IMPACT OF IDEOLOGY AND MILITARY EXPERIENCE GAP ON DEFENSE SPENDING IN THE UNITED STATES, 1952-2000

    E-Print Network [OSTI]

    Lee, Byeonggu

    2010-01-01T23:59:59.000Z

    Previous studies of civil-military gap have argued that the difference in values, perspectives, and opinions between civilians and the military matters because it determines military effectiveness, but empirical analyses ...

  4. military

    National Nuclear Security Administration (NNSA)

    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 Approved:AdministrationAnalysisDarby Dietrich57/%2A en4/%2A en

  5. On Military Innovation: Toward an Analytical Framework

    E-Print Network [OSTI]

    Ross, Andrew L

    2010-01-01T23:59:59.000Z

    new The Study of Innovation and Technology in China (SITC)components of military innovation (technology, doctrine, andinnovations: robotics and information technologies for

  6. Wind Industry Training for Our Military Veterans

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Energy Department is taking steps to leverage the skill sets of our military veterans in support of the wind energy industry.

  7. High pressure storage vessel

    DOE Patents [OSTI]

    Liu, Qiang

    2013-08-27T23:59:59.000Z

    Disclosed herein is a composite pressure vessel with a liner having a polar boss and a blind boss a shell is formed around the liner via one or more filament wrappings continuously disposed around at least a substantial portion of the liner assembly combined the liner and filament wrapping have a support profile. To reduce susceptible to rupture a locally disposed filament fiber is added.

  8. 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.

  9. Center for Environmental Management of Military Lands

    E-Print Network [OSTI]

    for professionalism and hard work. Sincerely, Dr. Lee Barber, Director Center for Environmental Management of MilitaryCenter for Environmental Management of Military Lands 1490 Campus Delivery Fort Collins, Colorado extent been due to our ability to address our sponsors' natural and cultural resource management

  10. Overview of Hydrogen and Fuel Cell Activities: 2010 Military...

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

    Overview of Hydrogen and Fuel Cell Activities: 2010 Military Energy and Alternative Fuels Conference Overview of Hydrogen and Fuel Cell Activities: 2010 Military Energy and...

  11. Oxygen-Enriched Combustion for Military Diesel Engine Generators...

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

    Oxygen-Enriched Combustion for Military Diesel Engine Generators Oxygen-Enriched Combustion for Military Diesel Engine Generators Substantial increases in brake power and...

  12. Electric Vehicle Grid Integration for Sustainable Military Installations (Presentation)

    SciTech Connect (OSTI)

    Simpson, M.

    2011-05-05T23:59:59.000Z

    This presentation discusses electric vehicle grid integration for sustainable military installations. Fort Carson Military Reservation in Colorado Springs is used as a case study.

  13. Probing Emissions of Military Cargo Aircraft: Description of...

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

    Emissions of Military Cargo Aircraft: Description of a Joint Field Measurement Strategic Environmental Research and Probing Emissions of Military Cargo Aircraft: Description of a...

  14. Leveraging Tribal Renewable Resources to Support Military Energy...

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

    Leveraging Tribal Renewable Resources to Support Military Energy Goals Leveraging Tribal Renewable Resources to Support Military Energy Goals May 30-31, 2013 Image of a speaker at...

  15. academic military treatment: Topics by E-print Network

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

    Impact of Civilian and Military Biology and Medicine Websites Summary: Uncovering the Stealth Cluster The Economic Impact of Civilian and Military Aerospace on South of...

  16. War Upon the Map: The Politics of Military User Innovation

    E-Print Network [OSTI]

    Lindsay, Jon R.

    2006-07-18T23:59:59.000Z

    While military personnel are often involved in the design of information technology, the literature on military innovation generally assumes defense contractors are the primary producers. Furthermore, general organizational ...

  17. Overview of Hydrogen and Fuel Cell Activities: 2010 Military...

    Energy Savers [EERE]

    0 Military Energy and Alternative Fuels Conference Overview of Hydrogen and Fuel Cell Activities: 2010 Military Energy and Alternative Fuels Conference This presentation by DOE's...

  18. Amendment 80 vessel replacement 1 Implementation and of Amendment 80 Vessel Replacement Provisions

    E-Print Network [OSTI]

    Amendment 80 vessel replacement 1 Implementation and of Amendment 80 Vessel Replacement Provisions vessels to use non-qualifying vessels in the sector, thus allowing replacement of a lost qualifying vessel of the CRP ambiguous as to whether replacement of qualifying vessels with non-qualifying vessels

  19. Vessel structural support system

    DOE Patents [OSTI]

    Jenko, James X. (N. Versailles, PA); Ott, Howard L. (Kiski Twp., Allegheny County, PA); Wilson, Robert M. (Plum Boro, PA); Wepfer, Robert M. (Murrysville, PA)

    1992-01-01T23:59:59.000Z

    Vessel structural support system for laterally and vertically supporting a vessel, such as a nuclear steam generator having an exterior bottom surface and a side surface thereon. The system includes a bracket connected to the bottom surface. A support column is pivotally connected to the bracket for vertically supporting the steam generator. The system also includes a base pad assembly connected pivotally to the support column for supporting the support column and the steam generator. The base pad assembly, which is capable of being brought to a level position by turning leveling nuts, is anchored to a floor. The system further includes a male key member attached to the side surface of the steam generator and a female stop member attached to an adjacent wall. The male key member and the female stop member coact to laterally support the steam generator. Moreover, the system includes a snubber assembly connected to the side surface of the steam generator and also attached to the adjacent wall for dampening lateral movement of the steam generator. In addition, the system includes a restraining member of "flat" attached to the side surface of the steam generator and a bumper attached to the adjacent wall. The flat and the bumper coact to further laterally support the steam generator.

  20. Coal gasification vessel

    DOE Patents [OSTI]

    Loo, Billy W. (Oakland, CA)

    1982-01-01T23:59:59.000Z

    A vessel system (10) comprises an outer shell (14) of carbon fibers held in a binder, a coolant circulation mechanism (16) and control mechanism (42) and an inner shell (46) comprised of a refractory material and is of light weight and capable of withstanding the extreme temperature and pressure environment of, for example, a coal gasification process. The control mechanism (42) can be computer controlled and can be used to monitor and modulate the coolant which is provided through the circulation mechanism (16) for cooling and protecting the carbon fiber and outer shell (14). The control mechanism (42) is also used to locate any isolated hot spots which may occur through the local disintegration of the inner refractory shell (46).

  1. Information friction : information technology and military performance

    E-Print Network [OSTI]

    Lindsay, Jon Randall

    2011-01-01T23:59:59.000Z

    Militaries have long been eager to adopt the latest technology (IT) in a quest to improve knowledge of and control over the battlefield. At the same time, uncertainty and confusion have remained prominent in actual experience ...

  2. 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.

  3. CHF Enhancement by Vessel Coating for External Reactor Vessel Cooling

    SciTech Connect (OSTI)

    Fan-Bill Cheung; Joy L. Rempe

    2004-06-01T23:59:59.000Z

    In-vessel retention (IVR) is a key severe accident management (SAM) strategy that has been adopted by some operating nuclear power plants and advanced light water reactors (ALWRs). One viable means for IVR is the method of external reactor vessel cooling (ERVC) by flooding of the reactor cavity during a severe accident. As part of a joint Korean – United States International Nuclear Energy Research Initiative (K-INERI), an experimental study has been conducted to investigate the viability of using an appropriate vessel coating to enhance the critical heat flux (CHF) limits during ERVC. Toward this end, transient quenching and steady-state boiling experiments were performed in the SBLB (Subscale Boundary Layer Boiling) facility at Penn State using test vessels with micro-porous aluminum coatings. Local boiling curves and CHF limits were obtained in these experiments. When compared to the corresponding data without coatings, substantial enhancement in the local CHF limits for the case with surface coatings was observed. Results of the steady state boiling experiments showed that micro-porous aluminum coatings were very durable. Even after many cycles of steady state boiling, the vessel coatings remained rather intact, with no apparent changes in color or structure. Moreover, the heat transfer performance of the coatings was found to be highly desirable with an appreciable CHF enhancement in all locations on the vessel outer surface but with very little effect of aging.

  4. Level indicator for pressure vessels

    DOE Patents [OSTI]

    Not Available

    1982-04-28T23:59:59.000Z

    A liquid-level monitor for tracking the level of a coal slurry in a high-pressure vessel including a toroidal-shaped float with magnetically permeable bands thereon disposed within the vessel, two pairs of magnetic-field generators and detectors disposed outside the vessel adjacent the top and bottom thereof and magnetically coupled to the magnetically permeable bands on the float, and signal-processing circuitry for combining signals from the top and bottom detectors for generating a monotonically increasing analog control signal which is a function of liquid level. The control signal may be utilized to operate high-pressure control valves associated with processes in which the high-pressure vessel is used.

  5. China’s Military Representatives: Striving Toward Professional Contracting and Procurement

    E-Print Network [OSTI]

    Puska, Susan M; McReynolds, Joe; Geary, Debra

    2011-01-01T23:59:59.000Z

    di- rection. Military representative reform could raise2011 China’s Military Representatives: Striving Towardreforms is the Military Representative Office (MRO) system

  6. ARPA-E: Improving Military Energy Security

    SciTech Connect (OSTI)

    Willson, Bryan; Mahvi, Allison; Stepien, Tom; Wasco, Mick

    2014-02-24T23:59:59.000Z

    The U.S. military has a vested interest in advancing microgrid technologies that can power forward operating bases. These technologies could not only help the military significantly reduce its energy demand both at home and abroad, but also they could reduce the number of fuel-supply convoys required on the battlefield and the number of troops killed in fuel-supply convoy attacks. This video highlights two ARPA-E projects that have formed strategic partnerships with the military to enable these microgrids at forward operating bases. Georgia Tech is developing an innovative absorption heat pump that utilizes exhaust heat to provide heating and cooling, which could cut the amount of energy used to heat and cool forward operating bases by 50%. Primus Power is developing a low-cost, energy-dense storage system that could store enough energy to operate a base for several days in the event of a disruption.

  7. ARPA-E: Improving Military Energy Security

    ScienceCinema (OSTI)

    Willson, Bryan; Mahvi, Allison; Stepien, Tom; Wasco, Mick

    2014-03-13T23:59:59.000Z

    The U.S. military has a vested interest in advancing microgrid technologies that can power forward operating bases. These technologies could not only help the military significantly reduce its energy demand both at home and abroad, but also they could reduce the number of fuel-supply convoys required on the battlefield and the number of troops killed in fuel-supply convoy attacks. This video highlights two ARPA-E projects that have formed strategic partnerships with the military to enable these microgrids at forward operating bases. Georgia Tech is developing an innovative absorption heat pump that utilizes exhaust heat to provide heating and cooling, which could cut the amount of energy used to heat and cool forward operating bases by 50%. Primus Power is developing a low-cost, energy-dense storage system that could store enough energy to operate a base for several days in the event of a disruption.

  8. Tailoring Topology Optimization to Composite Pressure Vessel Design with Simultaneous

    E-Print Network [OSTI]

    Paulino, Glaucio H.

    ;Introduction ­ CNG Pressure Vessels Compressed Natural Gas (CNG) Pressure Vessels CNG Cargo Containment System

  9. electricity rates for military bases | OpenEI Community

    Open Energy Info (EERE)

    electricity rates for military bases Home > Groups > Utility Rate Hi, I was hoping to find rates for military bases, but have been unable to find anything. Are they just charged as...

  10. Tribal and Military Leaders Come Together to Talk Renewable Energy...

    Office of Environmental Management (EM)

    and Military Leaders Come Together to Talk Renewable Energy Tribal and Military Leaders Come Together to Talk Renewable Energy June 12, 2013 - 7:06pm Addthis The DOE Office of...

  11. Net Zero Energy Military Installations: A Guide to Assessment...

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

    Net Zero Energy Military Installations: A Guide to Assessment and Planning Net Zero Energy Military Installations: A Guide to Assessment and Planning In 2008, DoD and DOE defined a...

  12. Military Munitions Waste Working Group report

    SciTech Connect (OSTI)

    Not Available

    1993-11-30T23:59:59.000Z

    This report presents the findings of the Military Munitions Waste Working Group in its effort to achieve the goals directed under the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT Committee) for environmental restoration and waste management. The Military Munitions Waste Working Group identified the following seven areas of concern associated with the ordnance (energetics) waste stream: unexploded ordnance; stockpiled; disposed -- at known locations, i.e., disposal pits; discharged -- impact areas, unknown disposal sites; contaminated media; chemical sureties/weapons; biological weapons; munitions production; depleted uranium; and rocket motor and fuel disposal (open burn/open detonation). Because of time constraints, the Military Munitions Waste Working Group has focused on unexploded ordnance and contaminated media with the understanding that remaining waste streams will be considered as time permits. Contents of this report are as follows: executive summary; introduction; Military Munitions Waste Working Group charter; description of priority waste stream problems; shortcomings of existing approaches, processes and technologies; innovative approaches, processes and technologies, work force planning, training, and education issues relative to technology development and cleanup; criteria used to identify and screen potential demonstration projects; list of potential candidate demonstration projects for the DOIT committee decision/recommendation and appendices.

  13. Nanowarriors: Military Nanotechnology and Comic Books

    E-Print Network [OSTI]

    Nanowarriors: Military Nanotechnology and Comic Books Colin Milburn U N I V E R S I T Y O F C A L I with nanotechnology. The Army Research Office had issued broad agency solicitations for such a center in October 2001 what became dubbed the MIT Institute for Soldier Nanotechnologies (ISN). MIT's proposal out- lined

  14. Cultural intelligence support for military operations

    SciTech Connect (OSTI)

    Guthormsen, Amy M. [Los Alamos National Laboratory; MacKerrow, Edward P [Los Alamos National Laboratory; Merritt, Terence M [Los Alamos National Laboratory; Morgart, Ruth E [INTERNATIONAL ATOMIC ENERGY

    2010-04-08T23:59:59.000Z

    It has long been recognized that military success relies on knowledge of the enemy. In the context of standard warfare, adequate knowledge of the enemy may be gained by analyzing observable, measurable data. In the context of modern counterinsurgency operations and the global war on terror, the task of predicting the behavior of the enemy is vastly more complex and difficult. Without an understanding of the ways individuals in the host nation interpret and react to events, no amount of objective information can provide the insight required to accurately predict behavior. US military doctrine has begun to recognize the importance of the many ways that local culture can affect operation success. Increasingly military decision makers use cultural information in the service of operation planning, and troops are provided with pre-deployment cultural training. However, no amount of training can cover the breadth and depth of potentially useful cultural information, and no amount of careful planning can avoid the need to adapt as situations develop. Therefore, a critical challenge is to provide useful tools to US personnel in their efforts to collect, analyze, and utilize cultural information. Essential functions for cultural support tools include the following: (1) to narrow down a broad range of available data and focus the user's attention on context-relevant information, (2) to present cultural information in an easily understood form, (3) to prompt the user to seek relevant information in the environment, (4) to synthesize information, and (5) to predict outcomes based on possible courses of operation. In this paper, we begin by reviewing the ways in which military operations can benefit from cultural intelligence. We then discuss frameworks for analyzing cultural information in the context of a military operation. We conclude with a demonstration of our current efforts to develop a tool that meets the aforementioned functional challenges.

  15. Military housing foam application and analysis

    SciTech Connect (OSTI)

    Torres, J. J.

    2012-03-01T23:59:59.000Z

    Sandia and Forest City have established a Cooperative Research and Development Agreement (CRADA), the partnership provides a unique opportunity to take technology research and development from demonstration to application in sustainable communities. This project consists of two activities conducted in Hawaii that focus on performance, integration and application of energy saving technologies. Hawaii has many energy challenges, making this location an excellent testbed for these activities. Under this project, spray foam technology was applied at military housing on Oahu and the consumption data collected. A cost benefit and operational analysis of the foam was completed. The second phase of this project included design, integration, and analysis of photovoltaic systems at a military community on Oahu. This phase of the project was conducted as part of Forest City's second Solar America Showcase Award.

  16. Light Sources on the Nylon Vessels' Surfaces

    E-Print Network [OSTI]

    Chapter 7 Light Sources on the Nylon Vessels' Surfaces The nylon vessels are justifiably the most the IV. A set of light diffusers has been placed on pre-defined points of both vessels. These are attached to the tip of an optical fiber that carries light from a source outside the WT (LED 184 #12

  17. Sandia National Laboratories: Integrated Military Systems

    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 ScienceandMesa del Sol HomeFacebook Twitter YouTube Flickr RSS Top DefenseIntegrated Military Systems

  18. Net Zero Energy Military Installations: A Guide to Assessment...

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

    Net Zero Energy Military Installations: A Guide to Assessment and Planning Samuel Booth, John Barnett, Kari Burman, Josh Hambrick and Robert Westby Technical Report NREL...

  19. ORNL tests energy-efficient technologies for expeditionary military...

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

    tests energy-efficient technologies for expeditionary military bases in the tropics Over the summer, ORNL researchers tested the performance of various tent configurations and HVAC...

  20. Report: U.S. Military Accelerates Deployment of Clean Energy...

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

    Navigant Research, Pew's clean energy research partner for this report, 384 megawatts of installed renewable energy capacity are intalled on military facilities in mid-2013. By...

  1. army military government: Topics by E-print Network

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

    2012-01-01 4 Politicized armies, militarized politics : civil-military relations in Turkey and Greece MIT - DSpace Summary: Despite their common Ottoman heritage, Greece and...

  2. army size military: Topics by E-print Network

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

    2012-01-01 4 Politicized armies, militarized politics : civil-military relations in Turkey and Greece MIT - DSpace Summary: Despite their common Ottoman heritage, Greece and...

  3. Political and military implications of the ''nuclear winter'' theory

    SciTech Connect (OSTI)

    Lynch, A.

    1987-01-01T23:59:59.000Z

    Soviet and U.S. views of the nuclear winter theory and the theory's significance for alliance relationships and military policy are discussed in this book.

  4. The Relationship between Grit and Academic, Military and Physical Performance at the United States Military Academy

    E-Print Network [OSTI]

    Buller, Eric F.

    2012-12-31T23:59:59.000Z

    during the admissions process and utilizes the recently developed and validated Grit Scale, a 12-question instrument that measures trait-level perseverance and passion for long-term goals. The Grit Scale was given to the United States Military Academy...

  5. Changes in Russia's Military and Nuclear Doctrine

    SciTech Connect (OSTI)

    Wolkov, Benjamin M. [Los Alamos National Laboratory; Balatsky, Galya I. [Los Alamos National Laboratory

    2012-07-26T23:59:59.000Z

    In 1993, the Russian Federation set out a new military doctrine that would determine the direction of its armed forces until President Putin set out the next doctrine in 2000. The Russian Federation creating the doctrine was new; the USSR had recently collapsed, Gorbachev - the creator of the predecessor to this doctrine in 1987 - was out of office, and the new Russian military had only been formed in May, 1992.1 The analysis of the 1993 doctrine is as follows: a definition of how doctrine is defined; a short history of Russian military doctrine leading up to the 1993 doctrine (officially the Basic Provisions of the Military Doctrine of the Russian Federation); and finally, what the doctrine established. An overview of the 1993 doctrine is: (1) Russia's 1993 doctrine was a return to older, more aggressive doctrine as a result of stability concerns surrounding the recent collapse of the USSR; (2) Russia turned from Gorbachev's 'defensive defense' in the 1987 doctrine to aggressive defense with the option of preempting or striking back against an aggressor; (3) Russia was deeply concerned about how nationalism would affect the former Soviet Republics, particularly in respect to the ethnic Russians still living abroad; and (4) Nuclear doctrine pledged to not be the first to use nuclear weapons but provided for the potential for escalation from a conventional to a nuclear war. The 2000 doctrine (officially the Russian Federation Military Doctrine) was created in a more stable world than the 1993 doctrine was. The Russian Federation had survived independence and the 'threat of direct military aggression against the Russian Federation and its allies' had diminished. It had secured all of the nuclear weapons from its neighbors Ukraine, Belarus, and Kazakhstan, and had elected a new president, Vladimir Putin, to replace Boris Yeltsin. Yet, even as the doctrine took more defensive tones than the 1993 doctrine, it expanded its nuclear options. Below are a new definition of what doctrine meant in 2000 and an outline of the 2000 doctrine. An overview of the 2000 doctrine is: (1) The 2000 doctrine was a return to a more defensive posture; the threat of nuclear retaliation, rather than that of preemptive force, would be its deterrence; (2) In order to strengthen its nuclear deterrence, Russia extended and redefined the cases in which nuclear weapons could be used to include a wider range of conflict types and a larger spectrum of attackers; and (3) Russia's threats changed to reflect its latest fear of engaging in a limited conflict with no prospect of the use of nuclear deterrence. In 2006, the defense minister and deputy prime minister Sergei Ivanov announced that the government was starting on a draft of a future doctrine. Four years later, in 2010, the Military Doctrine of the Russian Federation was put into effect with the intent of determining Russian doctrine until 2020. The 2010 doctrine, like all previous doctrines, was a product of the times in which it was written. Gone were many of the fears that had followed Russia for the past two decades. Below are an examination of the 2010 definition of doctrine as well as a brief analysis of the 2010 doctrine and its deviations from past doctrines. An overview of the 2010 doctrine is: (1) The new doctrine emphasizes the political centralization of command both in military policy and the use of nuclear weapons; (2) Nuclear doctrine remains the same in many aspects including the retention of first-use; (3) At the same time, doctrine was narrowed to using nuclear weapons only when the Russian state's existence is in danger; to continue strong deterrence, Russia also opted to follow the United States by introducing precision conventional weapons; (4) NATO is defined as Russia's primary external threat because of its increased global presence and its attempt to recruit states that are part of the Russian 'bloc'; and (5) The 2000 doctrine's defensive stance was left out of the doctrine; rumored options for use of nuclear weapons in local wars and in preemptive strikes were also left out.

  6. 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.

  7. Tow Vessel | 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 IRaghuraji Agro Industries PvtStratosolarTharaldsonInformationTorpedo SpecialityVessel Jump to:

  8. Net Zero Energy Military Installations: A Guide to

    E-Print Network [OSTI]

    Net Zero Energy Military Installations: A Guide to Assessment and Planning Samuel Booth, John;Technical Report Net Zero Energy Military NREL/TP-7A2-48876 Installations: A Guide to August 2010 Assessment .......................................................................................................................................1 1 Introduction: Net Zero Energy In DoD Context

  9. ITAM SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    ITAM SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS CEMML | 1490 Campus Delivery://www.cemml.colostate.edu The Integrated Training Area Management (ITAM) Program maintains training lands so that they meet Army doctrinal with conservation of the soils, water, flora, and fauna on military installations. The ITAM Program comprises four

  10. SPONSOREDBY The University of North Texas Military History Center and

    E-Print Network [OSTI]

    Mohanty, Saraju P.

    SPONSOREDBY The University of North Texas Military History Center and The Texas A&M University ­ Central Texas Department of History and Political Science WITHTHESUPPORTOFOURPARTNERS The Association Military Academy at West Point Author of: GeorgeWashington&BenedictArnold:ATaleofTwoPatriots 1330

  11. The military lens : doctrinal differences, misperception, and deterrence failure in Sino-American relations

    E-Print Network [OSTI]

    Twomey, Christopher P

    2005-01-01T23:59:59.000Z

    Nations, because of their different strategic situations, histories, and military cultures can have dramatically different beliefs about the nature of effective military doctrine, strategy, and capabilities. This dissertation ...

  12. Reactor pressure vessel vented head

    DOE Patents [OSTI]

    Sawabe, J.K.

    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. 6 figures.

  13. 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)

  14. Fabrication of Separator Demonstration Facility process vessel

    SciTech Connect (OSTI)

    Oberst, E.F.

    1985-01-15T23:59:59.000Z

    The process vessel system is the central element in the Separator Development Facility (SDF). It houses the two major process components, i.e., the laser-beam folding optics and the separators pods. This major subsystem is the critical-path procurement for the SDF project. Details of the vaious parts of the process vessel are given.

  15. Foam vessel for cryogenic fluid storage

    DOE Patents [OSTI]

    Spear, Jonathan D (San Francisco, CA)

    2011-07-05T23:59:59.000Z

    Cryogenic storage and separator vessels made of polyolefin foams are disclosed, as are methods of storing and separating cryogenic fluids and fluid mixtures using these vessels. In one embodiment, the polyolefin foams may be cross-linked, closed-cell polyethylene foams with a density of from about 2 pounds per cubic foot to a density of about 4 pounds per cubic foot.

  16. Application for Amendment 80 Vessel Replacement Page 1 of 6

    E-Print Network [OSTI]

    Application for Amendment 80 Vessel Replacement Page 1 of 6 Revised: 12/23/2013 OMB Control No. 0648-0565 Expiration Date: 01/31/2016 APPLICATION FOR AMENDMENT 80 VESSEL REPLACEMENT United States OF THE AMENDMENT 80 VESSEL BEING REPLACED 1. Vessel Name: 2. ADF&G Vessel Registration No.: 3. USCG Documentation

  17. 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.

  18. Role of nuclear reactors in future military satellites

    SciTech Connect (OSTI)

    Buden, D.; Angelo, J.A. Jr.

    1982-01-01T23:59:59.000Z

    Future military capabilities will be profoundly influenced by emerging Shuttle Era space technology. Regardless of the specific direction or content of tomorrow's military space program, it is clear that advanced space transportation systems, orbital support facilities, and large-capacity power subsystems will be needed to create the generally larger, more sophisticated military space systems of the future. This paper explores the critical role that space nuclear reactors should play in America's future space program and reviews the current state of nuclear reactor power plant technology. Space nuclear reactor technologies have the potential of satisfying power requirements ranging from 10 kW/sub (e)/ to 100 MW/sub (e)/.

  19. Loyalty for Sale? Military Spending and Coups d'Etat

    E-Print Network [OSTI]

    Leon, Gabriel

    2012-02-27T23:59:59.000Z

    and ragged uniform, sometimes without boots during his training period" (Afrifa, 1966). Furthermore, governments can use military spending to ?buy o¤?the military and keep it from staging coups. Nordlinger (1977) cites the example of President Romulo... their sample to cases in which the weapon was used, so that the outcome of the assassination attempt can be taken as random. 3 that mean average military spending (as a fraction of GDP) before a successful coup is lower than that before a failed coup...

  20. Reactor pressure vessel. Status report

    SciTech Connect (OSTI)

    Elliot, B.J.; Hackett, E.M.; Lee, A.D. [and others

    1996-10-01T23:59:59.000Z

    This report describes the issues raised as a result of the staffs review of Generic Letter (GL) 92-01, Revision 1, responses and plant-specific reactor pressure vessel (RPV) assessments and the actions taken or work in progress to address these issues. In addition, the report describes actions taken by the staff and the nuclear industry to develop a thermal annealing process for use at U.S. commercial nuclear power plants. This process is intended to be used as a means of mitigating the effects of neutron radiation on the fracture toughness of RPV materials. The Nuclear Regulatory Commission (NRC) issued GL 92-01, Revision 1, Supplement 1, to obtain information needed to assess compliance with regulatory requirements and licensee commitments regarding RPV integrity. GL 92-01, Revision 1, Supplement 1, was issued as a result of generic issues that were raised in the NRC staff`s reviews of licensee responses to GL 92-01, Revision 1, and plant-specific RPV evaluations. In particular, an integrated review of all data submitted in response to GL 92-01, Revision 1, indicated that licensees may not have considered all relevant data in their RPV assessments. This report is representative of submittals to and evaluations by the staff as of September 30, 1996. An update of this report will be issued at a later date.

  1. Lightweight bladder lined pressure vessels

    DOE Patents [OSTI]

    Mitlitsky, F.; Myers, B.; Magnotta, F.

    1998-08-25T23:59:59.000Z

    A lightweight, low permeability liner is described for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using tori spherical or near tori spherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film sealed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life. 19 figs.

  2. Lightweight bladder lined pressure vessels

    DOE Patents [OSTI]

    Mitlitsky, Fred (1125 Canton Ave., Livermore, CA 94550); Myers, Blake (4650 Almond Cir., Livermore, CA 94550); Magnotta, Frank (1206 Bacon Way, Lafayette, CA 94549)

    1998-01-01T23:59:59.000Z

    A lightweight, low permeability liner for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using torispherical or near torispherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film seamed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life.

  3. Establishing a virtual manufacturing environment for military robots

    E-Print Network [OSTI]

    Andersen, Ryan J. (Ryan John)

    2007-01-01T23:59:59.000Z

    Recent advances in the robotics industry have given the military an opportunity to capitalize on industry's innovation. Not only has core robotics technology improved but robotics manufacturing technology has also made ...

  4. UNIT TYPE MILITARY PROVIDES IIT PROVIDES (Navy/Marines)

    E-Print Network [OSTI]

    Heller, Barbara

    UNIT TYPE MILITARY PROVIDES IIT PROVIDES Naval (Navy/Marines) 4 year­Type 1 Full tuition and fees. Room and board* for all 4 years. Navy (Must be currently enlisted personnel) STA-21 Seaman to Admiral

  5. 17.952 Great Power Military Intervention, Spring 2004

    E-Print Network [OSTI]

    Posen, Barry

    The purpose of this seminar is to examine systematically, and comparatively, great and middle power military interventions into civil wars during the 1990's. These civil wars were high on the policy agenda of western states ...

  6. Military housing privatization & the promise of design innovation

    E-Print Network [OSTI]

    Ellis, Jason (Jason Robert)

    2009-01-01T23:59:59.000Z

    The objective of this paper is to answer the question, "Has the military housing privatization process produced design innovation?" Secondary questions are, "What specific role has the Army's Residential Communities ...

  7. Shooting up : the impact of illicit economics on military conflict

    E-Print Network [OSTI]

    Felbab-Brown, Vanda

    2007-01-01T23:59:59.000Z

    The study explores the nexus between illicit economies and military conflicts. It investigates when and how access by belligerents to the production and trafficking of illicit substances affects the strength of belligerents ...

  8. 17.950 Understanding Modern Military Operations, Spring 2005

    E-Print Network [OSTI]

    Cote, Owen R., 1960-

    A proper understanding of modern military operations requires a prior understanding of both the material side of war, including especially weapon, sensor, communication, and information processing technologies, and the ...

  9. CULTURAL RESOURCES SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    D installations. SERVICES · Planning level surveys for archaeological resources, traditional cultural properties and structures · Integrated Cultural Resource Management Plans (ICRMPs) · Archaeological resource monitoringCULTURAL RESOURCES SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS CEMML | 1490

  10. First War Syndrome : military culture, professionalization, and counterinsurgency doctrine

    E-Print Network [OSTI]

    Long, Austin G

    2010-01-01T23:59:59.000Z

    Counterinsurgency was a persistent and important challenge to military organizations in the second half of the 20th century and seems likely to continue to pose a challenge in the 21st century. This makes understanding how ...

  11. Glossary Glossary

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

    F-77), and Bunker C fuel oil. Residual fuel oil is used for the production of electric power, space heating, vessel bunkering, and various industrial purposes. Retailer: A firm...

  12. Glossary

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

    F-77), and Bunker C fuel oil. Residual fuel oil is used for the production of electric power, space heating, vessel bunkering, and various industrial purposes. Retailer: A firm...

  13. Domestic Audiences, Policy Feedback, and Sequential Decisions During Military Interventions

    E-Print Network [OSTI]

    Kuberski, Douglas Walter

    2011-02-22T23:59:59.000Z

    Committee Members, Michael Koch Guy Whitten Charles Hermann Head of Department, James Rogers December 2009 Major Subject: Political Science iii ABSTRACT Domestic Audiences, Policy Feedback, and Sequential Decisions During Military... how an individual citizen?s preference over commitment is impacted by policy feedback. The results of the experimental analyses suggest that citizens act as investors: they favor increasing commitment to military interventions when viewing negative...

  14. The occurrence of military coups in Latin America: some speculations 

    E-Print Network [OSTI]

    Cediel, Maria Cecilia Canals de

    1981-01-01T23:59:59.000Z

    THE OCCURRENCE OF MILITARY COUPS IN LATIN AMERICA: SOME SPECULATIONS A Thesis by MARIA CECILIA CANALS DE CEDIEL Submitted to the Graduate Colleqe of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER... OF ARTS Mav 1981 Major Subiect: Political Science THE OCCURRENCE OF MILITARY COUPS IN LATIN AMERICA: SOME SPECULATIONS A Thesis by MARIA CECILIA CANALS DE CEDIEL Approved as to sty1e and content by: (Chairman of Committee) / (Member) (Member...

  15. The occurrence of military coups in Latin America: some speculations

    E-Print Network [OSTI]

    Cediel, Maria Cecilia Canals de

    1981-01-01T23:59:59.000Z

    THE OCCURRENCE OF MILITARY COUPS IN LATIN AMERICA: SOME SPECULATIONS A Thesis by MARIA CECILIA CANALS DE CEDIEL Submitted to the Graduate Colleqe of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER... OF ARTS Mav 1981 Major Subiect: Political Science THE OCCURRENCE OF MILITARY COUPS IN LATIN AMERICA: SOME SPECULATIONS A Thesis by MARIA CECILIA CANALS DE CEDIEL Approved as to sty1e and content by: (Chairman of Committee) / (Member) (Member...

  16. Thermal wake/vessel detection technique

    DOE Patents [OSTI]

    Roskovensky, John K. (Albuquerque, NM); Nandy, Prabal (Albuquerque, NM); Post, Brian N (Albuquerque, NM)

    2012-01-10T23:59:59.000Z

    A computer-automated method for detecting a vessel in water based on an image of a portion of Earth includes generating a thermal anomaly mask. The thermal anomaly mask flags each pixel of the image initially deemed to be a wake pixel based on a comparison of a thermal value of each pixel against other thermal values of other pixels localized about each pixel. Contiguous pixels flagged by the thermal anomaly mask are grouped into pixel clusters. A shape of each of the pixel clusters is analyzed to determine whether each of the pixel clusters represents a possible vessel detection event. The possible vessel detection events are represented visually within the image.

  17. artificial blood vessel: Topics by E-print Network

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

    Websites Summary: HEART AND BLOOD VESSELS CARDIOVASCULARCARDIOVASCULAR SYSTEMSYSTEM SYSTEM COMPONENTS Heart pumps blood though blood vessels where exchanges can take place...

  18. Automatic Lung Vessel Segmentation via Stacked Multiscale Feature Learning

    E-Print Network [OSTI]

    Toronto, University of

    Automatic Lung Vessel Segmentation via Stacked Multiscale Feature Learning Ryan Kiros, Karteek We introduce a representation learning approach to segmenting vessels in the lungs. Our algorithm

  19. Ion transport membrane module and vessel system

    DOE Patents [OSTI]

    Stein, VanEric Edward (Allentown, PA); Carolan, Michael Francis (Allentown, PA); Chen, Christopher M. (Allentown, PA); Armstrong, Phillip Andrew (Orefield, PA); Wahle, Harold W. (North Canton, OH); Ohrn, Theodore R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Rackers, Keith Gerard (Louisville, OH); Blake, James Erik (Uniontown, OH); Nataraj, Shankar (Allentown, PA); van Doorn, Rene Hendrik Elias (Obersulm-Willsbach, DE); Wilson, Merrill Anderson (West Jordan, UT)

    2008-02-26T23:59:59.000Z

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel.The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

  20. Ion transport membrane module and vessel system

    DOE Patents [OSTI]

    Stein, VanEric Edward (Allentown, PA); Carolan, Michael Francis (Allentown, PA); Chen, Christopher M. (Allentown, PA); Armstrong, Phillip Andrew (Orefield, PA); Wahle, Harold W. (North Canton, OH); Ohrn, Theodore R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Rackers, Keith Gerard (Louisville, OH); Blake, James Erik (Uniontown, OH); Nataraj, Shankar (Allentown, PA); Van Doorn, Rene Hendrik Elias (Obersulm-Willsbach, DE); Wilson, Merrill Anderson (West Jordan, UT)

    2012-02-14T23:59:59.000Z

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an exterior, an inlet, and an outlet; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region, wherein any inlet and any outlet of the pressure vessel are in flow communication with exterior regions of the membrane modules; and (c) one or more gas manifolds in flow communication with interior regions of the membrane modules and with the exterior of the pressure vessel. The ion transport membrane system may be utilized in a gas separation device to recover oxygen from an oxygen-containing gas or as an oxidation reactor to oxidize compounds in a feed gas stream by oxygen permeated through the mixed metal oxide ceramic material of the membrane modules.

  1. Future characteristics of Offshore Support Vessels

    E-Print Network [OSTI]

    Rose, Robin Sebastian Koske

    2011-01-01T23:59:59.000Z

    The objective of this thesis is to examine trends in Offshore Support Vessel (OSV) design and determine the future characteristics of OSVs based on industry insight and supply chain models. Specifically, this thesis focuses ...

  2. 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.

  3. PURE NIOBIUM AS A PRESSURE VESSEL MATERIAL

    SciTech Connect (OSTI)

    Peterson, T. J.; Carter, H. F.; Foley, M. H.; Klebaner, A. L.; Nicol, T. H.; Page, T. M.; Theilacker, J. C.; Wands, R. H.; Wong-Squires, M. L.; Wu, G. [Fermi National Accelerator Laboratory, Batavia, Illinois 60510 (United States)

    2010-04-09T23:59:59.000Z

    Physics laboratories around the world are developing niobium superconducting radio frequency (SRF) cavities for use in particle accelerators. These SRF cavities are typically cooled to low temperatures by direct contact with a liquid helium bath, resulting in at least part of the helium container being made from pure niobium. In the U.S., the Code of Federal Regulations allows national laboratories to follow national consensus pressure vessel rules or use of alternative rules which provide a level of safety greater than or equal to that afforded by ASME Boiler and Pressure Vessel Code. Thus, while used for its superconducting properties, niobium ends up also being treated as a material for pressure vessels. This report summarizes what we have learned about the use of niobium as a pressure vessel material, with a focus on issues for compliance with pressure vessel codes. We present results of a literature search for mechanical properties and tests results, as well as a review of ASME pressure vessel code requirements and issues.

  4. The Shanghai Six:The Shanghai Six: Milit Th t E i Alli ?Milit Th t E i Alli ?Military Threat or Economic Alliance?Military Threat or Economic Alliance?

    E-Print Network [OSTI]

    New Hampshire, University of

    The Shanghai Six:The Shanghai Six: Milit Th t E i Alli ?Milit Th t E i Alli ?Military Threat or Economic Alliance?Military Threat or Economic Alliance? Anna BrownAnna Brown #12;Maps courtesy of Google Maps. #12;Is the SCO a Military Threat?Is the SCO a Military Threat?Is the SCO a Military Threat

  5. United States Department of Energy projects related to reactor pressure vessel annealing optimization

    SciTech Connect (OSTI)

    Rosinski, S.T.; Nakos, J.T.

    1993-09-01T23:59:59.000Z

    Light water reactor pressure vessel (RPV) material properties reduced by long-term exposure to neutron irradiation can be recovered through a thermal annealing treatment. This technique to extend RPV life, discussed in this report, provides a complementary approach to analytical methodologies to evaluate RPV integrity. RPV annealing has been successfully demonstrated in the former Soviet Union and on a limited basis by the US (military applications only). The process of demonstrating the technical feasibility of annealing commercial US RPVs is being pursued through a cooperative effort between the nuclear industry and the US Department of Energy (USDOE) Plant Lifetime Improvement (PLIM) Program. Presently, two projects are under way through the USDOE PLIM Program to demonstrate the technical feasibility of annealing commercial US RPVS, (1) annealing re-embrittlement data base development and (2) heat transfer boundary condition experiments.

  6. Vulnerability of Xylem Vessels to Cavitation in Sugar Maple. Scaling from Individual Vessels to

    E-Print Network [OSTI]

    Melcher, Peter

    nega- tive pressures (Dixon and Joly, 1895; Briggs, 1950) allows plants to power the movement of water to withstand tension-induced cavitation is typ- ically inferred from "vulnerability curves" generatedVulnerability of Xylem Vessels to Cavitation in Sugar Maple. Scaling from Individual Vessels

  7. A perspective on safeguarding and monitoring of excess military plutonium

    SciTech Connect (OSTI)

    Sutcliffe, W.G.

    1994-10-02T23:59:59.000Z

    The purpose of this paper is to provide a perspective and framework for the development of safeguarding and monitoring procedures for the various stages of disposition of excess military plutonium. The paper briefly outlines and comments on some of the issues involved in safeguarding and monitoring excess military plutonium as it progresses from weapons through dismantlement, to fabrication as reactor fuel, to use in a reactor, and finally to storage and disposal as spent fuel. {open_quotes}Military{close_quotes} refers to ownership, and includes both reactor-grade and weapon-grade plutonium. {open_quotes}Excess{close_quotes} refers to plutonium (in any form) that a government decides is no longer needed for military use and can be irrevocably removed from military stockpiles. Many of the issues and proposals presented in this paper are based on, or are similar to, those mentioned in the National Academy of Sciences (NAS) report on excess military plutonium. Safeguards for plutonium disposition are discussed elsewhere in terms of requirements established by the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission (NRC), and the International Atomic Energy Agency (IAEA). Here, the discussion is less specific. The term {open_quotes}safeguarding{close_quotes} is used broadly to refer to materials control and accountancy (MC&A), containment and surveillance (C&S), and physical protection of nuclear materials by the state that possesses those materials. This is also referred to as material protection, control, and accountancy (MPCA). The term {open_quotes}safeguarding{close_quotes} was chosen for brevity and to distinguish MPCA considered in this paper from international or IAEA safeguards. {open_quotes}Monitoring{close_quotes} is used to refer to activities designed to assure another party (state or international organization) that the nuclear materials of the host state (the United States or Russia) are secure and not subject to unauthorized use.

  8. Fourth Generation Nuclear Weapons: Military effectiveness and collateral effects

    E-Print Network [OSTI]

    Gsponer, A

    2005-01-01T23:59:59.000Z

    The paper begins with a general introduction and update to Fourth Generation Nuclear Weapons (FGNW), and then addresses some particularly important military aspects on which there has been only limited public discussion so far. These aspects concern the unique military characteristics of FGNWs which make them radically different from both nuclear weapons based on previous-generation nuclear-explosives and from conventional weapons based on chemical-explosives: yields in the 1 to 100 tons range, greatly enhanced coupling to targets, possibility to drive powerful shaped charged jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

  9. EDS V25 containment vessel explosive qualification test report.

    SciTech Connect (OSTI)

    Rudolphi, John Joseph

    2012-04-01T23:59:59.000Z

    The V25 containment vessel was procured by the Project Manager, Non-Stockpile Chemical Materiel (PMNSCM) as a replacement vessel for use on the P2 Explosive Destruction Systems. It is the first EDS vessel to be fabricated under Code Case 2564 of the ASME Boiler and Pressure Vessel Code, which provides rules for the design of impulsively loaded vessels. The explosive rating for the vessel based on the Code Case is nine (9) pounds TNT-equivalent for up to 637 detonations. This limit is an increase from the 4.8 pounds TNT-equivalency rating for previous vessels. This report describes the explosive qualification tests that were performed in the vessel as part of the process for qualifying the vessel for explosive use. The tests consisted of a 11.25 pound TNT equivalent bare charge detonation followed by a 9 pound TNT equivalent detonation.

  10. "The Second American School of Arms": the Virginia Military Institute and the advent of state military education, 1835-1851

    E-Print Network [OSTI]

    Wineman, Bradford Alexander

    2001-01-01T23:59:59.000Z

    ) Charles E. Brooks (Member) James Burk (Member) ia elder ( d of Depart t December 2001 Major Subject: History ABSTRACT "The Second American School of Arms": The Virginia Military Institute and the Advent of State Military Education, 1835... be established in Virginia. . . . . "" On August 28, 1835, the first of Preston's three articles appeared in the L~Gtt. g t bg b y d tyby fdtgbt d f their rights as free citizens of the republic. The use of public funds, the taxes from the state's residents...

  11. Synchronization of system-of-systems interfaces in military satellite communications

    E-Print Network [OSTI]

    Davis, Mark J. (Mark Jeffrey)

    2008-01-01T23:59:59.000Z

    Military systems continue to become more complex and nearly all are now part of one or more system of systems (SoS). Military satellite communications programs have expanded over the last decade from three distinct satellite ...

  12. The Harmony of Yin and Yank: The American Military Advisory Effort in China, 1941-1951

    E-Print Network [OSTI]

    Babb, Joseph G.

    2012-08-31T23:59:59.000Z

    THE HARMOMY OF YIN AND YANK: The American Military Advisory Effort in China, 1941-1951 By Joseph G. D. Babb Professor J. Megan Greene, Advisor The American military personnel assigned to advise and assist China's armed ...

  13. Center for Environmental Management of Military Lands (970) 491-2748 cemml@cemml.colostate.edu

    E-Print Network [OSTI]

    , Environmental and Biological Assessments, and Environmental Impact Statements. Sustaining a realistic military) and Environmental Impact Statements (EIS) are prepared to identify, consider, and resolve environmental problemsCenter for Environmental Management of Military Lands (970) 491-2748 · cemml

  14. A Paranoid State: The American Public, Military Surveillance and the Espionage Act of 1917

    E-Print Network [OSTI]

    Strauss, Lon Jeffrey

    2012-05-31T23:59:59.000Z

    "A Paranoid State" examines the influence of middle to upper class anxieties through military intelligence officers' investigations of the American public in the First World War. Products of their past, Military Intelligence ...

  15. Targeting Net Zero Energy for Military Installations (Presentation)

    SciTech Connect (OSTI)

    Burman, K.

    2012-05-01T23:59:59.000Z

    Targeting Net Zero Energy for Military Installations in Kaneohe Bay, Hawaii. A net zero energy installation (NZEI) is one that produces as much energy from on-site renewable sources as it consumes. NZEI assessment provides a systematic approach to energy projects.

  16. Ecological Site Applications on U.S. Military Installations

    E-Print Network [OSTI]

    live ammunition, etc #12;Military Training Impacts #12;Integrated Training Area Management (ITAM a defined land condition baseline for natural and cultural resources that will be maintained through ITAM and is relevant to the installation environmental setting and mission activity. #12;Ecological Sites and ITAM

  17. ENVIRONMENTAL COMPLIANCE SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    ENVIRONMENTAL COMPLIANCE SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS CEMML@cemml.colostate.edu | http://www.cemml.colostate.edu Environmental compliance and pollution prevention are critical aspects of any successful environmental program. The Center provides technical support in these key areas. CEMML

  18. WILDLAND FIRE SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    is already in place. Fire Management Planning CEMML provides high quality fire management planning adviceWILDLAND FIRE SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS CEMML | 1490 Campus installations present a serious risk to people, infrastructure, quality training areas, and important protected

  19. Performance Evaluation of Ad Hoc Routing Protocols for Military Communications

    E-Print Network [OSTI]

    Bouras, Christos

    in an environment without a fixed infrastructure, the nodes are mobile, the wireless medium has its own limitations are search-and-rescue operations, military deployment in hostile environment, and several types of police of these networks. The nodes act as routers in an environment without a fixed infrastructure, the nodes are mobile

  20. Inter-Korean military confidence building after 2003.

    SciTech Connect (OSTI)

    Tae-woo, Kim (Korea Institute for Defense Analyses, Seoul, Republic of Korea); Littlefield, Adriane C.; Vannoni, Michael Geoffrey; Sang-beom, Kim (Korea Institute for Defense Analyses, Seoul, Republic of Korea); Koelm, Jennifer Gay; Olsen, John Norman; Myong-jin, Kim (Korea Institute for Defense Analyses, Seoul, Republic of Korea); Sung-tack, Shin (Korea Institute for Defense Analyses, Seoul, Republic of Korea)

    2003-08-01T23:59:59.000Z

    Tensions on the Korean Peninsula remain high despite a long-term strategy by South Korea to increase inter-Korean exchanges in economics, culture, sports, and other topics. This is because the process of reconciliation has rarely extended to military and security topics and those initiatives that were negotiated have been ineffective. Bilateral interactions must include actions to reduce threats and improve confidence associated with conventional military forces (land, sea, and air) as well as nuclear, chemical, and biological activities that are applicable to developing and producing weapons of mass destruction (WMD). The purpose of this project is to develop concepts for inter-Korean confidence building measures (CBMs) for military and WMD topics that South Korea could propose to the North when conditions are right. This report describes the historical and policy context for developing security-related CBMs and presents an array of bilateral options for conventional military and WMD topics within a consistent framework. The conceptual CBMs address two scenarios: (1) improved relations where construction of a peace regime becomes a full agenda item in inter-Korean dialogue, and (2) continued tense inter-Korean relations. Some measures could be proposed in the short term under current conditions, others might be implemented in a series of steps, while some require a higher level of cooperation than currently exists. To support decision making by political leaders, this research focuses on strategies and policy options and does not include technical details.

  1. FLORISTICS LABORATORY CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    . A baseline floristic survey is an essential element for management of military lands. This information, and supports adequate training sites. The Center conducts comprehensive planning level surveys to document conservation measures. In addition invasive plants are documented to aid in land management decisions. Surveys

  2. Active Duty Military Tuition Waiver UNIVERSITY OF NEW MEXICO

    E-Print Network [OSTI]

    New Mexico, University of

    Active Duty Military Tuition Waiver UNIVERSITY OF NEW MEXICO SEMESTER: __________ YEAR of the (DUTY STATION) State of New Mexico. This active duty assignment is for the period from _______________________________________________________ ORGANIZATION Return waiver to: The University of New Mexico Division of Enrollment Management Office

  3. China’s Military Representatives: Striving Toward Professional Contracting and Procurement

    E-Print Network [OSTI]

    Puska, Susan M; McReynolds, Joe; Geary, Debra

    2011-01-01T23:59:59.000Z

    effect of specialization could be to develop military representatives who are experts in specific areas of the weapons and

  4. Reactor pressure vessel with forged nozzles

    DOE Patents [OSTI]

    Desai, Dilip R. (Fremont, CA)

    1993-01-01T23:59:59.000Z

    Inlet nozzles for a gravity-driven cooling system (GDCS) are forged with a cylindrical reactor pressure vessel (RPV) section to which a support skirt for the RPV is attached. The forging provides enhanced RPV integrity around the nozzle and substantial reduction of in-service inspection costs by eliminating GDCS nozzle-to-RPV welds.

  5. Proceedings of the 2002 American Society for Engineering Education Zone I Conference United States Military Academy

    E-Print Network [OSTI]

    Military Academy H Experiences using Flying Models in Competitions and Coursework Robert P. Hansen , Lyle N. Long/ , Todd A. Dellert United States Military Academy/ / Pennsylvania State University Abstract States Military Academy and the Pennsylvania State University are described. Free-flight model gliders

  6. Francis H. Smith: architect of antebellum southern military schools and educational reform

    E-Print Network [OSTI]

    Wineman, Bradford Alexander

    2006-10-30T23:59:59.000Z

    in Virginia and the South, both in military and non-military institutions. He also created a network of like-minded academics, mostly with alumni from the U.S. Military Academy who launched a movement to encourage a more practical education in the South...

  7. Large-scale dynamic observation planning for unmanned surface vessels

    E-Print Network [OSTI]

    Miller, John V. (John Vaala)

    2007-01-01T23:59:59.000Z

    With recent advances in research and technology, autonomous surface vessel capabilities have steadily increased. These autonomous surface vessel technologies enable missions and tasks to be performed without the direction ...

  8. aftercastle masted vessel with aftercastle is found on a Spanish

    E-Print Network [OSTI]

    masted vessel with aftercastle is found on a Spanish ations it would have any idea of crusader ships aces for the new tack as large as the crusader vessels (

  9. Study Reveals Challenges and Opportunities Related to Vessels...

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

    Reveals Challenges and Opportunities Related to Vessels for U.S. Offshore Wind Study Reveals Challenges and Opportunities Related to Vessels for U.S. Offshore Wind October 1, 2013...

  10. Structural loading of cross deck connections for trimaran vessels

    E-Print Network [OSTI]

    Rhoads, Jason L

    2004-01-01T23:59:59.000Z

    This work investigates the fundamental relationships of wave loading on cross deck structures for trimaran vessels. In contrast with a monohull ship, trimaran vessels experience several possible structural loading cases ...

  11. RETINAL BLOOD VESSEL SEGMENTATION USING GEODESIC VOTING METHODS Youssef Rouchdy

    E-Print Network [OSTI]

    Cohen, Laurent

    RETINAL BLOOD VESSEL SEGMENTATION USING GEODESIC VOTING METHODS Youssef Rouchdy and Laurent D to segment retinal blood vessels are presented. Many authors have used minimal cost paths, or similarly on the use of a set of such geodesic paths to extract retinal blood vessels, using minimal interaction

  12. Modeling Torsion of Blood Vessels in Surgical Simulation and Planning

    E-Print Network [OSTI]

    Leow, Wee Kheng

    Modeling Torsion of Blood Vessels in Surgical Simulation and Planning Hao LI a,1 , Wee Kheng LEOW a hybrid approach for modeling torsion of blood vessels that undergo deformation and joining. The proposed model takes 3D mesh of the blood vessel as input. It first fits a generalized cylinder to extract

  13. Photoacoustic removal of occlusions from blood vessels

    DOE Patents [OSTI]

    Visuri, Steven R. (Livermore, CA); Da Silva, Luiz B. (Danville, CA); Celliers, Peter M. (Berkeley, CA); London, Richard A. (Orinda, CA); Maitland, IV, Duncan J. (Lafayette, CA); Esch, Victor C. (San Francisco, CA)

    2002-01-01T23:59:59.000Z

    Partial or total occlusions of fluid passages within the human body are removed by positioning an array of optical fibers in the passage and directing treatment radiation pulses along the fibers, one at a time, to generate a shock wave and hydrodynamics flows that strike and emulsify the occlusions. A preferred application is the removal of blood clots (thrombin and embolic) from small cerebral vessels to reverse the effects of an ischemic stroke. The operating parameters and techniques are chosen to minimize the amount of heating of the fragile cerebral vessel walls occurring during this photo acoustic treatment. One such technique is the optical monitoring of the existence of hydrodynamics flow generating vapor bubbles when they are expected to occur and stopping the heat generating pulses propagated along an optical fiber that is not generating such bubbles.

  14. In-situ corrosivity monitoring of military hardware environments

    SciTech Connect (OSTI)

    Agarwala, V.S. [Naval Air Warfare Center, Patuxent River, MD (United States). Aircraft Div.

    1996-10-01T23:59:59.000Z

    A method to monitor corrosive conditions (environments) for military equipment was developed. The concept is based on the electrochemical principles of galvanic corrosion. It consisted of a novel thin film device (interdigitized bimetallic strips on a kapton polymer) which was galvanically coupled or short circuited through a zero resistance ammeter (ZRA) and interfaced to a custom design data acquisition system called Corrosion Monitoring System (CMS). The sensor`s unique design allowed the use of any metal as the active element or anode to form the galvanic couple, which enhanced sensor`s versatility and usefulness in almost any application. In most applications Cd-Au sensor was used. For in-situ corrosivity monitoring sensors were installed in the interior of the aircraft, hidden structures, avionics bays, and embedded under coatings and sealants. The test sites included: military bases, aircraft carrier flight decks, marine atmosphere and operational aircraft and weapons storage areas. The results show a significant correlation between the output of the sensors and the corrosive conditions present, and may become a basis for condition based maintenance of military hardware in the future.

  15. Confinement Vessel Assay System: Calibration and Certification Report

    SciTech Connect (OSTI)

    Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Gomez, Cipriano [Retired CMR-OPS: OPERATIONS; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

    2012-07-17T23:59:59.000Z

    Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1 to 2 inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the vessels. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of SNM in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le} 100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The system was calibrated in three different mass regions (low, medium, and high) to cover the entire plutonium mass range that will be assayed. The low mass calibration and medium mass calibration were verified for material positioned in the center of an empty vessel. The systematic uncertainty due to position bias was estimated using an MCNPX model to simulate the response of the system to material localized at various points along the inner surface of the vessel. The background component due to cosmic ray spallation was determined by performing measurements of an empty vessel and comparing to measurements in the same location with no vessel present. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements of CVs before and after cleanout.

  16. "The Second American School of Arms": the Virginia Military Institute and the advent of state military education, 1835-1851 

    E-Print Network [OSTI]

    Wineman, Bradford Alexander

    2001-01-01T23:59:59.000Z

    with other early narrative histories such as Jennings Wise's Milit Histo of VMI from 1839 and Superintendent Francis H. Smith's Histo of the Vir 'a Militar Institute, are all hindered by personal biases that often interrupt their narratives to exalt... years later. Chapter Three traces VMI's development from an abstract proposal initiated by the local townspeople to a fully functioning military academy. The Institute's three founders, J. T. L. Preston, Colonel Claudius Crozet, and Francis H. Smith...

  17. Autonomous Radiation Monitoring of Small Vessels

    SciTech Connect (OSTI)

    Fabris, Lorenzo [ORNL; Hornback, Donald Eric [ORNL

    2010-01-01T23:59:59.000Z

    Small private vessels are one avenue by which nuclear materials may be smuggled across international borders. While one can contemplate using the terrestrial approach of radiation portal monitors on the navigable waterways that lead to many ports, these systems are ill-suited to the problem. They require vehicles to pass at slow speeds between two closely-spaced radiation sensors, relying on the uniformity of vehicle sizes to space the detectors, and on proximity to link an individual vehicle to its radiation signature. In contrast to roadways where lanes segregate vehicles, and motion is well controlled by inspection booths; channels, inlets, and rivers present chaotic traffic patterns populated by vessels of all sizes. We have developed a unique solution to this problem based on our portal-less portal monitor instrument that is designed to handle free-flowing traffic on roadways with up to five-traffic lanes. The instrument uses a combination of visible-light and gamma-ray imaging to acquire and link radiation images to individual vehicles. It was recently tested in a maritime setting. In this paper we present the instrument, how it functions, and the results of the recent tests.

  18. Application of Computational Physics: Blood Vessel Constrictions and Medical Infuses

    E-Print Network [OSTI]

    Suprijadi; Mohamad Rendi; Petrus Subekti; Sparisoma Viridi

    2013-12-14T23:59:59.000Z

    Application of computation in many fields are growing fast in last two decades. Increasing on computation performance helps researchers to understand natural phenomena in many fields of science and technology including in life sciences. Computational fluid dynamic is one of numerical methods which is very popular used to describe those phenomena. In this paper we propose moving particle semi-implicit (MPS) and molecular dynamics (MD) to describe different phenomena in blood vessel. The effect of increasing the blood pressure on vessel wall will be calculate using MD methods, while the two fluid blending dynamics will be discussed using MPS. Result from the first phenomenon shows that around 80% of constriction on blood vessel make blood vessel increase and will start to leak on vessel wall, while from the second phenomenon the result shows the visualization of two fluids mixture (drugs and blood) influenced by ratio of drugs debit to blood debit. Keywords: molecular dynamic, blood vessel, fluid dynamic, moving particle semi implicit.

  19. Application of Computational Physics: Blood Vessel Constrictions and Medical Infuses

    E-Print Network [OSTI]

    Suprijadi,; Subekti, Petrus; Viridi, Sparisoma

    2013-01-01T23:59:59.000Z

    Application of computation in many fields are growing fast in last two decades. Increasing on computation performance helps researchers to understand natural phenomena in many fields of science and technology including in life sciences. Computational fluid dynamic is one of numerical methods which is very popular used to describe those phenomena. In this paper we propose moving particle semi-implicit (MPS) and molecular dynamics (MD) to describe different phenomena in blood vessel. The effect of increasing the blood pressure on vessel wall will be calculate using MD methods, while the two fluid blending dynamics will be discussed using MPS. Result from the first phenomenon shows that around 80% of constriction on blood vessel make blood vessel increase and will start to leak on vessel wall, while from the second phenomenon the result shows the visualization of two fluids mixture (drugs and blood) influenced by ratio of drugs debit to blood debit. Keywords: molecular dynamic, blood vessel, fluid dynamic, movin...

  20. Ukraine's Military Role in the Black Sea Region

    E-Print Network [OSTI]

    Coffman, Amy Beth; Crump, James Andrew; Dickson, Robbi K.; Mueller, Meaghan; Pulis, Sarah L.

    2010-01-01T23:59:59.000Z

    UK T RAIN HE B E’S LAC MILI K S TARY EA R RO EGI LE IN ON Ukraine’s Military Role in the Black Sea Region       The Bush School of Government and Public Service at Texas A&M University  2      Authors Amy Beth... America, Washington DC.  It was authored by members of  the Bush School of Government and Public Service.  The authors would like to thank the Ukrainian Congress Committee of  America, the George Bush School of Government and Public Service at  Texas A&M University...

  1. Military students access top R&D

    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 SECTION A. Revised:7, at 3:00Military students access

  2. RESOURCE INVENTORY AND MONITORING CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    RESOURCE INVENTORY AND MONITORING CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS CEMML assessments · Rangeland health assessments #12;RESOURCE INVENTORY AND MONITORING CENTER FOR ENVIRONMENTAL

  3. Behavioral representation of military tactics for single-vehicle autonomous rotorcraft via statecharts

    E-Print Network [OSTI]

    Hickie, Mark M

    2005-01-01T23:59:59.000Z

    Over the past several years, aerospace companies have developed unmanned helicopters suitable for integration into military operations as reconnaissance platforms. These rotorcraft, however, require ground-based human ...

  4. Uncovering the Stealth Cluster The Economic Impact of Civilian and Military

    E-Print Network [OSTI]

    Almor, Amit

    Uncovering the Stealth Cluster The Economic Impact of Civilian and Military Aerospace on South on advanced composite materials, precision metal parts, and systems integration, the jobs

  5. Power Triangle: Military, Security, and Politics in the Shaping of the Egyptian, Iranian, and Turkish Regimes

    E-Print Network [OSTI]

    Kandil, Hazem Khaled

    2012-01-01T23:59:59.000Z

    on the Liquidation of Feudalism),” in Al-Tali’ah 3 (3): 124-economic enticements. Under feudalism, military commandersafter eradicating feudalism and manipulative capitalism,

  6. alternative reactor vessel: Topics by E-print Network

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

    FOR ADDED ESCORT van Dorp, Johan Ren 111 FIRE Vacuum Vessel Design and Analysis Plasma Physics and Fusion Websites Summary: pressure, coolant pressure - EM loads on...

  7. Forum Agenda: International Hydrogen Fuel and Pressure Vessel...

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

    Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings Workshop Agenda: Compressed Natural Gas and Hydrogen Fuels, Lesssons Learned for the Safe Deployment of Vehicles...

  8. asme pressure vessels: Topics by E-print Network

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

    Program & Sensors Hydrogen Delivery Composite Overwrapped Pressure Vessels (COPVs) Pipeline for Off-Board Hydrogen: L-C Atmosphere: 1500 psi H2, ambient pressure Air...

  9. asme pressure vessel: Topics by E-print Network

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

    Program & Sensors Hydrogen Delivery Composite Overwrapped Pressure Vessels (COPVs) Pipeline for Off-Board Hydrogen: L-C Atmosphere: 1500 psi H2, ambient pressure Air...

  10. alloy pressure vessels: Topics by E-print Network

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

    Program & Sensors Hydrogen Delivery Composite Overwrapped Pressure Vessels (COPVs) Pipeline for Off-Board Hydrogen: L-C Atmosphere: 1500 psi H2, ambient pressure Air...

  11. alloy pressure vessel: Topics by E-print Network

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

    Program & Sensors Hydrogen Delivery Composite Overwrapped Pressure Vessels (COPVs) Pipeline for Off-Board Hydrogen: L-C Atmosphere: 1500 psi H2, ambient pressure Air...

  12. aged pressure vessel: Topics by E-print Network

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

    Program & Sensors Hydrogen Delivery Composite Overwrapped Pressure Vessels (COPVs) Pipeline for Off-Board Hydrogen: L-C Atmosphere: 1500 psi H2, ambient pressure Air...

  13. Webinar: Material Characterization of Storage Vessels for Fuel Cell Forklifts

    Broader source: Energy.gov [DOE]

    Video recording of the webinar titled, Material Characterization of Storage Vessels for Fuel Cell Forklifts, originally presented on August 14, 2012.

  14. Method and device for supporting blood vessels during anastomosis

    DOE Patents [OSTI]

    Doss, J.D.

    1985-05-20T23:59:59.000Z

    A device and method for preventing first and second severed blood vessels from collapsing during attachment to each other. The device comprises a dissolvable non-toxic stent that is sufficiently rigid to prevent the blood vessels from collapsing during anastomosis. The stent can be hollow or have passages to permit blood flow before it dissolves. A single stent can be inserted with an end in each of the two blood vessels or separate stents can be inserted into each blood vessel. The stent may include a therapeutically effective amount of a drug which is slowly released into the blood stream as the stent dissolves. 12 figs.

  15. Water Quality Impacts of Bunker Silos

    E-Print Network [OSTI]

    Balser, Teri C.

    and water) as well as feed particles and soil transported by flow. #12;Management and Disposal Options 1 Engineering Department UW ­ Madison with assistance from Larry D. Geohring Biological and Environmental Engineering Department Cornell University Area Soil and Soil & Water Meetings November 28 ­ December 7, 2006

  16. Bunker Fuel | OpenEI Community

    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 beingZealand Jump to:EzfeedflagBiomassSustainable andBucoda, Washington: Energy(B2G)

  17. Heat-transfer coefficients in agitated vessels. Sensible heat models

    SciTech Connect (OSTI)

    Kumpinsky, E. [Ashland Chemical Co., Columbus, OH (United States). Research and Development Dept.

    1995-12-01T23:59:59.000Z

    Transient models for sensible heat were developed to assess the thermal performance of agitated vessels with coils and jackets. Performance is quantified with the computation of heat-transfer coefficients by introducing vessel heating and cooling data into model equations. Of the two model categories studied, differential and macroscopic, the latter is preferred due to mathematical simplicity and lower sensitivity to experimental data variability.

  18. Austenite Grain Growth in a Nuclear Pressure Vessel Steel

    E-Print Network [OSTI]

    Cambridge, University of

    . Cogswellb , H. K. D. H. Bhadeshiaa aDepartment of Materials Science and Metallurgy, University of Cambridge vessels, partly because the qualifica- tion of such materials requires an enormous amount of time-consuming work. The reactor pressure vessels (RPV) in particular have demanding requirements for tensile strength

  19. Coalesced Martensite in Pressure Vessel Steels Hector Pous-Romero

    E-Print Network [OSTI]

    Cambridge, University of

    Coalesced Martensite in Pressure Vessel Steels Hector Pous-Romero Department of Materials Science.ac.uk Harry Bhadeshia Department of Materials Science & Metallurgy University of Cambridge Cambridge RPV Reactor pressure vessels. SEM Scanning electron microscopy. HAZ Heat affected zone. Bs Bainite

  20. Simultaneous Irradiation and Imaging of Blood Vessels During Pulsed

    E-Print Network [OSTI]

    Barton, Jennifer K.

    energy produced hemorrhage. In larger vessels, coagula often were attached to the superficial vessel wall; port wine stains INTRODUCTION Previous studies examining the effect of la- ser irradiation on cutaneous preparation. The short pulse duration illus- trated an extreme; energy was deposited quickly Contract grant

  1. Commercial marine vessel contributions to emission inventories. Final report

    SciTech Connect (OSTI)

    Not Available

    1991-10-07T23:59:59.000Z

    The Clean Air Act Amendments of 1990 require the US Environmental Protection Agency (EPA) to conduct a survey of emissions from combustion engines associates with non-road vehicles and stationary sources. Among the emission source categories under scrutiny of the EPA are commercial marine vessels. This group of sources includes revenue vessels operated on US ports and waterways in such diverse pursuits as international and domestic trade, port and ship service, offshore and coastal industry, and passenger transport. For the purposes of the study, EPA is assessing commercial marine vessel operations at selected ports around the country which are characterized by a high level of commercial marine vessel activity. Booz-Allen has been retained by the EPA to assist in developing emission inventories from marine vessels for up to six ports, based on vessel arrival/departure data, are believed to exhibit high levels of marine generated emissions. Booz-Allen developed a listing of the top 20 major ports in terms of total vessel activity (as measured by annual tonnage of cargo and annual vessel calls).

  2. Optimal Short-Range Routing of Vessels in a Seaway

    E-Print Network [OSTI]

    Smith, Robert L.

    Optimal Short-Range Routing of Vessels in a Seaway Irina S. Dolinskaya¹ Miltiadis Kotinis² Michael Industrial and Operations Engineering 1205 Beal Avenue Ann Arbor, Michigan 48109 ²Old Dominion University Short-Range Routing of Vessels in a Seaway Dolinskaya, I. S.1 , Kotinis, M.2 , Parsons, M. G.3

  3. Assessing the impacts of military vehicle traffic on natural areas. Introduction to the special

    E-Print Network [OSTI]

    Fehmi, Jeffrey S.

    Assessing the impacts of military vehicle traffic on natural areas. Introduction to the special issue and review of the relevant military vehicle impact literature Alan B. Anderson a,*, Antonio J, and the International Society for Terrain-Vehicle Systems cosponsored a symposium titled ``Assessing the Impacts

  4. ENVIRONMENTAL PLANNING / NEPA SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS

    E-Print Network [OSTI]

    ENVIRONMENTAL PLANNING / NEPA SERVICES CENTER FOR ENVIRONMENTAL MANAGEMENT OF MILITARY LANDS CEMML@cemml.colostate.edu | http://www.cemml.colostate.edu Effective environmental planning and management of military and testing. The Center develops environmental planning documents for installations to incorporate

  5. Center for Environmental Management of Military Lands (970) 491-2748 cemml@cemml.colostate.edu

    E-Print Network [OSTI]

    of environmental professionals experienced in the conservation and sustainable management of natural and culturalCenter for Environmental Management of Military Lands (970) 491-2748 · cemml@cemml.colostate.edu http://www.cemml.colostate.edu Center for Environmental Management of Military Lands Who We Are

  6. Center for Ecological Management of Military Lands 1 LCTA Relational Database

    E-Print Network [OSTI]

    Center for Ecological Management of Military Lands 1 LCTA Relational Database Center for Ecological Management of Military Lands No. 5 - 1997 The LCTA data is stored in a relational database, currently SQLBase from Gupta Technologies Inc. To the inexperienced user the LCTA database can seem very complex with 45

  7. 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.

  8. Acculturation and Transformation among Female Immigrant Military Spouses in an ESL Learning Program at a Community College 

    E-Print Network [OSTI]

    Darnell, Patricia

    2012-07-16T23:59:59.000Z

    population of military spouses who enrolled in educational programs that offered English language development. The nearest ESL program, located at a community college near the military base, became an information-rich site for the study. The findings from...

  9. The weight of an assassin's mace : vulnerabilities in the US military's satellite communications and China's information warfare threat

    E-Print Network [OSTI]

    Brooks, Benjamin M

    2005-01-01T23:59:59.000Z

    Believing that an information Revolution of Military Affairs has occurred, the US military is currently transforming to achieve dominance over the full spectrum of deployment scenarios with a lighter, more mobile, and more ...

  10. The role of cemeteries in the development of municipal and national military parks: the cemetery-park connection

    E-Print Network [OSTI]

    White, Carlton J

    1995-01-01T23:59:59.000Z

    This thesis examines how cemeteries, both municipal and military, have developed in America based on internal and external influences and the role that they have played in the development of municipal and national military parks, respectively...

  11. Testing military grade magnetics (transformers, inductors and coils).

    SciTech Connect (OSTI)

    Not Available

    2009-09-01T23:59:59.000Z

    Engineers and designers are constantly searching for test methods to qualify or 'prove-in' new designs. In the High Reliability world of military parts, design test, qualification tests, in process tests and product characteristic tests, become even more important. The use of in process and function tests has been adopted as a way of demonstrating that parts will operate correctly and survive its 'use' environments. This paper discusses various types of tests to qualify the magnetic components - the current carrying capability of coils, a next assembly 'as used' test, a corona test and inductance at temperature test. Each of these tests addresses a different potential failure on a component. The entire process from design to implementation is described.

  12. Simulations of Design Modifications in Military Health Facilities

    E-Print Network [OSTI]

    Kiss, Christopher William

    2012-07-16T23:59:59.000Z

    the military population. Civilian medical 0 1 2 3 4 5 6 7 8 9 10 50+ 40-49 30-39 20-29 1-19 N u m b e r o f Faci litie s Age (years) 6 leadership, such as former Assistant Secretaries of Defense for Health Affairs, Dr. W... --------------------------------------------------------------------------------------------------------------------------------- ENGLISH MULTIPLIED BY GIVES METRIC MULTIPLIED BY GIVES ENGLISH 1 1.000000 1.000000 2 1.000000 1.000000 3 BTU 0.293000 WH 3.412969 BTU 4 BTU/HR 0.293000 WATT 3.412969 BTU/HR 5 BTU/LB-F 4183.830078 J/KG-K 0.000239 BTU/LB-F 6 BTU/HR-SQFT-F 5.678260 W/M2-K 0...

  13. Welding the AT-400A Containment Vessel

    SciTech Connect (OSTI)

    Brandon, E.

    1998-11-01T23:59:59.000Z

    Early in 1994, the Department of Energy assigned Sandia National Laboratories the responsibility for designing and providing the welding system for the girth weld for the AT-400A containment vessel. (The AT-400A container is employed for the shipment and long-term storage of the nuclear weapon pits being returned from the nation's nuclear arsenal.) Mason Hanger Corporation's Pantex Plant was chosen to be the production facility. The project was successfully completed by providing and implementing a turnkey welding system and qualified welding procedure at the Pantex Plant. The welding system was transferred to Pantex and a pilot lot of 20 AT-400A containers with W48 pits was welded in August 1997. This document is intended to bring together the AT-400A welding system and product (girth weld) requirements and the activities conducted to meet those requirements. This document alone is not a complete compilation of the welding development activities but is meant to be a summary to be used with the applicable references.

  14. Radiation effects on reactor pressure vessel supports

    SciTech Connect (OSTI)

    Johnson, R.E. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Lipinski, R.E. [Idaho National Engineering Lab., Rockville, MD (United States)

    1996-05-01T23:59:59.000Z

    The purpose of this report is to present the findings from the work done in accordance with the Task Action Plan developed to resolve the Nuclear Regulatory Commission (NRC) Generic Safety Issue No. 15, (GSI-15). GSI-15 was established to evaluate the potential for low-temperature, low-flux-level neutron irradiation to embrittle reactor pressure vessel (RPV) supports to the point of compromising plant safety. An evaluation of surveillance samples from the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) had suggested that some materials used for RPV supports in pressurized-water reactors could exhibit higher than expected embrittlement rates. However, further tests designed to evaluate the applicability of the HFIR data to reactor RPV supports under operating conditions led to the conclusion that RPV supports could be evaluated using traditional method. It was found that the unique HFIR radiation environment allowed the gamma radiation to contribute significantly to the embrittlement. The shielding provided by the thick steel RPV shell ensures that degradation of RPV supports from gamma irradiation is improbable or minimal. The findings reported herein were used, in part, as the basis for technical resolution of the issue.

  15. Reactor Pressure Vessel Head Packaging & Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.; Posivak, E.; Freitag, A.; Geddes, B.

    2003-02-26T23:59:59.000Z

    Reactor Pressure Vessel (RPV) Head replacements have come to the forefront due to erosion/corrosion and wastage problems resulting from the susceptibility of the RPV Head alloy steel material to water/boric acid corrosion from reactor coolant leakage through the various RPV Head penetrations. A case in point is the recent Davis-Besse RPV Head project, where detailed inspections in early 2002 revealed significant wastage of head material adjacent to one of the Control Rod Drive Mechanism (CRDM) nozzles. In lieu of making ASME weld repairs to the damaged head, Davis-Besse made the decision to replace the RPV Head. The decision was made on the basis that the required weld repair would be too extensive and almost impractical. This paper presents the packaging, transport, and disposal considerations for the damaged Davis-Besse RPV Head. It addresses the requirements necessary to meet Davis Besse needs, as well as the regulatory criteria, for shipping and burial of the head. It focuses on the radiological characterization, shipping/disposal package design, site preparation and packaging, and the transportation and emergency response plans that were developed for the Davis-Besse RPV Head project.

  16. Start-up control system and vessel for LMFBR

    DOE Patents [OSTI]

    Durrant, Oliver W. (Akron, OH); Kakarala, Chandrasekhara R. (Clinton, OH); Mandel, Sheldon W. (Galesburg, IL)

    1987-01-01T23:59:59.000Z

    A reflux condensing start-up system includes a steam generator, a start-up vessel connected parallel to the steam generator, a main steam line connecting steam outlets of the steam generator and start-up vessel to a steam turbine, a condenser connected to an outlet of the turbine and a feedwater return line connected between the condenser and inlets of the steam generator and start-up vessel. The start-up vessel has one or more heaters at the bottom thereof for heating feedwater which is supplied over a start-up line to the start-up vessel. Steam is thus generated to pressurize the steam generator before the steam generator is supplied with a heat transfer medium, for example liquid sodium, in the case of a liquid metal fast breeder reactor. The start-up vessel includes upper and lower bulbs with a smaller diameter mid-section to act as water and steam reservoirs. The start-up vessel can thus be used not only in a start-up operation but as a mixing tank, a water storage tank and a level control at low loads for controlling feedwater flow.

  17. Start-up control system and vessel for LMFBR

    DOE Patents [OSTI]

    Durrant, Oliver W. (Akron, OH); Kakarala, Chandrasekhara R. (Clinton, OH); Mandel, Sheldon W. (Galesburg, IL)

    1987-01-01T23:59:59.000Z

    A reflux condensing start-up system comprises a steam generator, a start-up vessel connected parallel to the steam generator, a main steam line connecting steam outlets of the steam generator and start-up vessel to a steam turbine, a condenser connected to an outlet of the turbine and a feedwater return line connected between the condenser and inlets of the steam generator and start-up vessel. The start-up vessel has one or more heaters at the bottom thereof for heating feedwater which is supplied over a start-up line to the start-up vessel. Steam is thus generated to pressurize the steam generator before the steam generator is supplied with a heat transfer medium, for example liquid sodium, in the case of a liquid metal fast breeder reactor. The start-up vessel includes upper and lower bulbs with a smaller diameter mid-section to act as water and steam reservoirs. The start-up vessel can thus be used not only in a start-up operation but as a mixing tank, a water storage tank and a level control at low loads for controlling feedwater flow.

  18. Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

    SciTech Connect (OSTI)

    Cooke, Conrad; Spann, Holger [Siempelkamp Nuclear Services: 5229 Sunset Blvd., (Suite M), West Columbia, SC, 29169 (United States)] [Siempelkamp Nuclear Services: 5229 Sunset Blvd., (Suite M), West Columbia, SC, 29169 (United States)

    2013-07-01T23:59:59.000Z

    Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle Plates to the Baffle Former Plates. The FaST is designed to remove the Baffle Former Plates from the Core Barrel. The VRS further volume reduces segmented components using multiple configurations of the 38i and horizontal reciprocating saws. After the successful removal and volume reduction of the Internals, the RV will be segmented using a 'First in the US' thermal cutting process through a co-operative effort with Siempelkamp NIS Ingenieurgesellschaft mbH using their experience at the Stade NPP and Karlsruhe in Germany. SNS mobilized in the fall of 2011 to commence execution of the project in order to complete the RVI segmentation, removal and packaging activities for the first unit (Unit 2) by end of the 2012/beginning 2013 and then mobilize to the second unit, Unit 1. Parallel to the completion of the segmentation of the reactor vessel internals at Unit 1, SNS will segment the Unit 2 pressure vessel and at completion move to Unit 1. (authors)

  19. PERFORMANCE OF A CONTAINMENT VESSEL CLOSURE FOR RADIOACTIVE GAS CONTENTS

    SciTech Connect (OSTI)

    Blanton, P.; Eberl, K.

    2010-07-09T23:59:59.000Z

    This paper presents a summary of the design and testing of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This package is a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The containment vessel closure incorporates features specifically designed for the containment of tritium when subjected to the normal and hypothetical conditions required of Type B radioactive material shipping Packages. The paper discusses functional performance of the containment vessel closure of the BTSP prototype packages and separate testing that evaluated the performance of the metallic C-Rings used in a mock BTSP closure.

  20. Float level switch for a nuclear power plant containment vessel

    DOE Patents [OSTI]

    Powell, J.G.

    1993-11-16T23:59:59.000Z

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

  1. Processing and analysis techniques involving in-vessel material generation

    DOE Patents [OSTI]

    Schabron, John F. (Laramie, WY); Rovani, Jr., Joseph F. (Laramie, WY)

    2011-01-25T23:59:59.000Z

    In at least one embodiment, the inventive technology relates to in-vessel generation of a material from a solution of interest as part of a processing and/or analysis operation. Preferred embodiments of the in-vessel material generation (e.g., in-vessel solid material generation) include precipitation; in certain embodiments, analysis and/or processing of the solution of interest may include dissolution of the material, perhaps as part of a successive dissolution protocol using solvents of increasing ability to dissolve. Applications include, but are by no means limited to estimation of a coking onset and solution (e.g., oil) fractionating.

  2. Float level switch for a nuclear power plant containment vessel

    DOE Patents [OSTI]

    Powell, James G. (Clifton Park, NY)

    1993-01-01T23:59:59.000Z

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

  3. Processing and analysis techniques involving in-vessel material generation

    DOE Patents [OSTI]

    Schabron, John F. (Laramie, WY); Rovani, Jr., Joseph F. (Laramie, WY)

    2012-09-25T23:59:59.000Z

    In at least one embodiment, the inventive technology relates to in-vessel generation of a material from a solution of interest as part of a processing and/or analysis operation. Preferred embodiments of the in-vessel material generation (e.g., in-vessel solid material generation) include precipitation; in certain embodiments, analysis and/or processing of the solution of interest may include dissolution of the material, perhaps as part of a successive dissolution protocol using solvents of increasing ability to dissolve. Applications include, but are by no means limited to estimation of a coking onset and solution (e.g., oil) fractionating.

  4. PISCES FY11 Research Highlight Tritium accumulation within the ITER vessel is expected to be dominated

    E-Print Network [OSTI]

    PISCES FY11 Research Highlight Tritium accumulation within the ITER vessel is expected vessel. Another possible technique to mitigate tritium accumulation in these codeposited surfaces

  5. Affect of Title III of the 1990 Clean Air Act Amendments on military facilities

    SciTech Connect (OSTI)

    Trembly, L.A. [Naval Facilities Engineering Service Center, Port Hueneme, CA (United States)

    1997-12-31T23:59:59.000Z

    EPA has promulgated a number of NESHAPs in accordance with Title III of the Clean Air Act Amendments of 1990 (CAAA90) that have affected military installations. This paper provides a survey of NESHAP applicability on military installations and where feasible outlines compliance efforts and quantifies the emission reductions achieved. This paper focuses on NESHAPs promulgated since CAAA90. Specific NESHAPs that will be discussed include Halogenated Solvent Cleaners, Perchloroethylene Dry Cleaners, Chromium Electroplating and Anodizing Tanks, Ship Building and Repair Operations and Aerospace Manufacturing and Rework Operations. Other NESHAPs affecting military installations may be addressed if data are available.

  6. Subsea Kick Detection on Floating Vessels: A Parametric Study

    E-Print Network [OSTI]

    Collette, Eric Peter

    2013-07-22T23:59:59.000Z

    SUBSEA KICK DETECTION ON FLOATING VESSELS: A PARAMETRIC STUDY A Thesis by ERIC P. COLLETTE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree...

  7. Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel...

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

    This document presents the results of one of these workshops, the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPVs). These workshops made a substantial effort to...

  8. 2005 ASME Pressure Vessels and Piping Conference Denver, Colorado, USA

    E-Print Network [OSTI]

    Özer, Mutlu

    1 DRAFT 2005 ASME Pressure Vessels and Piping Conference Denver, Colorado, USA July 17-21, 2005 subjected to lateral earthquake loads. The results are verified with different codes (e.g. Eurocode8, API

  9. DESIGN OF THE ITER IN-VESSEL COILS

    SciTech Connect (OSTI)

    Neumeyer, C; Bryant, L; Chrzanowski, J; Feder, R; Gomez, M; Heitzenroeder, P; Kalish, M; Lipski, A; Mardenfeld, M; Simmons, R; Titus, P; Zatz, I; Daly, E; Martin, A; Nakahira, M; Pillsbury, R; Feng, J; Bohm, T; Sawan, M; Stone, H; Griffiths, I

    2010-11-27T23:59:59.000Z

    The ITER project is considering the inclusion of two sets of in-vessel coils, one to mitigate the effect of Edge Localized Modes (ELMs) and another to provide vertical stabilization (VS). The in-vessel location (behind the blanket shield modules, mounted to the vacuum vessel inner wall) presents special challenges in terms of nuclear radiation (~3000 MGy) and temperature (100oC vessel during operations, 200oC during bakeout). Mineral insulated conductors are well suited to this environment but are not commercially available in the large cross section required. An R&D program is underway to demonstrate the production of mineral insulated (MgO or Spinel) hollow copper conductor with stainless steel jacketing needed for these coils. A preliminary design based on this conductor technology has been developed and is presented herein.

  10. aging blood vessels: Topics by E-print Network

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

    Japan is one 302 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Engineering Websites Summary: Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 12132013 1 GW-VCU December 2013...

  11. abdominal blood vessels: Topics by E-print Network

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

    Terri 311 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Engineering Websites Summary: Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 12132013 1 GW-VCU December 2013...

  12. abnormal blood vessels: Topics by E-print Network

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

    Japan is one 327 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Engineering Websites Summary: Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 12132013 1 GW-VCU December 2013...

  13. alters blood vessel: Topics by E-print Network

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

    G Tien, Joe 308 VESSEL TRAFFIC RISK ASSESSMENT (VTRA) 2010 Engineering Websites Summary: Oil Loss Dr. J. Rene van Dorp and Dr. Jason R.W Merrick 12132013 1 GW-VCU December 2013...

  14. Simple program calculates partial liquid volumes in vessels

    SciTech Connect (OSTI)

    Koch, P.

    1992-04-13T23:59:59.000Z

    This paper reports on a simple calculator program which solves problems of partial liquid volumes for a variety of storage and process vessels, including inclined cylindrical vessels and those with conical heads. Engineers in the oil refining and chemical industries are often confronted with the problem of estimating partial liquid volumes in storage tanks or process vessels. Cistern, the calculator program presented here, allows fast and accurate resolution of problems for a wide range of vessels without user intervention, other than inputting the problem data. Running the program requires no mathematical skills. Cistern is written for Hewlett-Packard HP 41CV or HP 41CX programmable calculators (or HP 41C with extended memory modules).

  15. Hydrodynamic evaluation of high-speed semi-SWATH vessels

    E-Print Network [OSTI]

    Guttenplan, Adam (Adam David)

    2007-01-01T23:59:59.000Z

    High-speed semi-displacement vessels have enjoyed rapid development and widespread use over the past 25 years. Concurrent with their growth as viable commercial and naval platforms, has been the advancement of three-dimensional ...

  16. A cog-like vessel from the Netherlands

    E-Print Network [OSTI]

    Van de Moortel, Aleydis Maria P. A.

    1987-01-01T23:59:59.000Z

    , more than thirty iconographic representations, mostly medieval city seals, have been discovered. 4 They show that cogs were compact and tubby vessels with a sharply built lower hull, combining a large cargo capacity with good sailing qualities.... The broad central part of the vessel immedistelv suaaested it had been a merchantman, but no trace of cargo was found. The onlv contents were some fraaments of bricks and ceramics. a Few iron serape' some smail cattle bones, and, under the ceiling...

  17. Using SA508/533 for the HTGR Vessel Material

    SciTech Connect (OSTI)

    Larry Demick

    2012-06-01T23:59:59.000Z

    This paper examines the influence of High Temperature Gas-cooled Reactor (HTGR) module power rating and normal operating temperatures on the use of SA508/533 material for the HTGR vessel system with emphasis on the calculated times at elevated temperatures approaching or exceeding ASME Code Service Limits (Levels B&C) to which the reactor pressure vessel could be exposed during postulated pressurized and depressurized conduction cooldown events over its design lifetime.

  18. Energy efficiency in military housing: Monitoring to support revitalization guidebook

    SciTech Connect (OSTI)

    Levins, W.P.; Ternes, M.P.

    1994-11-01T23:59:59.000Z

    Oak Ridge National Laboratory is working with the US Army, the US Air Force, and the US Department of Energy to develop a guidebook to be used by architectural and engineering firms in the design phases of military family housing revitalization projects. The purpose of the guidebook is to ensure that energy efficiency is properly addressed in revitalization projects. Monitoring space-heating and cooling energy used in houses both before and after they are revitalized is necessary in order to assess the amount of energy saved by the revitalization process. Three different methods of conducting monitoring experiments are discussed, as well as the methods of data analysis to be used. Houses will be monitored individually using standard gas and electric meters to obtain heating and cooling data for the houses. The authors recommend conducting monitoring programs at Altus Air Force Base, Oklahoma, and Fort Monmouth, New Jersey, because of their project schedules and potential for savings. They do not recommend doing any monitoring at Malmstrom Air Force Base, Montana, because of the relatively small savings that they expect revitalization to accomplish there. They do not recommend seeking out alternative sites for monitoring because of the time required to become familiar with the installation and also because revitalization schedules at alternative sites may be no better than those at the sites they inspected.

  19. Regime legitimacy and military resilience : lessons from World War II and Yugoslavia

    E-Print Network [OSTI]

    Russell, Jacob Hale

    2008-01-01T23:59:59.000Z

    This thesis argues that regime legitimacy creates military resilience. A regime is legitimate when its constituents believe-whether because of ideological solidarity, patriotism, nationalism, or good governance-that a ...

  20. Developing a Crowd Federate for Military Simulation Mikel D. Petty1

    E-Print Network [OSTI]

    McKenzie, Rick

    forces involved. U. S. military actions in Mogadishu, Bosnia, and Iraq exemplify the significant effects-throwing women and children. In Bosnia, U. S. Army soldiers had to disperse angry mobs of Serb hard-liners near

  1. Finding Common Ground: A Value-Focused Approach to Military UAS Airspace Integration

    E-Print Network [OSTI]

    Cropsey, Major Luke C.G.

    2009-04-20T23:59:59.000Z

    Integrating unmanned aircraft systems (UAS) into nonsegregated1 airspace is a topic of much debate and significant energy, particularly with respect to military operations. This paper applies leading?edge research in ...

  2. Optimization-based routing and scheduling of IED-detection assets in contemporary military operations

    E-Print Network [OSTI]

    Marks, Christopher E. (Christopher Edward)

    2009-01-01T23:59:59.000Z

    Improvised Explosive Devices, or IEDs, have become a familiar and lethal part of contemporary military operations in Iraq and Afghanistan, producing more casualties than any other weapons system. One reason for their success ...

  3. Development of rapidly deployable structures for military applications : a system based approach to command post facilities

    E-Print Network [OSTI]

    Hopping, Jakob A

    2006-01-01T23:59:59.000Z

    Today's battlespace is the most dynamic in recorded history. Accompanying other military improvements, Command and Control (C2) technology has also been modernized. In spite of advances in technology, it currently takes ...

  4. Borderland Intimacies: GIs, Koreans, and American Military Landscapes in Cold War Korea

    E-Print Network [OSTI]

    Hwang, Whitney Taejin

    2010-01-01T23:59:59.000Z

    1994. Fischer, Hannah. “American War and Military OperationsThe Origins of the Korean War: Liberation and the EmergenceThe Origins of the Korean War: The Roaring of the Cataracts,

  5. Politicized armies, militarized politics : civil-military relations in Turkey and Greece

    E-Print Network [OSTI]

    Liaras, Evangelos

    2007-01-01T23:59:59.000Z

    Despite their common Ottoman heritage, Greece and Turkey have diverged widely in their modem history of civil-military relations. The armed forces have a long record of intervention in both countries, but there is a crucial ...

  6. A review of "English Military News Pamphlets, 1513-1637" by David Randall

    E-Print Network [OSTI]

    Greenspan, Nicole

    2013-01-01T23:59:59.000Z

    between Sweden and Poland shows the wide circulation of, and interest in, international military news. On the whole the pamphlets are good representations of the genre and illustrate the content, range, and breadth of news pamphlets. #2;e anthology...

  7. Net Zero Energy Military Installations: A Guide to Assessment and Planning

    Office of Energy Efficiency and Renewable Energy (EERE)

    In 2008, DoD and DOE defined a joint initiative to address military energy use by identifying specific actions to reduce energy demand and increase use of renewable energy on DoD installations.

  8. Personality Predictors of First-Year Attrition From A Military Training Program

    E-Print Network [OSTI]

    Chalupa, Samantha Brooke

    2013-09-24T23:59:59.000Z

    versus those who leave the Corps during the first semester their freshman year. The goal is to enhance the selection and retention of recruits in future military training programs as well as in business and industry....

  9. 17.953 U.S. Military Budget and Force Planning, Fall 2004

    E-Print Network [OSTI]

    Williams, Cindy

    The United States is spending about $400 billion this year on national defense, some $40 billion on homeland security, and $85 billion on military operations and nation-building in Iraq and Afghanistan. This course is for ...

  10. A comparative study of the life satisfaction of early retirement military officers

    E-Print Network [OSTI]

    Graves, Russ Thomas

    2005-11-01T23:59:59.000Z

    This study compared the life satisfaction of early retirement military officers with several comparison groups on the basis of Retirement Descriptive Index (RDI) scale scores. The RDI is a self-report instrument that assesses life satisfaction...

  11. A versatile simulation tool for the design and verification of military vehicle power systems 

    E-Print Network [OSTI]

    Lipscomb, Melissa Anne

    2005-11-01T23:59:59.000Z

    The design of the electric platform in military vehicles requires the ability to determine the best combination of power system components that support the desired operational abilities, while minimizing the size, weight, cost, and impact...

  12. Essays using military-induced variation to study social interactions, human capital development, and labor markets

    E-Print Network [OSTI]

    Lyle, David S. (David Stephen), 1971-

    2003-01-01T23:59:59.000Z

    This dissertation consists of four empirical studies, each using military-induced variation to examine various aspects of human capital production and the U.S. labor market. The first two chapters study the effects of ...

  13. Francis H. Smith: architect of antebellum southern military schools and educational reform 

    E-Print Network [OSTI]

    Wineman, Bradford Alexander

    2006-10-30T23:59:59.000Z

    This study examines the historical significance of the Virginia Military Institute�s (VMI) first superintendent, Francis Henney Smith, and his influence not only at his home institution but also on his broader social, educational, and political...

  14. Changing Military Dynamics in East Asia: Australia’s Evolving Grand Strategy

    E-Print Network [OSTI]

    SHEARER, Andrew

    2012-01-01T23:59:59.000Z

    White, Hugh. 2010. Power Shift: Australia’s Future Betweenand military power closer to Australia, position- ingAs power shifts in the Asia-Pacific, Australia’s grand

  15. Center for Environmental Management of Military Lands (970) 491-2748 cemml@cemml.colostate.edu

    E-Print Network [OSTI]

    , and frequency · Woody plant density and basal area · Plant productivity · Disturbance and land uses, disturbance, soil erosion, and wildlife on military installations as part of the Land Condition-Trend Analysis

  16. Demographic study of military selection in the state of Ohio, 1917-1919 

    E-Print Network [OSTI]

    Saberian, Michael Reza

    2006-04-12T23:59:59.000Z

    This thesis studies the influence of ethnicity, nationality, and occupation upon military selection of the residents of Ohio during the First World War. This is a quantitative study, based on a data set constructed from ...

  17. A comparative study of the life satisfaction of early retirement military officers 

    E-Print Network [OSTI]

    Graves, Russ Thomas

    2005-11-01T23:59:59.000Z

    This study compared the life satisfaction of early retirement military officers with several comparison groups on the basis of Retirement Descriptive Index (RDI) scale scores. The RDI is a self-report instrument that ...

  18. A versatile simulation tool for the design and verification of military vehicle power systems

    E-Print Network [OSTI]

    Lipscomb, Melissa Anne

    2005-11-01T23:59:59.000Z

    The design of the electric platform in military vehicles requires the ability to determine the best combination of power system components that support the desired operational abilities, while minimizing the size, weight, cost, and impact...

  19. A critical appraisal of Byzantine military strategy, 400 - 1000 A.D.

    E-Print Network [OSTI]

    Bacon, Peter Kirk

    1998-01-01T23:59:59.000Z

    A CRITICAL APPRAISAL OF BYZANTINE MILITARY STRATEGY, 400 - 1000 A. D. A Thesis by PETER KIRK BACON Submitted to the Office of Graduate Studies of Texas AkM University in partial fulfillment of the requirements for the degree of MASTER... OF ARTS May 1998 Major Subject: History A CRITICAL APPRAISAL OF BYZANTINE MILITARY STRATEGY, 400 - 1000 A. D. A Thesis by PETER KIRK BACON Submitted to Texas AErM University in partial fulfillment of the requirements for the degree of MASTER...

  20. Military Construction Appropriations and Emergency Hurricane Supplemental Appropriations Act, 2005 (released in AEO2005)

    Reports and Publications (EIA)

    2005-01-01T23:59:59.000Z

    H.R. 4837, The Military Construction Appropriations and Emergency Hurricane Supplemental Appropriations Act, 2005, was signed into law on October 13, 2004. The Act provides for construction to support the operations of the U.S. Armed Forces and for military family housing. It also provides funds to help citizens in Florida and elsewhere in the aftermath of multiple hurricanes and other natural disasters. In addition, it authorizes construction of an Alaska Natural Gas Pipeline.

  1. The Legal-Military Dilemma in the Response to International Terrorism

    E-Print Network [OSTI]

    Allan, Matthew W.

    2010-07-14T23:59:59.000Z

    THE LEGAL-MILITARY DILEMMA IN THE RESPONSE TO INTERNATIONAL TERRORISM A Dissertation by MATTHEW WESLEY ALLAN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements... for the degree of DOCTOR OF PHILOSOPHY December 2009 Major Subject: Political Science THE LEGAL-MILITARY DILEMMA IN THE RESPONSE TO INTERNATIONAL TERRORISM A Dissertation by MATTHEW WESLEY ALLAN Submitted to the Office of Graduate...

  2. Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

  3. Predictive Simulation of Bidirectional Glenn Shunt Using a Hybrid Blood Vessel Model

    E-Print Network [OSTI]

    Leow, Wee Kheng

    Predictive Simulation of Bidirectional Glenn Shunt Using a Hybrid Blood Vessel Model Hao Li1 to model the deformation of blood vessels. The hybrid blood vessel model consists of a reference Cosserat rod and a surface mesh. The reference Cosserat rod models the blood vessel's global bending

  4. Photoacoustic spectroscopy sample array vessel and photoacoustic spectroscopy method for using the same

    DOE Patents [OSTI]

    Amonette, James E.; Autrey, S. Thomas; Foster-Mills, Nancy S.; Green, David

    2005-03-29T23:59:59.000Z

    Methods and apparatus for analysis of multiple samples by photoacoustic spectroscopy are disclosed. Particularly, a photoacoustic spectroscopy sample array vessel including a vessel body having multiple sample cells connected thereto is disclosed. At least one acoustic detector is acoustically coupled with the vessel body. Methods for analyzing the multiple samples in the sample array vessels using photoacoustic spectroscopy are provided.

  5. Investigation of vessel exterior air cooling for a HLMC reactor

    SciTech Connect (OSTI)

    Sienicki, J. J.; Spencer, B. W.

    2000-01-13T23:59:59.000Z

    The Secure Transportable Autonomous Reactor (STAR) concept under development at Argonne National Laboratory provides a small (300 MWt) reactor module for steam supply that incorporates design features to attain proliferation resistance, heightened passive safety, and improved cost competitiveness through extreme simplification. Examples are the achievement of 100%+ natural circulation heat removal from the low power density/low pressure drop ultra-long lifetime core and utilization of lead-bismuth eutectic (LBE) coolant enabling elimination of main coolant pumps as well as the need for an intermediate heat transport circuit. It is required to provide a passive means of removing decay heat and effecting reactor cooldown in the event that the normal steam generator heat sink, including its normal shutdown heat removal mode, is postulated to be unavailable. In the present approach, denoted as the Reactor Exterior Cooling System (RECS), passive decay heat removal is provided by cooling the outside of the containment/guard vessel with air. RECS is similar to the Reactor Vessel Auxiliary Cooling System (RVACS) incorporated into the PRISM design. However, to enhance the heat removal, RECS incorporates fins on the containment vessel exterior to enhance heat transfer to air as well as removable steel venetian conductors that provide a conduction heat transfer path across the reactor vessel-containment vessel gap to enhance heat transfer between the vessels. The objective of the present work is to investigate the effectiveness of air cooling in removing heat from the vessel and limiting the coolant temperature increase following a sudden complete loss of the steam generator heat sink.

  6. Investigation of vessel exterior air cooling for an HLMC reactor

    SciTech Connect (OSTI)

    Sienicki, J.J.; Spencer, B.W.

    2000-07-01T23:59:59.000Z

    The secure transportable autonomous reactor (STAR) concept under development at Argonne National Laboratory provides a small [300-MW(thermal)] reactor module for steam supply that incorporates design features to attain proliferation resistance, heightened passive safety, and improved cost competitiveness through extreme simplification. Examples are the achievement of 100% + natural-circulation heat removal from the low-power-density/low-pressure-drop ultralong lifetime core and utilization of lead-bismuth eutectic (LBE) coolant enabling elimination of main coolant pumps as well as the need for an intermediate heat transport circuit. It is required to provide a passive means of removing decay heat and effecting reactor cooldown in the event that the normal steam generator heat sink, including its normal shutdown heat removal mode, is postulated to be unavailable. In the present approach, denoted as the reactor exterior cooling system (RECS), passive decay heat removal is provided by cooling the outside of the containment/guard vessel with air. RECS is similar to the reactor vessel auxiliary cooling system (RVACS) incorporated into the PRISM design. However, to enhance the heat removal, RECS incorporates fins on the containment vessel exterior to enhance heat transfer to air as well as removable steel venetian conductors that provide a conduction heat transfer path across the reactor vessel-containment vessel gap to enhance heat transfer between the vessels. The objective of the present work is to investigate the effectiveness of air cooling in removing heat from the vessel and limiting the coolant temperature increase following a sudden complete loss of the steam generator heat sink.

  7. A Comprehensive Program for Measurement of Military Aircraft Emissions

    SciTech Connect (OSTI)

    Cheng, Mengdawn [ORNL

    2009-11-01T23:59:59.000Z

    Emissions of gases and particulate matter by military aircraft were characterized inplume by 'extractive' and 'optical remote-sensing (ORS)' technologies. Non-volatile particle size distribution, number and mass concentrations were measured with good precision and reproducibly. Time-integrated particulate filter samples were collected and analyzed for smoke number, elemental composition, carbon contents, and sulfate. Observed at EEP the geometric mean diameter (as measured by the mobility diameter) generally increased as the engine power setting increased, which is consistent with downstream observations. The modal diameters at the downstream locations are larger than that at EEP at the same engine power level. The results indicate that engine particles were processed by condensation, for example, leading to particle growth in-plume. Elemental analysis indicated little metals were present in the exhaust, while most of the exhaust materials in the particulate phase were carbon and sulfate (in the JP-8 fuel). CO, CO{sub 2}, NO, NO{sub 2}, SO{sub 2}, HCHO, ethylene, acetylene, propylene, and alkanes were measured. The last five species were most noticeable under engine idle condition. The levels of hydrocarbons emitted at high engine power level were generally below the detection limits. ORS techniques yielded real-time gaseous measurement, but the same techniques could not be extended directly to ultrafine particles found in all engine exhausts. The results validated sampling methodology and measurement techniques used for non-volatile particulate aircraft emissions, which also highlighted the needs for further research on sampling and measurement for volatile particulate matter and semi-volatile species in the engine exhaust especially at the low engine power setting.

  8. Design Considerations For Blast Loads In Pressure Vessels.

    SciTech Connect (OSTI)

    Rodriguez, E. A. (Edward A.); Nickell, Robert E.; Pepin, J. E. (Jason E.)

    2007-01-01T23:59:59.000Z

    Los Alamos National Laboratory (LANL), under the auspices of the U.S. Department of Energy (DOE) and the National Nuclear Security Administration (NNSA), conducts confined detonation experiments utilizing large, spherical, steel pressure vessels to contain the reaction products and hazardous materials from high-explosive (HE) events. Structural design and analysis considerations include: (a) Blast loading phase (i.e., impulsive loading); (b) Dynamic structural response; (c) Fragment (i.e., shrapnel) generation and penetration; (d) Ductile and non-ductile fracture; and (e) Design Criteria to ASME Code Sec. VIII, Div. 3, Impulsively Loaded Vessels. These vessels are designed for one-time-use only, efficiently utilizing the significant plastic energy absorption capability of ductile vessel materials. Alternatively, vessels may be designed for multiple-detonation events, in which case the material response is restricted to elastic or near-elastic range. Code of Federal Regulations, Title 10 Part 50 provides requirements for commercial nuclear reactor licensing; specifically dealing with accidental combustible gases in containment structures that might cause extreme loadings. The design philosophy contained herein may be applied to extreme loading events postulated to occur in nuclear reactor and non-nuclear systems or containments.

  9. Sterilization of fermentation vessels by ethanol/water mixtures

    DOE Patents [OSTI]

    Wyman, C.E.

    1999-02-09T23:59:59.000Z

    A method is described for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process. 2 figs.

  10. Sterilization of fermentation vessels by ethanol/water mixtures

    DOE Patents [OSTI]

    Wyman, Charles E. (Lakewood, CO)

    1999-02-09T23:59:59.000Z

    A method for sterilizing process fermentation vessels with a concentrated alcohol and water mixture integrated in a fuel alcohol or other alcohol production facility. Hot, concentrated alcohol is drawn from a distillation or other purification stage and sprayed into the empty fermentation vessels. This sterilizing alcohol/water mixture should be of a sufficient concentration, preferably higher than 12% alcohol by volume, to be toxic to undesirable microorganisms. Following sterilization, this sterilizing alcohol/water mixture can be recovered back into the same distillation or other purification stage from which it was withdrawn. The process of this invention has its best application in, but is not limited to, batch fermentation processes, wherein the fermentation vessels must be emptied, cleaned, and sterilized following completion of each batch fermentation process.

  11. Report of the terawatt laser pressure vessel committee

    SciTech Connect (OSTI)

    Woodle, M.H.; Beauman, R.; Czajkowski, C.; Dickinson, T.; Lynch, D.; Pogorelsky, I.; Skjaritka, J.

    2000-09-25T23:59:59.000Z

    In 1995 the ATF project sent out an RFP for a CO2 Laser System having a TeraWatt output. Eight foreign and US firms responded. The Proposal Evaluation Panel on the second round selected Optoel, a Russian firm based in St. Petersburg, on the basis of the technical criteria and cost. Prior to the award, BNL representatives including the principal scientist, cognizant engineer and a QA representative visited the Optoel facilities to assess the company's capability to do the job. The contract required Optoel to provide a x-ray preionized high pressure amplifier that included: a high pressure cell, x-ray tube, internal optics and a HV pulse forming network for the main discharge and preionizer. The high-pressure cell consists of a stainless steel pressure vessel with various ports and windows that is filled with a gas mixture operating at 10 atmospheres. In accordance with BNL Standard ESH 1.4.1 ''Pressurized Systems For Experimental Use'', the pressure vessel design criteria is required to comply with the ASME Boiler and Pressure Vessel Code In 1996 a Preliminary Design Review was held at BNL. The vendor was requested to furnish drawings so that we could confirm that the design met the above criteria. The vendor furnished drawings did not have all dimensions necessary to completely analyze the cell. Never the less, we performed an analysis on as much of the vessel as we could with the available information. The calculations concluded that there were twelve areas of concern that had to be addressed to assure that the pressure vessel complied with the requirements of the ASME code. This information was forwarded to the vendor with the understanding that they would resolve these concerns as they continued with the vessel design and fabrication. The assembled amplifier pressure vessel was later hydro tested to 220 psi (15 Atm) as well as pneumatically to 181 psi (12.5 Atm) at the fabricator's Russian facility and was witnessed by a BNL engineer. The unit was shipped to the US and installed at the ATF. As part of the commissioning of the device the amplifier pressure vessel was disassembled several times at which time it became apparent that the vendor had not addressed 7 of the 12 issues previously identified. Closer examination of the vessel revealed some additional concerns including quality of workmanship. Although not required by the contract, the vendor furnished radiographs of a number of pressure vessel welds. A review of the Russian X-rays revealed radiographs of both poor and unreadable quality. However, a number of internal weld imperfections could be observed. All welds in question were excavated and then visually and dye penetrant inspected. These additional inspections confirmed that the weld techniques used to make some of these original welds were substandard. The applicable BNL standard, ESH 1.4.1, addresses the problem of pressure vessel non-compliance by having a committee appointed by the Department Chairman review the design and provide engineering solutions to assure equivalent safety. On January 24, 2000 Dr. M. Hart, the NSLS Chairman, appointed this committee with this charge. This report details the engineering investigations, deliberations, solutions and calculations which were developed by members of this committee to determine that with repairs, new components, appropriate NDE, and lowering the design pressure, the vessel can be considered safe to use.

  12. Retrospective dosimetry analyses of reactor vessel cladding samples

    SciTech Connect (OSTI)

    Greenwood, L. R.; Soderquist, C. Z. [Battelle Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Fero, A. H. [Westinghouse Electric Company, Cranberry Twp., PA 16066 (United States)

    2011-07-01T23:59:59.000Z

    Reactor pressure vessel cladding samples for Ringhals Units 3 and 4 in Sweden were analyzed using retrospective reactor dosimetry techniques. The objective was to provide the best estimates of the neutron fluence for comparison with neutron transport calculations. A total of 51 stainless steel samples consisting of chips weighing approximately 100 to 200 mg were removed from selected locations around the pressure vessel and were sent to Pacific Northwest National Laboratory for analysis. The samples were fully characterized and analyzed for radioactive isotopes, with special interest in the presence of Nb-93m. The RPV cladding retrospective dosimetry results will be combined with a re-evaluation of the surveillance capsule dosimetry and with ex-vessel neutron dosimetry results to form a comprehensive 3D comparison of measurements to calculations performed with 3D deterministic transport code. (authors)

  13. Ex-vessel demand by size for the Gulf shrimp

    E-Print Network [OSTI]

    Chui, Margaret Kam-Too

    1980-01-01T23:59:59.000Z

    EX-VESSEL DEMAND BY SIZE FOR THE GULF SHRIMP A Thesis by MARGARET RAM-TOO CHUI Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE August 1980 Major... Subject: Agricultural Economics EX-VESSEL DEMAND BY SIZE FOR SHRIMP IN THE GULF OF MEXICO A Thesis by MARGARET KAM-TOO CHUI Approved as to style and content by: ai an of Committee) (Hea f ep tment) (Member) (Member) August 1980 ABSTRACT Ex...

  14. Simulation of Diffusive Lithium Evaporation Onto the NSTX Vessel Walls

    SciTech Connect (OSTI)

    Stotler, D. P.; Skinner, C. H.; Blanchard, W. R.; Krstic, P. S.; Kugel, H. W.; Schneider, H.; Zakharov, L. E.

    2010-12-09T23:59:59.000Z

    A model for simulating the diffusive evaporation of lithium into a helium filled NSTX vacuum vessel is described and validated against an initial set of deposition experiments. The DEGAS 2 based model consists of a three-dimensional representation of the vacuum vessel, the elastic scattering process, and a kinetic description of the evaporated atoms. Additional assumptions are required to account for deuterium out-gassing during the validation experiments. The model agrees with the data over a range of pressures to within the estimated uncertainties. Suggestions are made for more discriminating experiments that will lead to an improved model.

  15. MELCOR ex-vessel LOCA simulations for ITER{sup +}

    SciTech Connect (OSTI)

    Gaeta, M.J.; Merrill, B.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Bartels, H.W. [ITER San Diego Joint Work Site, La Jolla, CA (United States)] [and others

    1995-11-01T23:59:59.000Z

    Ex-vessel Loss-of-Coolant-Accident (LOCA) simulations for the International Thermonuclear Experimental Reactor (ITER) were performed using the MELCOR code. The main goals of this work were to estimate the ultimate pressurization of the heat transport system (HTS) vault in order to gauge the potential for stack releases and to estimate the total amount of hydrogen generated during a design basis ex-vessel LOCA. Simulation results indicated that the amount of hydrogen produced in each transient was below the flammability limit for the plasma chamber. In addition, only moderate pressurization of the HTS vault indicated a very small potential for releases through the stack.

  16. Lightweight cryogenic-compatible pressure vessels for vehicular fuel storage

    DOE Patents [OSTI]

    Aceves, Salvador; Berry, Gene; Weisberg, Andrew H.

    2004-03-23T23:59:59.000Z

    A lightweight, cryogenic-compatible pressure vessel for flexibly storing cryogenic liquid fuels or compressed gas fuels at cryogenic or ambient temperatures. The pressure vessel has an inner pressure container enclosing a fuel storage volume, an outer container surrounding the inner pressure container to form an evacuated space therebetween, and a thermal insulator surrounding the inner pressure container in the evacuated space to inhibit heat transfer. Additionally, vacuum loss from fuel permeation is substantially inhibited in the evacuated space by, for example, lining the container liner with a layer of fuel-impermeable material, capturing the permeated fuel in the evacuated space, or purging the permeated fuel from the evacuated space.

  17. Ion transport membrane module and vessel system with directed internal gas flow

    DOE Patents [OSTI]

    Holmes, Michael Jerome (Thompson, ND); Ohrn, Theodore R. (Alliance, OH); Chen, Christopher Ming-Poh (Allentown, PA)

    2010-02-09T23:59:59.000Z

    An ion transport membrane system comprising (a) a pressure vessel having an interior, an inlet adapted to introduce gas into the interior of the vessel, an outlet adapted to withdraw gas from the interior of the vessel, and an axis; (b) a plurality of planar ion transport membrane modules disposed in the interior of the pressure vessel and arranged in series, each membrane module comprising mixed metal oxide ceramic material and having an interior region and an exterior region; and (c) one or more gas flow control partitions disposed in the interior of the pressure vessel and adapted to change a direction of gas flow within the vessel.

  18. Inexpensive delivery of compressed hydrogen with advanced vessel technology

    E-Print Network [OSTI]

    of flexible refueling (compressed/cryogenic H2/(L)H2) #12;The PVT properties of H2 drive storage and delivery) Explore station demand from 70 kg H2/day to 1000 kg H2/day · Real hydrogen thermodynamic and PVT diagram and vessel characteristics to minimize delivery cost · Hydrogen and material properties Increased

  19. Response of a vessel to waves at zero ship speed

    E-Print Network [OSTI]

    Response of a vessel to waves at zero ship speed: preliminary full scale experiments By: Kim Klaka of experiment were conducted ­ free roll decay tests and irregular wave tests. An inclining test was also with and without the mainsail hoisted, in very light winds. The irregular wave tests were conducted again in very

  20. International Hydrogen Fuel and Pressure Vessel Forum 2010 Beijing, China

    E-Print Network [OSTI]

    challenges in harmonizing test protocols and requirements for compressed natural gas (CNG), hydrogen, and CNGInternational Hydrogen Fuel and Pressure Vessel Forum 2010 Beijing, China September 27-29, 2010 Background The China Association for Hydrogen Energy, the Engineering Research Center of High Pressure

  1. Modelling the Induced Magnetic Signature of Naval Vessels

    E-Print Network [OSTI]

    Low, Robert

    vessels stealth is an important design feature. With recent advances in electromagnetic sensor technology with the magnetic signature resulting from the magnetisation of the ferromagnetic material of the ship, under is constructed from non-magnetic materials, but arises from the combined e#11;ect of the individual items

  2. Large Blood Vessels 1.1 Introduction --The Cardiovascular System

    E-Print Network [OSTI]

    Luo, Xiaoyu

    Chapter 1 Large Blood Vessels 1.1 Introduction -- The Cardiovascular System The heart is a pump that circulates blood to the lungs for oxygenation (pul- monary circulation) and then throughout the systemic arterial system with a total cycle time of about one minute. From the left ventricle of the heart, blood

  3. PublicationsmailagreementNo.40014024 the VeSSeL WILL

    E-Print Network [OSTI]

    Pedersen, Tom

    fuel. The hybrid system will provide energy for low-speed maneuvering and stationPublicationsmailagreementNo.40014024 THE 1st the VeSSeL WILL Be the WORLD'S FIRSt PLUG-IN hYBRID's first plug-in hybrid "green ship" powered by electricity, hydrogen fuel cells and low- emission diesel

  4. Net Zero Energy Military Installations: A Guide to Assessment and Planning

    SciTech Connect (OSTI)

    Booth, S.; Barnett, J.; Burman, K.; Hambrick, J.; Westby, R.

    2010-08-01T23:59:59.000Z

    The U.S. Department of Defense (DoD) recognizes the strategic importance of energy to its mission, and is working to reduce energy consumption and enhance energy self-sufficiency by drawing on local clean energy sources. A joint initiative formed between DoD and the U.S. Department of Energy (DOE) in 2008 to address military energy use led to a task force to examine the potential for net zero energy military installations, which would produce as much energy on site as they consume in buildings, facilities, and fleet vehicles. This report presents an assessment and planning process to examine military installations for net zero energy potential. Net Zero Energy Installation Assessment (NZEIA) presents a systematic framework to analyze energy projects at installations while balancing other site priorities such as mission, cost, and security.

  5. An overview of the sustainability of solid waste management at military installations

    SciTech Connect (OSTI)

    Borglin, S.; Shore, J.; Worden, H.; Jain, R.

    2009-08-15T23:59:59.000Z

    Sustainable municipal solid waste management at military solutions necessitates a combined approach that includes waste reduction, alternative disposal techniques, and increased recycling. Military installations are unique because they often represent large employers in the region in which they are located, thereby making any practices they employ impact overall waste management strategies of the region. Solutions for waste sustainability will be dependent on operational directives and base location, availability of resources such as water and energy, and size of population. Presented in this paper are descriptions of available waste strategies that can be used to support sustainable waste management. Results presented indicate source reduction and recycling to be the most sustainable solutions. However, new waste-to-energy plants and composting have potential to improve on these well proven techniques and allow military installations to achieve sustainable waste management.

  6. Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project...

    Energy Savers [EERE]

    Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project Scoping and Feasibility Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project Scoping and Feasibility...

  7. Pulmonary Hypertension and Computed Tomography Measurement of Small Pulmonary Vessels in

    E-Print Network [OSTI]

    Pulmonary Hypertension and Computed Tomography Measurement of Small Pulmonary Vessels in Severe alteration of small pulmonary vessels is one of the characteristic features of pulmonary hypertension in chronic obstruc- tive pulmonary disease. The in vivo relationship between pulmonary hypertension

  8. E-Print Network 3.0 - axicell vacuum vessel Sample Search Results

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

    T. Brown, H-M Fan, G. Jones... 12;13 July 2002 Snowmass Review: FIRE Vacuum Vessel and Remote Handling 2 Presentation Outline... Vacuum Vessel - Design requirements - Design...

  9. The Paradoxes of Military Risk Assessment: Will the Enterprise Risk Assessment Model, Composite Risk Management and Associated

    E-Print Network [OSTI]

    Johnson, Chris

    to assess the nation's military preparedness. However, risk management is not a panacea for the problemsThe Paradoxes of Military Risk Assessment: Will the Enterprise Risk Assessment Model, Composite Risk Management and Associated Techniques Provide the Predicted Benefits? Chris. W. Johnson, Glasgow

  10. LOW ALLOY STEELS FOR THICK WALL PRESSURE VESSELS Yearly Report for Period Oct. 1, 1976 to Sept. 30, 1977.

    E-Print Network [OSTI]

    Horn, R.M.

    2011-01-01T23:59:59.000Z

    Vessel Fabrication Under ASME Code Current Pressure Vessel Sc a t i o n under the ASME code current s t e e l s , and (VESSEL FABRICATION UNDER ASME CODE Interactions with Babcock

  11. A Survey of Pressure Vessel Code Compliance for Superconducting RF Cryomodules

    SciTech Connect (OSTI)

    Peterson, Thomas; Klebaner, Arkadiy; Nicol, Tom; Theilacker, Jay; /Fermilab; Hayano, Hitoshi; Kako, Eiji; Nakai, Hirotaka; Yamamoto, Akira; /KEK, Tsukuba; Jensch, Kay; Matheisen, Axel; /DESY; Mammosser, John; /Jefferson Lab

    2011-06-07T23:59:59.000Z

    Superconducting radio frequency (SRF) cavities made from niobium and cooled with liquid helium are becoming key components of many particle accelerators. The helium vessels surrounding the RF cavities, portions of the niobium cavities themselves, and also possibly the vacuum vessels containing these assemblies, generally fall under the scope of local and national pressure vessel codes. In the U.S., Department of Energy rules require national laboratories to follow national consensus pressure vessel standards or to show ''a level of safety greater than or equal to'' that of the applicable standard. Thus, while used for its superconducting properties, niobium ends up being treated as a low-temperature pressure vessel material. Niobium material is not a code listed material and therefore requires the designer to understand the mechanical properties for material used in each pressure vessel fabrication; compliance with pressure vessel codes therefore becomes a problem. This report summarizes the approaches that various institutions have taken in order to bring superconducting RF cryomodules into compliance with pressure vessel codes. In Japan, Germany, and the U.S., institutions building superconducting RF cavities integrated in helium vessels or procuring them from vendors have had to deal with pressure vessel requirements being applied to SRF vessels, including the niobium and niobium-titanium components of the vessels. While niobium is not an approved pressure vessel material, data from tests of material samples provide information to set allowable stresses. By means of procedures which include adherence to code welding procedures, maintaining material and fabrication records, and detailed analyses of peak stresses in the vessels, or treatment of the vacuum vessel as the pressure boundary, research laboratories around the world have found methods to demonstrate and document a level of safety equivalent to the applicable pressure vessel codes.

  12. RIS-M-2186 INTERPRETATIOM OF STRAIN HBASUREMEMTS ON NUCLEAR PRESSURE VESSELS

    E-Print Network [OSTI]

    RISÃ?-M- 2186 INTERPRETATIOM OF STRAIN HBASUREMEMTS ON NUCLEAR PRESSURE VESSELS Svend Ib Andersen Preben Engbzk Abstract. Selected results from strain measurements on 4 nuclear pressure vessels, EXPERIMENTAL DATA, GRAPHS, MECHANICAL TESTS, PERFORMANCE TESTING, PRESSURE VESSELS, tMR TYPE REACTORS, STEELS

  13. NEUTRON DAMAGE IN REACTOR PRESSURE-VESSEL STEEL EXAMINED WITH POSITRON ANNIHILATION LIFETIME SPECTROSCOPY

    E-Print Network [OSTI]

    Motta, Arthur T.

    NEUTRON DAMAGE IN REACTOR PRESSURE-VESSEL STEEL EXAMINED WITH POSITRON ANNIHILATION LIFETIME-vessel steels. We irradiated samples ofASTM A508 nuclear reactor pressure-vessel steel to fast neutron 17 2 (PALS) to study the effects of neutron damage in the steels on positron lifetimes. Non

  14. Photoacoustic spectroscopy sample array vessels and photoacoustic spectroscopy methods for using the same

    DOE Patents [OSTI]

    Amonette, James E.; Autrey, S. Thomas; Foster-Mills, Nancy S.

    2006-02-14T23:59:59.000Z

    Methods and apparatus for simultaneous or sequential, rapid analysis of multiple samples by photoacoustic spectroscopy are disclosed. Particularly, a photoacoustic spectroscopy sample array vessel including a vessel body having multiple sample cells connected thereto is disclosed. At least one acoustic detector is acoustically positioned near the sample cells. Methods for analyzing the multiple samples in the sample array vessels using photoacoustic spectroscopy are provided.

  15. Center for Ecological Management of Military Lands 1 Loading Handheld Data Files

    E-Print Network [OSTI]

    a parent table and a child table by the use of primary and foreign keys. A parent is defined with a data element or set of elements as a primary key. #12;Center for Ecological Management of Military Lands 2 The primary key is a unique value that constrains the entry of data into the dependent child table

  16. CEMP-EC 13 February 1995 TRI-SERVICE MILITARY CONSTRUCTION PROGRAM (MCP) INDEX

    E-Print Network [OSTI]

    US Army Corps of Engineers

    CEMP-EC 13 February 1995 TABLE IV TRI-SERVICE MILITARY CONSTRUCTION PROGRAM (MCP) INDEX FOR FY 1996 for projection beyond FY 2001. 2. Tri-Service MCP Index (1,000) = 1 October 1979 ENR Historical Building Cost THRU FY 2001 PROGRAMS ESCALATION PERCENTAGE DATE INDEX FOR FISCAL YEAR 1 OCT 1992 ------------- 1825

  17. A system architecture for long duration free floating flight for military applications

    SciTech Connect (OSTI)

    Epley, L.E. (CIRRUS Aerospace Corp., Burke, VA (USA))

    1990-08-31T23:59:59.000Z

    Accessibility is today's space frontier. Our need for wide-band global communications, earth imaging an sensing, atmospheric measurements and military reconnaissance is endless but growing dependence on space-based systems raises concerns about potential vulnerability. Military commanders want space assets more accessible and under direct local control. As a result, a robust and low cost access to space-like capability has become a national priority. Buoyant vehicles, free floating in the middle stratosphere could provide the kind of cost effective access to space-like capability needed for a verity of missions. These vehicles are inexpensive, invisible and easily launched. Developments in payload electronics, atmospheric wind modeling and materials combined with ever-improving communications and navigation infrastructure are making balloon-borne concepts more attractive. The fundamental question is whether a free floating balloon, used in a pseudo-satellite role, has value in a military system. Flight tests are ongoing under NASA sponsorship. Following these tests NASA intends to use the vehicles for research in the Antarctic. The concept is being reviewed by other agencies interested in stratospheric research. We believe that LDFFF systems have applications in areas of communications, surveillance and other traditional satellite missions. Dialogue with the broader community of space users is needed to expand the applications. This report reviews the status of the recent flight tests and presents an overview of the concept of Long Duration Free Floating Flight for military applications. 12 refs., 13 figs.

  18. U.S. military action in Panama: justifying OPERATION JUST CAUSE

    E-Print Network [OSTI]

    Reich, Theodore Herman

    2000-01-01T23:59:59.000Z

    The project of this thesis is a moral evaluation of OPERATION JUST CAUSE, the United States' use of military force in Panama in 1989. I begin by arguing that just war theory, both in its classic and contemporary forms, needs to be revised...

  19. PRESSURIZATION OF CONTAINMENT VESSELS FROM PLUTONIUM OXIDE CONTENTS

    SciTech Connect (OSTI)

    Hensel, S.

    2012-03-27T23:59:59.000Z

    Transportation and storage of plutonium oxide is typically done using a convenience container to hold the oxide powder which is then placed inside a containment vessel. Intermediate containers which act as uncredited confinement barriers may also be used. The containment vessel is subject to an internal pressure due to several sources including; (1) plutonium oxide provides a heat source which raises the temperature of the gas space, (2) helium generation due to alpha decay of the plutonium, (3) hydrogen generation due to radiolysis of the water which has been adsorbed onto the plutonium oxide, and (4) degradation of plastic bags which may be used to bag out the convenience can from a glove box. The contributions of these sources are evaluated in a reasonably conservative manner.

  20. Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database

    SciTech Connect (OSTI)

    Wang, Jy-An John [ORNL

    2010-08-01T23:59:59.000Z

    Materials behaviors caused by neutron irradiation under fission and/or fusion environments can be little understood without practical examination. Easily accessible material information system with large material database using effective computers is necessary for design of nuclear materials and analyses or simulations of the phenomena. The developed Embrittlement Data Base (EDB) at ORNL is this comprehensive collection of data. EDB database contains power reactor pressure vessel surveillance data, the material test reactor data, foreign reactor data (through bilateral agreements authorized by NRC), and the fracture toughness data. The lessons learned from building EDB program and the associated database management activity regarding Material Database Design Methodology, Architecture and the Embedded QA Protocol are described in this report. The development of IAEA International Database on Reactor Pressure Vessel Materials (IDRPVM) and the comparison of EDB database and IAEA IDRPVM database are provided in the report. The recommended database QA protocol and database infrastructure are also stated in the report.

  1. Superheat effects on localized vessel breach enlargement during corium ejection

    SciTech Connect (OSTI)

    Sienicki, J.J.; Spencer, B.W.

    1986-01-01T23:59:59.000Z

    The evaluation of the consequences of hypothetical severe accident sequences in light water reactors includes those sequences in which molten corium is postulated to melt through the reactor pressure vessel (RPV) lower head and enter the region beneath the RPV. An important issue is the mode by which the lower head is breached and molten corium introduced into the reactor cavity (PWR) or pedestal (BWR). Reported here are the results of an investigation into the dependency of ablation-induced enlargement on the initial corium temperature, or more specifically, the initial corium superheat (i.e., excess temperature above the freezing temperature). A model is introduced here to predict the vessel erosion and is employed to scope the effects of variations in the superheat.

  2. IMPACT OF NUCLEAR MATERIAL DISSOLUTION ON VESSEL CORROSION

    SciTech Connect (OSTI)

    Mickalonis, J.; Dunn, K.; Clifton, B.

    2012-10-01T23:59:59.000Z

    Different nuclear materials require different processing conditions. In order to maximize the dissolver vessel lifetime, corrosion testing was conducted for a range of chemistries and temperature used in fuel dissolution. Compositional ranges of elements regularly in the dissolver were evaluated for corrosion of 304L, the material of construction. Corrosion rates of AISI Type 304 stainless steel coupons, both welded and non-welded coupons, were calculated from measured weight losses and post-test concentrations of soluble Fe, Cr and Ni.

  3. Dynamic response of containment vessels to blast loading

    SciTech Connect (OSTI)

    Karpp, R.R.; Duffey, T.A.; Neal, T.R.; Warnes, R.H.; Thompson, J.D.

    1982-01-01T23:59:59.000Z

    The dynamic response of steel, spherical containment vessels loaded by internal explosive blast was studied by experiments, computations, and analysis. Instrumentation used in the experiments consisted of strain and pressure gauges and a velocity interferometer. Data were used to rank the blast wave mitigating properties of several filler materials and to develop a scaling law relating strain, filler material, and explosive energy or explosive mass.

  4. PARTICLE TRANSPORTATION AND DEPOSITION IN HOT GAS FILTER VESSELS - A COMPUTATIONAL AND EXPERIMENTAL MODELING APPROACH

    SciTech Connect (OSTI)

    Goodarz Ahmadi

    2002-07-01T23:59:59.000Z

    In this project, a computational modeling approach for analyzing flow and ash transport and deposition in filter vessels was developed. An Eulerian-Lagrangian formulation for studying hot-gas filtration process was established. The approach uses an Eulerian analysis of gas flows in the filter vessel, and makes use of the Lagrangian trajectory analysis for the particle transport and deposition. Particular attention was given to the Siemens-Westinghouse filter vessel at Power System Development Facility in Wilsonville in Alabama. Details of hot-gas flow in this tangential flow filter vessel are evaluated. The simulation results show that the rapidly rotation flow in the spacing between the shroud and the vessel refractory acts as cyclone that leads to the removal of a large fraction of the larger particles from the gas stream. Several alternate designs for the filter vessel are considered. These include a vessel with a short shroud, a filter vessel with no shroud and a vessel with a deflector plate. The hot-gas flow and particle transport and deposition in various vessels are evaluated. The deposition patterns in various vessels are compared. It is shown that certain filter vessel designs allow for the large particles to remain suspended in the gas stream and to deposit on the filters. The presence of the larger particles in the filter cake leads to lower mechanical strength thus allowing for the back-pulse process to more easily remove the filter cake. A laboratory-scale filter vessel for testing the cold flow condition was designed and fabricated. A laser-based flow visualization technique is used and the gas flow condition in the laboratory-scale vessel was experimental studied. A computer model for the experimental vessel was also developed and the gas flow and particle transport patterns are evaluated.

  5. Fracture toughness test results of thermal aged reactor vessel materials

    SciTech Connect (OSTI)

    DeVan, M.J.; Lowe, A.L. Jr. [B and W Nuclear Technologies Inc., Lynchburg, VA (United States). Nuclear Engineering Dept.; Hall, J.B. [Babcock and Wilcox Co., Alliance, OH (United States)

    1996-12-31T23:59:59.000Z

    Thermal-aged surveillance materials consisting of Sa-533, Grade B, Class 1 plate material; SA-508, Class 2 forging material; and 2 Mn-Mo-Ni/Linde 80 weld metals were removed from two commercial reactor pressure vessels. The material from the first reactor vessel received a thermal exposure of approximately 103,000 hours at 282 C, while the material from the second reactor vessel received a thermal exposure of approximately 93,000 hours at 282 C. Tensile and 1/2 T compact fracture toughness specimens were fabricated from these materials and tested. In addition, to examine the effects of annealing, selected thermal-aged and unaged specimens were annealed at 454 C (850 F) and tested. Varying responses in the fracture toughness properties were observed for all materials after exposure to the thermal-aging temperature. The base metal plate had an observed decrease in J-values after its respective aging exposure, while no significant difference in the J-values were observed for the Linde 80 weld metals. No significant difference was seen in the J-data for the aged/annealed materials, but because of the small number of test specimens available, no conclusion could be determined for the response to annealing.

  6. Start-up control system and vessel for lmfbr

    SciTech Connect (OSTI)

    Durrant, O.W.; Kakarala, C.R.; Mandel, S.W.

    1987-04-07T23:59:59.000Z

    This patent describes a start-up vessel for a start-up system suitable for liquid metal fast breeder reactors comprising: a lower bulb defining a lower space; an upper bulb defining an upper space; a mid-section of a cross-sectional diameter less than that of the lower and upper bulbs, defining a mid-space and connected between the upper and lower bulbs; heating means associated with the lower bulb for heating water in the lower space; at least one inlet conduit connection connected to the vessel for admitting feed water to the lower space to be heated by the heating means to produce steam; at least one outlet conduit connection connected to the vessel for discharging steam; an auxiliary feed water line connected through the upper bulb having at least one nozzle at the end thereof for spraying feed water into the upper space; and a main steam inlet connection connected to the upper bulb for heating the auxiliary feed water to produce steam.

  7. Understanding the EPA guidance on major source determinations for military installations

    SciTech Connect (OSTI)

    Ling, A.D. [Dept. of the Navy, Washington, DC (United States)

    1997-12-31T23:59:59.000Z

    In August 1996, the Environmental Protection Agency (EPA) issued the first ever Clean Air Act (CAA) guidance directed specifically at military facilities. The Guidance, titled Major Source Determinations for Military Installations under the Air Toxics, New Source Review and Title V Operating Permit Programs of the Clean Air Act, was negotiated by an EPA/DoD workgroup that included field and headquarters EPA and DoD representatives, and was led by the Navy. This paper describes the development and contents of the guidance and the significant legal and policy issues raised. By statute and rule, all sources under common control on contiguous or adjacent property and belonging to the same two digit Standard Industrial Classification (SIC) Code must be aggregated when determining if the source is a major source. DoD requested that EPA develop the guidance because of a move by EPA to impose a fenceline-to-fenceline interpretation of what constitutes a major source for purposes of the three programs identified above. Such an interpretation could and did result in more stringent regulation of industrial sources on military installations than of similar industrial plants. The guidance establishes EPA`s allowable interpretation of two of the three key elements of the major source definition. First, the guidance specifies that common control occurs at the military service level; therefore, sources belonging to the Army, Navy, Marine Corps, Air Force, the National Guard or a Defense Agency that are located on the same installation could each be treated separately. Second, the guidance allows the military to assign SIC codes to functional industrial groupings in a manner similar to the private sector. Past practice grouped all national defense activities under the same SIC code.

  8. Method and apparatus for detecting irregularities on or in the wall of a vessel

    DOE Patents [OSTI]

    Bowling, Michael Keith (Blackborough Cullompton, GB)

    2000-09-12T23:59:59.000Z

    A method of detecting irregularities on or in the wall of a vessel by detecting localized spatial temperature differentials on the wall surface, comprising scanning the vessel surface with a thermal imaging camera and recording the position of the or each region for which the thermal image from the camera is indicative of such a temperature differential across the region. The spatial temperature differential may be formed by bacterial growth on the vessel surface; alternatively, it may be the result of defects in the vessel wall such as thin regions or pin holes or cracks. The detection of leaks through the vessel wall may be enhanced by applying a pressure differential or a temperature differential across the vessel wall; the testing for leaks may be performed with the vessel full or empty, and from the inside or the outside.

  9. Dual shell pressure balanced reactor vessel. Final project report

    SciTech Connect (OSTI)

    Robertus, R.J.; Fassbender, A.G.

    1994-10-01T23:59:59.000Z

    The Department of Energy`s Office of Energy Research (OER) has previously provided support for the development of several chemical processes, including supercritical water oxidation, liquefaction, and aqueous hazardous waste destruction, where chemical and phase transformations are conducted at high pressure and temperature. These and many other commercial processes require a pressure vessel capable of operating in a corrosive environment where safety and economy are important requirements. Pacific Northwest Laboratory (PNL) engineers have recently developed and patented (U.S. patent 5,167,930 December 1, 1992) a concept for a novel Dual Shell Pressure Balanced Vessel (DSPBV) which could solve a number of these problems. The technology could be immediately useful in continuing commercialization of an R&D 100 award-winning technology, Sludge-to-oil Reactor System (STORS), originally developed through funding by OER. Innotek Corporation is a small business that would be one logical end-user of the DSPBV reactor technology. Innotek is working with several major U.S. engineering firms to evaluate the potential of this technology in the disposal of wastes from sewage treatment plants. PNL entered into a CRADA with Innotek to build a bench-scale demonstration reactor and test the system to advance the economic feasibility of a variety of high pressure chemical processes. Hydrothermal processing of corrosive substances on a large scale can now be made significantly safer and more economical through use of the DSPBV. Hydrothermal chemical reactions such as wet-air oxidation and supercritical water oxidation occur in a highly corrosive environment inside a pressure vessel. Average corrosion rates from 23 to 80 miles per year have been reported by Rice (1994) and Latanision (1993).

  10. Vessel eddy current measurement for the National Spherical Torus Experiment

    SciTech Connect (OSTI)

    Gates, D.A.; Menard, J.E.; Marsala, R.J. [Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton, New Jersey 08543 (United States)

    2004-12-01T23:59:59.000Z

    A simple analog circuit that measures the National Spherical Torus Experiment (NSTX) axisymmetric eddy current distribution has been designed and constructed. It is based on simple circuit model of the NSTX vacuum vessel that was calibrated using a special axisymmetric eddy current code which was written so that accuracy was maintained in the vicinity of the current filaments [J. Menard, J. Fusion Tech. (to be published)]. The measurement and the model have been benchmarked against data from numerous vacuum shots and they are in excellent agreement. This is an important measurement that helps give more accurate equilibrium reconstructions.

  11. Heat-transfer coefficients in agitated vessels. Latent heat models

    SciTech Connect (OSTI)

    Kumpinsky, E. [Ashland Chemical Co., Columbus, OH (United States)] [Ashland Chemical Co., Columbus, OH (United States)

    1996-03-01T23:59:59.000Z

    Latent heat models were developed to calculate heat-transfer coefficients in agitated vessels for two cases: (1) heating with a condensable fluid flowing through coils and jackets; (2) vacuum reflux cooling with an overhead condenser. In either case the mathematical treatment, based on macroscopic balances, requires no iterative schemes. In addition to providing heat-transfer coefficients, the models predict flow rates of service fluid through the coils and jackets, estimate the percentage of heat transfer due to latent heat, and compute reflux rates.

  12. Facing the transition. [Retrofitting vessels for burning coal

    SciTech Connect (OSTI)

    Not Available

    1981-08-01T23:59:59.000Z

    Historically, environmental regulations prohibiting black smoke in port and marine disposal of ashes caused many coal-burning vessels in the Great Lakes shipping industry to convert to oil-burning systems. With a return to coal-burning plants on-board, these problems and others are being addressed. Improvements are being made in stack emission control. The need for monitoring devices is discussed. Mechanisms are described which will help control dust, heat, noise and ash. To reduce the need for excessive stockpiles of various grades of coal, equipment is being designed which will burn a range of coals available in many ports. (JMT)

  13. Military Base Off-Taker Opportunities for Tribal Renewable Energy Projects

    SciTech Connect (OSTI)

    Nangle, J.

    2013-05-01T23:59:59.000Z

    This white paper surveys DOD installations that could have an increased potential interest in the purchase of energy from renewable energy projects on tribal lands. Identification of likely purchasers of renewable energy is a first step in the energy project development process, and this paper aims to identify likely electricity customers that tribal commercial-scale projects could serve. This white paper builds on a geospatial analysis completed in November 2012 identifying 53 reservations within 10 miles of military bases (DOE 2012). This analysis builds on those findings by further refining the list of potential opportunity sites to 15 reservations (Table ES-1), based on five additional factors: 1) The potential renewable resources required to meet the installation energy loads; 2) Proximity to transmission lines; 3) Military installation energy demand; 4) State electricity prices; 5) Local policy and regulatory environment.

  14. The campaign of mud: a military-political analysis of the Third Battle of Ypres 

    E-Print Network [OSTI]

    Duffy, Stephen Mark

    1989-01-01T23:59:59.000Z

    , Bri. tain, Prussia and Russia guaranteeing Belgium's security) plunged Britain into the war in 1914 with the aim of restoring Belgium as a sovereign and neutral State. &4 The deliverance of the Belgian people from the clutc2&es of a tyrannical... but also render great military advant- ages by resting the flank of the British armies on the Dutch border. Communications could then be shortened and the whole German position in France turned without an appreciable lengthening of the battle line...

  15. Detecting Inaccurate Response Patterns in Korean Military Personality Inventory: An Application of Item Response Theory

    E-Print Network [OSTI]

    Hong, Seunghwa

    2013-07-27T23:59:59.000Z

    representing themselves. Much literature has argued that inaccurate responses in personality measures could occur by several reasons including social desirability, poor motivation, deliberate faking, or alignment error, etc (Hulin, Drasow, & Parsons, 1983... in conflict areas so that both mental strength and personality soundness are required for military personnel. Although inaccurate responses in a faking-good manner is more frequent in a personnel selection context, deliberate faking-bad may be another...

  16. A study to examine community involvement in major U.S.military base closures and realignments from 1988 to 2001

    E-Print Network [OSTI]

    Yahn, Nancy Stiles

    2005-11-01T23:59:59.000Z

    This study examines community involvement in major U.S. military base closures and realignments from 1988 to 2001. There were four waves of base closures during this time. They were in 1988, 1991, 1993, and 1995. Community involvement became...

  17. Identifying and estimating the distributional effects of unionization and the long-term consequences of military service

    E-Print Network [OSTI]

    Frandsen, Brigham R

    2010-01-01T23:59:59.000Z

    This thesis is concerned with the economic consequences for individuals of two important U.S. labor market institutions: unionization and the military draft. The first chapter develops an econometric procedure for estimating ...

  18. Proceedings of the 2002 American Society for Engineering Education Zone I Conference United States Military Academy, West Point, New York

    E-Print Network [OSTI]

    Roylance, David

    Session H Proceedings of the 2002 American Society for Engineering Education Zone I Conference;Proceedings of the 2002 American Society for Engineering Education Zone I Conference United States Military

  19. Exposure to risk and its impact on human capital : essays on combat exposure, military labor, and conflict duration

    E-Print Network [OSTI]

    Yankovich, Michael F

    2013-01-01T23:59:59.000Z

    This dissertation examines the impact of contemporaneous American participation in war on military labor and conflict duration. Chapter one uses variation in occupation-specific retention bonuses and mortality risks observed ...

  20. Secure Military Social Networking and Rapid Sensemaking in Domain Specific Concept Systems: Research Issues and Future Solutions

    E-Print Network [OSTI]

    Garside, Debbie

    This paper identifies the need for a secure military social networking site and the underlying research issues linked to the successful development of such sites. The paper further proposes a solution to the most basic ...

  1. Preliminary assessment report for Olney Military Reservation, Installation 24175, Olney, Maryland. Installation Restoration Program

    SciTech Connect (OSTI)

    Hansen, J.; Rose, C.

    1993-07-01T23:59:59.000Z

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Maryland Army National Guard property near Olney, Maryland. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies Phase I of the US Department of Defense Installation Restoration Program for Olney Military Reservation property. Olney Military Reservation is an 8-acre site located in the southwestern portion of Maryland, about six miles northwest of Washington, DC, in Montgomery County. The major facilities included in this PA comprise the administration building, barracks, and motor repair shops. The environmentally significant operations associated with the property are underground and aboveground storage tanks, a vehicle wash rack, a flammable materials storage area (a lean-to structure), and a hazardous materials storage building. The review of both historical and current practices at the property indicates that Olney Military Reservation property poses no immediate threat to human health or the environment. Argonne`s reviewers noted several historical potential threats to the environment that have occurred at the property that installation personnel have corrected or eliminated.

  2. Acculturation and Transformation among Female Immigrant Military Spouses in an ESL Learning Program at a Community College

    E-Print Network [OSTI]

    Darnell, Patricia

    2012-07-16T23:59:59.000Z

    ACCULTURATION AND TRANSFORMATION AMONG FEMALE IMMIGRANT MILITARY SPOUSES IN AN ESL LEARNING PROGRAM AT A COMMUNITY COLLEGE A Dissertation by PATRICIA DARNELL Submitted to the Office of Graduate Studies of Texas A&M University in partial... Copyright 2012 Patricia Darnell ACCULTURATION AND TRANSFORMATION AMONG FEMALE IMMIGRANT MILITARY SPOUSES IN AN ESL LEARNING PROGRAM AT A COMMUNITY COLLEGE A Dissertation by PATRICIA DARNELL Submitted to the Office of Graduate Studies of Texas A...

  3. Gamma ray-induced embrittlement of pressure vessel alloys

    SciTech Connect (OSTI)

    Alexander, D.E.; Rehn, L.E. [Argonne National Lab., IL (United States); Farrell, K.; Stoller, R.E. [Oak Ridge National Lab., TN (United States)

    1994-11-01T23:59:59.000Z

    High-energy gamma rays emitted from the core of a nuclear reactor produce displacement damage in the reactor pressure vessel (RPV). The contribution of gamma damage to RPV embrittlement has in the past been largely ignored. However, in certain reactor designs the gamma flux at the RPV is sufficiently large that its contribution to displacement damage can be substantial. For example, gamma rays have been implicated in the accelerated RPV embrittlement observed in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. In the present study, mechanical property changes induced by 10-MeV electron irradiation of a model Fe alloy and an RPV alloy of interest to the HFIR were examined. Mini-tensile specimens were irradiated with high-energy electrons to reproduce damage characteristic of the Compton recoil-electrons induced by gamma bombardment. Substantial increases in yield and ultimate stress were observed in the alloys after irradiation to doses up to 5.3x10{sup {minus}3} dpa at temperatures ({approximately}50{degrees}C) characteristic of the HFIR pressure vessel. These measured increases were similar to those previously obtained following neutron irradiation, despite the highly disparate nature of the damage generated during electron and neutron irradiation.

  4. Impacts of reducing shipboard NOx? and SOx? emissions on vessel performance

    E-Print Network [OSTI]

    Caputo, Ronald J., Jr. (Ronald Joseph)

    2010-01-01T23:59:59.000Z

    The international maritime community has been experiencing tremendous pressures from environmental organizations to reduce the emissions footprint of their vessels. In the last decade, air emissions, including nitrogen ...

  5. a533b pressure vessel: Topics by E-print Network

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

    Program & Sensors Hydrogen Delivery Composite Overwrapped Pressure Vessels (COPVs) Pipeline for Off-Board Hydrogen: L-C Atmosphere: 1500 psi H2, ambient pressure Air...

  6. Nuclear reactor having a polyhedral primary shield and removable vessel insulation

    DOE Patents [OSTI]

    Ekeroth, D.E.; Orr, R.

    1993-12-07T23:59:59.000Z

    A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel. 5 figures.

  7. Nuclear reactor having a polyhedral primary shield and removable vessel insulation

    DOE Patents [OSTI]

    Ekeroth, Douglas E. (Delmont, PA); Orr, Richard (Pittsburgh, PA)

    1993-01-01T23:59:59.000Z

    A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel.

  8. R&D of Large Stationary Hydrogen/CNG/HCNG Storage Vessels

    Broader source: Energy.gov [DOE]

    These slides were presented at the International Hydrogen Fuel and Pressure Vessel Forum on September 27 – 29, 2010, in Beijing, China.

  9. Albatrosses Following Fishing Vessels: How Badly Hooked Are They on an Easy Meal?

    E-Print Network [OSTI]

    Resources, Fisheries Department, Stanley, Falkland Islands, 4 Eco-Ethology Research Unit, ISPA, Lisboa effort was spent near ships. Nevertheless, a few individuals repeatedly visited fishing vessels, which

  10. Evaluation of hydrogen pressure vessels using slow strain rate testing and fracture mechanics analysis

    SciTech Connect (OSTI)

    Murray, S.H. [National Aeronautics and Space Administration, Kennedy Space Center, FL (United States). Materials Science Div.; Desai, V.H. [Univ. of Central Florida, Orlando, FL (United States)

    1998-12-31T23:59:59.000Z

    A total of 108 seamless, forged pressure vessels, fabricated from ASTM A372 type IV (UNS K14508) and type V low alloy steel, are currently in 4,200 psi (29 MPa) gaseous hydrogen (GH{sub 2}) service at the Kennedy Space Center`s (KSC) Space Shuttle Launch Complex 39 (LC-39). The vessels were originally used in 6,000 psi (41 MPa) GH{sub 2} service during the Apollo program. NASA recently received a letter of warning from the manufacturer of the vessels stating that the subject vessels should be now be removed from GH{sub 2} service due to the fact that the ultimate tensile strength (UTS) of many of the vessels exceeds the maximum limit of 126 ksi (869 MPa) now imposed on A372 steel intended for GH{sub 2} service, and therefore are susceptible to hydrogen environment embrittlement. Due to the expense associated with vessel replacement, it was decided to determine by testing and analysis whether or not the vessels needed to be removed from GH{sub 2} service. Slow strain rate testing was performed under hydrogen charging conditions to determine the value of the threshold fracture toughness for sustained loading crack growth in GH{sub 2}, (K{sub H}) for the vessel material, this value was then used in a fracture mechanics safe-life analysis (a 20-year service life was modeled) that indicated the vessels are safe for continued use.

  11. X:\\L6046\\Data_Publication\\Pma\\current\\ventura\\pma.vp

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

    No. 6 fuel oil includes Bunker C fuel oil and is used for the pro- duction of electric power, space heating, vessel bunk- ering, and various industrial purposes. Retailer: A...

  12. untitled

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

    No. 6 fuel oil includes Bunker C fuel oil and is used for the pro- duction of electric power, space heating, vessel bunk- ering, and various industrial purposes. Retailer: A...

  13. The Disruption of Vessel-Spanning Bubbles with Sloped Fins in Flat-Bottom and 2:1 Elliptical-Bottom Vessels

    SciTech Connect (OSTI)

    Gauglitz, Phillip A.; Buchmiller, William C.; Jenks, Jeromy WJ; Chun, Jaehun; Russell, Renee L.; Schmidt, Andrew J.; Mastor, Michael M.

    2010-09-22T23:59:59.000Z

    Radioactive sludge was generated in the K-East Basin and K-West Basin fuel storage pools at the Hanford Site while irradiated uranium metal fuel elements from the N Reactor were being stored and packaged. The fuel has been removed from the K Basins, and currently, the sludge resides in the KW Basin in large underwater Engineered Containers. The first phase to the Sludge Treatment Project being led by CH2MHILL Plateau Remediation Company (CHPRC) is to retrieve and load the sludge into sludge transport and storage containers (STSCs) and transport the sludge to T Plant for interim storage. The STSCs will be stored inside T Plant cells that are equipped with secondary containment and leak-detection systems. The sludge is composed of a variety of particulate materials and water, including a fraction of reactive uranium metal particles that are a source of hydrogen gas. If a situation occurs where the reactive uranium metal particles settle out at the bottom of a container, previous studies have shown that a vessel-spanning gas layer above the uranium metal particles can develop and can push the overlying layer of sludge upward. The major concern, in addition to the general concern associated with the retention and release of a flammable gas such as hydrogen, is that if a vessel-spanning bubble (VSB) forms in an STSC, it may drive the overlying sludge material to the vents at the top of the container. Then it may be released from the container into the cell’s secondary containment system at T Plant. A previous study demonstrated that sloped walls on vessels, both cylindrical coned-shaped vessels and rectangular vessels with rounded ends, provided an effective approach for disrupting a VSB by creating a release path for gas as a VSB began to rise. Based on the success of sloped-wall vessels, a similar concept is investigated here where a sloped fin is placed inside the vessel to create a release path for gas. A key potential advantage of using a sloped fin compared to a vessel with a sloped wall is that a small fin decreases the volume of a vessel available for sludge storage by a very small fraction compared to a cone-shaped vessel. The purpose of this study is to quantify the capability of sloped fins to disrupt VSBs and to conduct sufficient tests to estimate the performance of fins in full-scale STSCs. Experiments were conducted with a range of fin shapes to determine what slope and width were sufficient to disrupt VSBs. Additional tests were conducted to demonstrate how the fin performance scales with the sludge layer thickness and the sludge strength, density, and vessel diameter based on the gravity yield parameter, which is a dimensionless ratio of the force necessary to yield the sludge to its weight.( ) Further experiments evaluated the difference between vessels with flat and 2:1 elliptical bottoms and a number of different simulants, including the KW container sludge simulant (complete), which was developed to match actual K-Basin sludge. Testing was conducted in 5-in., 10-in., and 23-in.-diameter vessels to quantify how fin performance is impacted by the size of the test vessel. The most significant results for these scale-up tests are the trend in how behavior changes with vessel size and the results from the 23-in. vessel. The key objective in evaluating fin performance is to determine the conditions that minimize the volume of a VSB when disruption occurs because this reduces the potential for material inside the STSC from being released through vents.

  14. Bull. U. S. F. C. 1890. Fashine Vessels of the Pacific Coast. (To lace page 13.) PLATEV. %-THE FISHING VESSELS AND BOATS OF THE PACIFIC*COAST."

    E-Print Network [OSTI]

    Bull. U. S. F. C. 1890. Fashine Vessels of the Pacific Coast. (To lace page 13.) PLATEV. #12;%-THE iiitenciod for publication as n part of a report on tho fisheries of the Pacific Coast of the TJnited Stattes

  15. Effect of the Young modulus variability on the mechanical behaviour of a nuclear containment vessel

    E-Print Network [OSTI]

    Effect of the Young modulus variability on the mechanical behaviour of a nuclear containment vessel on the mechanical behaviour of a nuclear containment vessel in case of a loss of cooling agent accident and under values are observed. Preprint submitted to Nuclear Engineering and Design April 19, 2010 hal-00542640

  16. Integrated Design, Operation and Control of Batch Extractive Distillation with a Middle Vessel

    E-Print Network [OSTI]

    Skogestad, Sigurd

    Integrated Design, Operation and Control of Batch Extractive Distillation with a Middle Vessel E. K distillation for separating homogeneous minimum-boiling azeotropic mixtures, where the extractive agent and a control structure for the batch extractive middle vessel distillation is proposed. In extractive

  17. Integrated Design, Operation and Control of Batch Extractive Distillation with a Middle Vessel

    E-Print Network [OSTI]

    Skogestad, Sigurd

    Integrated Design, Operation and Control of Batch Extractive Distillation with a Middle Vessel E. K distillation for separating homogeneous minimum­boiling azeotropic mixtures, where the extractive agent and a control structure for the batch extractive middle vessel distillation is proposed. In extractive

  18. Tissue-Engineered Vascular Grafts as In Vitro Blood Vessel Mimics for the Evaluation of Endothelialization

    E-Print Network [OSTI]

    Barton, Jennifer K.

    -dimensional in vitro blood vessel mimic (BVM) would be ideal for device testing before animal or clinicalTissue-Engineered Vascular Grafts as In Vitro Blood Vessel Mimics for the Evaluation nuclear staining and optical coherence tomography (OCT). En face and cross-sectional evaluation

  19. Modelling the Electron Beam Welding of Nuclear Reactor Pressure Vessel Steel

    E-Print Network [OSTI]

    Cambridge, University of

    Modelling the Electron Beam Welding of Nuclear Reactor Pressure Vessel Steel Christopher J. Duffy fabrication of thick-section steel for critical components such as reactor pressure vessels. Electron beam weld tests performed by Rolls-Royce and The Welding Institute of SA 508 Grade 3 and SA 508 Grade 4N

  20. D0 Silicon Upgrade: Gas Helium Storage Tank Pressure Vessel Engineering Note

    SciTech Connect (OSTI)

    Rucinski, Russ; /Fermilab

    1996-11-11T23:59:59.000Z

    This is to certify that Beaird Industries, Inc. has done a white metal blast per SSPC-SP5 as required per specifications on the vessel internal. Following the blast, a black light inspection was performed by Beaird Quality Control personnel to assure that all debris, grease, etc. was removed and interior was clean prior to closing vessel for helium test.

  1. Southwest Research Institute (SwRI) designs, analyzes, and fabricates pressure vessels

    E-Print Network [OSTI]

    Chapman, Clark R.

    vessels using: n ASME B&PV Code, Section VIII, Division 1 n ASME B&PV Code, Section VIII, Division 2 n ASME B&PV Code, Section VIII, Division 3 n ASME Pressure Vessels for Human Occupancy n American Bureau for the Design, Fabrication, and Erection of Structural Steel for Buildings" n Fabrication n ASME B&PV Code

  2. Sustainable What Federal permits are required for charter/party vessels?

    E-Print Network [OSTI]

    the fish is lying on its size (see Figure 1 on page 2). For black sea bass, the total length measurement flounder, scup, and black sea bass are among the most popular recreationally caught fish along the Atlantic types of summer flounder, scup, and black sea bass vessel permits-- one for vessels for hire (charter

  3. Conceptual Design of a Reactor Pressure Vessel and its Internals for a HPLWR

    SciTech Connect (OSTI)

    Fischer, Kai [EnBW Kraftwerke AG, Kernkraftwerk Philippsburg, Rheinschanzinsel D-76661 Philippsburg (Germany); Starflinger, Joerg; Schulenberg, Thomas [Forschungszentrum Karlsruhe GmbH, Institute for Nuclear and Energy Technologies P.O. Box 3640, D-76021 Karlsruhe (Germany)

    2006-07-01T23:59:59.000Z

    A design for the Reactor Pressure Vessel (RPV) and its internals for a HPLWR (High Performance Light Water Reactor) is presented. The RPV has been dimensioned using the pressure vessel code for nuclear power plants in Germany. In order to use conventional vessel materials such as 20 MnMoNi 5 5 (United States: SA 508), the vessel inner wall has to be kept only in contact with coolant at inlet temperature. Therefore, the hot coolant pipe connection from the steam plenum to the outlet is separated from the RPV inner wall using a thermal sleeve. The core inside the vessel rests on a support plate which is connected to the core barrel. The steam plenum is fixed on top of the core using support brackets which are attached to the adjustable steam outlet pipes. This way, the steam plenum rests on the outlet flanges of the lower vessel, while the core barrel is suspended at the closure head flange of the vessel to control thermal expansions between the internals and the RPV and to minimize thermal stresses. Both, inlet and outlet mass flows are separated via C-ring seals to prevent mixing. The control rod guides in the upper plenum are also suspended at the vessel flange and aligned inside the core barrel using centering pins. (authors)

  4. PPPL-3458 PPPL-3458 Visual Tritium Imaging Of In-Vessel Surfaces

    E-Print Network [OSTI]

    PPPL-3458 PPPL-3458 UC-70 Visual Tritium Imaging Of In-Vessel Surfaces by C. A. Gentile, S. J: http://www.ntis.gov/ordering.htm #12;1 Visual Tritium Imaging Of In-Vessel Surfaces C. A. Gentile, S. J Energy Research Institute, Tritium Engineering Laboratory, Tokai, Ibaraki 319-1195, Japan Abstract

  5. Military Support

    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 SECTION A. Revised:7, at 3:00

  6. Technical analysis of US Army Weapons Systems and related advanced technologies of military interest. Final report

    SciTech Connect (OSTI)

    NONE

    1991-06-14T23:59:59.000Z

    This report summarizes the activities and accomplishments of an US Army technology security project designed to identify and develop effective policy guidelines for militarily critical technologies in specific Army systems and in broad generic technology areas of military interest, Individual systems analyses are documented in separate Weapons Systems Technical Assessments (WSTAs) and the general generic technology areas are evaluated in the Advanced Technology Assessment Reports (ATARs), However, specific details of these assessments are not addressed here, only recommendations regarding aspects of the defined approach, methodology, and format are provided and discussed.

  7. Blood Vessel Normalization in the Hamster Oral Cancer Model for Experimental Cancer Therapy Studies

    SciTech Connect (OSTI)

    Ana J. Molinari; Romina F. Aromando; Maria E. Itoiz; Marcela A. Garabalino; Andrea Monti Hughes; Elisa M. Heber; Emiliano C. C. Pozzi; David W. Nigg; Veronica A. Trivillin; Amanda E. Schwint

    2012-07-01T23:59:59.000Z

    Normalization of tumor blood vessels improves drug and oxygen delivery to cancer cells. The aim of this study was to develop a technique to normalize blood vessels in the hamster cheek pouch model of oral cancer. Materials and Methods: Tumor-bearing hamsters were treated with thalidomide and were compared with controls. Results: Twenty eight hours after treatment with thalidomide, the blood vessels of premalignant tissue observable in vivo became narrower and less tortuous than those of controls; Evans Blue Dye extravasation in tumor was significantly reduced (indicating a reduction in aberrant tumor vascular hyperpermeability that compromises blood flow), and tumor blood vessel morphology in histological sections, labeled for Factor VIII, revealed a significant reduction in compressive forces. These findings indicated blood vessel normalization with a window of 48 h. Conclusion: The technique developed herein has rendered the hamster oral cancer model amenable to research, with the potential benefit of vascular normalization in head and neck cancer therapy.

  8. Creep of A508/533 Pressure Vessel Steel

    SciTech Connect (OSTI)

    Richard Wright

    2014-08-01T23:59:59.000Z

    ABSTRACT Evaluation of potential Reactor Pressure Vessel (RPV) steels has been carried out as part of the pre-conceptual Very High Temperature Reactor (VHTR) design studies. These design studies have generally focused on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Initially, three candidate materials were identified by this process: conventional light water reactor (LWR) RPV steels A508 and A533, 2¼Cr-1Mo in the annealed condition, and Grade 91 steel. The low strength of 2¼Cr-1Mo at elevated temperature has eliminated this steel from serious consideration as the VHTR RPV candidate material. Discussions with the very few vendors that can potentially produce large forgings for nuclear pressure vessels indicate a strong preference for conventional LWR steels. This preference is based in part on extensive experience with forging these steels for nuclear components. It is also based on the inability to cast large ingots of the Grade 91 steel due to segregation during ingot solidification, thus restricting the possible mass of forging components and increasing the amount of welding required for completion of the RPV. Grade 91 steel is also prone to weld cracking and must be post-weld heat treated to ensure adequate high-temperature strength. There are also questions about the ability to produce, and very importantly, verify the through thickness properties of thick sections of Grade 91 material. The availability of large components, ease of fabrication, and nuclear service experience with the A508 and A533 steels strongly favor their use in the RPV for the VHTR. Lowering the gas outlet temperature for the VHTR to 750°C from 950 to 1000°C, proposed in early concept studies, further strengthens the justification for this material selection. This steel is allowed in the ASME Boiler and Pressure Vessel Code for nuclear service up to 371°C (700°F); certain excursions above that temperature are allowed by Code Case N-499-2 (now incorporated as an appendix to Section III Division 5 of the Code). This Code Case was developed with a rather sparse data set and focused primarily on rolled plate material (A533 specification). Confirmatory tests of creep behavior of both A508 and A533 are described here that are designed to extend the database in order to build higher confidence in ensuring the structural integrity of the VHTR RPV during off-normal conditions. A number of creep-rupture tests were carried out at temperatures above the 371°C (700°F) Code limit; longer term tests designed to evaluate minimum creep behavior are ongoing. A limited amount of rupture testing was also carried out on welded material. All of the rupture data from the current experiments is compared to historical values from the testing carried out to develop Code Case N-499-2. It is shown that the A508/533 basemetal tested here fits well with the rupture behavior reported from the historical testing. The presence of weldments significantly reduces the time to rupture. The primary purpose of this report is to summarize and record the experimental results in a single document.

  9. Lucrative Opportunities in Asia Pacific to Help Global Bunker...

    Open Energy Info (EERE)

    Energy Concerns to Push Global Market to Grow at 8.1% CAGR from 2013 to 2019 Oil Shale Market is Estimated to Reach USD 7,400.70 Million by 2022 more Group members (32)...

  10. The readers point vessel: hull analysis of an eighteenth century merchant sloop excavated in St. Ann's Bay, Jamaica

    E-Print Network [OSTI]

    Cook, Gregory D.

    1997-01-01T23:59:59.000Z

    's Bay, Jamaica in 1994. Excavators removed overburden and the ballast pile, recovering over 600 artifacts associated with the vessel-After exposing well-preserved hull remains, divers recorded the ship's structure. The vessel is preserved from the base...

  11. Investigation of downward facing critical heat flux with water-based nanofluids for In-Vessel Retention applications

    E-Print Network [OSTI]

    DeWitt, Gregory L

    2011-01-01T23:59:59.000Z

    In-Vessel Retention ("IVR") is a severe accident management strategy that is power limiting to the Westinghouse AP1000 due to critical heat flux ("CHF") at the outer surface of the reactor vessel. Increasing the CHF level ...

  12. Weapons proliferation and organized crime: The Russian military and security force dimension

    SciTech Connect (OSTI)

    Turbiville, G.H.

    1996-06-01T23:59:59.000Z

    One dimension of international security of the post-Cold War era that has not received enough attention is how organized crime facilitates weapons proliferation worldwide. The former Soviet Union (FSU) has emerged as the world`s greatest counterproliferation challenge. It contains the best developed links among organized crime, military and security organizations, and weapons proliferation. Furthermore, Russian military and security forces are the principle source of arms becoming available to organized crime groups, participants in regional conflict, and corrupt state officials engaged in the black, gray, and legal arms markets in their various dimensions. The flourishing illegal trade in conventional weapons is the clearest and most tangible manifestation of the close links between Russian power ministries and criminal organizations. The magnitude of the WMD proliferation problem from the FSU is less clear and less tangible. There have been many open reports of small-scale fissile material smuggling out of the FSU. The situation with regard to the proliferation of chemical weapon usually receives less attention but may be more serious. With an acknowledged stockpile of 40,000 metric tons of chemical agents, the potential for proliferation is enormous.

  13. Distribution of Hydrogen Isotopes, Carbon and Beryllium on In-Vessel Surfaces in the Various JET Divertors

    E-Print Network [OSTI]

    Distribution of Hydrogen Isotopes, Carbon and Beryllium on In-Vessel Surfaces in the Various JET Divertors

  14. Theoretical and Experimental Simulation of Accident Scenarios of the JET Cryogenic Components Part I: The JET In-vessel Cryopump

    E-Print Network [OSTI]

    Theoretical and Experimental Simulation of Accident Scenarios of the JET Cryogenic Components Part I: The JET In-vessel Cryopump

  15. Method for forming a bladder for fluid storage vessels

    DOE Patents [OSTI]

    Mitlitsky, Fred (Livermore, CA); Myers, Blake (Livermore, CA); Magnotta, Frank (Lafayette, CA)

    2000-01-01T23:59:59.000Z

    A lightweight, low permeability liner for graphite epoxy composite compressed gas storage vessels. The liner is composed of polymers that may or may not be coated with a thin layer of a low permeability material, such as silver, gold, or aluminum, deposited on a thin polymeric layer or substrate which is formed into a closed bladder using torispherical or near torispherical end caps, with or without bosses therein, about which a high strength to weight material, such as graphite epoxy composite shell, is formed to withstand the storage pressure forces. The polymeric substrate may be laminated on one or both sides with additional layers of polymeric film. The liner may be formed to a desired configuration using a dissolvable mandrel or by inflation techniques and the edges of the film seamed by heat sealing. The liner may be utilized in most any type of gas storage system, and is particularly applicable for hydrogen, gas mixtures, and oxygen used for vehicles, fuel cells or regenerative fuel cell applications, high altitude solar powered aircraft, hybrid energy storage/propulsion systems, and lunar/Mars space applications, and other applications requiring high cycle life.

  16. Immersive Volume Rendering of Blood Vessels Gregory Long, Han Suk Kim, Alison Marsden, Yuri Bazilevs, Jurgen P. Schulze

    E-Print Network [OSTI]

    Schulze, Jürgen P.

    Immersive Volume Rendering of Blood Vessels Gregory Long, Han Suk Kim, Alison Marsden, Yuri ABSTRACT In this paper, we present a novel method of visualizing flow in blood vessels. Our approach reads to the sparse structure of blood vessels, we utilize an octree to efficiently store the resampled data

  17. High pressure ejection of melt from a reactor pressure vessel. The discharge phase. Revision 7

    SciTech Connect (OSTI)

    Pilch, M.; Tarbell, W.M.

    1985-09-01T23:59:59.000Z

    Recent probabilistic risk-assessment studies identified potential accident sequences in which reactor vessel failure occurs while the primary system is at elevated pressure. The phenomenology of the discharge phase is reviewed here. We propose an improved model for hole ablation following vessel failure, and we compare the model with experiment data. Gas blowthrough is identified as a mechanism that allows steam to escape through the vessel breach before melt ejection is complete. Gas blowthrough leads to pneumatic atomization of the remaining melt before significant depressurization of the primary system occurs.

  18. Navy Mobility Fuels Forecasting System Phase 6 report: The potential impacts of a worst-case military conflict on world petroleum availability

    SciTech Connect (OSTI)

    Lee, R.; Das, S.; Leiby, P.N.

    1991-01-01T23:59:59.000Z

    A major Middle East and European military confrontation would cause an extremely large disruption in the supply of oil worldwide. There would be imbalances between oil supply and demand. These imbalances can only be solved by rationing and by military actions to ensure an adequate flow of crude oil and products. 25 refs., 5 tabs.

  19. R&D of Large Stationary Hydrogen/CNG/HCNG Storage Vessels

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

    Stationary HydrogenCNGHCNG Storage Vessels September 28, 2010 Add hydrogen to natural gas makes it burn more cleanly (notably reducing smog-causing NO X by 50%). HCNG...

  20. Bronchopulmonary Dysplasia, Idiopathic Pulmonary Arterial Hypertension, and Wave Modeling in Stented Vessels

    E-Print Network [OSTI]

    Peters, Andrew

    2011-08-04T23:59:59.000Z

    arterial hypertension (PAH), to identify the hemodynamic attributes which could be altered to ameliorate the progression of these diseases. We then simulated blood flow through five, simple finite element vessel models to determine the effects of stents...

  1. Potential market for LNG-fueled marine vessels in the United States

    E-Print Network [OSTI]

    Brett, Bridget C

    2008-01-01T23:59:59.000Z

    The growing global concern over ship emissions in recent years has driven policy change at the international level toward more stringent vessel emissions standards. The policy change has also been an impetus for innovation ...

  2. Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel

    DOE Patents [OSTI]

    Schreiber, R.B.; Fero, A.H.; Sejvar, J.

    1997-12-16T23:59:59.000Z

    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 to form 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 valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor. 8 figs.

  3. Analyses of a steel containment vessel with an outer contact structure under severe internal overpressurization conditions

    SciTech Connect (OSTI)

    Porter, V.L.

    1993-12-31T23:59:59.000Z

    Many Mark-I and Mark-II BWR plants are designed with a steel vessel as the primary containment. Typically, the steel containment vessel (SCV) is enclosed within a reinforced concrete shield building with only a small gap (50--90mm) separating the two structures. This paper describes finite element analyses performed to evaluate the effects of contact and friction between a steel containment vessel and an outer contact structure when the containment vessel is subjected to large internal pressures. These computations were motivated by a joint program on containment integrity involving the Nuclear Power Engineering Corporation (NUPEC) of Japan, the US Nuclear Regulatory Commission (NRC), and Sandia National Laboratories for testing model containments.

  4. A model for determining the fate of hazardous constituents in waste during in-vessel composting

    E-Print Network [OSTI]

    Bollineni, Prasanthi

    1994-01-01T23:59:59.000Z

    compound undergoes when subjected to composting. The purpose of this thesis is to define these processes and develop a model for determining the fate of organic compounds in waste during in-vessel composting Volatilization and biodegradation are found...

  5. Blood vessel detection in retinal images and its application in diabetic retinopathy screening

    E-Print Network [OSTI]

    Zhang, Ming

    2009-05-15T23:59:59.000Z

    transform (RCT) algorithm, which converts the intensity information in spatial domain to a high dimensional radial contrast domain. Different feature descriptors are designed to improve the speed, sensitivity, and expandability of the vessel detection system...

  6. ITER vacuum vessel design (D201 subtask 1.3 and subtask 3). Final report

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    ITER Task No. D201, Vacuum Vessel Design (Subtask 1.3 and Subtask 3), was initiated to propose and evaluate local vacuum vessel reinforcement alternatives in proximity to the Neutral Beam, Radial Mid-Plane, Top, and Divertor Ports. These areas were reported to be highly stressed regions based on the results of preliminary stress analyses performed by the USHT (US Home Team) and the ITER Joint Central Team (JCT) at the Garching JWS (Joint Work Site). Initial design activities focused on the divertor port region which was reported to experience the highest stress intensities. Existing stress analysis models and results were reviewed with the USHT stress analysts to obtain an overall understanding of the vessel response to the various applied loads. These reviews indicated that the reported stress intensities in the divertor port region were significantly affected by the loads applied to the vessel in adjacent regions.

  7. Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project...

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

    Unlimited Release Printed February 2013 Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project Scoping and Feasibility Joseph W. Pratt and Aaron P. Harris Prepared by...

  8. E-Print Network 3.0 - advanced in-vessel retention Sample Search...

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

    Technologies... reactors. 12;Engineering Peer Review June 5-7, 2001 19 FIRE In-Vessel Remote Handling System Mi Transfer... Cask Articulated Boom Boom End-Effector Midplane...

  9. Cost reduction of polar class vessels : structural optimization that includes production factors

    E-Print Network [OSTI]

    Normore, Stephen S. (Stephen Selwyn)

    2013-01-01T23:59:59.000Z

    The design of ship structures was normally optimized to reduce construction material and maintain adequate strength while adhering to a given classification society's rules. In the case of Polar Class vessels, where weight ...

  10. Metallic Pressure Vessels Failures M. Mosnier, B. Daudonnet, J. Renard and G. Mavrothalassitis

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    to store or to transport gas or pressurized liquid (such as LPG or LNG), to dry, or as steam boiler... etc of thé vessel is usually achieved with thé help of handbooks, that sometimes overestimate effects

  11. Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel

    DOE Patents [OSTI]

    Schreiber, Roger B. (Penn Twp., PA); Fero, Arnold H. (New Kensington, PA); Sejvar, James (Murrysville, PA)

    1997-01-01T23:59:59.000Z

    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 to form 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 valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor.

  12. Painting blood vessels and atherosclerotic plaques with an adhesive drug depot

    E-Print Network [OSTI]

    Kastrup, Christian J.

    The treatment of diseased vasculature remains challenging, in part because of the difficulty in implanting drug-eluting devices without subjecting vessels to damaging mechanical forces. Implanting materials using adhesive ...

  13. Hydrogen degradation and microstructural effects of the near-threshold fatigue resistance of pressure vessel steels

    E-Print Network [OSTI]

    Fuquen-Molano, Rosendo

    1982-01-01T23:59:59.000Z

    Safety of pressure vessels for applications such as coal conversion reactors requires understanding of the mechanism of environmentally-induced crack propagation and the mechanism by which process-induced microstructures ...

  14. UNIT COSTS fot ARMY FACILITIES -MILITARY CONSTRUCTION PAX NEWSLETTER NO. 3.2.2, dated 30 Mar 2006

    E-Print Network [OSTI]

    US Army Corps of Engineers

    ENGLISH UNIT COSTS fot ARMY FACILITIES - MILITARY CONSTRUCTION PAX NEWSLETTER NO. 3.2.2, dated 30 Mar 2006 1. APPENDIX A - FACILITY UNIT COST TABLE (FOR FY08 and later MILCON, BRAC, IGPBS Projects Newsletter No. 3.2.2, 15 March 2005, and updates the Appendix A, Facility Unit Cost Table, Appendix C, Tri

  15. Antonescu's Regime Revisionism -the Transylvanian Syndrome The main thesis of this paper is that eastern ideological, military, territory recovering

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    and diplomatic activities in order to modify the Balkan boundaries and above all to recover northern Transylvania before the annexation by Romania in 1917-1918 as a secondary consequence of defeat on the western front as participate to the remodeling of the Balkans after the war, or gaining by military efforts Bessarabia

  16. Abstract--In the control of heterogeneous unmanned vehicles in future military operations, it will be critical to provide goal-

    E-Print Network [OSTI]

    Cummings, Mary "Missy"

    of unmanned underwater and aerial vehicles, which included the automatic target recognition acknowledgement1 Abstract-- In the control of heterogeneous unmanned vehicles in future military operations heterogeneous unmanned vehicles (UVs). The DCDT was applied to several decision making processes involving a mix

  17. The 2011 Military Communications Conference -Track 3 -Cyber Security and Network Operations From Security to Vulnerability: Data Authentication

    E-Print Network [OSTI]

    Wang, Wenye

    lines and transform ers [5], to perform critical functions of energy transmission and distributionThe 2011 Military Communications Conference - Track 3 - Cyber Security and Network Operations From Wang· Zhuo Lu* Jianfeng Mat "Department of Electrical and Computer Engineering, NC State University

  18. Pulmonary toxicity after exposure to military-relevant heavy metal tungsten alloy particles

    SciTech Connect (OSTI)

    Roedel, Erik Q., E-mail: Erik.Roedel@amedd.army.mil [Department of General Surgery, Tripler Army Medical Center, Honolulu, HI 96859 (United States); Cafasso, Danielle E., E-mail: Danielle.Cafasso@amedd.army.mil [Department of General Surgery, Tripler Army Medical Center, Honolulu, HI 96859 (United States); Lee, Karen W.M., E-mail: Karen.W.Lee@amedd.army.mil [Department of Clinical Investigation, Tripler Army Medical Center, Honolulu, HI 96859 (United States); Pierce, Lisa M., E-mail: Lisa.Pierce@amedd.army.mil [Department of Clinical Investigation, Tripler Army Medical Center, Honolulu, HI 96859 (United States)

    2012-02-15T23:59:59.000Z

    Significant controversy over the environmental and public health impact of depleted uranium use in the Gulf War and the war in the Balkans has prompted the investigation and use of other materials including heavy metal tungsten alloys (HMTAs) as nontoxic alternatives. Interest in the health effects of HMTAs has peaked since the recent discovery that rats intramuscularly implanted with pellets containing 91.1% tungsten/6% nickel/2.9% cobalt rapidly developed aggressive metastatic tumors at the implantation site. Very little is known, however, regarding the cellular and molecular mechanisms associated with the effects of inhalation exposure to HMTAs despite the recognized risk of this route of exposure to military personnel. In the current study military-relevant metal powder mixtures consisting of 92% tungsten/5% nickel/3% cobalt (WNiCo) and 92% tungsten/5% nickel/3% iron (WNiFe), pure metals, or vehicle (saline) were instilled intratracheally in rats. Pulmonary toxicity was assessed by cytologic analysis, lactate dehydrogenase activity, albumin content, and inflammatory cytokine levels in bronchoalveolar lavage fluid 24 h after instillation. The expression of 84 stress and toxicity-related genes was profiled in lung tissue and bronchoalveolar lavage cells using real-time quantitative PCR arrays, and in vitro assays were performed to measure the oxidative burst response and phagocytosis by lung macrophages. Results from this study determined that exposure to WNiCo and WNiFe induces pulmonary inflammation and altered expression of genes associated with oxidative and metabolic stress and toxicity. Inhalation exposure to both HMTAs likely causes lung injury by inducing macrophage activation, neutrophilia, and the generation of toxic oxygen radicals. -- Highlights: ? Intratracheal instillation of W–Ni–Co and W–Ni–Fe induces lung inflammation in rats. ? W–Ni–Co and W–Ni–Fe alter expression of oxidative stress and toxicity genes. ? W–Ni–Co induces a greater oxidative burst response than W–Ni–Fe in lung macrophages.

  19. A critical contraction frequency in lymphatic vessels: transition to a state of partial summation

    E-Print Network [OSTI]

    Meisner, Joshua Keith

    2009-06-02T23:59:59.000Z

    , 57)). Therefore, the relaxation rate of ventricles is high, and a calcium plateau creates an extended refractory period in the cardiac action potential to minimize summation. In contrast, blood vessels, which must regulate blood flow through... lymphatic vessels possess a refractory period that prevents tetanus, the effective refractory period is less 3 than total contraction time, ending at ~50% relaxation (28). Taken together, no one has demonstrated a mechanism that prevents the summation...

  20. Transient PVT measurements and model predictions for vessel heat transfer. Part II.

    SciTech Connect (OSTI)

    Felver, Todd G.; Paradiso, Nicholas Joseph; Winters, William S., Jr.; Evans, Gregory Herbert; Rice, Steven F.

    2010-07-01T23:59:59.000Z

    Part I of this report focused on the acquisition and presentation of transient PVT data sets that can be used to validate gas transfer models. Here in Part II we focus primarily on describing models and validating these models using the data sets. Our models are intended to describe the high speed transport of compressible gases in arbitrary arrangements of vessels, tubing, valving and flow branches. Our models fall into three categories: (1) network flow models in which flow paths are modeled as one-dimensional flow and vessels are modeled as single control volumes, (2) CFD (Computational Fluid Dynamics) models in which flow in and between vessels is modeled in three dimensions and (3) coupled network/CFD models in which vessels are modeled using CFD and flows between vessels are modeled using a network flow code. In our work we utilized NETFLOW as our network flow code and FUEGO for our CFD code. Since network flow models lack three-dimensional resolution, correlations for heat transfer and tube frictional pressure drop are required to resolve important physics not being captured by the model. Here we describe how vessel heat transfer correlations were improved using the data and present direct model-data comparisons for all tests documented in Part I. Our results show that our network flow models have been substantially improved. The CFD modeling presented here describes the complex nature of vessel heat transfer and for the first time demonstrates that flow and heat transfer in vessels can be modeled directly without the need for correlations.

  1. Automated segmentation of the pulmonary arteries in low-dose CT by vessel tracking

    E-Print Network [OSTI]

    Wala, Jeremiah; Lee, Jaesung; Jirapatnakul, Artit; Biancardi, Alberto; Reeves, Anthony

    2011-01-01T23:59:59.000Z

    We present a fully automated method for top-down segmentation of the pulmonary arterial tree in low-dose thoracic CT images. The main basal pulmonary arteries are identified near the lung hilum by searching for candidate vessels adjacent to known airways, identified by our previously reported airway segmentation method. Model cylinders are iteratively fit to the vessels to track them into the lungs. Vessel bifurcations are detected by measuring the rate of change of vessel radii, and child vessels are segmented by initiating new trackers at bifurcation points. Validation is accomplished using our novel sparse surface (SS) evaluation metric. The SS metric was designed to quantify the magnitude of the segmentation error per vessel while significantly decreasing the manual marking burden for the human user. A total of 210 arteries and 205 veins were manually marked across seven test cases. 134/210 arteries were correctly segmented, with a specificity for arteries of 90%, and average segmentation error of 0.15 mm...

  2. Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2) at the inside surface of the reactor vessel. 1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced cha...

  3. CFD Analyses of Damaged Fuel Inside a Cleaning Vessel

    SciTech Connect (OSTI)

    Legradi, Gabor; Boros, Ildiko; Aszodi, Attila [Budapest University of Technology and Economics, Muegyetem rkp. 3-9. H-1111 Budapest (Hungary)

    2006-07-01T23:59:59.000Z

    On 10-11 of April, 2003, a serious incident occurred in a special fuel assembly cleaning tank, which was installed into the service shaft of the 2. unit of the Paks NPP in Hungary. During this incident, most of the 30 fuel assemblies put into the cleaning tank have seriously damaged. In the Institute of Nuclear Techniques of the Budapest University of Technology and Economics several CFD investigations were performed concerning the course of the incident, the post incidental conditions and the recovery work. The main reason of the incident can be originated from the defective design of the cleaning tank which resulted in the insufficient cooling of the system in a special operational mode. Our investigation performed with a complex 3D CFX model clearly showed how could as strong temperature stratification develop inside the cleaning tank that it was able to block the coolant flow through the fuel assemblies. After the blocking of the flow, the coolant turned into boiling and the assemblies became uncovered. The temperature of the surfaces of the fuel assemblies went above 1000 deg. C. With the aid of the radiative heat transfer model of the CFX-5.6 code, the surface temperatures were analyzed. When the cleaning instrument got opened the fuel assemblies suffered a serious thermal shock and the assemblies highly damaged. The post-incident thermo-hydraulic state inside the cleaning vessel was investigated with a rather complex CFX model. The uncertainties were decreased by a wide parameter study. The recovery work is planned to be started in the close future. The operators of the damaged fuel removing equipments will work standing on a platform which will be placed into the service shaft just above the surface of the coolant of decreased level. Protecting the workers against unnecessary personal doses is a very important task. In this situation, while the coolant is important part of the biological shielding, it is also a source of radiation due to the considerable amount of radioactive contamination dispersed into it. Therefore, the 3D distribution of the contamination in the service shaft was estimated for different operational and incidental scenarios with a wide parameter study made by a 3D CFX model. This comprehensive work performed with several models and calculations is tersely outlined according to the limited extent of the paper. (authors)

  4. Distinguishing Realistic Military Blasts from Firecrackers in Mitigation Studies of Blast Induced Traumatic Brain Injury

    SciTech Connect (OSTI)

    Moss, W C; King, M J; Blackman, E G

    2011-01-21T23:59:59.000Z

    In their Contributed Article, Nyein et al. (1,2) present numerical simulations of blast waves interacting with a helmeted head and conclude that a face shield may significantly mitigate blast induced traumatic brain injury (TBI). A face shield may indeed be important for future military helmets, but the authors derive their conclusions from a much smaller explosion than typically experienced on the battlefield. The blast from the 3.16 gm TNT charge of (1) has the following approximate peak overpressures, positive phase durations, and incident impulses (3): 10 atm, 0.25 ms, and 3.9 psi-ms at the front of the head (14 cm from charge), and 1.4 atm, 0.32 ms, and 1.7 psi-ms at the back of a typical 20 cm head (34 cm from charge). The peak pressure of the wave decreases by a factor of 7 as it traverses the head. The blast conditions are at the threshold for injury at the front of the head, but well below threshold at the back of the head (4). The blast traverses the head in 0.3 ms, roughly equal to the positive phase duration of the blast. Therefore, when the blast reaches the back of the head, near ambient conditions exist at the front. Because the headform is so close to the charge, it experiences a wave with significant curvature. By contrast, a realistic blast from a 2.2 kg TNT charge ({approx} an uncased 105 mm artillery round) is fatal at an overpressure of 10 atm (4). For an injury level (4) similar to (1), a 2.2 kg charge has the following approximate peak overpressures, positive phase durations, and incident impulses (3): 2.1 atm, 2.3 ms, and 18 psi-ms at the front of the head (250 cm from charge), and 1.8 atm, 2.5 ms, and 16.8 psi-ms at the back of the head (270 cm from charge). The peak pressure decreases by only a factor of 1.2 as it traverses the head. Because the 0.36 ms traversal time is much smaller than the positive phase duration, pressures on the head become relatively uniform when the blast reaches the back of the head. The larger standoff implies that the headform locally experiences a nearly planar blast wave. Also, the positive phase durations and blast impulses are much larger than those of (1). Consequently, the blast model used in (1) is spatially and temporally very different from a military blast. It would be useful to repeat the calculations using military blast parameters. Finally, (1) overlooks a significant part of (5). On page 1 and on page 3, (1) states that (5) did not consider helmet pads. But pages pages 3 and 4 of (5) present simulations of blast wave propagation across an ACH helmeted head form with and without pads. (5) states that when the pads are present, the 'underwash' of air under the helmet is blocked when compared to the case without. (1) reaches this same conclusion, but reports it as a new result rather than a confirmation of that already found in (5).

  5. Structural integrity assessment of type 201LN stainless steel cryogenic pressure vessels

    SciTech Connect (OSTI)

    Rana, M.D.; Zawierucha, R. [Praxair, Inc., Tonawanda, NY (United States)

    1995-12-01T23:59:59.000Z

    The ASME Boiler and Pressure Vessel Code Committee approved the Code Case 2123 in 1992 which allows the use of Type 201LN stainless steel in the construction of ASME Section VIII, Division 1 and Division 2 pressure vessels for -320{degrees}F applications. Type 201LN stainless steel is a nitrogen strengthened modified version of ASTM A240, Type 201 stainless steel with a restricted chemistry. The Code allowable design stresses for Type 201LN for Division 1 vessels are approximately 27% higher than Type 304 stainless steel and equal to that of the 5 Ni and 9 Ni steels. This paper discusses the important features of the Code Case 2123 and the structural integrity assessment of Type 201LN stainless steel cryogenic vessels. Tensile, Charpy-V-notch and fracture properties have been obtained on several heats of this steel including weldments. A linear-elastic fracture mechanics analysis has been conducted to assess the expected fracture mode and the fracture-critical crack sizes. The results have been compared with Type 304 stainless steel, 5 Ni and 9 Ni steel vessels.

  6. Ex-Vessel Core Melt Modeling Comparison between MELTSPREAD-CORQUENCH and MELCOR 2.1

    SciTech Connect (OSTI)

    Robb, Kevin R [ORNL; Farmer, Mitchell [Argonne National Laboratory (ANL); Francis, Matthew W [ORNL

    2014-03-01T23:59:59.000Z

    System-level code analyses by both United States and international researchers predict major core melting, bottom head failure, and corium-concrete interaction for Fukushima Daiichi Unit 1 (1F1). Although system codes such as MELCOR and MAAP are capable of capturing a wide range of accident phenomena, they currently do not contain detailed models for evaluating some ex-vessel core melt behavior. However, specialized codes containing more detailed modeling are available for melt spreading such as MELTSPREAD as well as long-term molten corium-concrete interaction (MCCI) and debris coolability such as CORQUENCH. In a preceding study, Enhanced Ex-Vessel Analysis for Fukushima Daiichi Unit 1: Melt Spreading and Core-Concrete Interaction Analyses with MELTSPREAD and CORQUENCH, the MELTSPREAD-CORQUENCH codes predicted the 1F1 core melt readily cooled in contrast to predictions by MELCOR. The user community has taken notice and is in the process of updating their systems codes; specifically MAAP and MELCOR, to improve and reduce conservatism in their ex-vessel core melt models. This report investigates why the MELCOR v2.1 code, compared to the MELTSPREAD and CORQUENCH 3.03 codes, yield differing predictions of ex-vessel melt progression. To accomplish this, the differences in the treatment of the ex-vessel melt with respect to melt spreading and long-term coolability are examined. The differences in modeling approaches are summarized, and a comparison of example code predictions is provided.

  7. AB-Net Method of Protection from Projectiles (city, military base, battle-front, etc.)

    E-Print Network [OSTI]

    Alexander Bolonkin

    2008-02-13T23:59:59.000Z

    The author suggests a low cost special AB-Net from artificial fiber, which may protect cities and important objects from rockets, artillery and mortar shells, projectiles, bullets, and strategic weapons. The idea is as follows: The offered AB-Net joins an incoming projectile to a small braking parachute and this incoming projectile loses speed by air braking after a drag distance of 50 - 150 meters. A following interception net after the first may serve to collect the slowed projectiles and their fragments or bomblets so that they do not reach the aimpoint. The author offers the design of AB-Net, a developed theory of snagging with a small braking parachute by AB-Net; and sample computations. These nets may be used for defense of a town, city, military base, battle-front line, road (from terrorists), or any important objects or installations (for example nuclear electric station, government buildings, etc.). Computed projects are: Net to counter small rockets (for example, from Qassam), net to counter artillery projectile (caliber 76 mm), net to counter bullets (caliber 7.6 mm). The offered method is cheaper by thousands of times than protection of a city by current anti-rocket systems. Discussion and results are at the end of the article. Key words: Protection from missile and projectile weapons, mortar, rocket, AB-Net, Qassam defense, incoming defense, armor.

  8. Final report for LDRD project 11-0783 : directed robots for increased military manpower effectiveness.

    SciTech Connect (OSTI)

    Rohrer, Brandon Robinson; Rothganger, Fredrick H.; Wagner, John S.; Xavier, Patrick Gordon; Morrow, James Dan

    2011-09-01T23:59:59.000Z

    The purpose of this LDRD is to develop technology allowing warfighters to provide high-level commands to their unmanned assets, freeing them to command a group of them or commit the bulk of their attention elsewhere. To this end, a brain-emulating cognition and control architecture (BECCA) was developed, incorporating novel and uniquely capable feature creation and reinforcement learning algorithms. BECCA was demonstrated on both a mobile manipulator platform and on a seven degree of freedom serial link robot arm. Existing military ground robots are almost universally teleoperated and occupy the complete attention of an operator. They may remove a soldier from harm's way, but they do not necessarily reduce manpower requirements. Current research efforts to solve the problem of autonomous operation in an unstructured, dynamic environment fall short of the desired performance. In order to increase the effectiveness of unmanned vehicle (UV) operators, we proposed to develop robots that can be 'directed' rather than remote-controlled. They are instructed and trained by human operators, rather than driven. The technical approach is modeled closely on psychological and neuroscientific models of human learning. Two Sandia-developed models are utilized in this effort: the Sandia Cognitive Framework (SCF), a cognitive psychology-based model of human processes, and BECCA, a psychophysical-based model of learning, motor control, and conceptualization. Together, these models span the functional space from perceptuo-motor abilities, to high-level motivational and attentional processes.

  9. Development of a Fluxless Flip Chip Bonding Process for Optical Military Electronics

    SciTech Connect (OSTI)

    Girardi, Michael

    2007-11-11T23:59:59.000Z

    As military electronics tend to become lighter, smaller, thinner, and lower cost, the use of flip chip technology is becoming more common place to meet system requirements, yet survive environments. This paper explores the development of an optical flip chip application and details the selection/qualification of the substrate. The selected assembly consists of a procured 1x12 Vertical Cavity Surface Emitting Laser (VCSEL) die, having 80um diameter eutectic AuSn solder bumps at 250um pitch and flip chip bonded to a .006” thick 99.6% alumina substrate with .006” diameter thru holes and metallized with 500Å WTi, under minimum 2.0-3.0?m (80-120?”) thin film deposited Au. An 8 run, 3 factor, 2 level Full Factorial Design of Experiments (DOE) was completed on procured detector arrays and procured ceramic substrates using the Suss Microtec FC150. The optimum settings for the peak temperature, peak time and final die z-height were selected using the ANOVA results and interaction plots. Additional studies were completed to qualify in-house produced substrates. An epoxy glob-top encapsulant was selected to dissipate stress on the flip chip solder joints and to enhance thermal shock performance.

  10. EA-1999: Proposal to Permit 750 Acres at the Savannah River Site for Use by the State of South Carolina Military Department

    Broader source: Energy.gov [DOE]

    This EA will evaluate the potential environmental impacts from a proposal by South Carolina Military Department (SCMD) to permit the use of 750 acres at SRS for military training exercises and permanent facilities to support training. This proposal, if implemented, would further the purposes of the Memorandum of Understanding between the U.S. Department of the Army and DOE concerning the Use of SRS Lands for Military Training Activities, signed in 2007. SCMD has requested permitting two tracts of land, one near B-Area and one west of L-Lake and north of South Carolina Route 125, to establish facilities for military training purposes. SCMD does not propose to conduct live-fire training or to use tracked vehicles at SRS.

  11. Airborne protected military satellite communications : analysis of open-loop pointing and closed-loop tracking with noisy platform attitude information

    E-Print Network [OSTI]

    Deike, William D

    2010-01-01T23:59:59.000Z

    U.S. military assets' increasing need for secure global communications has led to the design and fabrication of airborne satellite communication terminals that operate under protected security protocol. Protected transmission ...

  12. The impact of individual-, unit-, and enterprise-level factors on psychological health outcomes : a system dynamics study of the U.S. military

    E-Print Network [OSTI]

    Wang, Judy Y. H

    2011-01-01T23:59:59.000Z

    Post-traumatic stress disorder (PTSD) and other psychological health issues have emerged as a signature pathology of combat operations in Iraq and Afghanistan. However, the full continuum of care in the U.S. military for ...

  13. Growing consumption of petroleum products worldwide has resulted in the proliferation of vessels carrying oil, chemicals, and gases

    E-Print Network [OSTI]

    Neimark, Alexander V.

    Growing consumption of petroleum products worldwide has resulted in the proliferation of vessels carrying oil, chemicals, and gases into our harbors. Meeting our society's surging demand for commodities

  14. Modular Inspection System for a Complete IN-Service Examination of Nuclear Reactor Pressure Vessel, Including Beltline Region

    SciTech Connect (OSTI)

    David H. Bothell

    2000-04-30T23:59:59.000Z

    Final Report for a DOE Phase II Contract Describing the design and fabrication of a reactor inspection modular rover prototype for reactor vessel inspection.

  15. Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2003-01-01T23:59:59.000Z

    1.1 This guide covers the general procedures to be considered for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1). 1.2 This guide is designed to accommodate the variable response of reactor-vessel materials in post-irradiation annealing at various temperatures and different time periods. Certain inherent limiting factors must be considered in developing an annealing procedure. These factors include system-design limitations; physical constrain...

  16. RELAP5/MOD2 split reactor vessel model and steamline break analysis

    SciTech Connect (OSTI)

    Petelin, S.; Mavko, B.; Gortnar, O. (Univ. of Ljubljana, (Slovenia))

    1993-04-01T23:59:59.000Z

    A split reactor vessel model for the RELAP5/ MOD2 computer code is developed in an attempt to realize more realistic predictions of asymmetrical transients in a two-loop nuclear power plant. Based on this split reactor model, coolant mixing processes within the reactor vessel are examined. This study evaluates the model improvements in terms of thermal-hydraulic simulations of the reactor core inlet fluid condition and the consequent core behavior. Furthermore, the split reactor vessel model is introduced into an integral RELAP5/MOD2 power plant model, and a steamline break analysis is performed to determine the influence of the boron concentration in the boron injection tank on accident consequences.

  17. In-Vessel Coil Material Failure Rate Estimates for ITER Design Use

    SciTech Connect (OSTI)

    L. C. Cadwallader

    2013-01-01T23:59:59.000Z

    The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

  18. Reactor pressure vessel head vents and methods of using the same

    DOE Patents [OSTI]

    Gels, John L; Keck, David J; Deaver, Gerald A

    2014-10-28T23:59:59.000Z

    Internal head vents are usable in nuclear reactors and include piping inside of the reactor pressure vessel with a vent in the reactor upper head. Piping extends downward from the upper head and passes outside of the reactor to permit the gas to escape or be forcibly vented outside of the reactor without external piping on the upper head. The piping may include upper and lowers section that removably mate where the upper head joins to the reactor pressure vessel. The removable mating may include a compressible bellows and corresponding funnel. The piping is fabricated of nuclear-reactor-safe materials, including carbon steel, stainless steel, and/or a Ni--Cr--Fe alloy. Methods install an internal head vent in a nuclear reactor by securing piping to an internal surface of an upper head of the nuclear reactor and/or securing piping to an internal surface of a reactor pressure vessel.

  19. The chemistry of tributyl phosphate at elevated temperatures in the Plutonium Finishing Plant Process Vessels

    SciTech Connect (OSTI)

    Barney, G.S.; Cooper, T.D.

    1994-06-01T23:59:59.000Z

    Potentially violent chemical reactions of the tributyl phosphate solvent used by the Plutonium Finishing Plant at the Hanford Site were investigated. There is a small probability that a significant quantity of this solvent could be accidental transferred to heated process vessels and react there with nitric acid or plutonium nitrate also present in the solvent extraction process. The results of laboratory studies of the reactions show that exothermic oxidation of tributyl phosphate by either nitric acid or actinide nitrates is slow at temperatures expected in the heated vessels. Less than four percent of the tributyl phosphate will be oxidized in these vented vessels at temperatures between 125{degrees}C and 250{degrees}C because the oxidant will be lost from the vessels by vaporization or decomposition before the tributyl phosphate can be extensively oxidized. The net amounts of heat generated by oxidation with concentrated nitric acid and with thorium nitrate (a stand-in for plutonium nitrate) were determined to be about -150 and -220 joules per gram of tributyl phosphate initially present, respectively. This is not enough heat to cause violent reactions in the vessels. Pyrolysis of the tributyl phosphate occurred in these mixtures at temperatures of 110{degrees}C to 270{degrees}C and produced mainly 1-butene gas, water, and pyrophosphoric acid. Butene gas generation is slow at expected process vessel temperatures, but the rate is faster at higher temperatures. At 252{degrees}C the rate of butene gas generated was 0.33 g butene/min/g of tributyl phosphate present. The measured heat absorbed by the pyrolysis reaction was 228 J/g of tributyl phosphate initially present (or 14.5 kcal/mole of tributyl phosphate). Release of flammable butene gas into process areas where it could ignite appears to be the most serious safety consideration for the Plutonium Finishing Plant.

  20. Scaled Testing to Evaluate Pulse Jet Mixer Performance in Waste Treatment Plant Mixing Vessels

    SciTech Connect (OSTI)

    Fort, James A.; Meyer, Perry A.; Bamberger, Judith A.; Enderlin, Carl W.; Scott, Paul A.; Minette, Michael J.; Gauglitz, Phillip A.

    2010-03-07T23:59:59.000Z

    The Waste Treatment and Immobilization Plant (WTP) at Hanford is being designed and built to pre-treat and vitrify the waste in Hanford’s 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. These vessels have pulse jet mixer (PJM) systems. A test program was developed to evaluate the adequacy of mixing system designs in the solids-containing vessels in the WTP. The program focused mainly on non-cohesive solids behavior. Specifically, the program addressed the effectiveness of the mixing systems to suspend settled solids off the vessel bottom, and distribute the solids vertically. Experiments were conducted at three scales using various particulate simulants. A range of solids loadings and operational parameters were evaluated, including jet velocity, pulse volume, and duty cycle. In place of actual PJMs, the tests used direct injection from tubes with suction at the top of the tank fluid. This gave better control over the discharge duration and duty cycle and simplified the facility requirements. The mixing system configurations represented in testing varied from 4 to 12 PJMs with various jet nozzle sizes. In this way the results collected could be applied to the broad range of WTP vessels with varying geometrical configurations and planned operating conditions. Data for “just-suspended velocity”, solids cloud height, and solids concentration vertical profile were collected, analyzed, and correlated. The correlations were successfully benchmarked against previous large-scale test results, then applied to the WTP vessels using reasonable assumptions of anticipated waste properties to evaluate adequacy of the existing mixing system designs.

  1. The Interagency Process in Support & Stability Operations: Integrating and Aligning the Roles and Missions of Military and Civilian Agencies in Conflict and Post-Conflict Environments

    E-Print Network [OSTI]

    Baetjer, Patrick; Cline, Chris; Hernandorena, Carlos; Polley, Brian; Rogers, Kate; Smith, Amanda; Voelkel, Tyson

    2007-01-01T23:59:59.000Z

    of Government and Public Service at Texas A&M University. May 11, 2007 2 Capstone Research Project “The Interagency Process in Support & Stability Operations: Integrating and Aligning the Roles and Missions of Military and Civilian Agencies...The Bush School of Government and Public Service Texas A&M University Capstone Research Project “The Interagency Process in Support & Stability Operations: Integrating and Aligning the Roles and Missions of Military and Civilian...

  2. Protective interior wall and attach8ing means for a fusion reactor vacuum vessel

    DOE Patents [OSTI]

    Phelps, Richard D. (Greeley, CO); Upham, Gerald A. (Valley Center, CA); Anderson, Paul M. (San Diego, CA)

    1988-01-01T23:59:59.000Z

    An array of connected plates mounted on the inside wall of the vacuum vessel of a magnetic confinement reactor in order to provide a protective surface for energy deposition inside the vessel. All fasteners are concealed and protected beneath the plates, while the plates themselves share common mounting points. The entire array is installed with torqued nuts on threaded studs; provision also exists for thermal expansion by mounting each plate with two of its four mounts captured in an oversize grooved spool. A spool-washer mounting hardware allows one edge of a protective plate to be torqued while the other side remains loose, by simply inverting the spool-washer hardware.

  3. Ceramic vessel production, use and distribution in Northern Mesopotamia and Syria during the Middle Bronze Age II (c. 1800-1600 BC). A functional analysis of vessels from Tell Ahmar, North Syria. 

    E-Print Network [OSTI]

    Perini, Silvia

    2014-07-03T23:59:59.000Z

    and ceramic production at a local and regional level are further investigated. Since there is no one-to-one relation between vessel type and vessel function, the research adopts a multi-dimensional approach formed by the following hierarchical investigations...

  4. Suitability of Agent Technology for Military Command and Control in the Future Combat System Environment

    SciTech Connect (OSTI)

    Potok, TE

    2003-02-13T23:59:59.000Z

    The U.S. Army is faced with the challenge of dramatically improving its war fighting capability through advanced technologies. Any new technology must provide significant improvement over existing technologies, yet be reliable enough to provide a fielded system. The focus of this paper is to assess the novelty and maturity of agent technology for use in the Future Combat System (FCS). The FCS concept represents the U.S. Army's ''mounted'' form of the Objective Force. This concept of vehicles, communications, and weaponry is viewed as a ''system of systems'' which includes net-centric command and control (C{sup 2}) capabilities. This networked C{sup 2} is an important transformation from the historically centralized, or platform-based, C{sup 2} function since a centralized command architecture may become a decision-making and execution bottleneck, particularly as the pace of war accelerates. A mechanism to ensure an effective network-centric C{sup 2} capacity (combining intelligence gathering and analysis available at lower levels in the military hierarchy) is needed. Achieving a networked C{sup 2} capability will require breakthroughs in current software technology. Many have proposed the use of agent technology as a potential solution. Agents are an emerging technology, and it is not yet clear whether it is suitable for addressing the networked C{sup 2} challenge, particularly in satisfying battlespace scalability, mobility, and security expectations. We have developed a set of software requirements for FCS based on military requirements for this system. We have then evaluated these software requirements against current computer science technology. This analysis provides a set of limitations in the current technology when applied to the FCS challenge. Agent technology is compared against this set of limitations to provide a means of assessing the novelty of agent technology in an FCS environment. From this analysis we find that existing technologies will not likely be sufficient to meet the networked C{sup 2} requirements of FCS due to limitations in scalability, mobility, and security. Agent technology provides a number of advantages in these areas, mainly through much stronger messaging and coordination models. These models theoretically allow for significant improvements in many areas, including scalability, mobility, and security. However, the demonstration of such capabilities in an FCS environment does not currently exist, although a number of strong agent-based systems have been deployed in related areas. Additionally, there are challenges in FCS that neither current technology nor agent technology are particularly well suited, such as information fusion and decision support. In summary, we believe that agent technology has the capability to support most of the networked C{sup 2} requirements of FCS. However, we would recommend proof of principle experiments to verify the theoretical advantages of this technology in an FCS environment.

  5. A Report on Policies and Practices of the U.S. Navy for Naming the Vessels of the Navy

    E-Print Network [OSTI]

    A Report on Policies and Practices of the U.S. Navy for Naming the Vessels of the Navy Prepared by: Department of the Navy 1000 Navy Pentagon Rm. 4E720 Washington, DC the Vessels of the Navy 1 Purpose Background Orthodox Traditionalists versus Pragmatic

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

    SciTech Connect (OSTI)

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

    2010-04-13T23:59:59.000Z

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

  7. High-resolution imaging of vessels in the isolated rat brain M. F. Valverde Salzmann1

    E-Print Network [OSTI]

    for the distribution of vessels in the rat brain. Angiography is able to use the blood flow in the brain of the living into a test tube filled with fluorocarbon fluid for susceptibility matching. MR Images were acquired at a horizontal 16.4 T scanner with a homemade microstrip volume coil, using gradient echo sequences

  8. Scaling Theory for Pulsed Jet Mixed Vessels, Sparging, and Cyclic Feed Transport Systems for Slurries

    SciTech Connect (OSTI)

    Kuhn, William L.; Rector, David R.; Rassat, Scot D.; Enderlin, Carl W.; Minette, Michael J.; Bamberger, Judith A.; Josephson, Gary B.; Wells, Beric E.; Berglin, Eric J.

    2013-09-27T23:59:59.000Z

    This document is a previously unpublished work based on a draft report prepared by Pacific Northwest National Laboratory (PNNL) for the Hanford Waste Treatment and Immobilization Plant (WTP) in 2012. Work on the report stopped when WTP’s approach to testing changed. PNNL is issuing a modified version of the document a year later to preserve and disseminate the valuable technical work that was completed. This document establishes technical bases for evaluating the mixing performance of Waste Treatment Plant (WTP) pretreatment process tanks based on data from less-than-full-scale testing, relative to specified mixing requirements. The technical bases include the fluid mechanics affecting mixing for specified vessel configurations, operating parameters, and simulant properties. They address scaling vessel physical performance, simulant physical performance, and “scaling down” the operating conditions at full scale to define test conditions at reduced scale and “scaling up” the test results at reduced scale to predict the performance at full scale. Essentially, this document addresses the following questions: • Why and how can the mixing behaviors in a smaller vessel represent those in a larger vessel? • What information is needed to address the first question? • How should the information be used to predict mixing performance in WTP? The design of Large Scale Integrated Testing (LSIT) is being addressed in other, complementary documents.

  9. Proceedings of PVP2006-ICPVT-11 2006 ASME Pressure Vessels and Piping Division Conference

    E-Print Network [OSTI]

    Barr, Al

    Proceedings of PVP2006-ICPVT-11 2006 ASME Pressure Vessels and Piping Division Conference July 23 response leading to large deformations. Some issues in measurement technique and validation testing of scientific investigation. It is a hazard that is occasion- ally encountered in the chemical [1,2], nuclear [3

  10. HFIR Vessel Maximum Permissible Pressures for Operating Period 26 to 50 EFPY (100 MW)

    SciTech Connect (OSTI)

    Cheverton, R.D.; Inger, J.R.

    1999-01-01T23:59:59.000Z

    Extending the life of the HFIR pressure vessel from 26 to 50 EFPY (100 MW) requires an updated calculation of the maximum permissible pressure for a range in vessel operating temperatures (40-120 F). The maximum permissible pressure is calculated using the equal-potential method, which takes advantage of knowledge gained from periodic hydrostatic proof tests and uses the test conditions (pressure, temperature, and frequency) as input. The maximum permissible pressure decreases with increasing time between hydro tests but is increased each time a test is conducted. The minimum values that occur just prior to a test either increase or decrease with time, depending on the vessel temperature. The minimum value of these minimums is presently specified as the maximum permissible pressure. For three vessel temperatures of particular interest (80, 88, and 110 F) and a nominal time of 3.0 EFPY(100 MVV)between hydro tests, these pressures are 677, 753, and 850 psi. For the lowest temperature of interest (40 F), the maximum permissible pressure is 295 psi.

  11. An investigation of RVACS (reactor vessel auxiliary cooling system) design improvements

    SciTech Connect (OSTI)

    Tzanos, C.P.; Tessier, J.H.; Pedersen, D.R. (Argonne National Laboratory, IL (USA))

    1989-11-01T23:59:59.000Z

    One of the main safety features of the current liquid-metal reactor (LMR) designs is the utilization of decay heat removal systems that remove heat by natural convection. In the reactor vessel auxiliary cooling system (RVACS), decay heat is removed by naturally circulating air in the gap between the guard vessel and a baffle wall surrounding the guard vessel. The objective of this work was to determine the impact of a number of design parameters on the performance of the RVACS of a pool LMR. These parameters were (a) the stack height, (b) the size of the airflow gap, (c) the system pressure loss, (d) fins on the guard vessel or the baffle wall, and (e) roughness (in the form of repeated ribs) on the airflow channel walls. Reactor designs ranging from 400 to 3,500 MW(thermal) were considered. From the RVACS design parameters considered in this analysis, an optimized ribbed configuration gave the best improvement in RVACS performance. For a 3,500-MW(thermal) LMR, the peak sodium and cladding temperatures were reduced by 52 K.

  12. High Gain Observer for Backstepping Control of a MRI-guided Therapeutic Microrobot in Blood Vessels

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    -planned trajectory inherited from the model, with robustness concerns. This paper reports modeling and controlHigh Gain Observer for Backstepping Control of a MRI-guided Therapeutic Microrobot in Blood Vessels Laurent Arcese, Ali Cherry, Matthieu Fruchard, Antoine Ferreira Abstract-- This paper reports modeling

  13. Stingray / Skate / Angel Shark Species Description Observer code:________________________ Vessel Code: ________________ Trip ID: _______________

    E-Print Network [OSTI]

    spines How many? Pelvic fin lobes Dorsal fins Pairs rostral teeth Nearer to pelvic fin than tail tip Nearer to tail tip then pelvic fin None First dorsal fin (check one) VentralStingray / Skate / Angel Shark Species Description Observer code:________________________ Vessel

  14. NEWASH AND TECUMSETH: ANALYSIS OF TWO POST-WAR OF 1812 VESSELS ON THE GREAT LAKES

    E-Print Network [OSTI]

    Gordon, Leeanne E.

    2010-01-16T23:59:59.000Z

    In 1953 the tangled, skeletal remains of a ship were pulled from the small harbor of Penetanguishene, Ontario. Local historians had hoped to raise the hull of a War of 1812 veteran, but the vessel pulled from the depths did not meet the criteria...

  15. Designing A Pattern Stabilization Method Using Scleral Blood Vessels For Laser Eye Surgery

    E-Print Network [OSTI]

    Erdem, Erkut

    Designing A Pattern Stabilization Method Using Scleral Blood Vessels For Laser Eye Surgery Aydin,abc}@cs.hacettepe.edu.tr, hbcakmak@gmail.com Abstract-- In laser eye surgery, the accuracy of operation depends on coherent eye tracking and registration techniques. Main approach used in image processing based eye trackers

  16. Walking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels

    E-Print Network [OSTI]

    Chen, Sheng

    Walking and Climbing Service Robots for Safety Inspection of Nuclear Reactor Pressure Vessels B of Electronics and Computer Science, University of Southampton, Southampton, UK Abstract: Nuclear reactor and the usefulness of these robots for improving safety inspection of nuclear reactors in general are discussed

  17. A Liquid Xenon Ionization Chamber in an All-fluoropolymer Vessel

    SciTech Connect (OSTI)

    LePort, F.; Pocar, A.; Bartoszek, L.; DeVoe, R.; Fierlinger, P.; Flatt, B.; Gratta, G.; Green, M.; Montero Diez, M.; Neilson, R.; O'Sullivan, K.; Wodin, J.; Woisard, D.; Baussan, E.; Breidenbach, M.; Conley, R.; Fairbank, W., Jr.; Farine, J.; Hall, K.; Hallman, D.; Hargrove, C.; /Stanford U., Phys. Dept. /Applied Plastics Technology, Bristol/Neuchatel U. /SLAC /Colorado State U. /Laurentian U. /Carleton U. /Alabama U. /Moscow, ITEP; ,

    2007-02-26T23:59:59.000Z

    A novel technique has been developed to build vessels for liquid xenon ionization detectors entirely out of ultra-clean fluoropolymer. We describe the advantages in terms of low radioactivity contamination, provide some details of the construction techniques, and show the energy resolution achieved with a prototype all-fluoropolymer ionization detector.

  18. The strategic allocation of cyclically calling vessels for multi-terminal container operators

    E-Print Network [OSTI]

    Armbruster, Dieter

    The strategic allocation of cyclically calling vessels for multi-terminal container operators M.P.M. Hendriks , D. Armbruster, , M. Laumanns , E. Lefeber , J.T. Udding Abstract We consider a terminal operator, who provides his logistics services of container handling at multiple terminals within the same port

  19. First International Symposium on Fishing Vessel Energy Efficiency E-Fishing, Vigo, Spain, May 2010

    E-Print Network [OSTI]

    Lewandowski, Roger

    First International Symposium on Fishing Vessel Energy Efficiency E-Fishing, Vigo, Spain, May 2010 HydroPêche: a way to improve energy efficiency of fishing devices Grégory Germain 1 , Philippe Druault 2 should provide a substantial gain on the fuel consumed of actual fishing devices while maintaining

  20. DOE H2 Program Annual Review, 5-20-2003 Insulated Pressure Vessels for

    E-Print Network [OSTI]

    range. J. We are generating tank performance data. K. Testing BOP components. L. Low venting losses) car, km 0 1 2 3 4 5 hydrogenlosses,kg low-pressure LH2 tank MLVSI insulated pressure vessel fueled with LH2 LH2 80 K CH2 1998: thermodynamic analysis 1999: cryogenic cycling 2001: DOT/ISO Tests 2003

  1. J. Fluid Mech. (in press) 1 Shallow-water sloshing in vessels undergoing

    E-Print Network [OSTI]

    Bridges, Tom

    J. Fluid Mech. (in press) 1 Shallow-water sloshing in vessels undergoing prescribed rigid the predominant types of solution are the standing wave and travelling hydraulic jump. But in 3D shallow-dimensional hydraulic jumps and analytical methods are very effective for identifying parameter regimes for these basic

  2. ITER vacuum vessel fabrication plan and cost study (D 68) for the international thermonuclear experimental reactor

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    ITER Task No. 8, Vacuum Vessel Fabrication Plan and Cost Study (D68), was initiated to assess ITER vacuum vessel fabrication, assembly, and cost. The industrial team of Raytheon Engineers & Constructors and Chicago Bridge & Iron (Raytheon/CB&I) reviewed the current vessel basis and prepared a manufacturing plan, assembly plan, and cost estimate commensurate with the present design. The guidance for the Raytheon/CB&I assessment activities was prepared by the ITER Garching Work Site. This guidance provided in the form of work descriptions, sketches, drawings, and costing guidelines for each of the presently identified vacuum vessel Work Breakdown Structure (WBS) elements was compiled in ITER Garching Joint Work Site Memo (Draft No. 9 - G 15 MD 01 94-17-05 W 1). A copy of this document is provided as Appendix 1 to this report. Additional information and clarifications required for the Raytheon/CB&I assessments were coordinated through the US Home Team (USHT) and its technical representative. Design details considered essential to the Task 8 assessments but not available from the ITER Joint Central Team (JCT) were generated by Raytheon/CB&I and documented accordingly.

  3. A Synthesis of Cost and Revenue Surveys for Gulf of Mexico Shrimp Vessels

    E-Print Network [OSTI]

    series cost data are not routinely collected for vessels operat ing in any of the U.S. southeast region of Published Cost and Revenue Data Differences underlying the cost and revenue surveys prevent direct compari in the survey data. For example, changes in the cost an

  4. Certification Testing and Demonstration of Insulated Pressure Vessels for Vehicular Hydrogen Storage

    E-Print Network [OSTI]

    characteristics as liquid hydrogen tanks (low weight and volume), with reduced energy consumption for liquefaction Ave., L-644, Livermore, CA 94551, USA, saceves@llnl.gov Abstract Insulated pressure vessels of electric vehicles to improve environmental quality and energy security, while providing the range

  5. 1 Copyright 2012 by ASME Proceedings of the ASME 2012 Pressure Vessels & Piping Division Conference

    E-Print Network [OSTI]

    Tijsseling, A.S.

    1 Copyright © 2012 by ASME Proceedings of the ASME 2012 Pressure Vessels & Piping Division.P. Andersens veg 7 N-7465 Trondheim Norway E-mail: bjoernar.svingen@rainpower.no Anton BERGANT Litostroj Power = 50 m; inner diameters D1 = 1 m and D2 = 0.2 m [1]. #12;2 Copyright © 2012 by ASME Figure 2. Technical

  6. Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning *

    E-Print Network [OSTI]

    Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning * W of the torus, a three tier system was developed for the outage in order to reduce and control the free tritium. The first phase of the program to reduce the free tritium consisted of direct flowthrough of room air

  7. Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning*

    E-Print Network [OSTI]

    Tritium Reduction and Control in the Vacuum Vessel During TFTR Outage and Decommissioning* W, a three tier system was developed for the outage in order to reduce and control the free tritium. The first phase of the program to reduce the free tritium consisted of direct flowthrough of room air

  8. CALCULATIONS OF TRITIUM FLOW BETWEEN THE BUFFER VESSEL UP TO THE FIRST VACUUM SYSTEM

    E-Print Network [OSTI]

    Sharipov, Felix

    CALCULATIONS OF TRITIUM FLOW BETWEEN THE BUFFER VESSEL UP TO THE FIRST VACUUM SYSTEM Felix Sharipov diff., Eq.(32) µ viscosity of tritium Pa s 1 Introduction The present work is a continuation of the previous report [1], where the preliminary results were obtained for the tritium flow through the source

  9. Mechanical Recanalization of Subacute Vessel Occlusion in Peripheral Arterial Disease with a Directional Atherectomy Catheter

    SciTech Connect (OSTI)

    Massmann, Alexander, E-mail: Alexander.Massmann@uks.eu; Katoh, Marcus [Saarland University Hospital, Department of Diagnostic and Interventional Radiology (Germany); Shayesteh-Kheslat, Roushanak [Saarland University Hospital, Department of General Surgery, Visceral, Vascular, and Pediatric Surgery (Germany); Buecker, Arno [Saarland University Hospital, Department of Diagnostic and Interventional Radiology (Germany)

    2012-10-15T23:59:59.000Z

    Purpose: To retrospectively examine the technical feasibility and safety of directional atherectomy for treatment of subacute infrainguinal arterial vessel occlusions. Methods: Five patients (one woman, four men, age range 51-81 years) with peripheral arterial disease who experienced sudden worsening of their peripheral arterial disease-related symptoms during the last 2-6 weeks underwent digital subtraction angiography, which revealed vessel occlusion in native popliteal artery (n = 4) and in-stent occlusion of the superficial femoral artery (n = 1). Subsequently, all patients were treated by atherectomy with the SilverHawk (ev3 Endovascular, USA) device. Results: The mean diameter of treated vessels was 5.1 {+-} 1.0 mm. The length of the occlusion ranged 2-14 cm. The primary technical success rate was 100%. One patient experienced a reocclusion during hospitalization due to heparin-induced thrombocytopenia. There were no further periprocedural complications, in particular no peripheral embolizations, until hospital discharge or during the follow-up period of 1 year. Conclusion: The recanalization of infrainguinal arterial vessel occlusions by atherectomy with the SilverHawk device is technically feasible and safe. In our limited retrospective study, it was associated with a high technical success rate and a low procedure-related complication rate.

  10. Solar technical assistance provided to Forest City military communities in Hawaii for incorporation of 20-30 MW of solar energy generation to power family housing for US Navy personnel.

    SciTech Connect (OSTI)

    Dominick, Jeff (National Renewable Energy Laboratory, Golden, CO); Merrigan, Tim (National Renewable Energy Laboratory, Golden, CO); Boudra, Will (Forest City Military Communities, Honolulu, HI); Miller, Ryan (CH2M Hill, Englewood, CO); Cisneros, Gabriela (New Mexico State University, Las Cruces, NM); Rosenthal, Andrew L. (New Mexico State University, Las Cruces, NM); Kuszmaul, Scott S.; Gupta, Vipin P.

    2010-06-01T23:59:59.000Z

    In May 2007, Forest City Military Communities won a US Department of Energy Solar America Showcase Award. As part of this award, executives and staff from Forest City Military Communities worked side-by-side with a DOE technical assistance team to overcome technical obstacles encountered by this large-scale real estate developer and manager. This paper describes the solar technical assistance that was provided and the key solar experiences acquired by Forest City Military Communities over an 18 month period.

  11. In-vessel Retention Strategy for High Power Reactors - K-INERI Final Report (includes SBLB Test Results for Task 3 on External Reactor Vessel Cooling (ERVC) Boiling Data and CHF Enhancement Correlations)

    SciTech Connect (OSTI)

    F. B. Cheung; J. Yang; M. B. Dizon; J. Rempe

    2005-01-01T23:59:59.000Z

    In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe PWR (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing LWRs. However, it is not clear that currently proposed external reactor vessel cooling (ERVC) without additional enhancements could provide sufficient heat removal for higher-power reactors (up to 1500 MWe). Hence, a collaborative, three-year, U.S. - Korean International Nuclear Energy Research Initiative (INERI) project was completed in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) investigated the performance of ERVC and an in-vessel core catcher (IVCC) to determine if IVR is feasible for reactors up to 1500 MWe.

  12. A STUDY OF EXTRACTIVE AND REMOTE-SENSING SAMPLING AND MEASUREMENT OF EMISSIONS FROM MILITARY AIRCRAFT ENGINES

    SciTech Connect (OSTI)

    Cheng, Mengdawn [ORNL; Corporan, E. [Air Force Research Laboratory, Wright-Patterson AFB, OH

    2010-01-01T23:59:59.000Z

    Aircraft emissions contribute to the increased atmospheric burden of particulate matter (e.g., black carbon and secondary organic compounds) that plays a role in air quality, contrail formation and climate change. Sampling and measurement of modern aircraft emissions at the engine exhaust plane (EEP) for to engine and fuel certification remains a daunting task, no agency-certified method is available for the task. In this paper we summarize the results of a recent study that was devoted to investigate both extractive and optical remote-sensing (ORS) technologies in sampling and measurement of gaseous and particulate matter (PM) emitted by a number of military aircraft engines operated with JP-8 and a Fischer-Tropsch (FT) fuel at various engine conditions. These engines include cargo, bomber, and helicopter types of military aircraft that consumes 70-80% of the military aviation fuel each year. The emission indices of selected pollutants are discussed as these data may be of interest for atmospheric modeling and for design of air quality control strategies around the airports and military bases. It was found that non-volatile particles in the engine emissions were all in the ultrafine range. The mean diameter of particles increased as the engine power increased; the mode diameters were in the 20nm range for the low power condition of a new helicopter engine to 80nm for the high power condition of a newly maintained bomber engine. Elemental analysis indicated little metals were present on particles in the exhaust, while most of the materials on the exhaust particles were based on carbon and sulfate. Carbon monoxide, carbon dioxide, nitrogen oxide, sulfur dioxide, formaldehyde, ethylene, acetylene, propylene, and alkanes were detected using both technologies. The last five species (in the air toxics category) were most noticeable only under the low engine power. The emission indices calculated based on the ORS data were however observed to differ significantly (up to 90%) from (typically lower than) those based on the extractive techniques. However, the ORS techniques were useful in providing non-intrusive real-time measurements of gaseous species in the exhaust plume, which warrants further development. The results obtained in this program validate sampling methodology and measurement techniques used for non-volatile PM aircraft emissions as described in the SAE AIR-6037.

  13. ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING DEACTIVATION AND DECOMMISSIONING OF REACTOR VESSELS AT THE SAVANNAH RIVER SITE

    SciTech Connect (OSTI)

    Wiersma, B.; Serrato, M.; Langton, C.

    2010-11-10T23:59:59.000Z

    The R- and P-reactor vessels at the Savannah River Site (SRS) are being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of physically isolating and stabilizing the reactor vessel by filling it with a grout material. The reactor vessels contain aluminum alloy materials, which pose a concern in that aluminum corrodes rapidly when it comes in contact with the alkaline grout. A product of the corrosion reaction is hydrogen gas and therefore potential flammability issues were assessed. A model was developed to calculate the hydrogen generation rate as the reactor is being filled with the grout material. Three options existed for the type of grout material for D&D of the reactor vessels. The grout formulation options included ceramicrete (pH 6-8), a calcium aluminate sulfate (CAS) based cement (pH 10), or Portland cement grout (pH 12.4). Corrosion data for aluminum in concrete were utilized as input for the model. The calculations considered such factors as the surface area of the aluminum components, the open cross-sectional area of the reactor vessel, the rate at which the grout is added to the reactor vessel, and temperature. Given the hydrogen generation rate, the hydrogen concentration in the vapor space of the reactor vessel above the grout was calculated. This concentration was compared to the lower flammability limit for hydrogen. The assessment concluded that either ceramicrete or the CAS grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters did not provide a margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. Therefore, it was recommended that this grout not be utilized for this task. On the other hand, the R-reactor vessel contained significantly less aluminum surface area that the P-reactor vessel based on current facility process knowledge, surface observations, and drawings. Therefore, a Portland cement grout may be considered for grouting operations as well as the other grout formulations.

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

    SciTech Connect (OSTI)

    Cannell, Gary L. [Fluor Enterprises, Inc.; Huth, Ralph J. [CH2MHill Plateau Remediation Company; Hallum, Randall T. [Fluor Government Group

    2013-08-26T23:59:59.000Z

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

  15. Use of Polycarbonate Vacuum Vessels in High-Temperature Fusion-Plasma Research

    SciTech Connect (OSTI)

    B. Berlinger, A. Brooks, H. Feder, J. Gumbas, T. Franckowiak and S.A. Cohen

    2012-09-27T23:59:59.000Z

    Magnetic fusion energy (MFE) research requires ultrahigh-vacuum (UHV) conditions, primarily to reduce plasma contamination by impurities. For radiofrequency (RF)-heated plasmas, a great benefit may accrue from a non-conducting vacuum vessel, allowing external RF antennas which avoids the complications and cost of internal antennas and high-voltage high-current feedthroughs. In this paper we describe these and other criteria, e.g., safety, availability, design flexibility, structural integrity, access, outgassing, transparency, and fabrication techniques that led to the selection and use of 25.4-cm OD, 1.6-cm wall polycarbonate pipe as the main vacuum vessel for an MFE research device whose plasmas are expected to reach keV energies for durations exceeding 0.1 s

  16. Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This guide discusses test procedures that can be used in conjunction with, but not as alternatives to, those required by Practices E185 and E2215 for the surveillance of nuclear reactor vessels. The supplemental mechanical property tests outlined permit the acquisition of additional information on radiation-induced changes in fracture toughness, notch ductility, and yield strength properties of the reactor vessel steels. 1.2 This guide provides recommendations for the preparation of test specimens for irradiation, and identifies special precautions and requirements for reactor surveillance operations and postirradiation test planning. Guidance on data reduction and computational procedures is also given. Reference is made to other ASTM test methods for the physical conduct of specimen tests and for raw data acquisition.

  17. Calculational criticality analyses of 10- and 20-MW UF[sub 6] freezer/sublimer vessels

    SciTech Connect (OSTI)

    Jordan, W.C.

    1993-02-01T23:59:59.000Z

    Calculational criticality analyses have been performed for 10- and 20-MW UF[sub 6] freezer/sublimer vessels. The freezer/sublimers have been analyzed over a range of conditions that encompass normal operation and abnormal conditions. The effects of HF moderation of the UF[sub 6] in each vessel have been considered for uranium enriched between 2 and 5 wt % [sup 235]U. The results indicate that the nuclearly safe enrichments originally established for the operation of a 10-MW freezer/sublimer, based on a hydrogen-to-uranium moderation ratio of 0.33, are acceptable. If strict moderation control can be demonstrated for hydrogen-to-uranium moderation ratios that are less than 0.33, then the enrichment limits for the 10-MW freezer/sublimer may be increased slightly. The calculations performed also allow safe enrichment limits to be established for a 20-NM freezer/sublimer under moderation control.

  18. Calculational criticality analyses of 10- and 20-MW UF{sub 6} freezer/sublimer vessels

    SciTech Connect (OSTI)

    Jordan, W.C.

    1993-02-01T23:59:59.000Z

    Calculational criticality analyses have been performed for 10- and 20-MW UF{sub 6} freezer/sublimer vessels. The freezer/sublimers have been analyzed over a range of conditions that encompass normal operation and abnormal conditions. The effects of HF moderation of the UF{sub 6} in each vessel have been considered for uranium enriched between 2 and 5 wt % {sup 235}U. The results indicate that the nuclearly safe enrichments originally established for the operation of a 10-MW freezer/sublimer, based on a hydrogen-to-uranium moderation ratio of 0.33, are acceptable. If strict moderation control can be demonstrated for hydrogen-to-uranium moderation ratios that are less than 0.33, then the enrichment limits for the 10-MW freezer/sublimer may be increased slightly. The calculations performed also allow safe enrichment limits to be established for a 20-NM freezer/sublimer under moderation control.

  19. USING A CONTAINMENT VESSEL LIFTING APPARATUS FOR REMOTE OPERATIONS OF SHIPPING PACKAGES

    SciTech Connect (OSTI)

    Loftin, Bradley [Savannah River National Laboratory; Koenig, Richard [Savannah River National Laboratory

    2013-08-08T23:59:59.000Z

    The 9977 and the 9975 shipping packages are used in various nuclear facilities within the Department of Energy. These shipping packages are often loaded in designated areas with designs using overhead cranes or A-frames with lifting winches. However, there are cases where loading operations must be performed in remote locations where these facility infrastructures do not exist. For these locations, a lifting apparatus has been designed to lift the containment vessels partially out of the package for unloading operations to take place. Additionally, the apparatus allows for loading and closure of the containment vessel and subsequent pre-shipment testing. This paper will address the design of the apparatus and the challenges associated with the design, and it will describe the use of the apparatus.

  20. Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability

    DOE Patents [OSTI]

    Hunsbedt, A.; Boardman, C.E.

    1995-04-11T23:59:59.000Z

    A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor is disclosed. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo`s structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated. 5 figures.

  1. Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability

    DOE Patents [OSTI]

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

    1995-01-01T23:59:59.000Z

    A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo's structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated.

  2. Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project Scoping and Feasibility.

    SciTech Connect (OSTI)

    Pratt, Joseph William; Harris, Aaron P

    2013-01-01T23:59:59.000Z

    A barge-mounted hydrogen-fueled proton exchange membrane (PEM) fuel cell system has the potential to reduce emissions and fossil fuel use of maritime vessels in and around ports. This study determines the technical feasibility of this concept and examines specific options on the U.S. West Coast for deployment practicality and potential for commercialization.The conceptual design of the system is found to be straightforward and technically feasible in several configurations corresponding to various power levels and run times.The most technically viable and commercially attractive deployment options were found to be powering container ships at berth at the Port of Tacoma and/or Seattle, powering tugs at anchorage near the Port of Oakland, and powering refrigerated containers on-board Hawaiian inter-island transport barges. Other attractive demonstration options were found at the Port of Seattle, the Suisun Bay Reserve Fleet, the California Maritime Academy, and an excursion vessel on the Ohio River.

  3. Analysis of hydrodynamic phenomena in simulant experiments investigating cavity interactions following postulated vessel meltthrough

    SciTech Connect (OSTI)

    Sienicki, J.J.; Spencer, B.W.

    1984-01-01T23:59:59.000Z

    An analysis of hydrodynamic phenomena in simulant experiments examining aspects of ex-vessel material interactions in a PWR reactor cavity following postulated core meltdown and localized breaching of the reactor vessel has been carried out. While previous analyses of the tests examined thresholds for the onset of sweepout of fluid from the cavity, the present analysis considers the progression of specific hydrodynamic phenomena involved in the dispersal process: crater formation due to gas jet impingement, radial wave motion and growth, entrainment and transport of liquid droplets, liquid layer formation due to droplet recombination, fluidization of liquid remaining in the cavity, removal of fluidized liquid droplets from the cavity, and the ultimate removal of the remaining liquid layer within the tunnel passageway. Phenomenological models which may be used to predict the phenomena are presented.

  4. Dosimetry assessments for the reactor pressure vessel and core barrel in UK PWR plant

    SciTech Connect (OSTI)

    Thornton, D.A.; Allen, D.A.; Huggon, A.P.; Picton, D.J.; Robinson, A.T.; Steadman, R.J. [Serco, Rutherford House, Quedgeley, Gloucester, Gl2 4NF (United Kingdom); Seren, T.; Lipponen, M.; Kekki, T. [VTT, Technical Research Centre of Finland, Otakaari 3 K, P.O. BOX 1000, Espoo, FI-02044 (Finland)

    2011-07-01T23:59:59.000Z

    Specimens for the Sizewell B reactor pressure vessel (RPV) inservice steels surveillance program are irradiated inside eight capsules located within the reactor pressure vessel and loaded prior to commissioning. The periodic removal of these capsules and testing of their contents provides material properties data at intervals during the lifetime of the plant. Neutron activation measurements and radiation transport calculations play an essential role in assessing the neutron exposure of the specimens and RPV. Following the most recent withdrawal, seven capsules have now been removed covering nine cycles of reactor operation. This paper summarizes the dosimetry results of the Sizewell B surveillance program obtained to date. In addition to an overview of the calculational methodology it includes a review of the measurements. Finally, it describes an extension of the methodology to provide dosimetry recommendations for the core barrel and briefly discusses the results that were obtained. (authors)

  5. Simulations of Blood Flow in Plain Cylindrical and Constricted Vessels with Single Cell Resolution

    E-Print Network [OSTI]

    Florian Janoschek; Federico Toschi; Jens Harting

    2011-05-31T23:59:59.000Z

    Understanding the physics of blood is challenging due to its nature as a suspension of soft particles and the fact that typical problems involve different scales. This is valid also for numerical investigations. In fact, many computational studies either neglect the existence of discrete cells or resolve relatively few cells very accurately. The authors recently developed a simple and highly efficient yet still particulate model with the aim to bridge the gap between currently applied methods. The present work focuses on its applicability to confined flows in vessels of diameters up to 100 micrometres. For hematocrit values below 30 percent, a dependence of the apparent viscosity on the vessel diameter in agreement with experimental literature data is found.

  6. Peristaltic Pumping of Blood Through Small Vessels of Varying Cross-section

    E-Print Network [OSTI]

    J. C. Misra; S. Maiti

    2012-01-30T23:59:59.000Z

    The paper is devoted to a study of the peristaltic motion of blood in the micro-circulatory system. The vessel is considered to be of varying cross-section. The progressive peristaltic waves are taken to be of sinusoidal nature. Blood is considered to be a Herschel-Bulkley fluid. Of particular concern here is to investigate the effects of amplitude ratio, mean pressure gradient, yield stress and the power law index on the velocity distribution, streamline pattern and wall shear stress. On the basis of the derived analytical expression, extensive numerical calculations have been made. The study reveals that velocity of blood and wall shear stress are appreciably affected due to the non-uniform geometry of blood vessels. They are also highly sensitive to the magnitude of the amplitude ratio and the value of the fluid index.

  7. Evaluation of low-residue soldering for military and commercial applications: A report from the Low-Residue Soldering Task Force

    SciTech Connect (OSTI)

    Iman, R.L.; Anderson, D.J. [Sandia National Labs., Albuquerque, NM (United States); Burress, R.V. [SEHO (United States)] [and others

    1995-06-01T23:59:59.000Z

    The LRSTF combined the efforts of industry, military, and government to evaluate low-residue soldering processes for military and commercial applications. These processes were selected for evaluation because they provide a means for the military to support the presidential mandate while producing reliable hardware at a lower cost. This report presents the complete details and results of a testing program conducted by the LRSTF to evaluate low-residue soldering for printed wiring assemblies. A previous informal document provided details of the test plan used in this evaluation. Many of the details of that test plan are contained in this report. The test data are too massive to include in this report, however, these data are available on disk as Excel spreadsheets upon request. The main purpose of low-residue soldering is to eliminate waste streams during the manufacturing process.

  8. Pressure vessel sliding support unit and system using the sliding support unit

    DOE Patents [OSTI]

    Breach, Michael R.; Keck, David J.; Deaver, Gerald A.

    2013-01-15T23:59:59.000Z

    Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.

  9. Analysis of the ANL Test Method for 6CVS Containment Vessels

    SciTech Connect (OSTI)

    Trapp, D.; Crow, G.

    2011-06-06T23:59:59.000Z

    In the fall of 2010, Argonne National Laboratory (ANL) contracted with vendors to design and build 6CVS containment vessels as part of their effort to ship Fuel Derived Mixed Fission Product material. The 6CVS design is based on the Savannah River National Laboratory's (SRNL) design for 9975 and 9977 six inch diameter containment vessels. The main difference between the designs is that the 6CVS credits the inner O-ring seal as the containment boundary while the SRNL design credits the outer O-ring seal. Since the leak test must be done with the inner O-ring in place, the containment vessel does not have a pathway for getting the helium into the vessel during the leak test. The leak testing contractor was not able to get acceptable leak rates with the specified O-ring, but they were able to pass the leak test with a slightly larger O-ring. ANL asked the SRNL to duplicate the leak test vendor's method to determine the cause of the high leak rates. The SRNL testing showed that the helium leak indications were caused by residual helium left within the 6CVS Closure Assembly by the leak test technique, and by helium permeation through the Viton O-ring seals. After SRNL completed their tests, the leak testing contractor was able to measure acceptable leak rates by using the slightly larger O-ring size, by purging helium from the lid threads, and by being very quick in getting the bell jar under a full vacuum. This paper describes the leak test vendor's test technique, and other techniques that could be have been used to successfully leak test the 6CVS's.

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

    SciTech Connect (OSTI)

    Jetter, Robert I [Consultant; Sham, Sam [ORNL; Swindeman, Robert W [Consultant

    2011-01-01T23:59:59.000Z

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

  11. Decommissioning experience: One-piece removal and transport of a LWR pressure vessel and internals

    SciTech Connect (OSTI)

    Closs, J.W. [Northern States Power Co., Minneapolis, MN (United States)

    1993-12-31T23:59:59.000Z

    After a brief historical perspective, this document describes several key events which took place during the decommissioning of a commercial nuclear power plant. The scope of decommissioning work included: (a) the reactor building, the reactor vessel and the contents of the reactor building; (b) the fuel handling building and its contents; (c) the fuel transfer vault between the reactor building and the fuel handling building.

  12. Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01T23:59:59.000Z

    1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for: 1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities. 1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures. 1.2 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/cm2 or 3.0 × 10?4 dpa. (See Terminology E 170.) 1.3 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and h...

  13. Fabrication Flaw Density and Distribution In Repairs to Reactor Pressure Vessel and Piping Welds

    SciTech Connect (OSTI)

    GJ Schuster, FA Simonen, SR Doctor

    2008-04-01T23:59:59.000Z

    The Pacific Northwest National Laboratory is developing a generalized fabrication flaw distribution for the population of nuclear reactor pressure vessels and for piping welds in U.S. operating reactors. The purpose of the generalized flaw distribution is to predict component-specific flaw densities. The estimates of fabrication flaws are intended for use in fracture mechanics structural integrity assessments. Structural integrity assessments, such as estimating the frequency of loss-of-coolant accidents, are performed by computer codes that require, as input, accurate estimates of flaw densities. Welds from four different reactor pressure vessels and a collection of archived pipes have been studied to develop empirical estimates of fabrication flaw densities. This report describes the fabrication flaw distribution and characterization in the repair weld metal of vessels and piping. This work indicates that large flaws occur in these repairs. These results show that repair flaws are complex in composition and sometimes include cracks on the ends of the repair cavities. Parametric analysis using an exponential fit is performed on the data. The relevance of construction records is established for describing fabrication processes and product forms. An analysis of these records shows there was a significant change in repair frequency over the years when these components were fabricated. A description of repair flaw morphology is provided with a discussion of fracture mechanics significance. Fabrication flaws in repairs are characterized using optimized-access, high-sensitivity nondestructive ultrasonic testing. Flaw characterizations are then validated by other nondestructive evaluation techniques and complemented by destructive testing.

  14. Predictive Reactor Pressure Vessel Steel Irradiation Embrittlement Models: Issues and Opportunities

    SciTech Connect (OSTI)

    Odette, George Robert [UCSB; Nanstad, Randy K [ORNL

    2009-01-01T23:59:59.000Z

    Nuclear plant life extension to 80 years will require accurate predictions of neutron irradiation-induced increases in the ductile-brittle transition temperature ( T) of reactor pressure vessel (RPV) steels at high fluence conditions that are far outside the existing database. Remarkable progress in mechanistic understanding of irradiation embrittlement has led to physically motivated T correlation models that provide excellent statistical fi ts to the existing surveillance database. However, an important challenge is developing advanced embrittlement models for low fl ux-high fl uence conditions pertinent to extended life. These new models must also provide better treatment of key variables and variable combinations and account for possible delayed formation of late blooming phases in low copper steels. Other issues include uncertainties in the compositions of actual vessel steels, methods to predict T attenuation away from the reactor core, verifi cation of the master curve method to directly measure the fracture toughness with small specimens and predicting T for vessel annealing remediation and re-irradiation cycles.

  15. A Multiscale Modeling Approach to Analyze Filament-Wound Composite Pressure Vessels

    SciTech Connect (OSTI)

    Nguyen, Ba Nghiep; Simmons, Kevin L.

    2013-07-22T23:59:59.000Z

    A multiscale modeling approach to analyze filament-wound composite pressure vessels is developed in this article. The approach, which extends the Nguyen et al. model [J. Comp. Mater. 43 (2009) 217] developed for discontinuous fiber composites to continuous fiber ones, spans three modeling scales. The microscale considers the unidirectional elastic fibers embedded in an elastic-plastic matrix obeying the Ramberg-Osgood relation and J2 deformation theory of plasticity. The mesoscale behavior representing the composite lamina is obtained through an incremental Mori-Tanaka type model and the Eshelby equivalent inclusion method [Proc. Roy. Soc. Lond. A241 (1957) 376]. The implementation of the micro-meso constitutive relations in the ABAQUS® finite element package (via user subroutines) allows the analysis of a filament-wound composite pressure vessel (macroscale) to be performed. Failure of the composite lamina is predicted by a criterion that accounts for the strengths of the fibers and of the matrix as well as of their interface. The developed approach is demonstrated in the analysis of a filament-wound pressure vessel to study the effect of the lamina thickness on the burst pressure. The predictions are favorably compared to the numerical and experimental results by Lifshitz and Dayan [Comp. Struct. 32 (1995) 313].

  16. The Louisiana State Museum Vessel: a historical and archaeological analysis of an American Civil War-era submersible boat

    E-Print Network [OSTI]

    Wills, Richard Keith

    2000-01-01T23:59:59.000Z

    During the spring of 1992, and again in the winter of 1993, seven graduate students from Texas A&M University's Nautical Archaeology Program participated in a project to document the Louisiana State Museum Vessel, an American Civil War...

  17. Avicennia germinans (black mangrove) vessel architecture is linked to chilling and salinity tolerance in the Gulf of Mexico

    E-Print Network [OSTI]

    Madrid, Eric N.; Armitage, Anna R.; Lopez-Portillo, Jorge

    2014-09-26T23:59:59.000Z

    Over the last several decades, the distribution of the black mangrove Avicennia germinans in the Gulf of Mexico has expanded, in part because it can survive the occasional freeze events and high soil salinities characteristic of the area. Vessel...

  18. Biomechanics of North Atlantic right whale bone : mandibular fracture as a fatal endpoint for blunt vessel-whale collision modeling

    E-Print Network [OSTI]

    Campbell-Malone, Regina P

    2007-01-01T23:59:59.000Z

    The North Atlantic right whale, Eubalaena glacialis, one of the most critically endangered whales in the world, is subject to high anthropogenic mortality. Vessel-whale collisions and entanglement in fishing gear were ...

  19. The Louisiana State Museum Vessel: a historical and archaeological analysis of an American Civil War-era submersible boat 

    E-Print Network [OSTI]

    Wills, Richard Keith

    2000-01-01T23:59:59.000Z

    During the spring of 1992, and again in the winter of 1993, seven graduate students from Texas A&M University's Nautical Archaeology Program participated in a project to document the Louisiana State Museum Vessel, an ...

  20. Seismic analysis of the Mirror Fusion Test Facility: soil structure interaction analyses of the Axicell vacuum vessel. Revision 1

    SciTech Connect (OSTI)

    Maslenikov, O.R.; Mraz, M.J.; Johnson, J.J.

    1986-03-01T23:59:59.000Z

    This report documents the seismic analyses performed by SMA for the MFTF-B Axicell vacuum vessel. In the course of this study we performed response spectrum analyses, CLASSI fixed-base analyses, and SSI analyses that included interaction effects between the vessel and vault. The response spectrum analysis served to benchmark certain modeling differences between the LLNL and SMA versions of the vessel model. The fixed-base analysis benchmarked the differences between analysis techniques. The SSI analyses provided our best estimate of vessel response to the postulated seismic excitation for the MFTF-B facility, and included consideration of uncertainties in soil properties by calculating response for a range of soil shear moduli. Our results are presented in this report as tables of comparisons of specific member forces from our analyses and the analyses performed by LLNL. Also presented are tables of maximum accelerations and relative displacements and plots of response spectra at various selected locations.

  1. Investigation of the use of nanofluids to enhance the In-Vessel Retention capabilities of Advanced Light Water Reactors

    E-Print Network [OSTI]

    Hannink, Ryan Christopher

    2007-01-01T23:59:59.000Z

    Nanofluids at very low concentrations experimentally exhibit a substantial increase in Critical Heat Flux (CHF) compared to water. The use of a nanofluid in the In-Vessel Retention (IVR) severe accident management strategy, ...

  2. Analysis of Mass Flow and Enhanced Mass Flow Methods of Flashing Refrigerant-22 from a Small Vessel

    E-Print Network [OSTI]

    Nutter, Darin Wayne

    The mass flow characteristics of flashing Refrigerant-22 from a small vessel were investigated. A flash boiling apparatus was designed and built. It was modeled after the flashing process encountered by the accumulator of air-source heat pump...

  3. Virtual Rogowskii loops for the evaluation of plasma and in-vessel eddy currents in the KSTAR tokamak

    SciTech Connect (OSTI)

    Tsaun, S.; Jhang, Hogun [RRC, Kurchatov Institute, Kurchartov Square 1, Moscow 123181 (Russian Federation); Korea Basic Science Institute, 52 Yeoeun-dong, Yusung-Gu, Daejon 305-333 (Korea, Republic of)

    2006-01-15T23:59:59.000Z

    A simple but effective method is proposed for the estimation of plasma and in-vessel eddy currents in the KSTAR device. It is based on the prescribed contour integrals of the tangential magnetic fields measured by magnetic probes. It is shown that the method can estimate the plasma current in 0.33% accuracy. It is also found that the total in-vessel eddy current can be determined with accuracy within a few kiloamperes regardless of plasma conditions.

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

    SciTech Connect (OSTI)

    Rana, M.D. (Praxair Inc., Tonawanda, NY (United States). Research and Development Dept.)

    1994-08-01T23:59:59.000Z

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

  5. Evidence for neutron irradiation-induced metallic precipitates in model alloys and pressure-vessel weld steel

    E-Print Network [OSTI]

    Motta, Arthur T.

    -vessel weld steel Stephen E. Cumblidge a , Arthur T. Motta a,*, Gary L. Catchen a , Gerhard Brauer b , Juurgen-irradiated model alloys (1 · 1023 n/m2 , E > 0:5 MeV) and 73W-weld steel (to 1.8 · 1023 n/m2 , E > 1 Me the pressure-vessel weld steel) showed evidence for both irradiation-induced metallic precipitation

  6. Military and diplomatic roles and options for managing and responding to the proliferation of ballistic missiles and weapons of mass destruction. Final report: Program on Stability and the Offense/Defense Relationship

    SciTech Connect (OSTI)

    Hallenbeck, R.A.; Gill, J.M.; Murray, B.L.

    1993-05-26T23:59:59.000Z

    The March seminar, ``Military and Diplomatic Roles and Options`` for managing and responding to proliferation, featured three presentations: the military and diplomatic implications of preemptive force as a counterproliferation option; an in-depth assessment of the threat posed by biological weapons; and, a new proposed US counterproliferation policy.

  7. Navy Mobility Fuels Forecasting System Phase 6 report: Impacts of a military disruption on Navy fuel availability and quality

    SciTech Connect (OSTI)

    Hadder, G.R.; Davis, R.M.

    1990-09-01T23:59:59.000Z

    The Refinery Yield Model of the Navy Mobility Fuels Forecasting System has been used to study the impacts of a severe military disruption on the production of Navy JP-5 jet fuel and F-76 marine diesel fuel in the year 1995. The global petroleum supply reduction due to the disruption was about 40 percent of the business-as-usual supply. Regional production cost increases for JP-5 were between $3 and $11 per gallon during the disruption. For F-76, the production cost increases were between $3 and $5 per gallon. The disruption caused substantial degradations for certain fuel quality properties of F-76 produced in the Pacific basin and in southern Europe. During both business-as-usual and disruption, the most prevalent Navy fuel quality problem was F-76 instability due to high levels of light cycle oils. 37 refs., 1 fig., 21 tabs.

  8. Physical and computer modeling of military earth grounding practices in a HEMP (high-altitude electromagnetic pulse) environment. Technical memo

    SciTech Connect (OSTI)

    Cuneo, A.A. Jr.; Loftus, J.J.; Perala, R.A.

    1983-06-01T23:59:59.000Z

    Military grounding practices compatible with hardening electronic systems to high-altitude electromagnetic pulse (HEMP) illumination are considered. This study concerns the grounding practices outlined in MIL-STD-188-124, Common Long-Haul/Tactical Communications Systems. Three standard grounding schemes and one new scheme were chosen for study at a 10:1 scale, illuminated by a 59-V/m peak simulated HEMP. There were several significant results: (a) The theoretical technique in general agrees to within a factor of three with the experimental results, (b) The type end of earth ground system does not appear to be important, and (c) Intrasite transients tend to be dominated by electromagnetic coupling to completed conductive loops. When the loop is broken, the transient is characterized by the half-wavelength resonance of the conductor. Grounding paths which do not form part of the loop do not contribute significantly to the transient in the loop.

  9. Degraded Modes and the `Culture of Coping' in Military Operations: An Analysis of a Fatal Incident On-Board HMS Tireless on 20/21 March 2007

    E-Print Network [OSTI]

    Johnson, Chris

    was following Standard operating Procedures (SOPs) using Self Contained Oxygen Generators (SCOGs) to maintain and operators must work together to ensure that maintenance intervals are scheduled so that critical componentsDegraded Modes and the `Culture of Coping' in Military Operations: An Analysis of a Fatal Incident

  10. Manufacturing Cost Analysis of Novel Steel/Concrete Composite Vessel for Stationary Storage of High-Pressure Hydrogen

    SciTech Connect (OSTI)

    Feng, Zhili [ORNL; Zhang, Wei [ORNL; Wang, Jy-An John [ORNL; Ren, Fei [ORNL

    2012-09-01T23:59:59.000Z

    A novel, low-cost, high-pressure, steel/concrete composite vessel (SCCV) technology for stationary storage of compressed gaseous hydrogen (CGH2) is currently under development at Oak Ridge National Laboratory (ORNL) sponsored by DOE s Fuel Cell Technologies (FCT) Program. The SCCV technology uses commodity materials including structural steels and concretes for achieving cost, durability and safety requirements. In particular, the hydrogen embrittlement of high-strength low-alloy steels, a major safety and durability issue for current industry-standard pressure vessel technology, is mitigated through the use of a unique layered steel shell structure. This report presents the cost analysis results of the novel SCCV technology. A high-fidelity cost analysis tool is developed, based on a detailed, bottom-up approach which takes into account the material and labor costs involved in each of the vessel manufacturing steps. A thorough cost study is performed to understand the SCCV cost as a function of the key vessel design parameters, including hydrogen pressure, vessel dimensions, and load-carrying ratio. The major conclusions include: The SCCV technology can meet the technical/cost targets set forth by DOE s FCT Program for FY2015 and FY2020 for all three pressure levels (i.e., 160, 430 and 860 bar) relevant to the hydrogen production and delivery infrastructure. Further vessel cost reduction can benefit from the development of advanced vessel fabrication technologies such as the highly automated friction stir welding (FSW). The ORNL-patented multi-layer, multi-pass FSW can not only reduce the amount of labor needed for assembling and welding the layered steel vessel, but also make it possible to use even higher strength steels for further cost reductions and improvement of vessel structural integrity. It is noted the cost analysis results demonstrate the significant cost advantage attainable by the SCCV technology for different pressure levels when compared to the industry-standard pressure vessel technology. The real-world performance data of SCCV under actual operating conditions is imperative for this new technology to be adopted by the hydrogen industry for stationary storage of CGH2. Therefore, the key technology development effort in FY13 and subsequent years will be focused on the fabrication and testing of SCCV mock-ups. The static loading and fatigue data will be generated in rigorous testing of these mock-ups. Successful tests are crucial to enabling the near-term impact of the developed storage technology on the CGH2 storage market, a critical component of the hydrogen production and delivery infrastructure. In particular, the SCCV has high potential for widespread deployment in hydrogen fueling stations.

  11. CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR

    SciTech Connect (OSTI)

    Vinson, Dennis

    2010-06-01T23:59:59.000Z

    The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HWCTR was operated for only a short duration, from March 1962 to December 1964 in order to test the viability of test fuel elements and other reactor components for use in a heavy water power reactor. The reactor achieved 13,882 MWd of total power while testing 36 different fuel assemblies. In the course of operation, HWCTR experienced the cladding failures of 10 separate test fuel assemblies. In each case, the cladding was breached with some release of fuel core material into the isolated test loop, causing fission product and actinide contamination in the main coolant loop and the liquid and boiling test loops. Despite the contribution of the contamination from the failed fuel, the primary source of radioactivity in the HWCTR vessel and internals is the activation products in the thermal shields, and to a lesser degree, activation products in the reactor vessel walls and liner. A detailed facility characterization report of the HWCTR facility was completed in 1996. Many of the inputs and assumptions in the 1996 characterization report were derived from the HWCTR decommissioning plan published in 1975. The current paper provides an updated assessment of the radioisotopic characteristics of the HWCTR vessel and internals to support decommissioning activities on the facility.

  12. Qualitative Reliability Issues for In-Vessel Solid and Liquid Wall Fusion Designs

    SciTech Connect (OSTI)

    Cadwallader, Lee Charles; Nygren, R. E.

    2001-10-01T23:59:59.000Z

    This paper presents the results of a study of the qualitative aspects of plasma facing component (PFC) reliability for actively cooled solid wall and liquid wall concepts for magnetic fusion reactor vessels. These two designs have been analyzed for component failure modes. The most important results of that study are given here. A brief discussion of reliability growth in design is included to illustrate how solid wall designs have begun as workable designs and have evolved over time to become more optimized designs with better longevity. The increase in tolerable heat fluxes shows the improvement. Liquid walls could also have reliability growth if the designs had similar development efforts.

  13. Vessel Eddy Current Measurement for the National Spherical Torus Experiment (NSTX)

    SciTech Connect (OSTI)

    D.A. Gates; J. Menard; R. Marsala

    2004-11-19T23:59:59.000Z

    A simple analog circuit that measures the NSTX axisymmetric eddy current distribution has been designed and constructed. It is based on simple circuit model of the NSTX vacuum vessel that was calibrated using a special axisymmetric eddy current code which was written so that accuracy was maintained in the vicinity of the current filaments. The measurement and the model have been benchmarked against data from numerous vacuum shots and they are in excellent agreement. This is an important measurement that helps give more accurate equilibrium reconstructions.

  14. Dye laser amplifier including a dye cell contained within a support vessel

    DOE Patents [OSTI]

    Davin, J.

    1992-12-01T23:59:59.000Z

    A large (high flow rate) dye laser amplifier in which a continuous replenished supply of dye is excited by a first light beam, specifically a copper vapor laser beam, in order to amplify the intensity of a second different light beam, specifically a dye beam, passing through the dye is disclosed herein. This amplifier includes a dye cell defining a dye chamber through which a continuous stream of dye is caused to pass at a flow rate of greater than 30 gallons/minute at a static pressure greater than 150 pounds/square inch and a specifically designed support vessel for containing the dye cell. 6 figs.

  15. Spreading of molten corium in Mk I geometry following vessel meltthrough

    SciTech Connect (OSTI)

    Sienicki, J.J.; Farmer, M.T.; Spencer, B.W.

    1988-01-01T23:59:59.000Z

    A one-dimensional, multicell, Eulerian computer code is under development to predict the gravity-driven spreading dynamics and thermal interactions of a molten corium layer flowing horizontally over a concrete substrate. The code is compared to recent experiments in which molten mixtures of iron and aluminum oxide flowed over concrete in the presence and absence of water. Results are presented from scoping calculations for the Mk I BWR system investigating the spreading-induced penetration immediately following the drainage of a predominantly oxide molten corium mixture from a localized breach in the reactor vessel. 12 refs., 7 figs.

  16. LNG Imports by Vessel into the U.S. Form | Department of Energy

    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 ofLetter Report:40PM toLED Lighting5-15Trade |Vessel into the U.S.

  17. The criteria of fracture in the case of the leak of pressure vessels

    SciTech Connect (OSTI)

    Habil; Ziliukas, A.

    1997-04-01T23:59:59.000Z

    In order to forecast the break of the high pressure vessels and the network of pipes in a nuclear reactor, according to the concept of leak before break of pressure vessels, it is necessary to analyze the conditions of project, production, and mounting quality as well as of exploitation. It is also necessary to evaluate the process of break by the help of the fracture criteria. In the Ignalina Nuclear Power Plant of, in Lithuania, the most important objects of investigation are: the highest pressure pipes, made of Japanese steel 19MN5 and having an anticorrosive austenitic: coal inside, the pipes of distribution, which arc made of 08X1810T steel. The steel of the network of pipes has a quality of plasticity: therefore the only criteria of fragile is impossible to apply to. The process of break would be best described by the universal criteria of elastic - plastic fracture. For this purpose the author offers the criterion of the double parameter.

  18. In-vessel coolability and retention of a core melt. Volume 2

    SciTech Connect (OSTI)

    Theofanous, T.G.; Liu, C.; Additon, S.; Angelini, S.; Kymaelaeinen, O.; Salmassi, T. [California Univ., Santa Barbara, CA (United States). Center for Risk Studies and Safety

    1996-10-01T23:59:59.000Z

    The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is physically unreasonable. Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The AP600 is particularly favorable to in-vessel retention. Some ideas to enhance the assessment basis as well as performance in this respect, for applications to larger and/or higher power density reactors are also provided.

  19. Calculation of Eddy Currents In the CTH Vacuum Vessel and Coil Frame

    SciTech Connect (OSTI)

    A. Zolfaghari, A. Brooks, A. Michaels, J. Hanson, and G. Hartwell

    2012-09-25T23:59:59.000Z

    Knowledge of eddy currents in the vacuum vessel walls and nearby conducting support structures can significantly contribute to the accuracy of Magnetohydrodynamics (MHD) equilibrium reconstruction in toroidal plasmas. Moreover, the magnetic fields produced by the eddy currents could generate error fields that may give rise to islands at rational surfaces or cause field lines to become chaotic. In the Compact Toroidal Hybrid (CTH) device (R0 = 0.75 m, a = 0.29 m, B ? 0.7 T), the primary driver of the eddy currents during the plasma discharge is the changing flux of the ohmic heating transformer. Electromagnetic simulations are used to calculate eddy current paths and profile in the vacuum vessel and in the coil frame pieces with known time dependent currents in the ohmic heating coils. MAXWELL and SPARK codes were used for the Electromagnetic modeling and simulation. MAXWELL code was used for detailed 3D finite-element analysis of the eddy currents in the structures. SPARK code was used to calculate the eddy currents in the structures as modeled with shell/surface elements, with each element representing a current loop. In both cases current filaments representing the eddy currents were prepared for input into VMEC code for MHD equilibrium reconstruction of the plasma discharge. __________________________________________________

  20. Standard practice for examination of seamless, Gas-Filled, pressure vessels using acoustic emission

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

    1.1 This practice provides guidelines for acoustic emission (AE) examinations of seamless pressure vessels (tubes) of the type used for distribution or storage of industrial gases. 1.2 This practice requires pressurization to a level greater than normal use. Pressurization medium may be gas or liquid. 1.3 This practice does not apply to vessels in cryogenic service. 1.4 The AE measurements are used to detect and locate emission sources. Other nondestructive test (NDT) methods must be used to evaluate the significance of AE sources. Procedures for other NDT techniques are beyond the scope of this practice. See Note 1. Note 1—Shear wave, angle beam ultrasonic examination is commonly used to establish circumferential position and dimensions of flaws that produce AE. Time of Flight Diffraction (TOFD), ultrasonic examination is also commonly used for flaw sizing. 1.5 The values stated in inch-pound units are to be regarded as the standard. The values given in parentheses are for information only. 1.6 Thi...

  1. Generic BWR-4 degraded core in-vessel study. Status report

    SciTech Connect (OSTI)

    Not Available

    1984-11-01T23:59:59.000Z

    Original intent of this project was to produce a phenomenological study of the in-vessel degradation which occurs during the TQUX and TQUV sequences for a generic BWR-4 from the initiation of the FSAR Chapter 15 operational transient through core debris bed formation to the failure of the primary pressure boundary. Bounding calculations were to be performed for the two high pressure and low pressure non-LOCA scenarios to assess the uncertainties in the current state of knowledge regarding the source terms for containment integrity studies. Source terms as such were defined in terms of hydrogen generation, unreacted metal, and coolant inventroy, and in terms of the form, sequencing and mode of dispersal through the primary vessel boundary. Fission product release was not to be considered as part of this study. Premature termination of the project, however, led to the dicontinuation of work on an as is basis. Work on the in-core phase from the point of scram to core debris bed formation was largely completed. A preliminary scoping calculation on the debris bed phase had been initiated. This report documents the status of the study at termination.

  2. Spreading of molten corium in MK I geometry following vessel melt-through

    SciTech Connect (OSTI)

    Sienicki, J.J.; Farmer, M.T.; Spencer, B.W.

    1988-01-01T23:59:59.000Z

    For Mk I boiling water reactor severe-accident sequences in which molten corium is postulated to melt through the reactor pressure vessel (RPV) lower head, an important question concerns the relocation of the corium material that drains from the vessel. After filling the sump pits located in the pedestal concrete floor beneath the RPV, the molten corium that collects on the pedestal floor is generally free to flow through the doorway, which provides personnel access to the pedestal, and to spread out over the concrete floor in the annular region between the pedestal wall and the steel liner of the containment shell. A significant issue is whether the corium, after exiting the doorway, can spread under gravity all the way to the liner where thermal attack on the liner steel might be postulated to occur. A computer code (MELTSPREAD) has been developed to investigate the spreading dynamics and thermal interactions of a molten corium layer flowing horizontally over an ablating concrete substrate that may be initially covered with water. The principal objective is to predict, for specific conditions of corium composition, mass, and temperature, the lateral penetration of the corium that drains from a localized hole in the lower head immediately following RPV failure.

  3. Results of scoping tests in corium-water thermal interactions in ex-vessel geometry

    SciTech Connect (OSTI)

    Spencer, B.W.; McUmber, L.; Sehgal, B.R.; Sienicki, J.J.; Squarer, D.

    1983-01-01T23:59:59.000Z

    Results of scoping tests are reported which were performed in the ANL/EPRI Corium Ex-vessel interactions (COREXIT) Facility located at ANL. These tests are examining issues related to containment loading (i.e., steam generation, H/sub 2/ production, and debris dispersal) for hypothetical LWR accidents that are postulated to progress to the point of molten corium breaching the vessel bottom head and entering the reactor cavity. The geometry selected for these tests is a 1 : 30 linear scale of the Zion PWR containment design in which the cavity is connected to the containment volume by an open tunnel through which pass the in-core detector guide tubes. The effects of the corium-water mixing modes were investigated in the first two tests in the series. In test CWTI-1 the molten corium was ejected into water which filled the cavity mockup volume to one-half the passageway height. In CWTI-2, the molten corium was dropped atop the refractory base in the cavity mockup without the presence of water, and water was injected atop the corium melt immediately afterward as per accumulator discharge. These tests have shown significant differences in fuel fragmentation, steam generation rate, hydrogen production, and fuel dispersal. Particularly noteworthy was the significant amount of dispersal of both water and corium debris from the cavity mockup due to the initially rapid steam generation rate in CWTI-1.

  4. Results and analysis of reactor-material experiments on ex-vessel corium quench and dispersal

    SciTech Connect (OSTI)

    Spencer, B.W.; McUmber, L.M.; Sienicki, J.J.; Squarer, D.

    1984-01-01T23:59:59.000Z

    Results of reactor-material experiments and related analysis are described in which molten corium is injected into a mock-up of the reactor cavity region of a PWR. The experiments address ex-vessel interactions such as steam generation (for those cases in which water is present), water and corium dispersal from the cavity, hydrogen generation, direct atmosphere heating by dispersed corium, and debris characterization. Test results indicate efficiencies of steam generation by corium quench ranging up to 65%. Corium sweepout of up to 62% of the injected material was found for those conditions in which steam generation flowrate was augmented by vessel blowdown. The dispersed corium caused very little direct heating of the atmosphere for the configuration employing a trap at the exit of the cavity-to-containment pathway. Corium sweepout phenomena were modeled for high-pressure blowdown conditions, and the results applied to the full-size reactor system predict essentially complete sweepout of corium from the reactor cavity.

  5. Radiation damage characterization in reactor pressure vessel steels with nonlinear ultrasound

    SciTech Connect (OSTI)

    Matlack, K. H. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States); Kim, J.-Y. [School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States); Wall, J. J. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 and Nuclear Sector, The Electric Power Research Institute, Charlotte, NC 28262 (United States); Qu, J. [Department of Civil and Environmental Engineering, Northwestern University, Evanston, IL 60208 (United States); Jacobs, L. J. [G.W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 and School of Civil and Environmental Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States)

    2014-02-18T23:59:59.000Z

    Nuclear generation currently accounts for roughly 20% of the US baseload power generation. Yet, many US nuclear plants are entering their first period of life extension and older plants are currently undergoing assessment of technical basis to operate beyond 60 years. This means that critical components, such as the reactor pressure vessel (RPV), will be exposed to higher levels of radiation than they were originally intended to withstand. Radiation damage in reactor pressure vessel steels causes microstructural changes such as vacancy clusters, precipitates, dislocations, and interstitial loops that leave the material in an embrittled state. The development of a nondestructive evaluation technique to characterize the effect of radiation exposure on the properties of the RPV would allow estimation of the remaining integrity of the RPV with time. Recent research has shown that nonlinear ultrasound is sensitive to radiation damage. The physical effect monitored by nonlinear ultrasonic techniques is the generation of higher harmonic frequencies in an initially monochromatic ultrasonic wave, arising from the interaction of the ultrasonic wave with microstructural features such as dislocations, precipitates, and their combinations. Current findings relating the measured acoustic nonlinearity parameter to increasing levels of neutron fluence for different representative RPV materials are presented.

  6. Comparison of attenuation coefficients for VVER-440 and VVER-1000 pressure vessels

    SciTech Connect (OSTI)

    Marek, M.; Rataj, J.; Vandlik, S. [Reactor Physics Dept., Research Centre Rez, Husinec 130, 25068 (Czech Republic)

    2011-07-01T23:59:59.000Z

    The paper summarizes the attenuation coefficient of the neutron fluence with E > 0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well as for operated nuclear power plant (NPP) units. The attenuation coefficient is possible to evaluate directly only by using the retro-dosimetry, based on a combination of the measured activities from the weld sample and concurrent ex-vessel measurement. The available neutron fluence attenuation coefficients (E > 0.5 MeV), calculated and measured at a mock-up experiment simulating the VVER-440-unit conditions, vary from 3.5 to 6.15. A similar situation is used for the calculations and mock-up experiment measurements for the VVER-1000 RPV, where the attenuation coefficient of the neutron fluence varies from 5.99 to 8.85. Because of the difference in calculations for the real units and the mock-up experiments, the necessity to design and perform calculation benchmarks both for VVER-440 and VVER-1000 would be meaningful if the calculation model is designed adequately to a given unit. (authors)

  7. Neutron flux estimations based on niobium impurities in reactor pressure vessel steel

    SciTech Connect (OSTI)

    Baers, L.B.; Hasanen, E.K. [Technical Research Centre of Finland, Espoo (Finland). Reactor Lab.

    1994-12-31T23:59:59.000Z

    The use of (ppm level) niobium impurities in reactor pressure vessel (RPV) steel for neutron flux estimations based on the reaction {sup 93}Nb (n,n{prime}) {sup 93m}Nb has been reported previously. The method has now been further investigated and refined. Small niobium fractions in RPV steel ({approx} ppm) and plating ({approx} 1%) materials have been separated by ion exchange chromatography in one to three steps. The measured Nb fractions in samples from some four pressure vessel (RPV) base materials were 1 to 3 ppm. The purification of tens of milligrams of RPV material provides sufficient amounts of niobium for mass determination with a highly sensitive (10{sup {minus}5} ppm) Inductively Coupled Plasma Mass Spectrometer (ICP-MS). The {sup 93m}Nb and small remaining {sup 54}Mn activities were measured with a Calibrated Liquid Scintillation Counter (LSC) based on dual label technique and almost 100% efficiency to {sup 93m}Nb. One purification is needed for plating materials ({approx}1% Nb) and two purifications of about one gram of steel with Nb impurities in order to resolve the needed activities ({approx}10 Bq {sup 93m}Nb/{mu}g Nb). The achieved accuracy of the measured specific {sup 93m}Nb activities was about {+-} 3% (1{sigma}) in irradiated RPV plating materials and about {+-} 4% for Nb ppm impurities.

  8. In-vessel coolability and retention of a core melt. Volume 1

    SciTech Connect (OSTI)

    Theofanous, T.G.; Liu, C.; Additon, S.; Angelini, S.; Kymaelaeinen, O.; Salmassi, T. [California Univ., Santa Barbara, CA (United States). Center for Risk Studies and Safety

    1996-10-01T23:59:59.000Z

    The efficacy of external flooding of a reactor vessel as a severe accident management strategy is assessed for an AP600-like reactor design. The overall approach is based on the Risk Oriented Accident Analysis Methodology (ROAAM), and the assessment includes consideration of bounding scenarios and sensitivity studies, as well as arbitrary parametric evaluations that allow the delineation of the failure boundaries. Quantification of the input parameters is carried out for an AP600-like design, and the results of the assessment demonstrate that lower head failure is physically unreasonable. Use of this conclusion for any specific application is subject to verifying the required reliability of the depressurization and cavity-flooding systems, and to showing the appropriateness (in relation to the database presented here, or by further testing as necessary) of the thermal insulation design and of the external surface properties of the lower head, including any applicable coatings. The AP600 is particularly favorable to in-vessel retention. Some ideas to enhance the assessment basis as well as performance in this respect, for applications to larger and/or higher power density reactors are also provided.

  9. Thermal Analysis to Calculate the Vessel Temperature and Stress in Alcator C-Mod Due to the Divertor Upgrade

    SciTech Connect (OSTI)

    Han Zhang, Peter H. Titus, Robert Ellis, Soren Harrison and Rui Vieira

    2012-08-29T23:59:59.000Z

    Alcator C-Mod is planning an upgrade to its outer divertor. The upgrade is intended to correct the existing outer divertor alignment with the plasma, and to operate at elevated temperatures. Higher temperature operation will allow study of edge physics behavior at reactor relevant temperatures. The outer divertor and tiles will be capable of operating at 600oC. Longer pulse length, together with the plasma and RF heat of 9MW, and the inclusion of heater elements within the outer divertor produces radiative energy which makes the sustained operation much more difficult than before. An ANSYS model based on ref. 1 was built for the global thermal analysis of C-Mod. It models the radiative surfaces inside the vessel and between the components, and also includes plasma energy deposition. Different geometries have been simulated and compared. Results show that steady state operation with the divertor at 600oC is possible with no damage to major vessel internal components. The differential temperature between inner divertor structure, or "girdle" and inner vessel wall is ~70oC. This differential temperature is limited by the capacity of the studs that hold the inner divertor backing plates to the vessel wall. At a 70oC temperature differential the stress on the studs is within allowable limits. The thermal model was then used for a stress pass to quantify vessel shell stresses where thermal gradients are significant.

  10. An Approach to Understanding Cohesive Slurry Settling, Mobilization, and Hydrogen Gas Retention in Pulsed Jet Mixed Vessels

    SciTech Connect (OSTI)

    Gauglitz, Phillip A.; Wells, Beric E.; Fort, James A.; Meyer, Perry A.

    2009-05-22T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) is being designed and built to pretreat and vitrify a large portion of the waste in Hanford’s 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. Some of these vessels have mixing-system requirements to maintain conditions where the accumulation of hydrogen gas stays below acceptable limits, and the mixing within the vessels is sufficient to release hydrogen gas under normal conditions and during off-normal events. Some of the WTP process streams are slurries of solid particles suspended in Newtonian fluids that behave as non-Newtonian slurries, such as Bingham yield-stress fluids. When these slurries are contained in the process vessels, the particles can settle and become progressively more concentrated toward the bottom of the vessels, depending on the effectiveness of the mixing system. One limiting behavior is a settled layer beneath a particle-free liquid layer. The settled layer, or any region with sufficiently high solids concentration, will exhibit non-Newtonian rheology where it is possible for the settled slurry to behave as a soft solid with a yield stress. In this report, these slurries are described as settling cohesive slurries.

  11. 1 Managed by UT-Battelle for the U.S. Department of Energy NF/IDS Hg Vessel Layout 30 Jun 09

    E-Print Network [OSTI]

    McDonald, Kirk

    1 Managed by UT-Battelle for the U.S. Department of Energy NF/IDS Hg Vessel Layout 30 Jun 09 Cryostat 2 Front Drain Mercury Vessel Concept Matthew F. Glisson Van Graves #12;2 Managed by UT-Battelle;3 Managed by UT-Battelle for the U.S. Department of Energy NF/IDS Hg Vessel Layout 30 Jun 09 Cross Section

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

    SciTech Connect (OSTI)

    Raske, D.T.

    1995-06-01T23:59:59.000Z

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

  13. Role of ex-vessel interactions in determining the severe reactor-accident source term for fission products. [PWR; BWR

    SciTech Connect (OSTI)

    Powers, D.A.; Brockmann, J.E.; Bradley, D.R.; Tarbell, W.W.

    1983-01-01T23:59:59.000Z

    The role fission-product release and aerosol generation outside the primary system can have in determining the severe reactor-accident source term is reviewed. Recent analytical and experimental studies of major causes of ex-vessel fission product release and aerosol generation are described. The ejection of molten-core debris from a pressurized-reactor vessel is shown to be a potentially large source of aerosols that has not been recognized in past severe-accident evaluations. A mechanistic model of fission-product release during core-debris interactions with concrete is discussed. Calculations with this model are compared to correlations of experimental data and previous estimates of ex-vessel fission-product release. Predictions with the mechanistic model agree quite well with the data correlations but do not agree at all well with estimates made in the past.

  14. ADDITIONAL STRESS AND FRACTURE MECHANICS ANALYSES OF PRESSURIZED WATER REACTOR PRESSURE VESSEL NOZZLES

    SciTech Connect (OSTI)

    Walter, Matthew [Structural Integrity Associates, Inc.; Yin, Shengjun [ORNL; Stevens, Gary [U.S. Nuclear Regulatory Commission; Sommerville, Daniel [Structural Integrity Associates, Inc.; Palm, Nathan [Westinghouse Electric Company, Cranberry Township, PA; Heinecke, Carol [Westinghouse Electric Company, Cranberry Township, PA

    2012-01-01T23:59:59.000Z

    In past years, the authors have undertaken various studies of nozzles in both boiling water reactors (BWRs) and pressurized water reactors (PWRs) located in the reactor pressure vessel (RPV) adjacent to the core beltline region. Those studies described stress and fracture mechanics analyses performed to assess various RPV nozzle geometries, which were selected based on their proximity to the core beltline region, i.e., those nozzle configurations that are located close enough to the core region such that they may receive sufficient fluence prior to end-of-life (EOL) to require evaluation of embrittlement as part of the RPV analyses associated with pressure-temperature (P-T) limits. In this paper, additional stress and fracture analyses are summarized that were performed for additional PWR nozzles with the following objectives: To expand the population of PWR nozzle configurations evaluated, which was limited in the previous work to just two nozzles (one inlet and one outlet nozzle). To model and understand differences in stress results obtained for an internal pressure load case using a two-dimensional (2-D) axi-symmetric finite element model (FEM) vs. a three-dimensional (3-D) FEM for these PWR nozzles. In particular, the ovalization (stress concentration) effect of two intersecting cylinders, which is typical of RPV nozzle configurations, was investigated. To investigate the applicability of previously recommended linear elastic fracture mechanics (LEFM) hand solutions for calculating the Mode I stress intensity factor for a postulated nozzle corner crack for pressure loading for these PWR nozzles. These analyses were performed to further expand earlier work completed to support potential revision and refinement of Title 10 to the U.S. Code of Federal Regulations (CFR), Part 50, Appendix G, Fracture Toughness Requirements, and are intended to supplement similar evaluation of nozzles presented at the 2008, 2009, and 2011 Pressure Vessels and Piping (PVP) Conferences. This work is also relevant to the ongoing efforts of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, Section XI, Working Group on Operating Plant Criteria (WGOPC) efforts to incorporate nozzle fracture mechanics solutions into a revision to ASME B&PV Code, Section XI, Nonmandatory Appendix G.

  15. RADIOACTIVE MATERIAL SHIPPING PACKAGINGS AND METAL TO METAL SEALS FOUND IN THE CLOSURES OF CONTAINMENT VESSELS INCORPORATING CONE SEAL CLOSURES

    SciTech Connect (OSTI)

    Loftin, B; Glenn Abramczyk, G; Allen Smith, A

    2007-06-06T23:59:59.000Z

    The containment vessels for the Model 9975 radioactive material shipping packaging employ a cone-seal closure. The possibility of a metal-to-metal seal forming between the mating conical surfaces, independent of the elastomer seals, has been raised. It was postulated that such an occurrence would compromise the containment vessel hydrostatic and leakage tests. The possibility of formation of such a seal has been investigated by testing and by structural and statistical analyses. The results of the testing and the statistical analysis demonstrate and procedural changes ensure that hydrostatic proof and annual leakage testing can be accomplished to the appropriate standards.

  16. TOPAZ: a computer code for modeling heat transfer and fluid flow in arbitrary networks of pipes, flow branches, and vessels

    SciTech Connect (OSTI)

    Winters, W.S.

    1984-01-01T23:59:59.000Z

    An overview of the computer code TOPAZ (Transient-One-Dimensional Pipe Flow Analyzer) is presented. TOPAZ models the flow of compressible and incompressible fluids through complex and arbitrary arrangements of pipes, valves, flow branches and vessels. Heat transfer to and from the fluid containment structures (i.e. vessel and pipe walls) can also be modeled. This document includes discussions of the fluid flow equations and containment heat conduction equations. The modeling philosophy, numerical integration technique, code architecture, and methods for generating the computational mesh are also discussed.

  17. EVALUATION OF TROQUE VS CLOSURE BOLT PRELOAD FOR A TYPICAL CONTAINMENT VESSEL UNDER SERVICE CONDITIONS

    SciTech Connect (OSTI)

    Smith, A.

    2010-02-16T23:59:59.000Z

    Radioactive material package containment vessels typically employ bolted closures of various configurations. Closure bolts must retain the lid of a package and must maintain required seal loads, while subjected to internal pressure, impact loads and vibration. The need for insuring that the specified preload is achieved in closure bolts for radioactive materials packagings has been a continual subject of concern for both designers and regulatory reviewers. The extensive literature on threaded fasteners provides sound guidance on design and torque specification for closure bolts. The literature also shows the uncertainty associated with use of torque to establish preload is typically between 10 and 35%. These studies have been performed under controlled, laboratory conditions. The ability to insure required preload in normal service is, consequently, an important question. The study described here investigated the relationship between indicated torque and resulting bolt load for a typical radioactive materials package closure using methods available under normal service conditions.

  18. Assemblies and methods for mitigating effects of reactor pressure vessel expansion

    DOE Patents [OSTI]

    Challberg, R.C.; Gou, P.F.; Chu, C.L.; Oliver, R.P.

    1999-07-27T23:59:59.000Z

    Support assemblies for allowing RPV radial expansion while simultaneously limiting horizontal, vertical, and azimuthal movement of the RPV within a nuclear reactor are described. In one embodiment, the support assembly includes a support block and a guide block. The support block includes a first portion and a second portion, and the first portion is rigidly coupled to the RPV adjacent the first portion. The guide block is rigidly coupled to a reactor pressure vessel support structure and includes a channel sized to receive the second portion of the support block. The second portion of the support block is positioned in the guide block channel to movably couple the guide block to the support block. 6 figs.

  19. Assemblies and methods for mitigating effects of reactor pressure vessel expansion

    DOE Patents [OSTI]

    Challberg, Roy C. (Livermore, CA); Gou, Perng-Fei (Saratoga, CA); Chu, Cherk Lam (San Jose, CA); Oliver, Robert P. (Topsham, ME)

    1999-01-01T23:59:59.000Z

    Support assemblies for allowing RPV radial expansion while simultaneously limiting horizontal, vertical, and azimuthal movement of the RPV within a nuclear reactor are described. In one embodiment, the support assembly includes a support block and a guide block. The support block includes a first portion and a second portion, and the first portion is rigidly coupled to the RPV adjacent the first portion. The guide block is rigidly coupled to a reactor pressure vessel support structure and includes a channel sized to receive the second portion of the support block. The second portion of the support block is positioned in the guide block channel to movably couple the guide block to the support block.

  20. Analysis of the pool critical assembly pressure vessel benchmark using pentran

    SciTech Connect (OSTI)

    Edgar, C. A.; Sjoden, G. E. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Inst. of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

    2012-07-01T23:59:59.000Z

    The internationally circulated Pool Critical Assembly (PCA) Pressure Vessel Benchmark was analyzed using the PENTRAN Parallel Sn code system for the geometry, material, and source specifications as described in the PCA Benchmark documentation. This research focused on utilizing the BUGLE-96 cross section library and accompanying reaction rates, while examining both adaptive differencing on a coarse mesh basis as well as Directional Theta Weighted Sn differencing in order to compare the calculated PENTRAN results to measured data. The results show good comparison with the measured data as well as to the calculated results provided from TORT for the BUGLE-96 cross sections and reaction rates, which suggests PENTRAN is a viable and reliable code system for calculation of light water reactor neutron shielding and dosimetry calculations. (authors)

  1. The influence of metallurgical variables on the temperature dependence of irradiation hardening in pressure vessel steels

    SciTech Connect (OSTI)

    Odette, G.R.; Lucas, G.E.; Klingensmith, R.D. [Univ. of California, Santa Barbara, CA (United States). Dept. of Mechanical Engineering

    1996-12-31T23:59:59.000Z

    Yield stress elevations ({Delta}{sigma}{sub y}) in pressure vessel steels irradiated at intermediate flux and fluence systematically decreased with increasing temperature and decreasing copper and nickel content. Lower stress relief temperature also decreased {Delta}{sigma}{sub y} at bulk copper concentrations greater than about 0.3%. The dependence of {Delta}{sigma}{sub y} on irradiation temperature between 260 and 316 C increased with copper and nickel content and decreased with phosphorus content. When normalized by the average {Delta}{sigma}{sub y}, the fractional temperature dependence correlates with a simple empirical chemistry factor of copper and phosphorus. The correlation predicts data on the irradiation temperature dependence of {Delta}{sigma}{sub y} found in the literature within a standard error of about 0.3 MPa/{degree}C and is consistent with current understanding of hardening mechanisms. However, questions remain about the effects at very low flux and finer scale variations over smaller temperature intervals.

  2. A Unified Cohesive Zone Approach to Model Ductile Brittle Transition in Reactor Pressure Vessel Steels

    SciTech Connect (OSTI)

    Pritam Chakraborty; S. Bulent Biner

    2014-08-01T23:59:59.000Z

    In this study, a unified cohesive zone model has been proposed to predict, Ductile to Brittle Transition, DBT, in Reactor Pressure Vessel, RPV, steels. A general procedure is described to obtain the Cohesive Zone Model, CZM, parameters for the different temperatures and fracture probabilities. In order to establish the full master-curve, the procedure requires three calibration points with one at the upper-shelf for ductile fracture and two for the fracture probabilities, Pf, of 5% and 95% at the lower-shelf. In the current study, these calibrations were carried out by utilizing the experimental fracture toughness values and flow curves. After the calibration procedure, the simulations of fracture behavior (ranging from completely unstable to stable crack extension behavior) in one inch thick compact tension specimens at different temperatures yielded values that were comparable to the experimental fracture toughness values, indicating the viability of such unified modeling approach.

  3. Research and Development Roadmaps for Nondestructive Evaluation of Cables, Concrete, Reactor Pressure Vessels, and Piping Fatique

    SciTech Connect (OSTI)

    Clayton, Dwight A [ORNL] [ORNL; Bakhtiari, Sasan [Argonne National Laboratory (ANL)] [Argonne National Laboratory (ANL); Smith, Cyrus M [ORNL] [ORNL; Simmons, Kevin [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Coble, Jamie [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Brenchley, David [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL); Meyer, Ryan [Pacific Northwest National Laboratory (PNNL)] [Pacific Northwest National Laboratory (PNNL)

    2013-01-01T23:59:59.000Z

    To address these research needs, the MAaD Pathway supported a series of workshops in the summer of 2012 for the purpose of developing R&D roadmaps for enhancing the use of Nondestructive Evaluation (NDE) technologies and methodologies for detecting aging and degradation of materials and predicting the remaining useful life. The workshops were conducted to assess requirements and technical gaps related to applications of NDE for cables, concrete, reactor pressure vessels (RPV), and piping fatigue for extended reactor life. An overview of the outcomes of the workshops is presented here. Details of the workshop outcomes and proposed R&D also are available in the R&D roadmap documents cited in the bibliography and are available on the LWRS Program website (http://www.inl.gov/lwrs).

  4. Reactor pressure vessel integrity research at the Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Corwin, W.R.; Pennell, W.E.; Pace, J.V.

    1995-12-31T23:59:59.000Z

    Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only key safety-related component of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the integrity inherent in the RPV. For this reason, the U.S. Nuclear Regulatory Commission has established the related research programs at ORNL described herein to provide for the development and confirmation of the methods used for: (1) establishing the irradiation exposure conditions within the RPV in the Embrittlement Data Base and Dosimetry Evaluation Program, (2) assessing the effects of irradiation on the RPV materials in the Heavy-Section Steel Irradiation Program, and (3) developing overall structural and fracture analyses of RPVs in the Heavy-Section Steel Technology Program.

  5. REACTOR PRESSURE VESSEL ISSUES FOR THE LIGHT-WATER REACTOR SUSTAINABILITY PROGRAM

    SciTech Connect (OSTI)

    Nanstad, Randy K [ORNL; Odette, George Robert [UCSB

    2010-01-01T23:59:59.000Z

    The Light Water Reactor Sustainability Program Plan is a collaborative program between the U.S. Department of Energy and the private sector directed at extending the life of the present generation of nuclear power plants to enable operation to at least 80 years. The reactor pressure vessel (RPV) is one of the primary components requiring significant research to enable such long-term operation. There are significant issues that need to be addressed to reduce the uncertainties in regulatory application, such as, 1) high neutron fluence/long irradiation times, and flux effects, 2) material variability, 3) high-nickel materials, 4)specimen size effects and the fracture toughness master curve, etc. The first issue is the highest priority to obtain the data and mechanistic understanding to enable accurate, reliable embrittlement predictions at high fluences. This paper discusses the major issues associated with long-time operation of existing RPVs and the LWRSP plans to address those issues.

  6. THE DEVELOPMENT OF RADIATION EMBRITTLEMENT MODELS FOR U.S. POWER REACTOR PRESSURE VESSEL STEELS

    SciTech Connect (OSTI)

    Wang, Jy-An John [ORNL; Rao, Nageswara S [ORNL

    2006-01-01T23:59:59.000Z

    The information fusion technique is used to develop radiation embrittlement prediction models for reactor pressure vessel (RPV) steels from U.S. power reactors, including boiling water reactors and pressurized water reactors. The Charpy transition temperature-shift data is used as the primary index of RPV radiation embrittlement in this study. Six parameters {Cu, Ni, P, neutron fluence, irradiation time, and irradiation temperature {are used in the embrittlement prediction models. The results indicate that this new embrittlement predictor achieved reductions of about 49.5% and 52% in the uncertainties for plate and weld data, respectively, for pressurized water reactor and boiling water reactor data, compared with the Nuclear Regulatory Commission Regulatory Guide 1.99, Rev. 2. The implications of dose-rate effect and irradiation temperature effects for the development of radiation embrittlement models are also discussed.

  7. Engineering evaluation and analysis for the improvement of military standard generators. Volume 1. Final report, 24 February-29 May 1987

    SciTech Connect (OSTI)

    Adolph, R.J.; Lawrence, L.G.; Perkins, G.W.; Thorwaldson, E.

    1987-05-29T23:59:59.000Z

    This Final Report provides an in-depth look at on-going projects for improving the Mobile Electric-Power-Generating System (MEPGS) sets. A detailed comparison of existing MEPGS requirements for generators against proposed requirements for commercial generators procured for tactical military use is presented. From this comparison, a list of areas and characteristics of the MEPGS sets, which fall short of the requirements imposed by the draft Required Operational Capability (ROC) document are presented. Major areas include: noise, reliability, Electro Magnetic Pulse (EMP), and built-in test equipment. This report analyzes industry response and suggestions for improvement of the MPEGS set family. Respondents' suggestions fell primarily in the areas of Reliability, Noise and Infrared (IR) suppression. The majority of recommended actions were general in nature, but the vendors were consistent in the areas they felt could be improved. Design modifications are proposed for all MEPGS sets considered in this study to upgrade the requirements in the areas of noise suppression and reliability. Major emphasis is placed on improvements to the 15-, 30-, and 60-kW generator sets.

  8. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2010-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750°C, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

  9. Effects of irradiation on strength and toughness of commercial LWR vessel cladding

    SciTech Connect (OSTI)

    Haggag, F.M.; Corwin, W.R.; Alexander, D.J.; Nanstad, R.K.

    1987-01-01T23:59:59.000Z

    The potential for stainless steel cladding to improve the fracture behavior of an operating nuclear reactor pressure vessel, particularly during certain overcooling transients, may depend greatly on the properties of the irradiated cladding. Therefore, weld overlay cladding irradiated at temperatures and to fluences relevant to power reactor operation was examined. The cladding was applied to a pressure vessel steel plate by the three-wire series-arc commercial method. Cladding was applied in three layers to provide adequate thickness for the fabrication of test specimens. The three-wire series-arc procedure, developed by Combustion Engineering, Inc., Chattanooga, Tennessee, produced a highly controlled weld chemistry, microstructure, and fracture properties in all three layers of the weld. Charpy V-notch and tensile specimens were irradiated at 288/sup 0/C to fluence levels of 2 and 5 x 10/sup 19/ neutrons/cm/sup 2/ (>1 MeV). Postirradiation testing results show that, in the test temperature range from -125 to 288/sup 0/C, the yield strength increased by 8 to 30%, ductility insignificantly increased, while there was almost no change in ultimate tensile strength. All cladding exhibited ductile-to-brittle transition behavior during Charpy impact testing, due to the dominance of delta-ferrite failures at low temperatures. On the upper shelf, energy was reduced, due to irradiation exposure, 15 and 20%, while the lateral expansion was reduced 43 and 41%, at 2 and 5 x 10/sup 19/ neutrons/cm/sup 2/ (>1 MeV), respectively. In addition, radiation damage resulted in 13 and 28/sup 0/C shifts of the Charpy impact transition temperature at the 41-J level for the low and high fluences, respectively.

  10. Advanced Models of LWR Pressure Vessel Embrittlement for Low Flux-HighFluence Conditions

    SciTech Connect (OSTI)

    Odette, G. Robert; Yamamoto, Takuya

    2013-06-17T23:59:59.000Z

    Neutron embrittlement of reactor pressure vessels (RPVs) is an unresolved issue for light water reactor life extension, especially since transition temperature shifts (TTS) must be predicted for high 80-year fluence levels up to approximately 1,020 n/cm{sup 2}, far beyond the current surveillance database. Unfortunately, TTS may accelerate at high fluence, and may be further amplified by the formation of late blooming phases that result in severe embrittlement even in low-copper (Cu) steels. Embrittlement by this mechanism is a potentially significant degradation phenomenon that is not predicted by current regulatory models. This project will focus on accurately predicting transition temperature shifts at high fluence using advanced physically based, empirically validated and calibrated models. A major challenge is to develop models that can adjust test reactor data to account for flux effects. Since transition temperature shifts depend on synergistic combinations of many variables, flux-effects cannot be treated in isolation. The best current models systematically and significantly under-predict transition temperature at high fluence, although predominantly for irradiations at much higher flux than actual RPV service. This project will integrate surveillance, test reactor and mechanism data with advanced models to address a number of outstanding RPV embrittlement issues. The effort will include developing new databases and preliminary models of flux effects for irradiation conditions ranging from very low (e.g., boiling water reactor) to high (e.g., accelerated test reactor). The team will also develop a database and physical models to help predict the conditions for the formation of Mn-Ni-Si late blooming phases and to guide future efforts to fully resolve this issue. Researchers will carry out other tasks on a best-effort basis, including prediction of transition temperature shift attenuation through the vessel wall, remediation of embrittlement by annealing, and fracture toughness master curve issues.

  11. The Interagency Process in Support & Stability Operations: Integrating and Aligning the Roles and Missions of Military and Civilian Agencies in Conflict and Post-Conflict Environments 

    E-Print Network [OSTI]

    Baetjer, Patrick; Cline, Chris; Hernandorena, Carlos; Polley, Brian; Rogers, Kate; Smith, Amanda; Voelkel, Tyson

    2007-01-01T23:59:59.000Z

    , reconstruction, or institution building. For instance, in post World War II Japan, the military ran operations for seven years in a hierarchical structure headed by General Douglas MacArthur. Some thinking about a transition to civilian control was discarded... of cultures that divide, dilute and fragment individuals, teams, organizations and institutions. Everyone with interagency experience knows that we can do much better. The following abstracts provide an overview of the attached research papers...

  12. Development of the RCRV Design: Top Level Requirements The Top Level Requirements (TLR) for the Regional Class Research Vessel (RCRV) are

    E-Print Network [OSTI]

    underwater vehicles (AUVs) Deployment and recovery of unmanned aerial systems (UASs) and weather balloons. The vessel's Underwater Radiated Noise (URN) will be minimized through treatments and vibration dampening, monitoring, and servicing of remotely operated vehicles (ROVs) (appropriate for vessel size) and autonomous

  13. In-Vessel Retention Technology Development and Use for Advanced PWR Designs in the USA and Korea

    SciTech Connect (OSTI)

    T.G. Theofanous; S.J. Oh; J.H. Scobel

    2004-05-18T23:59:59.000Z

    In-Vessel Retention (IVR) of molten core debris by means of external reactor vessel flooding is a cornerstone of severe accident management for Westinghouse's AP600 (advanced passive light water reactor) design. The case for its effectiveness (made in previous work by the PI) has been thoroughly documented, reviewed as part of the licensing certification, and accepted by the US Nuclear Regulatory Commission. A successful IVR would terminate a severe accident, passively, with the core in a stable, coolable configuration (within the lower head), thus avoiding the largely uncertain accident evolution with the molten debris on the containment floor. This passive plant design has been upgraded by Westinghouse to the AP1000, a 1000 MWe plant very similar to the AP600. The severe accident management approach is very similar too, including In-Vessel Retention as the cornerstone feature, and initial evaluations indicated that this would be feasible at the higher power as well. A similar strategy is adopted in Korea for the APR1400 plant. The overall goal of this project is to provide experimental data and develop the necessary basic understanding so as to allow the robust extension of the AP600 In-Vessel Retention strategy for severe accident management to higher power reactors, and in particular, to the AP1000 advanced passive design.

  14. BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING

    SciTech Connect (OSTI)

    Langton, C.; Stefanko, D.

    2011-03-10T23:59:59.000Z

    The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010].

  15. 1 Copyright 2010 by ASME Proceedings of the ASME 2010 Pressure Vessels & Piping Division / K-PVP Conference

    E-Print Network [OSTI]

    Tijsseling, A.S.

    1 Copyright © 2010 by ASME Proceedings of the ASME 2010 Pressure Vessels & Piping Division / K-6]. Developers and users of computational codes need full- scale data with which to compare their theoretical;2 Copyright © 2010 by ASME Here, a large-scale pipeline test rig at Deltares, Delft, The Netherlands has been

  16. Validation of vessel-based registration for correction of brain shift I. Reinertsen a,*, M. Descoteaux b,1

    E-Print Network [OSTI]

    Siddiqi, Kaleem

    Validation of vessel-based registration for correction of brain shift I. Reinertsen a,*, M April 2007 Abstract The displacement and deformation of brain tissue is a major source of error in image-guided neurosurgery systems. We have designed and implemented a method to detect and correct brain shift using pre

  17. Miniaturized reaction vessel system, method for performing site-specific biochemical reactions and affinity fractionation for use in DNA sequencing

    DOE Patents [OSTI]

    Mirzabekov, Andrei Darievich (Moscow, RU); Lysov, Yuri Petrovich (Moscow, RU); Dubley, Svetlana A. (Moscow, RU)

    2000-01-01T23:59:59.000Z

    A method for fractionating and sequencing DNA via affinity interaction is provided comprising contacting cleaved DNA to a first array of oligonucleotide molecules to facilitate hybridization between said cleaved DNA and the molecules; extracting the hybridized DNA from the molecules; contacting said extracted hybridized DNA with a second array of oligonucleotide molecules, wherein the oligonucleotide molecules in the second array have specified base sequences that are complementary to said extracted hybridized DNA; and attaching labeled DNA to the second array of oligonucleotide molecules, wherein the labeled re-hybridized DNA have sequences that are complementary to the oligomers. The invention further provides a method for performing multi-step conversions of the chemical structure of compounds comprising supplying an array of polyacrylamide vessels separated by hydrophobic surfaces; immobilizing a plurality of reactants, such as enzymes, in the vessels so that each vessel contains one reactant; contacting the compounds to each of the vessels in a predetermined sequence and for a sufficient time to convert the compounds to a desired state; and isolating the converted compounds from said array.

  18. Automated registration of multispectral MR vessel wall images of the carotid artery

    SciTech Connect (OSTI)

    Klooster, R. van 't; Staring, M.; Reiber, J. H. C.; Lelieveldt, B. P. F.; Geest, R. J. van der, E-mail: rvdgeest@lumc.nl [Department of Radiology, Division of Image Processing, Leiden University Medical Center, 2300 RC Leiden (Netherlands); Klein, S. [Department of Radiology and Department of Medical Informatics, Biomedical Imaging Group Rotterdam, Erasmus MC, Rotterdam 3015 GE (Netherlands)] [Department of Radiology and Department of Medical Informatics, Biomedical Imaging Group Rotterdam, Erasmus MC, Rotterdam 3015 GE (Netherlands); Kwee, R. M.; Kooi, M. E. [Department of Radiology, Cardiovascular Research Institute Maastricht, Maastricht University Medical Center, Maastricht 6202 AZ (Netherlands)] [Department of Radiology, Cardiovascular Research Institute Maastricht, Maastricht University Medical Center, Maastricht 6202 AZ (Netherlands)

    2013-12-15T23:59:59.000Z

    Purpose: Atherosclerosis is the primary cause of heart disease and stroke. The detailed assessment of atherosclerosis of the carotid artery requires high resolution imaging of the vessel wall using multiple MR sequences with different contrast weightings. These images allow manual or automated classification of plaque components inside the vessel wall. Automated classification requires all sequences to be in alignment, which is hampered by patient motion. In clinical practice, correction of this motion is performed manually. Previous studies applied automated image registration to correct for motion using only nondeformable transformation models and did not perform a detailed quantitative validation. The purpose of this study is to develop an automated accurate 3D registration method, and to extensively validate this method on a large set of patient data. In addition, the authors quantified patient motion during scanning to investigate the need for correction. Methods: MR imaging studies (1.5T, dedicated carotid surface coil, Philips) from 55 TIA/stroke patients with ipsilateral <70% carotid artery stenosis were randomly selected from a larger cohort. Five MR pulse sequences were acquired around the carotid bifurcation, each containing nine transverse slices: T1-weighted turbo field echo, time of flight, T2-weighted turbo spin-echo, and pre- and postcontrast T1-weighted turbo spin-echo images (T1W TSE). The images were manually segmented by delineating the lumen contour in each vessel wall sequence and were manually aligned by applying throughplane and inplane translations to the images. To find the optimal automatic image registration method, different masks, choice of the fixed image, different types of the mutual information image similarity metric, and transformation models including 3D deformable transformation models, were evaluated. Evaluation of the automatic registration results was performed by comparing the lumen segmentations of the fixed image and moving image after registration. Results: The average required manual translation per image slice was 1.33 mm. Translations were larger as the patient was longer inside the scanner. Manual alignment took 187.5 s per patient resulting in a mean surface distance of 0.271 ± 0.127 mm. After minimal user interaction to generate the mask in the fixed image, the remaining sequences are automatically registered with a computation time of 52.0 s per patient. The optimal registration strategy used a circular mask with a diameter of 10 mm, a 3D B-spline transformation model with a control point spacing of 15 mm, mutual information as image similarity metric, and the precontrast T1W TSE as fixed image. A mean surface distance of 0.288 ± 0.128 mm was obtained with these settings, which is very close to the accuracy of the manual alignment procedure. The exact registration parameters and software were made publicly available. Conclusions: An automated registration method was developed and optimized, only needing two mouse clicks to mark the start and end point of the artery. Validation on a large group of patients showed that automated image registration has similar accuracy as the manual alignment procedure, substantially reducing the amount of user interactions needed, and is multiple times faster. In conclusion, the authors believe that the proposed automated method can replace the current manual procedure, thereby reducing the time to analyze the images.

  19. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2008-04-01T23:59:59.000Z

    The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2¼Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

  20. Evolution of Nickel-Manganese-Silicon Dominated Phases in Highly Irradiated Reactor Pressure Vessel Steels

    SciTech Connect (OSTI)

    Peter B Wells; Yuan Wu; Tim Milot; G. Robert Odette; Takuya Yamamoto; Brandon Miller; James Cole

    2014-11-01T23:59:59.000Z

    Formation of a high density of Ni-Mn-Si nm-scale precipitates in irradiated reactor pressure vessel steels, both with and without Cu, could lead to severe embrittlement. Models long ago predicted that these precipitates, which are not treated in current embrittlement regulations, would emerge only at high fluence. However, the mechanisms and variables that control Ni-Mn- Si precipitate formation, and their detailed characteristics, have not been well understood. High flux irradiations of six steels with systematic variations in Cu and Ni were carried out at ˜ 295±5°C to high and very high neutron fluences of ˜ 1.3x1020 and 1.1x1021 n/cm2. Atom probe tomography (APT) shows that significant mole fractions of these precipitates form in the Cu bearing steels at ˜ 1.3x1020 n/cm2, while they are only beginning to develop in Cu-free steels. However, large mole fractions, far in excess of those found in previous studies, are observed at 1.1x1021 n/cm2 at all Cu levels. The precipitates diffract, and in one case are compositionally and structurally consistent with the Mn6Ni16Si7 G-phase. At the highest fluence, the large precipitate mole fractions primarily depend on the steel Ni content, rather than Cu, and lead to enormous strength increases up to about 700 MPa. The implications of these results to light water reactor life extension are discussed briefly.

  1. On-Site Oxy-Lance Size Reduction of South Texas Project Reactor Vessel Heads - 12324

    SciTech Connect (OSTI)

    Posivak, Edward [WMG, inc. (United States); Keeney, Gilbert; Wheeler, Dean [Shaw Group (United States)

    2012-07-01T23:59:59.000Z

    On-Site Oxy-Lance size reduction of mildly radioactive large components has been accomplished at other operating plants. On-Site Oxy-Lance size reduction of more radioactive components like Reactor Vessel Heads had previously been limited to decommissioning projects. Building on past decommissioning and site experience, subcontractors for South Texas Project Nuclear Operating Company (STPNOC) developed an innovative integrated system to control smoke, radioactive contamination, worker dose, and worker safety. STP's innovative, easy to use CEDM containment that provided oxy lance access, smoke control, and spatter/contamination control was the key to successful segmentation for cost-effective and ALARA packaging and transport for disposal. Relative to CEDM milling, STP oxy-lance segmentation saved approximately 40 person- REM accrued during 9,000 hours logged into the radiological controlled area (RCA) during more than 3,800 separate entries. Furthermore there were no personnel contamination events or respiratory uptakes of radioactive material during the course of the entire project. (authors)

  2. Lessons Learned Following the Successful Decommissioning of a Reaction Vessel Containing Lime Sludge and Technetium-99

    SciTech Connect (OSTI)

    Dawson, P. M.; Watson, D. D.; Hylko, J. M.

    2002-02-25T23:59:59.000Z

    This paper documents how WESKEM, LLC utilized available source term information, integrated safety management, and associated project controls to safely decommission a reaction vessel and repackage sludge containing various Resource Conservation and Recovery Act constituents and technetium-99 (Tc-99). The decommissioning activities were segmented into five separate stages, allowing the project team to control work related decisions based on their knowledge, experience, expertise, and field observations. The information and experience gained from each previous stage and rehearsals contributed to modifying subsequent entries, further emphasizing the importance of developing hold points and incorporating lessons learned. The hold points and lessons learned, such as performing detailed personal protective equipment (PPE) inspections during sizing and repackaging operations, and using foam-type piping insulation to prevent workers from cutting or puncturing their PPE on sharp edge s or small shards generated during sizing operations, minimized direct contact with the Tc-99. To prevent the spread of contamination, the decommissioning activities were performed inside a containment enclosure connected to negative air machines. After performing over 235 individual entries totaling over 285 project hours, only one first aid was recorded during this five-stage project.

  3. Head Loss Evaluation in a PWR Reactor Vessel Using CFD Analysis

    SciTech Connect (OSTI)

    Ji Hwan Jeong; Jong Pil Park [School of Mechanical Engineering, Pusan National University, Enesys Jangjeon-dong, Geumjeong-gu, Busan (Korea, Republic of); Byoung-Sub Han [Jangdae-dong, Yusong-gu, Daejeon (Korea, Republic of)

    2006-07-01T23:59:59.000Z

    Nuclear vendors and utilities perform lots of simulations and analyses in order to ensure the safe operation of nuclear power plants (NPPs). In general, the simulations are carried out using vendor-specific design codes and best-estimate system analysis codes and most of them were developed based on 1-dimensional lumped parameter models. During the past decade, however, computers, parallel computation methods, and 3-dimensional computational fluid dynamics (CFD) codes have been dramatically enhanced. It is believed to be beneficial to take advantage of advanced commercial CFD codes in safety analysis and design of NPPs. The present work aims to analyze the flow distribution in downcomer and lower plenum of Korean standard nuclear power plants (KSNPs) using STAR-CD. The lower plenum geometry of a PWR is very complicated since there are so many reactor internals, which hinders in CFD analysis for real reactor geometry up to now. The present work takes advantage of 3D CAD model so that real geometry of lower plenum is used. The results give a clear figure about flow fields in the reactor vessel, which is one of major safety concerns. The calculated pressure drop across downcomer and lower plenum appears to be in good agreement with the data in engineering calculation note. A algorithm which can evaluate head loss coefficient which is necessary for thermal-hydraulic system code running was suggested based on this CFD analysis results. (authors)

  4. Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors

    SciTech Connect (OSTI)

    Love, E.F.; Pauley, K.A.; Reid, B.D.

    1995-09-01T23:59:59.000Z

    This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activation levels of irradiated reactor vessel internals hardware. The purpose of the analysis is to produce data for the Department of Energy`s Greater-Than-Class C Low-Level Radioactive Waste Program. An MCNP model was developed to analyze the Yankee Rowe reactor facility. The model incorporates reactor geometry, material compositions, and operating history data acquired from Yankee Atomic Electric Company. In addition to the base activation analysis, parametric studies were performed to determine the sensitivity of activation to specific parameters. A component sampling plan was also developed to validate the model results, although the plan was not implemented. The calculations for the Yankee Rowe reactor predict that only the core baffle and the core support plates will be activated to levels above the Class C limits. The parametric calculations show, however, that the large uncertainties in the material compositions could cause errors in the estimates that could also increase the estimated activation level of the core barrel to above the Class C limits. Extrapolation of the results to other reactor facilities indicates that in addition to the baffle and support plates, core barrels may also be activated to above Class C limits; however the classification will depend on the specific operating conditions of the reactor and the specific material compositions of the metal, as well as the use of allowable concentration averaging practices in packaging and classifying the waste.

  5. Application of micromechanical models of ductile fracture initiation to reactor pressure vessel materials

    SciTech Connect (OSTI)

    Chaouadi, R.; Walle, E. van; Fabry, A.; Velde, J. van de [SCK-CEN, Mol (Belgium); Meester, P. de [KUL, Heverlee (Belgium). Metals and Materials Science Dept.

    1996-12-31T23:59:59.000Z

    The aim of the current study is the application of local micromechanical models to predict crack initiation in ductile materials. Two reactor pressure vessel materials have been selected for this study: JRQ IAEA monitor base metal (A533B Cl.1) and Doel-IV weld material. Charpy impact tests have been performed in both un-irradiated and irradiated conditions. In addition to standard tensile tests, notched tensile specimens have been tested. The upper shelf energy of the weld material remains almost un-affected by irradiation, whereas a decrease of 20% is detected for the base metal. Accordingly, the tensile properties of the weld material do not reveal a clear irradiation effect on the yield and ultimate stresses, this in contrast to the base material flow properties. The tensile tests have been analyzed in terms of micromechanical models. A good correlation is found between the standard tests and the micromechanical models, that are able to predict the ductile damage evolution in these materials. Additional information on the ductility behavior of these materials is revealed by this micromechanical analysis.

  6. Modeling of irradiation embrittlement and annealing/recovery in pressure vessel steels

    SciTech Connect (OSTI)

    Lott, R.G.; Freyer, P.D. [Westinghouse Science and Technology Center, Pittsburgh, PA (United States)

    1996-12-31T23:59:59.000Z

    The results of reactor pressure vessel (RPV) annealing studies are interpreted in light of the current understanding of radiation embrittlement phenomena in RPV steels. An extensive RPV irradiation embrittlement and annealing database has been compiled and the data reveal that the majority of annealing studies completed to date have employed test reactor irradiated weldments. Although test reactor and power reactor irradiations result in similar embrittlement trends, subtle differences between these two damage states can become important in the interpretation of annealing results. Microstructural studies of irradiated steels suggest that there are several different irradiation-induced microstructural features that contribute to embrittlement. The amount of annealing recovery and the post-anneal re-embrittlement behavior of a steel are determined by the annealing response of these microstructural defects. The active embrittlement mechanisms are determined largely by the irradiation temperature and the material composition. Interpretation and thorough understanding of annealing results require a model that considers the underlying physical mechanisms of embrittlement. This paper presents a framework for the construction of a physically based mechanistic model of irradiation embrittlement and annealing behavior.

  7. Effects of thermal annealing and reirradiation on toughness of reactor pressure vessel steels

    SciTech Connect (OSTI)

    Nanstad, R.K.; Iskander, S.K.; Sokolov, M.A. [and others

    1996-12-31T23:59:59.000Z

    One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. This paper summarizes recent experimental results from work performed at the Oak Ridge National Laboratory (ORNL) to study the annealing response, or {open_quotes}recovery,{close_quotes} of several irradiated RPV steels; it also includes recent results from both ORNL and the Russian Research Center-Kurchatov Institute (RRC-KI) on a cooperative program of irradiation, annealing and reirradiation of both U.S. and Russian RPV steels. The cooperative program was conducted under the auspices of Working Group 3, U.S./Russia Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS). The materials investigated are an RPV plate and various submerged-arc welds, with tensile, Charpy impact toughness, and fracture toughness results variously determined. Experimental results are compared with applicable prediction guidelines, while observed differences in annealing responses and reirradiation rates are discussed.

  8. Pressure vessel embrittlement predictions based on a composite model of copper precipitation and point defect clustering

    SciTech Connect (OSTI)

    Stoller, R.E. [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.

    1996-12-31T23:59:59.000Z

    A theoretical model is used to investigate the relative importance of point defect clusters (PDC) and copper-rich precipitates in reactor pressure vessel (RPV) embrittlement and to examine the influence of a broad range of irradiation and material parameters on predicted yield strength changes. The results indicate that there are temperature and displacement rate regimes wherein either CRP or PDC can dominate the material`s response to irradiation, with both interstitial and vacancy type defects contributing to the PDC component. The different dependencies of the CRP and PDC on temperature and displacement rate indicate that simple data extrapolations could lead to poor predictions of RPV embrittlement. It is significant that the yield strength changes predicted by the composite PDC/CRP model exhibit very little dependence on displacement rate below about 10{sup {minus}9} dpa/s. If this result is confirmed, concerns about accelerated displacement rates in power reactor surveillance programs should be minimized. The sensitivity of the model to microstructural parameters highlights the need for more detailed microstructural characterization of RPV steels.

  9. Nondestructive characterization of embrittlement in reactor pressure vessel steels -- A feasibility study

    SciTech Connect (OSTI)

    McHenry, H.I.; Alers, G.A. [National Inst. of Standards and Technology, Boulder, CO (United States). Materials Reliability Div.

    1998-03-01T23:59:59.000Z

    The Nuclear Regulatory Commission recently initiated a study by NIST to assess the feasibility of using physical-property measurements for evaluating radiation embrittlement in reactor pressure vessel (RPV) steels. Ultrasonic and magnetic measurements provide the most promising approaches for nondestructive characterization of RPV steels because elastic waves and magnetic fields can sense the microstructural changes that embrittle materials. The microstructural changes of particular interest are copper precipitation hardening, which is the likely cause of radiation embrittlement in RPV steels, and the loss of dislocation mobility that is an attribute of the ductile-to-brittle transition. Measurements were made on a 1% copper steel, ASTM grade A710, in the annealed, peak-aged and overaged conditions, and on an RPV steel, ASTM grade A533B. Nonlinear ultrasonic and micromagnetic techniques were the most promising measures of precipitation hardening. Ultrasonic velocity measurements and the magnetic properties associated with hysteresis-loop measurements were not particularly sensitive to either precipitation hardening or the ductile-to-brittle transition. Measurements of internal friction using trapped ultrasonic resonance modes detected energy losses due to the motion of pinned dislocations; however, the ultrasonic attenuation associated with these measurements was small compared to the attenuation caused by beam spreading that would occur in conventional ultrasonic testing of RPVs.

  10. Creep failure of a reactor pressure vessel lower head under severe accident conditions

    SciTech Connect (OSTI)

    Pilch, M.M.; Ludwigsen, J.S.; Chu, T.Y. [Sandia National Labs., Albuquerque, NM (United States); Rashid, Y.R. [Anatech, San Diego, CA (United States)

    1998-08-01T23:59:59.000Z

    A severe accident in a nuclear power plant could result in the relocation of large quantities of molten core material onto the lower head of he reactor pressure vessel (RPV). In the absence of inherent cooling mechanisms, failure of the RPV ultimately becomes possible under the combined effects of system pressure and the thermal heat-up of the lower head. Sandia National Laboratories has performed seven experiments at 1:5th scale simulating creep failure of a RPV lower head. This paper describes a modeling program that complements the experimental program. Analyses have been performed using the general-purpose finite-element code ABAQUS-5.6. In order to make ABAQUS solve the specific problem at hand, a material constitutive model that utilizes temperature dependent properties has been developed and attached to ABAQUS-executable through its UMAT utility. Analyses of the LHF-1 experiment predict instability-type failure. Predicted strains are delayed relative to the observed strain histories. Parametric variations on either the yield stress, creep rate, or both (within the range of material property data) can bring predictions into agreement with experiment. The analysis indicates that it is necessary to conduct material property tests on the actual material used in the experimental program. The constitutive model employed in the present analyses is the subject of a separate publication.

  11. Effects of thermal annealing and reirradiation on toughness of reactor pressure vessel steels

    SciTech Connect (OSTI)

    Nanstad, R.K.; Iskander, S.K.; Sokolov, M.A. [Oak Ridge National Lab., TN (United States)] [and others

    1997-02-01T23:59:59.000Z

    One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. This paper summarizes recent experimental results from work performed at the Oak Ridge National Laboratory (ORNL) to study the annealing response, or {open_quotes}recovery,{close_quotes} of several irradiated RPV steels; it also includes recent results from both ORNL and the Russian Research Center-Kurchatov Institute (RRC-KI) on a cooperative program of irradiation, annealing and reirradiation of both U.S. and Russian RPV steels. The cooperative program was conducted under the auspices of Working Group 3, U.S./Russia Joint Coordinating Committee for Civilian Nuclear Reactor Safety (JCCCNRS). The materials investigated are an RPV plate and various submerged-arc welds, with tensile, Charpy impact toughness, and fracture toughness results variously determined. Experimental results are compared with applicable prediction guidelines, while observed differences in annealing responses and reirradiation rates are discussed.

  12. A Modification of the Inner and Outer Core for Reactor Pressure Vessel Lifetime Extension

    SciTech Connect (OSTI)

    Seo, Bo Kyun [Hanyang University (Korea, Republic of); Kim, Jong Kyung [Hanyang University (Korea, Republic of); Shin, Chang Ho [Hanyang University (Korea, Republic of); Kwon, Tae Je [Nuclear Fuel Company (Korea, Republic of)

    2001-03-15T23:59:59.000Z

    The feasibility of nuclear power plant lifetime extension was examined by reducing the fast neutron fluence at the reactor pressure vessel (RPV) and relieving irradiation embrittlement of materials, and thus ensuring enough structural integrity beyond the design lifetime. Two fluence reduction options, peripheral assembly replacement and additional shield installation in the outer core structures, were applied to the Kori Unit-1 reactor, and the fluence reduction effect was carefully analyzed. For an accurate estimate of the neutron fluence at the RPV and a reasonable description of the modified peripheral assemblies, a full-scope explicit modeling of a Monte Carlo simulation was employed in all calculations throughout this study. The Kori Unit-1 cycle-16 core was modeled on a three-dimensional representation by using the MCNP4B code, and the fluence distribution was estimated at the inner wall beltline around the circumferential weld of the RPV. On the basis of fracture toughness requirements of the RPV, the two modified cases were predicted to have an additional life of 7 to 10 effective full-power years. Throughout the core nuclear characteristics analyses, it was confirmed that the critical peaking factors for safe reactor operation were satisfied with the design limits.

  13. International Atomic Energy Agency (IAEA) Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels

    SciTech Connect (OSTI)

    Server, W. L. [ATI Consulting, Pinehurst, NC; Nanstad, Randy K [ORNL

    2009-01-01T23:59:59.000Z

    The International Atomic Energy Agency (IAEA) has conducted a series of Coordinated Research Projects (CRPs) that have focused on irradiated reactor pressure vessel (RPV) steel fracture toughness properties and approaches for assuring structural integrity of RPVs throughout operating life. A series of nine CRPs have been sponsored by the IAEA, starting in the early 1970s, focused on neutron radiation effects on RPV steels. The purpose of the CRPs was to develop comparisons and correlations to test the uniformity of irradiated results through coordinated international research studies and data sharing. Consideration of dose rate effects, effects of alloying (nickel, manganese, silicon, etc.) and residual elements (eg., copper and phosphorus), and drop in upper shelf toughness are also important for assessing neutron embrittlement effects. The ultimate use of embrittlement understanding is assuring structural integrity of the RPV under current and future operation and accident conditions. Material fracture toughness is the key ingredient needed for this assessment, and many of the CRPs have focused on measurement and application of irradiated fracture toughness. This paper presents an overview of the progress made since the inception of the CRPs in the early 1970s. The chronology and importance of each CRP have been reviewed and put into context for continued and long-term safe operation of RPVs.

  14. BWR ex-vessel steam explosion analysis with MC3D code

    SciTech Connect (OSTI)

    Leskovar, M. [Josef Stefan Inst., Jamova cesta 39, 1001 Ljubljana (Slovenia)

    2012-07-01T23:59:59.000Z

    A steam explosion may occur, during a severe reactor accident, when the molten core comes into contact with the coolant water. A strong enough steam explosion in a nuclear power plant could jeopardize the containment integrity and so lead to a direct release of radioactive material to the environment. To resolve the open issues in steam explosion understanding and modeling, the OECD program SERENA phase 2 was launched at the end of year 2007, focusing on reactor applications. To verify the progress made in the understanding and modeling of fuel coolant interaction key phenomena for reactor applications a reactor exercise has been performed. In this paper the BWR ex-vessel steam explosion study, which was carried out with the MC3D code in conditions of the SERENA reactor exercise for the BWR case, is presented and discussed. The premixing simulations were performed with two different jet breakup modeling approaches and the explosion was triggered also at the expected most challenging time. For the most challenging case, at the cavity wall the highest calculated pressure was {approx}20 MPa and the highest pressure impulse was {approx}90 kPa.s. (authors)

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

    SciTech Connect (OSTI)

    Rawls, G

    2007-04-30T23:59:59.000Z

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

  16. The toughness of irradiated pressure water reactor (PWR) vessel shell rings and the effect of segregation zones

    SciTech Connect (OSTI)

    Bethmont, M.; Frund, J.M. [Electricite de France, Moret-sur-Loing (France); Housin, B. [Framatome, Paris La Defense (France). Materials and Technology Dept.; Soulat, P. [Commissariat a l`Energie Atomique, Gif-sur-Yvette (France)

    1996-12-31T23:59:59.000Z

    To establish the integrity of pressure water reactor (PWR) vessels it is necessary to determine the toughness of A508Cl.3 steel at the end of its life, that is after thermal aging and irradiation embrittlement. In safety analyses the toughness can be deduced from a reference curve set forth in the code (ASME or RCC-M). The validity of the reference curve has been verified for several years for unirradiated French reactor vessels. Tests were performed on specimens taken from materials having heterogeneities in chemical composition. For most of the test results the reference curve is a lower bound. To solve te problem of determining the toughness of SA 508 Cl.3 steel after irradiation and in the presence of possible heterogeneities, the toughness results were gathered. The synthesis shows that the RCC-M code curve is conservative.

  17. FINAL REPORT - HYBRID-MIXING TESTS SUPPORTING THE CONCENTRATE RECEIPT VESSEL (CRV-VSL-00002A/2B) CONFIGURATION

    SciTech Connect (OSTI)

    GUERRERO, HECTORN.

    2004-09-01T23:59:59.000Z

    The Savannah River National Laboratory (SRNL) has performed scaled physical modeling of Pulse Jet Mixing Systems applicable to the Concentrate Receipt Vessel (CRV) of Hanford's Waste Treatment Plant (WTP) as part of the overall effort to validate pulse jet mixer (PJM) mixing in WTP vessels containing non-Newtonian fluids. The strategy developed by the Pulse Jet Mixing Task Team was to construct a quarter-scale model of the CRV, use a clear simulant to understand PJM mixing behavior, and down-select from a number of PJM configurations to a ''best design'' configuration. This ''best design'' would undergo final validation testing using a particulate simulant that has rheological properties closely similar to WTP waste streams. The scaled PJM mixing tests were to provide information on the operating parameters critical for the uniform movement (total mobilization) of these non-Newtonian slurries. Overall, 107 tests were performed during Phase I and Phase II testing.

  18. ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN THE R- AND P-REACTOR VESSELS

    SciTech Connect (OSTI)

    Wiersma, B.

    2009-12-29T23:59:59.000Z

    The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS&T) of the Savannah River National Laboratory (SRNL) has been requested to review and evaluate existing experimental and analytical studies of this issue to determine if any process constraints on the chemistry of the fill material and the fill operation are necessary. Various options exist for the type of grout material that may be used for D&D of the reactor vessels. The grout formulation options include ceramicrete (pH 6-8), low pH portland cement + silica fume grout (pH 10.4), or Portland cement grout (pH 12.5). The assessment concluded that either ceramicrete or the silica fume grout may be used to safely grout the P-reactor vessel. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Portland cement grout, on the other hand, for the same range of process parameters does not provide a significant margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations in the P-reactor vessel. It is recommended that this grout not be utilized for this task. The R-reactor vessel contains significantly less aluminum and thus a Portland cement grout may be considered as well. For example, if the grout fill rate is less than 1 inch/min and the grout temperature is maintained at 70 C or less, the risk of hydrogen accumulation in the R-reactor vessel is very low for the Portland cement. Alternatively, if the grout fill rate is less than 0.5 inch/min and the grout is maintained at a temperature of 80 C, the risk will again be very low. Although these calculations are conservative, there are some measures that may be taken to further minimize the potential for hydrogen evolution. (1) Minimize the temperature of the grout as much as practical. Lower temperatures will mean lower hydrogen generation rates. For P-reactor, grout temperatures less than 100 C should provide an adequate safety margin for the pH 8 and pH 10.4 grout formulations. For R-reactor, grout temperatures less than 70 C or 80 C will provide an adequate safety margin for the Portland cement. The other grout formulations are also viable options for R-reactor. (2) Minimize the grout fill rate as much as practical. Lowering the fill rate takes advantage of passivation of the aluminum components and hence lower hydrogen generation rates. For P-reactor, fill rates that are less than 2 inches/min for the ceramicrete and the silica fume grouts will reduce the chance of significant hydrogen accumulation. For R-reactor, fill rates less than 1 inch/min will again minimize the risk of hydrogen accumulation. (3) Ventilate the building as much as practical (e.g., leave doors open) to further disperse hydrogen. The volumetric hydrogen generation rates in the P-reactor vessel, however, are low for the pH 8 and pH 10.4 grout, (i.e., less than 0.32 ft{sup 3}/min). If further walk-down inspections of the reactor vessels suggest an increase in the actual areal density of aluminum, the calculations should be re-visited.

  19. Recruit Military Job Fair

    Broader source: Energy.gov [DOE]

    Location:FedEx Field, Landover, MD 20785POC: DOECorporateRecruitmentWebsite: https://events.recruitmilitary.com/ 

  20. SPACEWAR WIRE MILITARY SPACE

    E-Print Network [OSTI]

    Oxygen Triggered The Evolution Of Complex Life Forms US Navy Awards Raytheon $138M AEGIS Weapon System