National Library of Energy BETA

Sample records for nuclear steam supply

  1. An Overview of Nuclear vs. Non-Nuclear Design Code Requirements for a Candidate Steam Supply System for Commercial Applications

    SciTech Connect (OSTI)

    Robert Jetter

    2011-04-01

    The objective is to identify (mostly for industrial end-users) the difference between a Section III nuclear steam generator (classified as Structures, Systems and Components (SSC)) and a Section VIII steam generator in the same general conditions, but used in a conventional application. Specifically, applicable temperature and pressure ranges and a more quantitative description of how materials change, design margins change and required design rigor changes are of interest. This overview focuses on the steam generator pressure boundary but the downstream piping will also be considered. Within the designations of Section III and Section VIII there are subcategories with their specific regions of applicability. Each of these subcategories has evolved their own unique features with respect to design rules and their implementation. A general overview of the various design codes will be provided in sufficient detail to illustrate the major differences; however, a detailed discussion of the various design requirements and their implementation is beyond the scope of this discussion. References (1) and (2) are sources of more detailed information. Also, example wall sizing calculations will be provided to illustrate the application of the relevant design codes under the candidate design conditions. The candidate steam supply Design Conditions are 600C (1112F) and 24MPa (3,480psi). The Operating Conditions or Service Levels will be somewhat lower and the difference shows up in some of the various design methodologies employed.

  2. Supercritical Water Nuclear Steam Supply System: Innovations In Materials, Neutronics & Thermal-Hydraulics

    SciTech Connect (OSTI)

    Mark Anderson; M.L. Corradini; K. Sridharan; P. WIlson; D. Cho; T.K. Kim; S. Lomperski

    2004-09-02

    In the 1990's supercritical light-water reactors were considered in conceptual designs. A nuclear reactor cooled by supercritical waster would have a much higher thermal efficiency with a once-through direct power cycle, and could be based on standardized water reactor components (light water or heavy water). The theoretical efficiency could be improved by more than 33% over that of other water reactors and could be simplified with higher reliability; e.g., a boiling water reactor without steam separators or dryers.

  3. LOCA analyses for nuclear steam supply systems with upper head injection. [PWR

    SciTech Connect (OSTI)

    Byers, R.K.; Bartel, T.J.

    1980-01-01

    The term Upper Head Injection describes a relatively new addition to a nuclear reactor's emergency cooling system. With this feature, water is delivered directly to the top of the reactor vessel during a loss-of-coolant accident, in addition to the later injection of coolant into the primary operating loops. Established computer programs, with various modifications to models for heat transfer and two-phase flow, were used to analyze a transient following a large break in one of the main coolant loops of a reactor equipped with upper head injection. The flow and heat transfer modifications combined to yield fuel cladding temperatures during blowdown which were as much as 440K (800/sup 0/F) lower than were obtained with standard versions of the codes (for best estimate calculations). The calculations also showed the need for more uniformity of applications of heat transfer models in the computer programs employed.

  4. NUCLEAR FLASH TYPE STEAM GENERATOR

    DOE Patents [OSTI]

    Johns, F.L.; Gronemeyer, E.C.; Dusbabek, M.R.

    1962-09-01

    A nuclear steam generating apparatus is designed so that steam may be generated from water heated directly by the nuclear heat source. The apparatus comprises a pair of pressure vessels mounted one within the other, the inner vessel containing a nuclear reactor heat source in the lower portion thereof to which water is pumped. A series of small ports are disposed in the upper portion of the inner vessel for jetting heated water under pressure outwardly into the atmosphere within the interior of the outer vessel, at which time part of the jetted water flashes into steam. The invention eliminates the necessity of any intermediate heat transfer medium and components ordinarily required for handling that medium. (AEC)

  5. STEAM GENERATOR FOR NUCLEAR REACTOR

    DOE Patents [OSTI]

    Kinyon, B.W.; Whitman, G.D.

    1963-07-16

    The steam generator described for use in reactor powergenerating systems employs a series of concentric tubes providing annular passage of steam and water and includes a unique arrangement for separating the steam from the water. (AEC)

  6. Downhole steam generator using low pressure fuel and air supply

    DOE Patents [OSTI]

    Fox, Ronald L.

    1983-01-01

    An apparatus for generation of steam in a borehole for penetration into an earth formation wherein a spiral, tubular heat exchanger is used in the combustion chamber to isolate the combustion process from the water being superheated for conversion into steam. The isolation allows combustion of a relatively low pressure oxidant and fuel mixture for generating high enthalpy steam. The fuel is preheated by feedback of combustion gases from the top of the combustion chamber through a fuel preheater chamber. The hot exhaust gases of combustion at the bottom of the combustion chamber, after flowing over the heat exchanger enter an exhaust passage and pipe. The exhaust pipe is mounted inside the water supply line heating the water flowing into the heat exchanger. After being superheated in the heat exchanger, the water is ejected through an expansion nozzle and converts into steam prior to penetration into the earth formation. Pressure responsive doors are provided at a steam outlet downstream of the nozzle and close when the steam pressure is lost due to flameout.

  7. Apparatus and methods for supplying auxiliary steam in a combined cycle system

    SciTech Connect (OSTI)

    Gorman, William G.; Carberg, William George; Jones, Charles Michael

    2002-01-01

    To provide auxiliary steam, a low pressure valve is opened in a combined cycle system to divert low pressure steam from the heat recovery steam generator to a header for supplying steam to a second combined cycle's steam turbine seals, sparging devices and cooling steam for the steam turbine if the steam turbine and gas turbine lie on a common shaft with the generator. Cooling steam is supplied the gas turbine in the combined cycle system from the high pressure steam turbine. Spent gas turbine cooling steam may augment the low pressure steam supplied to the header by opening a high pressure valve whereby high and low pressure steam flows are combined. An attemperator is used to reduce the temperature of the combined steam in response to auxiliary steam flows above a predetermined flow and a steam header temperature above a predetermined temperature. The auxiliary steam may be used to start additional combined cycle units or to provide a host unit with steam turbine cooling and sealing steam during full-speed no-load operation after a load rejection.

  8. Propellant actuated nuclear reactor steam depressurization valve

    DOE Patents [OSTI]

    Ehrke, Alan C.; Knepp, John B.; Skoda, George I.

    1992-01-01

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

  9. Nuclear-energy application studied as source of injection steam for heavy-oil recovery

    SciTech Connect (OSTI)

    Perrett, R.J.; Gledhill, P.R.; Dawson, P.; Stephenson, D.J.

    1981-08-03

    This study into the feasibility of adapting a well-proven nuclear reactor as a centralized source of injection steam for the recovery of heavy oil has shown that the reactor modifications are practicable and well within the bounds of current technology. The gas-cooled reactor is capable of meeting the highest steam supply pressure requirement and it possesses a high degree of inherent safety. The injection of steam for the recovery of heavy oil is the most well developed of the available options. At current price levels of oil and uranium, nuclear heat can be generated at a fraction of the running costs of oil fired thermal plant. Taken over a project lifetime of 25 years for the field model used for this assessment, the improved earnings for the nuclear option could amount to as much as /10 billion. The program requirements for a typical development have been examined and the construction times for the gas reactor steam plant, the oil-field development and the upgrading plant are compatible at between five and six years. The economic advantage of steam generation by nuclear energy gives a further recovery breakthrough. It becomes possible to continue the steam drive process up to much more adverse recovery ratios of steam quantity injected for unit oil produced if nuclear energy is employed.

  10. SUPERCRITICAL STEAM CYCLE FOR NUCLEAR POWER PLANT

    SciTech Connect (OSTI)

    Tsiklauri, Georgi V.; Talbert, Robert J.; Schmitt, Bruce E.; Filippov, Gennady A.; Bogojavlensky, Roald G.; Grishanin, Evgeny I.

    2005-07-01

    Revolutionary improvement of the nuclear plant safety and economy with light water reactors can be reached with the application of micro-fuel elements (MFE) directly cooled by a supercritical pressure light-water coolant-moderator. There are considerable advantages of the MFE as compared with the traditional fuel rods, such as: Using supercritical and superheated steam considerably increases the thermal efficiency of the Rankine cycle up to 44-45%. Strong negative coolant and void reactivity coefficients with a very short thermal delay time allow the reactor to shutdown quickly in the event of a reactivity or power excursion. Core melting and the creation of corium during severe accidents are impossible. The heat transfer surface area is larger by several orders of magnitude due to the small spherical dimensions of the MFE. The larger heat exchange surface significantly simplifies residual heat removal by natural convection and radiation from the core to a subsequent passive system of heat removal.

  11. supply chain | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    supply chain

  12. maritime supply chain | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    maritime supply chain NNSA Co-Hosts Nuclear Security Summit Workshop on Maritime Security with UK WASHINGTON - This week, the Department of Energy's National Nuclear Security Administration (DOE/NNSA) and the U.K. Department of Energy and Climate Change concluded a workshop at Wilton Park, United Kingdom, on the growing challenge of securing the global maritime supply chain. In

  13. Superheated steam power plant with steam to steam reheater. [LMFBR

    SciTech Connect (OSTI)

    Silvestri, G.J.

    1981-06-23

    A desuperheater is disposed in a steam supply line supplying superheated steam to a shell and tube reheater.

  14. Utility-led cogen plant meets tight specs on steam supply

    SciTech Connect (OSTI)

    Eckersley, R.

    1995-08-01

    No Purpa machine here, this plant adds low-cost generating capacity while supplying steam with guaranteed reliability to petrochemicals producer. This article examines the design which ensures recovery of export steam load with minimum time and pressure loss. EI DuPont de Nemours and Co needed a new source of reliable, inexpensive steam to replace aging, inefficient boilers at its LaPorte (Tex) plant, where agricultural chemicals and other products are manufactured. At the same time, Houston Lighting and Power Co (HL and P) was exploring new ways to add capacity cost effectively. San Jacinto steam/electric station was the ideal solution that satisfied both needs. Fully operation since last April, the station`s performance has been excellent. Operating with complete reliability, the system has respond smoothly to meet changes in DuPont`s steam demand without upset.

  15. Downhole steam generator using low-pressure fuel and air supply

    DOE Patents [OSTI]

    Fox, R.L.

    1981-01-07

    For tertiary oil recovery, an apparatus for downhole steam generation is designed in which water is not injected directly onto the flame in the combustor, the combustion process is isolated from the reservoir pressure, the fuel and oxidant are supplied to the combustor at relatively low pressures, and the hot exhaust gases is prevented from entering the earth formation but is used to preheat the fuel and oxidant and water. The combustion process is isolated from the steam generation process. (DLC)

  16. Steam supply system for superposed turbine and process chamber, such as coal gasification

    SciTech Connect (OSTI)

    Menger, W.M.

    1986-08-26

    A steam supply system is described for a process chamber consuming superheated steam at a pressure of about 600 psi or below which is driven by a boiler operating at a pressure of about 2000 psi, a pressure range above that needed by the process chamber for also driving a superposed turbine. The system consists of: (a) a high pressure boiler feed pump for supplying highly purified water to the boiler; (b) a condensing reboiler connected to receive steam from the superposed turbine in a high pressure side; (c) the condensing reboiler also having a low pressure side, essentially isolated from fluid contact with the high pressure side, for receiving water for use in the lower operating pressure steam processes; (d) the condensing reboiler further comprising integral superheating means for heating the water received in the low pressure side into superheated low pressure steam with the steam received in the high pressure side; (e) means for conveying fluid from the high pressure side of the condensing reboiler to the boiler feed pump; and (f) means for conveying the low pressure superheated steam from the condensing reboiler to the process chamber.

  17. Analysis and decision document in support of acquisition of steam supply for the Hanford 200 Area

    SciTech Connect (OSTI)

    Brown, D.R.; Daellenbach, K.K.; Hendrickson, P.L.; Kavanaugh, D.C.; Reilly, R.W.; Shankle, D.L.; Smith, S.A.; Weakley, S.A.; Williams, T.A. ); Grant, T.F. )

    1992-02-01

    The US Department of Energy (DOE) is now evaluating its facility requirements in support of its cleanup mission at Hanford. One of the early findings is that the 200-Area steam plants, constructed in 1943, will not meet future space heating and process needs. Because the 200 Area will serve as the primary area for waste treatment and long-term storage, a reliable steam supply is a critical element of Hanford operations. This Analysis and Decision Document (ADD) is a preliminary review of the steam supply options available to the DOE. The ADD contains a comprehensive evaluation of the two major acquisition options: line-term versus privatization. It addresses the life-cycle costs associated with each alternative, as well as factors such as contracting requirements and the impact of market, safety, security, and regulatory issues. Specifically, this ADD documents current and future steam requirements for the 200 Area, describes alternatives available to DOE for meeting these requirements, and compares the alternatives across a number of decision criteria, including life-cycle cost. DOE has currently limited the ADD evaluation alternatives to replacing central steam plants rather than expanding the study to include alternative heat sources, such as a distributed network of boilers or heat pumps. Thirteen project alternatives were analyzed in the ADD. One of the alternatives was the rehabilitation of the existing 200-East coal-fired facility. The other twelve alternatives are combinations of (1) coal- or gas-fueled plants, (2) steam-only or cogeneration facilities, (3) primary or secondary cogeneration of electricity, and (4) public or private ownership.

  18. Supply Security in Future Nuclear Fuel Markets

    SciTech Connect (OSTI)

    Seward, Amy M.; Wood, Thomas W.; Gitau, Ernest T.; Ford, Benjamin E.

    2013-11-18

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs – that is, reactors likely to be licensed and market ready over the next several decades – that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  19. Los Alamos National Laboratory Steam Plant Project | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Solicitation Los Alamos National Laboratory Steam Plant Project Welcome to the National Nuclear Security Administration's website for the Los Alamos National Laboratory Site (LANL) M&O Energy Performance Saving Contract Competition. LANL is a premier national security research institution, located 35 miles northwest of Santa Fe, New Mexico, on 36 square miles of Department of Energy-owned property. Its mission is to develop and apply science and

  20. Steam Dryer Segmentation and Packaging at Grand Gulf Nuclear Station - 13577

    SciTech Connect (OSTI)

    Kreitman, Paul J.; Sirianni, Steve R.; Pillard, Mark M.

    2013-07-01

    Entergy recently performed an Extended Power Up-rate (EPU) on their Grand Gulf Nuclear Station, near Port Gibson, Mississippi. To support the EPU, a new Steam Dryer Assembly was installed during the last refueling outage. Due to limited access into the containment, the large Replacement Steam Dryer (RSD) had to be brought into the containment in pieces and then final assembly was completed on the refueling floor before installation into the reactor. Likewise, the highly contaminated Original Steam Dryer (OSD) had to be segmented into manageable sections, loaded into specially designed shielded containers, and rigged out of containment where they will be safely stored until final disposal is accomplished at an acceptable waste repository. Westinghouse Nuclear Services was contracted by Entergy to segment, package and remove the OSD from containment. This work was performed on critical path during the most recent refueling outage. The segmentation was performed underwater to minimize radiation exposure to the workers. Special hydraulic saws were developed for the cutting operations based on Westinghouse designs previously used in Sweden to segment ABB Reactor Internals. The mechanical cutting method was selected because of its proven reliability and the minimal cutting debris that is generated by the process. Maintaining stability of the large OSD sections during cutting was accomplished using a custom built support stand that was installed into the Moisture Separator Pool after the Moisture Separator was installed back in the reactor vessel. The OSD was then moved from the Steam Dryer Pool to the Moisture Separator Pool for segmentation. This scenario resolved the logistical challenge of having two steam dryers and a moisture separator in containment simultaneously. A water filtration/vacuum unit was supplied to maintain water clarity during the cutting and handling operations and to collect the cutting chips. (authors)

  1. High Temperature Steam Corrosion of Cladding for Nuclear Applications: Experimental

    SciTech Connect (OSTI)

    McHugh, Kevin M; Garnier, John E; Sergey Rashkeev; Michael V. Glazoff; George W. Griffith; Shannong M. Bragg-Sitton

    2013-01-01

    Stability of cladding materials under off-normal conditions is an important issue for the safe operation of light water nuclear reactors. Metals, ceramics, and metal/ceramic composites are being investigated as substitutes for traditional zirconium-based cladding. To support down-selection of these advanced materials and designs, a test apparatus was constructed to study the onset and evolution of cladding oxidation, and deformation behavior of cladding materials, under loss-of-coolant accident scenarios. Preliminary oxidation tests were conducted in dry oxygen and in saturated steam/air environments at 1000OC. Tube samples of Zr-702, Zr-702 reinforced with 1 ply of a ß-SiC CMC overbraid, and sintered a-SiC were tested. Samples were induction heated by coupling to a molybdenum susceptor inside the tubes. The deformation behavior of He-pressurized tubes of Zr-702 and SiC CMC-reinforced Zr-702, heated to rupture, was also examined.

  2. Nuclear energy is an important source of power, supplying 20

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

    energy is an important source of power, supplying 20 percent of the nation's electricity. More than 100 nuclear power plants are operating in the U.S., and countries around the world are implementing nuclear power as a carbon-free alternative to fossil fuels. We can maximize the climate and energy security benefits provided by responsible global nuclear energy expansion by developing options to increase the energy extracted from nuclear fuel, improve waste management, and strengthen nuclear

  3. maritime supply chain | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration (DOENNSA) and the U.K. Department of Energy and Climate Change concluded a workshop at Wilton Park, About This Site Budget IG Web Policy...

  4. Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

    2011-01-01

    Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

  5. Supply Chain Management Center | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Supply Chain Management Center

  6. Locating hot and cold-legs in a nuclear powered steam generation system

    DOE Patents [OSTI]

    Ekeroth, Douglas E.; Corletti, Michael M.

    1993-01-01

    A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

  7. Locating hot and cold-legs in a nuclear powered steam generation system

    DOE Patents [OSTI]

    Ekeroth, D.E.; Corletti, M.M.

    1993-11-16

    A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet. 2 figures.

  8. Quantitative assessment of proposals on assurance of nuclear fuel supply

    SciTech Connect (OSTI)

    Tanaka, T.; Kuno, Y.; Tanaka, S.

    2013-07-01

    The assurance of nuclear fuel supply has the potential to contribute to balancing peaceful use of nuclear power and nuclear nonproliferation. 5 proposals which provide the backup supply of the enrichment service in case of supply disruption, are investigated in this study. We investigated the 20 NPT countries which are non-nuclear-weapon states and possess operable commercial LWRs in October 2012 as potential participants for each proposal. As a result of literature researching, we have extracted factors that can be considered as important for a country to participate or not participate in the assurance of nuclear fuel supply. Then we have computed incentive and disincentive parameters for each country. The results show that the participation expectancy decreases in the order of IAEA Fuel Bank proposal, Russian LEU Reserve proposal, AFS proposal, WNA proposal and 6-Country proposal. The 'IAEA fuel bank proposal' would be triggered in case of the supply disruption which cannot be solved by the market mechanism and bilateral agreements.

  9. HEU Minimization and the Reliable Supply of Medical Isotopes Nuclear

    National Nuclear Security Administration (NNSA)

    Security Summit: Fact Sheet | National Nuclear Security Administration | (NNSA) HEU Minimization and the Reliable Supply of Medical Isotopes Nuclear Security Summit: Fact Sheet March 26, 2012 Molybdenum-99 (Mo-99) is used to produce technetium-99m (Tc-99m), a medical isotope that is used in about 100,000 diagnostic medical procedures globally every day. Today, Mo-99 is produced at aging facilities in Europe, Canada and South Africa primarily using highly-enriched uranium (HEU) - a

  10. " "," ",,," Steam Turbines Supplied by Either Conventional or Fluidized Bed Boilers",,,"Conventional Combusion Turbines with Heat Recovery",,,"Combined-Cycle Combusion Turbines",,,"Internal Combusion Engines with Heat Recovery",,," Steam Turbines Supplied by Heat Recovered from High-Temperature Processes",,,," "

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

    3 Relative Standard Errors for Table 8.3;" " Unit: Percents." " "," ",,," Steam Turbines Supplied by Either Conventional or Fluidized Bed Boilers",,,"Conventional Combusion Turbines with Heat Recovery",,,"Combined-Cycle Combusion Turbines",,,"Internal Combusion Engines with Heat Recovery",,," Steam Turbines Supplied by Heat Recovered from High-Temperature Processes",,,," " " "," "

  11. ,,,"with Any"," Steam Turbines Supplied by Either Conventional or Fluidized Bed Boilers",,,"Conventional Combusion Turbines with Heat Recovery",,,"Combined-Cycle Combusion Turbines",,,"Internal Combusion Engines with Heat Recovery",,," Steam Turbines Supplied by Heat Recovered from High-Temperature Processes",,,," "

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

    3 Relative Standard Errors for Table 8.3;" " Unit: Percents." ,,,"Establishments" ,,,"with Any"," Steam Turbines Supplied by Either Conventional or Fluidized Bed Boilers",,,"Conventional Combusion Turbines with Heat Recovery",,,"Combined-Cycle Combusion Turbines",,,"Internal Combusion Engines with Heat Recovery",,," Steam Turbines Supplied by Heat Recovered from High-Temperature Processes",,,," "

  12. Method and apparatus for steam mixing a nuclear fueled electricity generation system

    DOE Patents [OSTI]

    Tsiklauri, Georgi V.; Durst, Bruce M.

    1996-01-01

    A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs. Another benefit of the instant invention is the extension of plant life and the reduction of downtime due to refueling.

  13. New Y-12 Steam Plant On Line | National Nuclear Security Administratio...

    National Nuclear Security Administration (NNSA)

    Blog Home Field Offices Welcome to the NNSA Production Office NPO News Releases New Y-12 Steam Plant On Line New Y-12 Steam Plant On Line applicationmsword icon R-6-15...

  14. Main Generator Seal Oil Supply Reliability Improvements at Southern California Edison's San Onofre Nuclear Generating Station

    SciTech Connect (OSTI)

    Simma, Fred Y.; Chetwynd, Russell J.; Rowe, Stuart A.

    2006-07-01

    This paper presents the justification for the approach, details and results of the Main Generator Seal Oil System reliability enhancements on the San Onofre Nuclear Generating Station, SONGS. The SONGS, Unit 3 experienced substantial turbine damage in early 2001 after the turbine bearings lubrication oil supply failed. During a loss of off-site power incident, power was lost to the two AC powered turbine lubrication oil pumps due to a breaker failure in the switchgear and the DC powered emergency bearing lubricating oil pump failed to start due to a breaker trip. The SONGS turbine generators coasted down from full speed to a full stop without lubricating oil. This resulted in significant bearing, journal and steam path damage that required a four-month duration repair outage during a time period where electricity was in short supply in the State of California. The generator hydrogen sealing system remained operable during this event, however it was recognized during the event follow up investigation that this system had vulnerabilities to failure similar to the bearing lubrication system. In order to prevent a reoccurrence of this extremely costly event, SONGS has taken actions to modify both of these critical turbine generator systems by adding additional, continuously operating pumps with a new, independent power source and independently routed cables. The main challenge was to integrate the additional equipment into the existing lubrication and seal oil systems. The lubrication Oil System was the first system to be retro-fitted and these results already have been presented. Reference 2. This paper provides the result of the reliability enhancements for the Main Generator Seal Oil System, which concludes the turbine/generator critical oil systems reliability improvements, performed by SONGS. It is worth noting that the design team discovered and corrected a number of other significant operational issues, which had been present from the early days and also learned

  15. Y-12 donates school supplies to ADFAC | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) donates school supplies to ADFAC Monday, September 29, 2014 - 3:00pm Y-12ers donated more than $2,000 and numerous school supplies to ensure students in need have everything required to start the school year. Working with Aid to Distressed Families of Appalachian Counties (ADFAC), employees donated money along with 144 notebooks, 132 boxes of crayons, 111 packs of pencils, 80 reams of paper and 66 packs of glue sticks. "Employees once again shared their giving

  16. Redundancy of Supply in the International Nuclear Fuel Fabrication Market: Are Fabrication Services Assured?

    SciTech Connect (OSTI)

    Seward, Amy M.; Toomey, Christopher; Ford, Benjamin E.; Wood, Thomas W.; Perkins, Casey J.

    2011-11-14

    For several years, Pacific Northwest National Laboratory (PNNL) has been assessing the reliability of nuclear fuel supply in support of the U.S. Department of Energy/National Nuclear Security Administration. Three international low enriched uranium reserves, which are intended back up the existing and well-functioning nuclear fuel market, are currently moving toward implementation. These backup reserves are intended to provide countries credible assurance that of the uninterrupted supply of nuclear fuel to operate their nuclear power reactors in the event that their primary fuel supply is disrupted, whether for political or other reasons. The efficacy of these backup reserves, however, may be constrained without redundant fabrication services. This report presents the findings of a recent PNNL study that simulated outages of varying durations at specific nuclear fuel fabrication plants. The modeling specifically enabled prediction and visualization of the reactors affected and the degree of fuel delivery delay. The results thus provide insight on the extent of vulnerability to nuclear fuel supply disruption at the level of individual fabrication plants, reactors, and countries. The simulation studies demonstrate that, when a reasonable set of qualification criteria are applied, existing fabrication plants are technically qualified to provide backup fabrication services to the majority of the world's power reactors. The report concludes with an assessment of the redundancy of fuel supply in the nuclear fuel market, and a description of potential extra-market mechanisms to enhance the security of fuel supply in cases where it may be warranted. This report is an assessment of the ability of the existing market to respond to supply disruptions that occur for technical reasons. A forthcoming report will address political disruption scenarios.

  17. Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants

    SciTech Connect (OSTI)

    Woo, H.H.; Lu, S.C.

    1981-09-15

    Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

  18. Issues Associated with IAEA Involvement in Assured Nuclear Fuel Supply Arrangements

    SciTech Connect (OSTI)

    Kessler, Carol E.; Mathews, Carrie E.

    2008-02-08

    Assured nuclear fuel supply has been discussed at various times as a mechanism to help limit expansion of enrichment and reprocessing (E&R) capability beyond current technology holders. Given the events in the last few years in North Korea and Iran, concern over weapons capabilities gained from acquisition of E&R capabilities has heightened and brought assured nuclear fuel supply (AFS) again to the international agenda. Successful AFS programs can be valuable contributions to strengthening the nonproliferation regime and helping to build public support for expanding nuclear energy.

  19. New Y-12 Steam Plant On Line | National Nuclear Security Administratio...

    National Nuclear Security Administration (NNSA)

    "The new Y-12 steam plant is a clear demonstration of NNSA's commitment to being an effective steward of the taxpayer's money," said Gerald Talbot, NNSA Assistant Administrator for ...

  20. Multimegawatt space nuclear power supply, Phase 1 Final report

    SciTech Connect (OSTI)

    Not Available

    1989-02-17

    This Specification establishes the performance, design, development, and test requirements for the Boeing Multimegawatt Space Nuclear Power System (MSNPS). The Boeing Multimegawatt Space Power System is part of the DOE/SDIO Multimegawatt Space Nuclear Power Program. The purpose of this program is to provide a space-based nuclear power system to meet the needs of SDIO missions. The Boeing MSNPS is a category 1 concept which is capable of delivering 10's of MW(e) for 100's of seconds with effluent permitted. A design goal is for the system to have growth or downscale capability for other power system concepts. The growth objective is to meet the category 3 capability of 100's of MW(e) for 100's of seconds, also with effluent permitted. The purpose of this preliminary document is to guide the conceptual design effort throughout the Phase 1 study effort. This document will be updated through out the study. It will thus result in a record of the development of the design effort.

  1. US Central Station Nuclear Electric Generating Units: significant milestones. (Status as of April 1, 1980)

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    Construction and operational milestones are tabulated for US nuclear power plants. Data are presented on nuclear steam supply system orders. A schedule of commercial operation through 1990 is given.

  2. Fuzzy Logic Controller Architecture for Water Level Control in Nuclear Power Plant Steam Generator (SG) Using ANFIS Training Method

    SciTech Connect (OSTI)

    Vosoughi, Naser; Naseri, Zahra

    2002-07-01

    Since suitable control of water level can greatly enhance the operation of a power station, a Fuzzy logic controller architecture is applied to show desired control of the water level in a Nuclear steam generator. with regard to the physics of the system, it is shown that two inputs, a single output and the least number of rules (9 rules) are considered for a controller, and the ANFIS training method is employed to model functions in a controlled system. By using ANFIS training method, initial member functions will be trained and appropriate functions are generated to control water level inside the steam generators while using the stated rules. The proposed architecture can construct an input output mapping based on both human knowledge (in from of Fuzzy if then rules) and stipulated input output data. In this paper with a simple test it has been shown that the architecture fuzzy logic controller has a reasonable response to one step input at a constant power. Through computer simulation, it is found that Fuzzy logic controller is suitable, especially for the water level deviation and abrupt steam flow disturbances that are typical in the existing power plant. (authors)

  3. Secured electrical supply at least cost: Coal, gas, nuclear, hydro

    SciTech Connect (OSTI)

    Gavor, J.; Stary, O.; Vasicek, J.

    1995-12-01

    Electric power sector in East Central European countries finds in a difficult period. In the situation of demand stagnation, enormous investments must be realized in a very short time. Today`s decisions in the development strategy will influence the long term future of the industry. The optimal structure of the sources is one of the most important problem to be solved. Paper describes the current structure of the sources in electric power sector in the Czech Republic. The importance of coal, oil and gas, nuclear and hydro in electric power generation is compared. Taking into account the different position in the load coverage, economy of individual sources is evaluated and basic results of discounted cash flow calculations are presented. Information on specific investment programs and projects are included and further trends are estimated.

  4. Steam generator support system

    DOE Patents [OSTI]

    Moldenhauer, James E.

    1987-01-01

    A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances.

  5. Steam generator support system

    DOE Patents [OSTI]

    Moldenhauer, J.E.

    1987-08-25

    A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source is disclosed. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances. 4 figs.

  6. Steam cooling system for a gas turbine

    DOE Patents [OSTI]

    Wilson, Ian David; Barb, Kevin Joseph; Li, Ming Cheng; Hyde, Susan Marie; Mashey, Thomas Charles; Wesorick, Ronald Richard; Glynn, Christopher Charles; Hemsworth, Martin C.

    2002-01-01

    The steam cooling circuit for a gas turbine includes a bore tube assembly supplying steam to circumferentially spaced radial tubes coupled to supply elbows for transitioning the radial steam flow in an axial direction along steam supply tubes adjacent the rim of the rotor. The supply tubes supply steam to circumferentially spaced manifold segments located on the aft side of the 1-2 spacer for supplying steam to the buckets of the first and second stages. Spent return steam from these buckets flows to a plurality of circumferentially spaced return manifold segments disposed on the forward face of the 1-2 spacer. Crossover tubes couple the steam supply from the steam supply manifold segments through the 1-2 spacer to the buckets of the first stage. Crossover tubes through the 1-2 spacer also return steam from the buckets of the second stage to the return manifold segments. Axially extending return tubes convey spent cooling steam from the return manifold segments to radial tubes via return elbows.

  7. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers, Volumes 1, 2

    SciTech Connect (OSTI)

    Upadhyaya, Belle R.; Hines, J. Wesley; Lu, Baofu

    2005-06-03

    The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001 September 2004. Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance.Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. Development of advanced signal processing methods using

  8. Evaluation of the Effectiveness of a New Technology for Extraction of Insoluble Impurities from Nuclear Power Plant Steam Generators with Purge Water

    SciTech Connect (OSTI)

    Bud'ko, I. O.; Zhukov, A. G.

    2013-11-15

    An experimental technology for the removal of insoluble impurities from a horizontal steam generator with purge water during planned shutdowns of the power generating unit is improved through a more representative determination of the concentration of impurities in the purge water ahead of the water cleanup facility and a more precise effective time for the duration of the purge process. Tests with the improved technique at power generating unit No. 1 of the Rostov Nuclear Power Plant show that the efficiency with which insoluble impurities are removed from the steam generator volume was more than two orders of magnitude greater than under the standard regulations.

  9. District steam and the St. Louis steam loop

    SciTech Connect (OSTI)

    Tierney, T.M.; Sauer, H.J. Jr.

    1999-07-01

    Owned and operated by large public electric utilities, district steam systems flourished in most northern US cities in the first half of this century. Following World War II, however, district steam systems became minor and, in some cases, unprofitable portions of the utilities' operations. Consequently, public utilities ceased promoting district steam to existing and potential customers, leading to the decline of their use. In recent years, district steam systems have been revitalized by independent enterprises that have the commitment and expertise to make these systems once again reliable and cost-effective energy sources. This paper reports on one such system, The St. Louis Steam Loop. The St. Louis steam loop consists of 22 miles of insulated underground steam piping encompassing a 400-square block area in the city's downtown business district. The loop is supplied with steam by the Ashley Plant, which was built in 1904 for the St. Louis World's Fair. Due to the rising cost of oil, which has been used to fuel the Ashley Plant since 1972, and the subsequent loss of customers, many people considered the steam system a dinosaur in the jet age. In 1982, Trigen-St. Louis Energy Corporation purchased the steam system and embarked on an aggressive campaign to upgrade all aspects of the system, including valves, piping, and meters. In 1999, Trigen-St. Louis will install an ISMW state-of-the-art combustion turbine cogenerator to provide 95% of the steam to the steam loop. A primary reason for the St. Louis Steam Loop's longevity is that it has reliably supplied steam to many downtown buildings for the better part of the 20th century.

  10. Apparatus and methods of reheating gas turbine cooling steam and high pressure steam turbine exhaust in a combined cycle power generating system

    DOE Patents [OSTI]

    Tomlinson, Leroy Omar; Smith, Raub Warfield

    2002-01-01

    In a combined cycle system having a multi-pressure heat recovery steam generator, a gas turbine and steam turbine, steam for cooling gas turbine components is supplied from the intermediate pressure section of the heat recovery steam generator supplemented by a portion of the steam exhausting from the HP section of the steam turbine, steam from the gas turbine cooling cycle and the exhaust from the HP section of the steam turbine are combined for flow through a reheat section of the HRSG. The reheated steam is supplied to the IP section inlet of the steam turbine. Thus, where gas turbine cooling steam temperature is lower than optimum, a net improvement in performance is achieved by flowing the cooling steam exhausting from the gas turbine and the exhaust steam from the high pressure section of the steam turbine in series through the reheater of the HRSG for applying steam at optimum temperature to the IP section of the steam turbine.

  11. KEY DESIGN REQUIREMENTS FOR THE HIGH TEMPERATURE GAS-COOLED REACTOR NUCLEAR HEAT SUPPLY SYSTEM

    SciTech Connect (OSTI)

    L.E. Demick

    2010-09-01

    Key requirements that affect the design of the high temperature gas-cooled reactor nuclear heat supply system (HTGR-NHSS) as the NGNP Project progresses through the design, licensing, construction and testing of the first of a kind HTGR based plant are summarized. These requirements derive from pre-conceptual design development completed to-date by HTGR Suppliers, collaboration with potential end users of the HTGR technology to identify energy needs, evaluation of integration of the HTGR technology with industrial processes and recommendations of the NGNP Project Senior Advisory Group.

  12. On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers.

    SciTech Connect (OSTI)

    Belle R. Upadhyaya; J. Wesley Hines

    2004-09-27

    The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001-September 2004. (1) Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. (2) Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. (3) Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. (4) Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. (5) Development of advanced signal

  13. Liquid level, void fraction, and superheated steam sensor for nuclear-reactor cores. [PWR; BWR

    DOE Patents [OSTI]

    Tokarz, R.D.

    1981-10-27

    This disclosure relates to an apparatus for monitoring the presence of coolant in liquid or mixed liquid and vapor, and superheated gaseous phases at one or more locations within an operating nuclear reactor core, such as pressurized water reactor or a boiling water reactor.

  14. Supplying the nuclear arsenal: Production reactor technology, management, and policy, 1942--1992

    SciTech Connect (OSTI)

    Carlisle, R.P.; Zenzen, J.M.

    1994-01-01

    This book focuses on the lineage of America`s production reactors, those three at Hanford and their descendants, the reactors behind America`s nuclear weapons. The work will take only occasional sideways glances at the collateral lines of descent, the reactor cousins designed for experimental purposes, ship propulsion, and electric power generation. Over the decades from 1942 through 1992, fourteen American production reactors made enough plutonium to fuel a formidable arsenal of more than twenty thousand weapons. In the last years of that period, planners, nuclear engineers, and managers struggled over designs for the next generation of production reactors. The story of fourteen individual machines and of the planning effort to replace them might appear relatively narrow. Yet these machines lay at the heart of the nation`s nuclear weapons complex. The story of these machines is the story of arming the winning weapon, supplying the nuclear arms race. This book is intended to capture the history of the first fourteen production reactors, and associated design work, in the face of the end of the Cold War.

  15. Evaluation of a main steam line break with induced, multiple tube ruptures: A comparison of NUREG 1477 (Draft) and transient methodologies Palo Verde Nuclear Generating Station

    SciTech Connect (OSTI)

    Parrish, K.R.

    1995-09-01

    This paper presents the approach taken to analyze the radiological consequences of a postulated main steam line break event, with one or more tube ruptures, for the Palo Verde Nuclear Generating Station. The analysis was required to support the restart of PVNGS Unit 2 following the steam generator tube rupture event on March 14, 1993 and to justify continued operation of Units 1 and 3. During the post-event evaluation, the NRC expressed concern that Unit 2 could have been operating with degraded tubes and that similar conditions could exist in Units 1 and 3. The NRC therefore directed that a safety assessment be performed to evaluate a worst case scenario in which a non-isolable main steam line break occurs inducing one or more tube failures in the faulted steam generator. This assessment was to use the generic approach described in NUREG 1477, Voltage-Based Interim Plugging Criteria for Steam Generator Tubes - Task Group Report. An analysis based on the NUREG approach was performed but produced unacceptable results for off-site and control room thyroid doses. The NUREG methodology, however, does not account for plant thermal-hydraulic transient effects, system performance, or operator actions which could be credited to mitigate dose consequences. To deal with these issues, a more detailed analysis methodology was developed using a modified version of the Combustion Engineering Plant Analysis Code, which examines the dose consequences for a main steam line break transient with induced tube failures for a spectrum equivalent to 1 to 4 double ended guillotine U-tube breaks. By incorporating transient plant system responses and operator actions, the analysis demonstrates that the off-site and control room does consequences for a MSLBGTR can be reduced to acceptable limits. This analysis, in combination with other corrective and recovery actions, provided sufficient justification for continued operation of PVNGS Units 1 and 3, and for the subsequent restart of Unit 2.

  16. Ultra-High Temperature Steam Corrosion of Complex Silicates for Nuclear Applications: A Computational Study

    SciTech Connect (OSTI)

    Rashkeev, Sergey N.; Glazoff, Michael V.; Tokuhiro, Akira

    2014-01-01

    Stability of materials under extreme conditions is an important issue for safety of nuclear reactors. Presently, silicon carbide (SiC) is being studied as a cladding material candidate for fuel rods in boiling-water and pressurized water-cooled reactors (BWRs and PWRs) that would substitute or modify traditional zircaloy materials. The rate of corrosion of the SiC ceramics in hot vapor environment (up to 2200 degrees C) simulating emergency conditions of light water reactor (LWR) depends on many environmental factors such as pressure, temperature, viscosity, and surface quality. Using the paralinear oxidation theory developed for ceramics in the combustion reactor environment, we estimated the corrosion rate of SiC ceramics under the conditions representing a significant power excursion in a LWR. It was established that a significant time at least 100 h is required for a typical SiC braiding to significantly degrade even in the most aggressive vapor environment (with temperatures up to 2200 C) which is possible in a LWR at emergency condition. This provides evidence in favor of using the SiC coatings/braidings for additional protection of nuclear reactor rods against off-normal material degradation during power excursions or LOCA incidents. Additionally, we discuss possibilities of using other silica based ceramics in order to find materials with even higher corrosion resistance than SiC. In particular, we found that zircon (ZrSiO4) is also a very promising material for nuclear applications. Thermodynamic and first-principles atomic-scale calculations provide evidence of zircon thermodynamic stability in aggressive environments at least up to 1535 degrees C.

  17. Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan

    SciTech Connect (OSTI)

    J. K. Wright

    2010-09-01

    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. 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 (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. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Today’s high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760°C. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. 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 at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for

  18. Fluidized Bed Steam Reforming (FBSR) Mineralization for High Organic and Nitrate Waste Streams for the Global Nuclear Energy Partnership (GNEP)

    SciTech Connect (OSTI)

    Jantzen, C.M.; Williams, M.R. [Savannah River National Laboratory, Aiken, SC (United States)

    2008-07-01

    Waste streams that may be generated by the Global Nuclear Energy Partnership (GNEP) Advanced Energy Initiative may contain significant quantities of organics (0-53 wt%) and/or nitrates (0-56 wt%). Decomposition of high nitrate streams requires reducing conditions, e.g. organic additives such as sugar or coal, to reduce the NOx in the off-gas to N{sub 2} to meet the Clean Air Act (CAA) standards during processing. Thus, organics will be present during waste form stabilization regardless of which GNEP processes are chosen, e.g. organics in the feed or organics for nitrate destruction. High organic containing wastes cannot be stabilized with the existing HLW Best Developed Available Technology (BDAT) which is HLW vitrification (HLVIT) unless the organics are removed by preprocessing. Alternative waste stabilization processes such as Fluidized Bed Steam Reforming (FBSR) operate at moderate temperatures (650-750 deg. C) compared to vitrification (1150-1300 deg. C). FBSR converts organics to CAA compliant gases, creates no secondary liquid waste streams, and creates a stable mineral waste form that is as durable as glass. For application to the high Cs-137 and Sr-90 containing GNEP waste streams a single phase mineralized Cs-mica phase was made by co-reacting illite clay and GNEP simulated waste. The Cs-mica accommodates up to 30% wt% Cs{sub 2}O and all the GNEP waste species, Ba, Sr, Rb including the Cs-137 transmutation to Ba-137. For reference, the cesium mineral pollucite (CsAlSi{sub 2}O{sub 6}), currently being studied for GNEP applications, can only be fabricated at {>=}1000 deg. C. Pollucite mineralization creates secondary aqueous waste streams and NOx. Pollucite is not tolerant of high concentrations of Ba, Sr or Rb and forces the divalent species into different mineral host phases. The pollucite can accommodate up to 33% wt% Cs{sub 2}O. (authors)

  19. FLUIDIZED BED STEAM REFORMING MINERALIZATION FOR HIGH ORGANIC AND NITRATE WASTE STREAMS FOR THE GLOBAL NUCLEAR ENERGY PARTNERSHIP

    SciTech Connect (OSTI)

    Jantzen, C; Michael Williams, M

    2008-01-11

    Waste streams that may be generated by the Global Nuclear Energy Partnership (GNEP) Advanced Energy Initiative may contain significant quantities of organics (0-53 wt%) and/or nitrates (0-56 wt%). Decomposition of high nitrate streams requires reducing conditions, e.g. organic additives such as sugar or coal, to reduce the NO{sub x} in the off-gas to N{sub 2} to meet the Clean Air Act (CAA) standards during processing. Thus, organics will be present during waste form stabilization regardless of which GNEP processes are chosen, e.g. organics in the feed or organics for nitrate destruction. High organic containing wastes cannot be stabilized with the existing HLW Best Developed Available Technology (BDAT) which is HLW vitrification (HLVIT) unless the organics are removed by preprocessing. Alternative waste stabilization processes such as Fluidized Bed Steam Reforming (FBSR) operate at moderate temperatures (650-750 C) compared to vitrification (1150-1300 C). FBSR converts organics to CAA compliant gases, creates no secondary liquid waste streams, and creates a stable mineral waste form that is as durable as glass. For application to the high Cs-137 and Sr-90 containing GNEP waste streams a single phase mineralized Cs-mica phase was made by co-reacting illite clay and GNEP simulated waste. The Cs-mica accommodates up to 30% wt% Cs{sub 2}O and all the GNEP waste species, Ba, Sr, Rb including the Cs-137 transmutation to Ba-137. For reference, the cesium mineral pollucite (CsAlSi{sub 2}O{sub 6}), currently being studied for GNEP applications, can only be fabricated at {ge} 1000 C. Pollucite mineralization creates secondary aqueous waste streams and NO{sub x}. Pollucite is not tolerant of high concentrations of Ba, Sr or Rb and forces the divalent species into different mineral host phases. The pollucite can accommodate up to 33% wt% Cs{sub 2}O.

  20. High efficiency, quasi-instantaneous steam expansion device utilizing fossil or nuclear fuel as the heat source

    SciTech Connect (OSTI)

    Claudio Filippone, Ph.D.

    1999-06-01

    Thermal-hydraulic analysis of a specially designed steam expansion device (heat cavity) was performed to prove the feasibility of steam expansions at elevated rates for power generation with higher efficiency. The steam expansion process inside the heat cavity greatly depends on the gap within which the steam expands and accelerates. This system can be seen as a miniaturized boiler integrated inside the expander where steam (or the proper fluid) is generated almost instantaneously prior to its expansion in the work-producing unit. Relatively cold water is pulsed inside the heat cavity, where the heat transferred causes the water to flash to steam, thereby increasing its specific volume by a large factor. The gap inside the heat cavity forms a special nozzle-shaped system in which the fluid expands rapidly, accelerating toward the system outlet. The expansion phenomenon is the cause of ever-increasing fluid speed inside the cavity system, eliminating the need for moving parts (pumps, valves, etc.). In fact, the subsequent velocity induced by the sudden fluid expansion causes turbulent conditions, forcing accelerating Reynolds and Nusselt numbers which, in turn, increase the convective heat transfer coefficient. When the combustion of fossil fuels constitutes the heat source, the heat cavity concept can be applied directly inside the stator of conventional turbines, thereby greatly increasing the overall system efficiency.

  1. Vapor generator steam drum spray head

    DOE Patents [OSTI]

    Fasnacht, Jr., Floyd A.

    1978-07-18

    A typical embodiment of the invention provides a combination feedwater and "cooldown" water spray head that is centrally disposed in the lower portion of a nuclear power plant steam drum. This structure not only discharges the feedwater in the hottest part of the steam drum, but also increases the time required for the feedwater to reach the steam drum shell, thereby further increasing the feedwater temperature before it contacts the shell surface, thus reducing thermal shock to the steam drum structure.

  2. Rotating diffuser for pressure recovery in a steam cooling circuit of a gas turbine

    DOE Patents [OSTI]

    Eldrid, Sacheverel Q.; Salamah, Samir A.; DeStefano, Thomas Daniel

    2002-01-01

    The buckets of a gas turbine are steam-cooled via a bore tube assembly having concentric supply and spent cooling steam return passages rotating with the rotor. A diffuser is provided in the return passage to reduce the pressure drop. In a combined cycle system, the spent return cooling steam with reduced pressure drop is combined with reheat steam from a heat recovery steam generator for flow to the intermediate pressure turbine. The exhaust steam from the high pressure turbine of the combined cycle unit supplies cooling steam to the supply conduit of the gas turbine.

  3. Inspect and Repair Steam Traps, Energy Tips: STEAM, Steam Tip...

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

    ... There are four basic ways to test steam traps: temperature, sound, visual, and electronic. Recommended Steam Trap Testing Intervals * High-Pressure (150 psig and above): Weekly to ...

  4. Wet-steam erosion of steam turbine disks and shafts

    SciTech Connect (OSTI)

    Averkina, N. V.; Zheleznyak, I. V.; Kachuriner, Yu. Ya.; Nosovitskii, I. A.; Orlik, V. G.; Shishkin, V. I.

    2011-01-15

    A study of wet-steam erosion of the disks and the rotor bosses or housings of turbines in thermal and nuclear power plants shows that the rate of wear does not depend on the diagrammed degree of moisture, but is determined by moisture condensing on the surfaces of the diaphragms and steam inlet components. Renovating the diaphragm seals as an assembly with condensate removal provides a manifold reduction in the erosion.

  5. Personnel supply and demand issues in the nuclear power industry. Final report of the Nuclear Manpower Study Committee

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    The anticipated personnel needs of the nuclear power industry have varied widely in recent years, in response to both increasing regulatory requirements and declining orders for new plants. Recent employment patterns in the nuclear energy field, with their fluctuations, resemble those of defense industries more than those traditionally associated with electric utilities. Reactions to the accident at Three Mile Island Unit 2 by industry and regulators have increased the demand for trained and experienced personnel, causing salaries to rise. Industry, for example, has established several advisory organizations like the Institute for Nuclear Power Operations (INPO). At the same time, the US Nuclear Regulatory Commission (NRC) has imposed many new construction and operating requirements in an effort to take advantage of lessons learned from the Three Mile Island incident and to respond to the perceived public interest in better regulation of nuclear power. Thus, at present, utilities, architect-engineer firms, reactor vendors, and organizations in the nuclear development community have heavy workloads.

  6. Achieve Steam System Excellence- Steam Overview

    Broader source: Energy.gov [DOE]

    This fact sheet describes a steam systems approach to help companies operate and maintain their industrial steam plants and thermal manufacturing processes more efficiently.

  7. Steam separator latch assembly

    DOE Patents [OSTI]

    Challberg, Roy C.; Kobsa, Irvin R.

    1994-01-01

    A latch assembly removably joins a steam separator assembly to a support flange disposed at a top end of a tubular shroud in a nuclear reactor pressure vessel. The assembly includes an annular head having a central portion for supporting the steam separator assembly thereon, and an annular head flange extending around a perimeter thereof for supporting the head to the support flange. A plurality of latches are circumferentially spaced apart around the head flange with each latch having a top end, a latch hook at a bottom end thereof, and a pivot support disposed at an intermediate portion therebetween and pivotally joined to the head flange. The latches are pivoted about the pivot supports for selectively engaging and disengaging the latch hooks with the support flange for fixedly joining the head to the shroud or for allowing removal thereof.

  8. Steam separator latch assembly

    DOE Patents [OSTI]

    Challberg, R.C.; Kobsa, I.R.

    1994-02-01

    A latch assembly removably joins a steam separator assembly to a support flange disposed at a top end of a tubular shroud in a nuclear reactor pressure vessel. The assembly includes an annular head having a central portion for supporting the steam separator assembly thereon, and an annular head flange extending around a perimeter thereof for supporting the head to the support flange. A plurality of latches are circumferentially spaced apart around the head flange with each latch having a top end, a latch hook at a bottom end thereof, and a pivot support disposed at an intermediate portion therebetween and pivotally joined to the head flange. The latches are pivoted about the pivot supports for selectively engaging and disengaging the latch hooks with the support flange for fixedly joining the head to the shroud or for allowing removal thereof. 12 figures.

  9. Y-12 Steam Plant Project Received National Recognition for Project

    National Nuclear Security Administration (NNSA)

    Management Excellence | National Nuclear Security Administration | (NNSA) Steam Plant Project Received National Recognition for Project Management Excellence March 23, 2011 Y-12 steam plant project receives national recognition for project management excellence. Y-12's Steam Plant Life Extension Project (SPLE) has received the Secretary of Energy's Project Management Improvement Award. Microsoft Office document icon NR-03-28

  10. Steam Digest Volume IV

    SciTech Connect (OSTI)

    2004-07-01

    This edition of the Steam Digest is a compendium of 2003 articles on the technical and financial benefits of steam efficiency, presented by the stakeholders of the U.S. Department of Energy's BestPractices Steam effort.

  11. Cradle-to-Grave Nuclear Fuel Supply Assurance Workshop: Industrys Potential Role

    SciTech Connect (OSTI)

    Bengelsdorf, Harold; Hund, Gretchen; Kessler, Carol E.; Mahy, Heidi A.; McGoldrick, Fred; Seward, Amy M.

    2007-09-30

    The Pacific Northwest Center for Global Security hosted a workshop on June 6, 2007 in Washington D.C. to discuss the feasibility, merits and implications of the United States offering cradle-to-grave nuclear fuel cycle services to other countries. The workshop consisted of a small group of senior individuals from the private sector, government and the national laboratories. The workshop is summarized and recommendations given.

  12. Downhole steam generator having a downhole oxidant compressor

    DOE Patents [OSTI]

    Fox, R.L.

    1981-01-07

    Am improved apparatus is described for the downhole injection of steam into boreholes, for tertiary oil recovery. It includes an oxidant supply, a fuel supply, an igniter, a water supply, an oxidant compressor, and a combustor assembly. The apparatus is designed for efficiency, preheating of the water, and cooling of the combustion chamber walls. The steam outlet to the borehole is provided with pressure-responsive doors for closing the outlet in response to flameout. (DLC)

  13. Methods for disassembling, replacing and assembling parts of a steam cooling system for a gas turbine

    DOE Patents [OSTI]

    Wilson, Ian D.; Wesorick, Ronald R.

    2002-01-01

    The steam cooling circuit for a gas turbine includes a bore tube assembly supplying steam to circumferentially spaced radial tubes coupled to supply elbows for transitioning the radial steam flow in an axial direction along steam supply tubes adjacent the rim of the rotor. The supply tubes supply steam to circumferentially spaced manifold segments located on the aft side of the 1-2 spacer for supplying steam to the buckets of the first and second stages. Spent return steam from these buckets flows to a plurality of circumferentially spaced return manifold segments disposed on the forward face of the 1-2 spacer. Crossover tubes couple the steam supply from the steam supply manifold segments through the 1-2 spacer to the buckets of the first stage. Crossover tubes through the 1-2 spacer also return steam from the buckets of the second stage to the return manifold segments. Axially extending return tubes convey spent cooling steam from the return manifold segments to radial tubes via return elbows. The bore tube assembly, radial tubes, elbows, manifold segments and crossover tubes are removable from the turbine rotor and replaceable.

  14. Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies. Final report

    SciTech Connect (OSTI)

    Berg, R.; Stroinski, M.; Giachetti, R.

    1994-02-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant battery chargers, inverters and uninterruptible power supplies important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already, experienced) and aging management program activities to the more generic results and recommendations presented herein.

  15. Internal combustion engine injection superheated steam

    SciTech Connect (OSTI)

    Mahoney, F.G.

    1991-01-22

    This patent describes a method for introducing water vapor to the combustion chambers of an internal combustion engine. It comprises: introducing a metered amount of liquid water into a heat exchanger; contacting the heat exchanger directly with hot exhaust gases emanating from the exhaust manifold; maintaining the water in the heat exchanger for a period sufficient to vaporize the water into steam and superheat same; reducing pressure and increasing temperature to create superheated steam; introducing the superheated steam into the air supply proximate to the air induction system, upstream of any carburetion, of the internal combustion engine.

  16. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Brunswick Steam Electric Plant, Units 1 and 2

    SciTech Connect (OSTI)

    Selan, J.C.

    1982-04-26

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Brunswick Steam Electric Plant, Units 1 and 2. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources.

  17. High-temperature oxidation of Zircaloy in hydrogen-steam mixtures. [PWR; BWR

    SciTech Connect (OSTI)

    Chung, H.M.; Thomas, G.R.

    1982-09-01

    Oxidation rates of Zircaloy-4 cladding tubes have been measured in hydrogen-steam mixtures at 1200 to 1700/sup 0/C. For a given isothermal oxidation temperature, the oxide layer thicknesses have been measured as a function of time, steam supply rate, and hydrogen overpressure. The oxidation rates in the mixtures were compared with similar data obtained in pure steam and helium-steam environments under otherwise identical conditions. The rates in pure steam and helium-steam mixtures were equivalent and comparable to the parabolic rates obtained under steam-saturated conditions and reported in the literature. However, when the helium was replaced with hydrogen of equivalent partial pressure, a significantly smaller oxidation rate was observed. For high steam-supply rates, the oxidation kinetics in a hydrogen-steam mixture were parabolic, but the rate was smaller than for pure steam or helium-steam mixtures. Under otherwise identical conditions, the ratio of the parabolic rate for hydrogen-steam to that for pure steam decreased with increasing temperature and decreasing steam-supply rate.

  18. Steam Field | Open Energy Information

    Open Energy Info (EERE)

    Steam Field Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Print PDF Sanyal Temperature Classification: Steam Field Dictionary.png Steam Field: No definition has been...

  19. Steam Oxidation of Advanced Steam Turbine Alloys

    SciTech Connect (OSTI)

    Holcomb, Gordon R.

    2008-01-01

    Power generation from coal using ultra supercritical steam results in improved fuel efficiency and decreased greenhouse gas emissions. Results of ongoing research into the oxidation of candidate nickel-base alloys for ultra supercritical steam turbines are presented. Exposure conditions range from moist air at atmospheric pressure (650C to 800C) to steam at 34.5 MPa (650C to 760C). Parabolic scale growth coupled with internal oxidation and reactive evaporation of chromia are the primary corrosion mechanisms.

  20. Steam atmosphere drying exhaust steam recompression system

    DOE Patents [OSTI]

    Becker, F.E.; Smolensky, L.A.; Doyle, E.F.; DiBella, F.A.

    1994-03-08

    This invention relates to a heated steam atmosphere drying system comprising dryer in combination with an exhaust recompression system which is extremely energy efficient and eliminates dangers known to air dryers. The system uses superheated steam as the drying medium, which recirculates through the system where its heat of evaporation and heat of compression is recovered, thereby providing a constant source of heat to the drying chamber. The dryer has inlets whereby feedstock and superheated steam are fed therein. High heat transfer and drying rates are achieved by intimate contact of the superheated steam with the particles being dried. The dryer comprises a vessel which enables the feedstock and steam to enter and recirculate together. When the feedstock becomes dry it will exit the dryer with the steam and become separated from the steam through the use of a curvilinear louver separator (CLS). The CLS enables removal of fine and ultrafine particles from the dryer. Water vapor separated from the particles in the CLS as superheated steam, may then be recovered and recirculated as steam through the use of a compressor to either directly or indirectly heat the dryer, and a heat exchanger or a heater to directly provide heat to the dryer. This system not only provides a very efficient heat transfer system but results in a minimum carry-over of ultrafine particles thereby eliminating any explosive hazard. 17 figures.

  1. Steam atmosphere drying exhaust steam recompression system

    DOE Patents [OSTI]

    Becker, Frederick E.; Smolensky, Leo A.; Doyle, Edward F.; DiBella, Francis A.

    1994-01-01

    This invention relates to a heated steam atmosphere drying system comprising dryer in combination with an exhaust recompression system which is extremely energy efficient and eliminates dangers known to air dryers. The system uses superheated steam as the drying medium, which recirculated through the system where its heat of evaporation and heat of compression is recovered, thereby providing a constant source of heat to the drying chamber. The dryer has inlets whereby feedstock and superheated steam are fed therein. High heat transfer and drying rates are achieved by intimate contact of the superheated steam with the particles being dried The dryer comprises a vessel which enables the feedstock and steam to enter recirculate together. When the feedstock becomes dry it will exit the dryer with the steam and become separated from the steam through the use of a curvilinear louver separator (CLS). The CLS enables removal of fine and ultrafine particles from the dryer. Water vapor separated from the particles in the CLS as superheated steam, may then be recovered and recirculated as steam through the use of a compressor to either directly or indirectly heat the dryer, and a heat exchanger or a heater to directly provide heat to the dryer. This system not only provides a very efficient heat transfer system but results in a minimum carry-over of ultrafine particles thereby eliminating any explosive hazard.

  2. Examining Supply Chain Resilience for the Intermodal Shipment of Spent Nuclear Fuel and High Level Radioactive Materials

    SciTech Connect (OSTI)

    Peterson, Steven K

    2016-01-01

    The U.S. Department of Energy (DOE) has a significant programmatic interest in the safe and secure routing and transportation of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States, including shipments entering the country from locations outside U.S borders. In any shipment of SNF/HLW, there are multiple chains; a jurisdictional chain as the material moves between jurisdictions (state, federal, tribal, administrative), a physical supply chain (which mode), as well as a custody chain (which stakeholder is in charge/possession) of the materials being transported. Given these interconnected networks, there lies vulnerabilities, whether in lack of communication between interested stakeholders or physical vulnerabilities such as interdiction. By identifying key links and nodes as well as administrative weaknesses, decisions can be made to harden the physical network and improve communication between stakeholders. This paper examines the parallel chains of oversight and custody as well as the chain of stakeholder interests for the shipments of SNF/HLW and the potential impacts on systemic resiliency. Using the Crystal River shutdown location as well as a hypothetical international shipment brought into the United States, this paper illustrates the parallel chains and maps them out visually.

  3. Steam Technical Brief: Steam Pressure Reduction: Opportunities and Issues

    SciTech Connect (OSTI)

    2010-06-25

    A BestPractices Technical Brief describing industrial steam generation systems and opportunities for reducing steam system operating pressure.

  4. Customizing pays off in steam generators

    SciTech Connect (OSTI)

    Ganapathy, V. (ABCO Industries, Inc., Abilene, TX (United States))

    1995-01-01

    Packaged steam generators are the workhorses of chemical process plants, power plants and cogeneration systems. They are available as oil- or gas-fired models, and are used to generate either high-pressure superheated steam (400 to 1,200 psig, at 500 to 900 F) or saturated steam at low pressures (100 to 300 psig). In today's emission- and efficiency- conscious environment, steam generators have to be custom designed. Gone are the days when a boiler supplier--or for that matter an end user--could look up a model number from a list of standard sizes and select one for a particular need. Thus, before selecting a system, it is desirable to know the features of oil- and gas-fired steam generators, and the important variables that influence their selection, design and performance. It is imperative that all of these data are supplied to the boiler supplier so that the engineers may come up with the right design. Some of the parameters which are discussed in this paper are: duty, steam temperature, steam purity, emissions, and furnace design. Superheaters, economizers, and overall performance are also discussed.

  5. Downhole steam quality measurement

    DOE Patents [OSTI]

    Lee, David O.; Montoya, Paul C.; Muir, James F.; Wayland, Jr., J. Robert

    1987-01-01

    An empirical method for the remote sensing of steam quality that can be easily adapted to downhole steam quality measurements by measuring the electrical properties of two-phase flow across electrode grids at low frequencies.

  6. Steam Digest 2001

    SciTech Connect (OSTI)

    Not Available

    2002-01-01

    Steam Digest 2001 chronicles BestPractices Program's contributions to the industrial trade press for 2001, and presents articles that cover technical, financial and managerial aspects of steam optimization.

  7. Downhole steam quality measurement

    DOE Patents [OSTI]

    Lee, D.O.; Montoya, P.C.; Muir, J.F.; Wayland, J.R. Jr.

    1985-06-19

    The present invention relates to an empirical electrical method for remote sensing of steam quality utilizing flow-through grids which allow measurement of the electrical properties of a flowing two-phase mixture. The measurement of steam quality in the oil field is important to the efficient application of steam assisted recovery of oil. Because of the increased energy content in higher quality steam it is important to maintain the highest possible steam quality at the injection sandface. The effectiveness of a steaming operation without a measure of steam quality downhole close to the point of injection would be difficult to determine. Therefore, a need exists for the remote sensing of steam quality.

  8. Power with STEAM

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

    » Power with STEAM Power with STEAM ROSES outreach program inspires New Mexico African-American youth to envision themselves working as scientists and professionals August 18, 2016 Students at Power with STEAM 2016 The Lab's first Power with STEAM program event, held recently at the Bradbury Science Museum, brought students and some interns in the Los Alamos student programs together for fun and learning. Contacts Michelle B. Lee (505) 667-3624 Email Reaching out to New Mexico's

  9. Fuel cell integrated with steam reformer

    DOE Patents [OSTI]

    Beshty, Bahjat S. (Lower Makefield, PA); Whelan, James A. (Bricktown, NJ)

    1987-01-01

    A H.sub.2 -air fuel cell integrated with a steam reformer is disclosed wherein a superheated water/methanol mixture is fed to a catalytic reformer to provide a continuous supply of hydrogen to the fuel cell, the gases exhausted from the anode of the fuel cell providing the thermal energy, via combustion, for superheating the water/methanol mixture.

  10. RELAP5/MOD3 Analysis of Transient Steam-Generator Behavior During Turbine Trip Test of a Prototype Fast Breeder Reactor MONJU

    SciTech Connect (OSTI)

    Yoshihisa Shindo; Hiroshi Endo; Tomoko Ishizu; Kazuo Haga

    2006-07-01

    In order to develop a thermal-hydraulic model of the steam-generator (SG) to simulate transient phenomena in the sodium cooled fast breeder reactor (FBR) MONJU, Japan Nuclear Energy Safety Organization (JNES) verified the SG model using the RELAP5/MOD3 code against the results of the turbine trip test at a 40% power load of MONJU. The modeling by using RELAP5 was considered to explain the significant observed behaviors of the pressure and the temperature of the EV steam outlet, and the temperature of water supply distributing piping till 600 seconds after the turbine trip. The analysis results of these behaviors showed good agreement with the test results based on results of parameter study as the blow efficiency (release coef.) and heat transferred from the helical coil region to the down-comer (temperature heating down-comer tubes). It was found that the RELAP5/MOD3 code with a two-fluids model can predict well the physical situation: the gas-phase of steam generated by the decompression boiling moves upward in the down-comer tubes accompanied by the enthalpy increase of the water supply chambers; and that the pressure change of a 'shoulder' like shape is induced by the mass balance between the steam mass generated in the down-comer tubes and the steam mass blown from the SG. The applicability of RELAP5/MOD3 to SG modeling was confirmed by simulating the actual FBR system. (authors)

  11. Steam trap monitor

    DOE Patents [OSTI]

    Ryan, M.J.

    1987-05-04

    A steam trap monitor positioned downstream of a steam trap in a closed steam system includes a first sensor (a hot finger) for measuring the energy of condensate and a second sensor (a cold finger) for measuring the total energy of condensate and steam in the line. The hot finger includes one or more thermocouples for detecting condensate level and energy, while the cold finger contains a liquid with a lower boiling temperature than that of water. Vapor pressure from the liquid is used to do work such as displacing a piston or bellow in providing an indication of total energy (steam + condensate) of the system. Processing means coupled to and responsive to outputs from the hot and cold fingers subtracts the former from the latter to provide an indication of the presence of steam downstream from the trap indicating that the steam trap is malfunctioning. 2 figs.

  12. Heat recovery steam generator outlet temperature control system for a combined cycle power plant

    SciTech Connect (OSTI)

    Martens, A.; Myers, G.A.; McCarty, W.L.; Wescott, K.R.

    1986-04-01

    This patent describes a command cycle electrical power plant including: a steam turbine and at least one set comprising a gas turbine, an afterburner and a heat recovery steam generator having an attemperator for supplying from an outlet thereof to the steam turbine superheated steam under steam turbine operating conditions requiring predetermined superheated steam temperature, flow and pressure; with the gas turbine and steam turbine each generating megawatts in accordance with a plant load demand; master control means being provided for controlling the steam turbine and the heat recovery steam generator so as to establish the steam operating conditions; the combination of: first control means responsive to the gas inlet temperature of the heat recovery steam generator and to the plant load demand for controlling the firing of the afterburner; second control means responsive to the superheated steam predetermined temperature and to superheated steam temperature from the outlet for controlling the attemperator between a closed and an open position; the first and second control means being operated concurrently to maintain the superheated steam outlet temperature while controlling the load of the gas turbine independently of the steam turbine operating conditions.

  13. Geothermal Steam Power Plant | Open Energy Information

    Open Energy Info (EERE)

    Geothermal Steam Power Plant (Redirected from Dry Steam) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home General List of Dry Steam Plants List of Flash Steam Plants...

  14. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    SciTech Connect (OSTI)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  15. Downhole steam injector

    DOE Patents [OSTI]

    Donaldson, A. Burl; Hoke, Donald E.

    1983-01-01

    An improved downhole steam injector has an angled water orifice to swirl the water through the device for improved heat transfer before it is converted to steam. The injector also has a sloped diameter reduction in the steam chamber to throw water that collects along the side of the chamber during slant drilling into the flame for conversion to steam. In addition, the output of the flame chamber is beveled to reduce hot spots and increase efficiency, and the fuel-oxidant inputs are arranged to minimize coking.

  16. Benchmark the Fuel Cost of Steam Generation, Energy Tips: STEAM...

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

    5 Benchmark the Fuel Cost of Steam Generation Benchmarking the fuel cost of steam generation, in dollars per 1,000 pounds (1,000 lb) of steam, is an effective way to assess the ...

  17. Steam Technical Brief: Industrial Steam System Process-Control Schemes

    SciTech Connect (OSTI)

    2003-07-01

    This BestPractices Steam Technical Brief was developed to provide a basic understanding of the different process-control schemes used in a typical steam system.

  18. Los Alamos National Laboratory Steam Plant Project Usage Data | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) Usage Data 2 10_SMSI_SteamPlant_ThermalBasis of Analysis-Q1(011514) 2.10_SMSI_ApproxEst$Reconcile-Bechtel2009-SMSI-2013 2.10_SMSI_PipingAnnualR&R-Est_Rev122313 2.10_SMSI_Steam_CombinedEcon_011714_100%(Rev1) 2.10_SMSI_Steam_DistSystemOnlyEcon_011714_100% 2.10_SMSI_Steam_Option1-SteamCapitalEst(No-LANL$'s)_011714_100% 2.10_SMSI-Steam_Option2-HW-CapitalEst(No-LANL$'s)_011714_100% 131209XU50_XURP-LANL-Data_w-CostAlloc_CHP_121213 DOE Complex Experience

  19. Low chemical concentrating steam generating cycle

    DOE Patents [OSTI]

    Mangus, James D. (Greensburg, PA)

    1983-01-01

    A steam cycle for a nuclear power plant having two optional modes of operation. A once-through mode of operation uses direct feed of coolant water to an evaporator avoiding excessive chemical concentration buildup. A recirculation mode of operation uses a recirculation loop to direct a portion of flow from the evaporator back through the evaporator to effectively increase evaporator flow.

  20. Automated Diagnosis and Classification of Steam Generator Tube Defects

    SciTech Connect (OSTI)

    Dr. Gabe V. Garcia

    2004-10-01

    A major cause of failure in nuclear steam generators is tube degradation. Tube defects are divided into seven categories, one of which is intergranular attack/stress corrosion cracking (IGA/SCC). Defects of this type usually begin on the outer surface of the tubes and propagate both inward and laterally. In many cases these defects occur at or near the tube support plates. Several different methods exist for the nondestructive evaluation of nuclear steam generator tubes for defect characterization.

  1. Steam trap monitor

    DOE Patents [OSTI]

    Ryan, Michael J. (Plainfield, IL)

    1988-01-01

    A steam trap monitor positioned downstream of a steam trap in a closed steam system includes a first sensor (the combination of a hot finger and thermocouple well) for measuring the energy of condensate and a second sensor (a cold finger) for measuring the total energy of condensate and steam in the line. The hot finger includes one or more thermocouples for detecting condensate level and energy, while the cold finger contains a liquid with a lower boiling temperature than that of water. Vapor pressure from the liquid is used to do work such as displacing a piston or bellows in providing an indication of total energy (steam+condensate) of the system. Processing means coupled to and responsive to outputs from the thermocouple well hot and cold fingers subtracts the condensate energy as measured by the hot finger and thermocouple well from the total energy as measured by the cold finger to provide an indication of the presence of steam downstream from the trap indicating that the steam trap is malfunctioning.

  2. Ukraine Steam Partnership

    SciTech Connect (OSTI)

    Gurvinder Singh

    2000-02-15

    The Ukraine Steam Partnership program is designed to implement energy efficiency improvements in industrial steam systems. These improvements are to be made by the private plants and local government departments responsible for generation and delivery of energy to end-users. One of the activities planned under this program was to provide a two-day training workshop on industrial steam systems focusing on energy efficiency issues related to the generation, distribution, and consumption of steam. The workshop was geared towards plant managers, who are not only technically oriented, but are also key decision makers in their respective companies. The Agency for Rational Energy Use and Ecology (ARENA-ECO), a non-governmental, not-for-profit organization founded to promote energy efficiency and environmental protection in Ukraine, in conjunction with the Alliance staff in Kiev sent out invitations to potential participants in all the regions of Ukraine. The purpose of this report is the describe the proceedings from the workshop and provide recommendations from the workshop's roundtable discussion. The workshop was broken down into two main areas: (1) Energy efficient boiler house steam generation; and Energy efficient steam distribution and consumption. The workshop also covered the following topics: (1) Ukrainian boilers; (2) Water treatment systems; (3) A profile of UKRESCO (Ukrainian Energy Services Company); (4) Turbine expanders and electricity generation; (5) Enterprise energy audit basics; and (6) Experience of steam use in Donetsk oblast.

  3. Steam generator tube failures

    SciTech Connect (OSTI)

    MacDonald, P.E.; Shah, V.N.; Ward, L.W.; Ellison, P.G.

    1996-04-01

    A review and summary of the available information on steam generator tubing failures and the impact of these failures on plant safety is presented. The following topics are covered: pressurized water reactor (PWR), Canadian deuterium uranium (CANDU) reactor, and Russian water moderated, water cooled energy reactor (VVER) steam generator degradation, PWR steam generator tube ruptures, the thermal-hydraulic response of a PWR plant with a faulted steam generator, the risk significance of steam generator tube rupture accidents, tubing inspection requirements and fitness-for-service criteria in various countries, and defect detection reliability and sizing accuracy. A significant number of steam generator tubes are defective and are removed from service or repaired each year. This wide spread damage has been caused by many diverse degradation mechanisms, some of which are difficult to detect and predict. In addition, spontaneous tube ruptures have occurred at the rate of about one every 2 years over the last 20 years, and incipient tube ruptures (tube failures usually identified with leak detection monitors just before rupture) have been occurring at the rate of about one per year. These ruptures have caused complex plant transients which have not always been easy for the reactor operators to control. Our analysis shows that if more than 15 tubes rupture during a main steam line break, the system response could lead to core melting. Although spontaneous and induced steam generator tube ruptures are small contributors to the total core damage frequency calculated in probabilistic risk assessments, they are risk significant because the radionuclides are likely to bypass the reactor containment building. The frequency of steam generator tube ruptures can be significantly reduced through appropriate and timely inspections and repairs or removal from service.

  4. Steam System Survey Guide

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

    ... when compared to fuel-oil and natural-gas-fired boilers. ... form throughout the combustion and heat transfer processes. ... removal are steam jet ejectors and mechanical vacuum pumps. ...

  5. Steam Systems | Department of Energy

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

    Steam Systems Steam Systems Many manufacturing facilities can recapture energy by installing more efficient steam equipment and processes and applying energy management practices. Use the software tools, training, and publications listed below to optimize performance and save energy. Steam Tools Tools to assess your energy system: Steam System Modeler Qualified Specialists Qualified Specialists have passed a rigorous competency examination on a specific industrial system assessment tool. Locate

  6. Natural gas-assisted steam electrolyzer

    DOE Patents [OSTI]

    Pham, Ai-Quoc; Wallman, P. Henrik; Glass, Robert S.

    2000-01-01

    An efficient method of producing hydrogen by high temperature steam electrolysis that will lower the electricity consumption to an estimated 65 percent lower than has been achievable with previous steam electrolyzer systems. This is accomplished with a natural gas-assisted steam electrolyzer, which significantly reduces the electricity consumption. Since this natural gas-assisted steam electrolyzer replaces one unit of electrical energy by one unit of energy content in natural gas at one-quarter the cost, the hydrogen production cost will be significantly reduced. Also, it is possible to vary the ratio between the electricity and the natural gas supplied to the system in response to fluctuations in relative prices for these two energy sources. In one approach an appropriate catalyst on the anode side of the electrolyzer will promote the partial oxidation of natural gas to CO and hydrogen, called Syn-Gas, and the CO can also be shifted to CO.sub.2 to give additional hydrogen. In another approach the natural gas is used in the anode side of the electrolyzer to burn out the oxygen resulting from electrolysis, thus reducing or eliminating the potential difference across the electrolyzer membrane.

  7. Bore tube assembly for steam cooling a turbine rotor

    DOE Patents [OSTI]

    DeStefano, Thomas Daniel; Wilson, Ian David

    2002-01-01

    An axial bore tube assembly for a turbine is provided to supply cooling steam to hot gas components of the turbine wheels and return the spent cooling steam. A pair of inner and outer tubes define a steam supply passage concentric about an inner return passage. The forward ends of the tubes communicate with an end cap assembly having sets of peripheral holes communicating with first and second sets of radial tubes whereby cooling steam from the concentric passage is supplied through the end cap holes to radial tubes for cooling the buckets and return steam from the buckets is provided through the second set of radial tubes through a second set of openings of the end cap into the coaxial return passage. A radial-to-axial flow transitioning device, including anti-swirling vanes is provided in the end cap. A strut ring adjacent the aft end of the bore tube assembly permits axial and radial thermal expansion of the inner tube relative to the outer tube.

  8. Deaerators in Industrial Steam Systems - Steam Tip Sheet #18

    SciTech Connect (OSTI)

    2006-01-01

    This revised AMO tip sheet on deaerators in industrial steam systems provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  9. Inspect and Repair Steam Traps - Steam Tip Sheet #1

    SciTech Connect (OSTI)

    2012-01-31

    This revised AMO tip sheet on inspecting and repairing steam traps provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  10. Deaerators in Industrial Steam Systems - Steam Tip Sheet #18

    SciTech Connect (OSTI)

    2012-01-01

    This revised AMO tip sheet on deaerators in industrial steam systems provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  11. Los Alamos National Laboratory Steam Plant Project Reports and Analysis |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) Reports and Analysis 2.10_SMSI_LANL Steam Plant Analysis_Concepts_120313.pptx 2.10_SMSI-SteamPlant_100%Report_011714_Rev1.pdf Analysis of Alternatives LANL Utilities Division.pdf CHP vs DB Analysis.docx Comparison of Air Quality Permitting Impact of New CHP Plant vs Local Boilers.docx Comparison of CO2 Emissions and Water Consumption.docx History of Alternatives and Decisions.docx LANL STEAM PLANT REPORT FINAL 9-29 -Bechtel.pdf Parsons AOA

  12. Assessment of superheated steam drying of wood waste

    SciTech Connect (OSTI)

    Woods, B.G.; Nguyen, Y.; Bruce, S.

    1994-12-31

    A 5 MW co-generation facility using wood waste is described which will supply power to Ontario Hydro, steam to the sawmill for process heating, and hot water for district heating customers in the town. The use of superheated steam for drying the wood was investigated to determine the impact on boiler performance, the environmental impact and the economic feasibility. The main benefit with superheated steam drying is the reduction in VOC emissions. The capital cost is currently higher with superheated steam drying, but further investigation is warranted to determine if the cost reductions which could be achieved by manufacturing the major components in North America are sufficient to make the technology cost competitive.

  13. Energy Supply Transformation Needed

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

    Supply Transformation Needed - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced

  14. Optical wet steam monitor

    DOE Patents [OSTI]

    Maxey, L.C.; Simpson, M.L.

    1995-01-17

    A wet steam monitor determines steam particle size by using laser doppler velocimeter (LDV) device to produce backscatter light. The backscatter light signal is processed with a spectrum analyzer to produce a visibility waveform in the frequency domain. The visibility waveform includes a primary peak and a plurality of sidebands. The bandwidth of at least the primary frequency peak is correlated to particle size by either visually comparing the bandwidth to those of known particle sizes, or by digitizing the waveform and comparing the waveforms electronically. 4 figures.

  15. Optical wet steam monitor

    DOE Patents [OSTI]

    Maxey, Lonnie C.; Simpson, Marc L.

    1995-01-01

    A wet steam monitor determines steam particle size by using laser doppler velocimeter (LDV) device to produce backscatter light. The backscatter light signal is processed with a spectrum analyzer to produce a visibility waveform in the frequency domain. The visibility waveform includes a primary peak and a plurality of sidebands. The bandwidth of at least the primary frequency peak is correlated to particle size by either visually comparing the bandwidth to those of known particle sizes, or by digitizing the waveform and comparing the waveforms electronically.

  16. Simplifying steam trap selection

    SciTech Connect (OSTI)

    Debat, R.J. )

    1994-01-01

    In the current economic world order, there is an obligation to eliminate waste and conserve economic and natural resources. One trap blowing 100-lb of steam through a 1/4-in. orifice can cost more than $12,000 a year in wasted energy. Richard J. Debat of Armstrong International, Inc. explains the operating principles of the four basic types of steam traps as the first step in simplifying the selection process so the right trap can be specified for a given application.

  17. Deaerators in Industrial Steam Systems

    SciTech Connect (OSTI)

    Not Available

    2006-01-01

    This revised ITP tip sheet on deaerators in industrial steam systems provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  18. Inspect and Repair Steam Traps

    SciTech Connect (OSTI)

    Not Available

    2006-01-01

    This revised ITP tip sheet on inspecting and repairing steam traps provide how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  19. Downhole steam generator with improved preheating, combustion and protection features

    DOE Patents [OSTI]

    Fox, Ronald L.

    1983-01-01

    An apparatus for generation of steam in a borehole for penetration into an earth formation wherein feedback preheater means are provided for the fuel and water before entering the combustor assembly. First, combustion gases are conducted from the combustion chamber to locations in proximity to the water and fuel supplies. Secondly, both hot combustion gases and steam are conducted from the borehole back to the water and fuel supply. The water used for conversion to steam is passed in a countercurrent manner through a plurality of annular water flow channels surrounding the combustion chamber. In this manner, the water is preheated, and the combustion chamber is cooled simultaneously, thereby minimizing thermal stresses and deterioration of the walls of the combustion chamber. The water is injected through slotted inlets along the combustion chamber wall to provide an unstable boundary layer and stripping of the water from the wall for efficient steam generation. Pressure responsive doors are provided at the steam outlet of the combustor assembly. The outlet doors and fluid flow functions may be controlled by a diagnostic/control module. The module is positioned in the water flow channel to maintain a relatively constant, controlled temperature.

  20. Water cooled steam jet

    DOE Patents [OSTI]

    Wagner, Jr., Edward P.

    1999-01-01

    A water cooled steam jet for transferring fluid and preventing vapor lock, or vaporization of the fluid being transferred, has a venturi nozzle and a cooling jacket. The venturi nozzle produces a high velocity flow which creates a vacuum to draw fluid from a source of fluid. The venturi nozzle has a converging section connected to a source of steam, a diffuser section attached to an outlet and a throat portion disposed therebetween. The cooling jacket surrounds the venturi nozzle and a suction tube through which the fluid is being drawn into the venturi nozzle. Coolant flows through the cooling jacket. The cooling jacket dissipates heat generated by the venturi nozzle to prevent vapor lock.

  1. Water cooled steam jet

    DOE Patents [OSTI]

    Wagner, E.P. Jr.

    1999-01-12

    A water cooled steam jet for transferring fluid and preventing vapor lock, or vaporization of the fluid being transferred, has a venturi nozzle and a cooling jacket. The venturi nozzle produces a high velocity flow which creates a vacuum to draw fluid from a source of fluid. The venturi nozzle has a converging section connected to a source of steam, a diffuser section attached to an outlet and a throat portion disposed there between. The cooling jacket surrounds the venturi nozzle and a suction tube through which the fluid is being drawn into the venturi nozzle. Coolant flows through the cooling jacket. The cooling jacket dissipates heat generated by the venturi nozzle to prevent vapor lock. 2 figs.

  2. Steam System Survey Guide | Department of Energy

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

    Survey Guide Steam System Survey Guide This guide provides technical information for steam system operational personnel and plant energy managers on some of the major opportunities available to improve the energy efficiency and productivity of industrial steam systems. The guide covers five main areas of investigation: (1) profiling a steam system, (2) identifying steam properties for the steam system, (3) improving boiler operations, (4) improving resource utilization in the steam system, and

  3. Nuclear plant-aging research on reactor protection systems

    SciTech Connect (OSTI)

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

  4. Steam Technical Brief: Industrial Steam System Heat-Transfer Solutions

    SciTech Connect (OSTI)

    2010-06-25

    This BestPractices Steam Technical Brief provides an overview of considerations for selecting the best heat-transfer solution for various applications.

  5. Process for purifying geothermal steam

    DOE Patents [OSTI]

    Li, C.T.

    Steam containing hydrogen sulfide is purified and sulfur recovered by passing the steam through a reactor packed with activated carbon in the presence of a stoichiometric amount of oxygen which oxidizes the hydrogen sulfide to elemental sulfur which is adsorbed on the bed. The carbon can be recycled after the sulfur has been recovered by vacuum distillation, inert gas entrainment or solvent extraction. The process is suitable for the purification of steam from geothermal sources which may also contain other noncondensable gases.

  6. Process for purifying geothermal steam

    DOE Patents [OSTI]

    Li, Charles T.

    1980-01-01

    Steam containing hydrogen sulfide is purified and sulfur recovered by passing the steam through a reactor packed with activated carbon in the presence of a stoichiometric amount of oxygen which oxidizes the hydrogen sulfide to elemental sulfur which is adsorbed on the bed. The carbon can be recycled after the sulfur has been recovered by vacuum distillation, inert gas entrainment or solvent extraction. The process is suitable for the purification of steam from geothermal sources which may also contain other noncondensable gases.

  7. Steam Pressure Reduction: Opportunities and Issues; A BestPractices Steam Technical Brief

    SciTech Connect (OSTI)

    Not Available

    2005-11-01

    A BestPractices Technical Brief describing industrial steam generation systems and opportunities for reducing steam system operating pressure.

  8. Downhole steam injector. [Patent application

    SciTech Connect (OSTI)

    Donaldson, A.B.; Hoke, E.

    1981-06-03

    An improved downhole steam injector has an angled water orifice to swirl the water through the device for improved heat transfer before it is converted to steam. The injector also has a sloped diameter reduction in the steam chamber to throw water that collects along the side of the chamber during slant drilling into the flame for conversion to steam. In addition, the output of the flame chamber is beveled to reduce hot spots and increase efficiency, and the fuel-oxidant inputs are arranged to minimize coking.

  9. Deaerators in Industrial Steam Systems

    Broader source: Energy.gov [DOE]

    This tip sheet on deaerators provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  10. Power supply

    DOE Patents [OSTI]

    Yakymyshyn, Christopher Paul; Hamilton, Pamela Jane; Brubaker, Michael Allen

    2007-12-04

    A modular, low weight impedance dropping power supply with battery backup is disclosed that can be connected to a high voltage AC source and provide electrical power at a lower voltage. The design can be scaled over a wide range of input voltages and over a wide range of output voltages and delivered power.

  11. Flow Characteristics Analysis of Widows' Creek Type Control Valve for Steam Turbine Control

    SciTech Connect (OSTI)

    Yoo, Yong H.; Sohn, Myoung S.; Suh, Kune Y.

    2006-07-01

    The steam turbine converts the kinetic energy of steam to mechanical energy of rotor blades in the power conversion system of fossil and nuclear power plants. The electric output from the generator of which the rotor is coupled with that of the steam turbine depends on the rotation velocity of the steam turbine bucket. The rotation velocity is proportional to the mass flow rate of steam entering the steam turbine through valves and nozzles. Thus, it is very important to control the steam mass flow rate for the load following operation of power plants. Among various valves that control the steam turbine, the control valve is most significant. The steam flow rate is determined by the area formed by the stem disk and the seat of the control valve. While the ideal control valve linearly controls the steam mass flow rate with its stem lift, the real control valve has various flow characteristic curves pursuant to the stem lift type. Thus, flow characteristic curves are needed to precisely design the control valves manufactured for the operating conditions of nuclear power plants. OMEGA (Optimized Multidimensional Experiment Geometric Apparatus) was built to experimentally study the flow characteristics of steam flowing inside the control valve. The Widows' Creek type control valve was selected for reference. Air was selected as the working fluid in the OMEGA loop to exclude the condensation effect in this simplified approach. Flow characteristic curves were plotted by calculating the ratio of the measured mass flow rate versus the theoretical mass flow rate of the air. The flow characteristic curves are expected to be utilized to accurately design and operate the control valve for fossil as well as nuclear plants. (authors)

  12. Steam Digest 2001: Office of Industrial Technologies

    SciTech Connect (OSTI)

    None, None

    2002-01-01

    Steam Digest 2001 chronicles Best Practices Program's contributions to the industrial trade press for 2001, and presents articles that cover technical, financial and managerial aspects of steam optimization.

  13. Steam-system upgrades | Open Energy Information

    Open Energy Info (EERE)

    upgrades Jump to: navigation, search TODO: Add description List of Steam-system upgrades Incentives Retrieved from "http:en.openei.orgwindex.php?titleSteam-systemupgrades&old...

  14. Standard Steam Trust LLC | Open Energy Information

    Open Energy Info (EERE)

    (Redirected from Standard Steam Trust) Jump to: navigation, search Name: Standard Steam Trust LLC Place: Denver, Colorado Sector: Geothermal energy Product: Subsidiary of...

  15. Benchmark the Fuel Cost of Steam Generation

    Broader source: Energy.gov [DOE]

    This tip sheet on benchmarking the fuel cost of steam provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  16. Steam boosted internal combustion engine

    SciTech Connect (OSTI)

    Green, M.A.

    1987-01-20

    A device is described to supplement the power produced by burning fuel in an internal combustion engine with steam, the device comprising: a means for producing a constant flow of water past a boiler means; a means for allowing the water to flow in the direction of the boiler; a boiler means external to the internal combustion engine to convert the water into superheated steam; a means for controlling the pressure of the water such that the water pressure is greater than the pressure of the steam produced by the boiler; and a means for injection of the superheated steam directly into a cylinder of the internal combustion engine, a means for producing a constant flow of water at a pressure greater than the pressure of the superheated steam, wherein the constant flow means at greater pressure comprises a chamber with a gaseous component, with the gaseous component being of constant volume and exerting constant pressure upon water within the chamber.

  17. The EURATOM Supply Agency

    SciTech Connect (OSTI)

    Lightner, J.

    1989-11-01

    With the coming liberalization of trade and industry within the European Community (EC) and a more centrally-coordinated EC external trade policy, it is timely to ask if in the 1990s there will be any significant changes in the commercial relations between the EC and non-EC companies trading in nuclear fuel. The key vehicle for implementing any change of policy would probably be the European Atomic Energy Community (EURATOM) Supply Agency in Brussels, which is charged under the EURATOM Treaty with overseeing the equitable supply of nuclear fuel to and among EC companies. The EURATOM Supply Agency (the Agency) is a signatory to almost all EC-company contracts for transactions that occur on the territory of the Community, which includes Belgium, Denmark, France, the Federal Republic of Germany (FRG), Great Britain, Greece, Ireland, Italy, Luxembourg, the Netherlands, Portugal, and Spain. During the 1980s, the Supply Agency has rarely tried to influence the commercial decisions of EC member companies. The nuclear fuel industry has largely perceived the Agency as an administrative office that registers contracts and maintains relations with some outside governments, particularly Australia, Canada, and the USA. However, in 1988 the Agency began to have a more direct commercial impact when it reviewed the practice-previously conducted routinely by the EURATOM Safeguards Directorate in Luxembourg at the request of EC-member companies-of swapping safeguards obligations on equivalent quantities of uranium at different locations (flag swapping). The Agency`s actions inhibiting flag swaps, as well as a related de facto policy restricting material swaps of Southern African uranium, caused it to be viewed as obstructive by some EC companies. During 1989 the discussion about flag swaps and swaps involving South African and Namibian uranium has subsided, and a far-reaching discussion has arisen about EC trade policy in general.

  18. nuclear

    National Nuclear Security Administration (NNSA)

    2%2A en U.S-, Japan Exchange Best Practices on Nuclear Emergency Response http:nnsa.energy.govmediaroompressreleasesu.s-japan-exchange-best-practices-nuclear-emergency-respon...

  19. Power supply

    DOE Patents [OSTI]

    Hart, Edward J.; Leeman, James E.; MacDougall, Hugh R.; Marron, John J.; Smith, Calvin C.

    1976-01-01

    An electric power supply employs a striking means to initiate ferroelectric elements which provide electrical energy output which subsequently initiates an explosive charge which initiates a second ferroelectric current generator to deliver current to the coil of a magnetic field current generator, creating a magnetic field around the coil. Continued detonation effects compression of the magnetic field and subsequent generation and delivery of a large output current to appropriate output loads.

  20. ULTRA-SUPERCRITICAL STEAM CORROSION

    SciTech Connect (OSTI)

    Holcomb, G.R.; Alman, D.E.; Bullard, S.B.; Covino, B.S., Jr.; Cramer, S.D.; Ziomek-Moroz, M.

    2003-04-22

    Efficiency increases in fossil energy boilers and steam turbines are being achieved by increasing the temperature and pressure at the turbine inlets well beyond the critical point of water. To allow these increases, advanced materials are needed that are able to withstand the higher temperatures and pressures in terms of strength, creep, and oxidation resistance. As part of a larger collaborative effort, the Albany Research Center (ARC) is examining the steam-side oxidation behavior for ultrasupercritical (USC) steam turbine applications. Initial tests are being done on six alloys identified as candidates for USC steam boiler applications: ferritic alloy SAVE12, austenitic alloy Super 304H, the high Cr-high Ni alloy HR6W, and the nickel-base superalloys Inconel 617, Haynes 230, and Inconel 740. Each of these alloys has very high strength for its alloy type. Three types of experiments are planned: cyclic oxidation in air plus steam at atmospheric pressure, thermogravimetric ana lysis (TGA) in steam at atmospheric pressure, and exposure tests in supercritical steam up to 650 C (1202 F) and 34.5 MPa (5000 psi). The atmospheric pressure tests, combined with supercritical exposures at 13.8, 20.7, 24.6, and 34.5 MPa (2000, 3000, 4000, and 5000 psi) should allow the determination of the effect of pressure on the oxidation process.

  1. Pebble Bed Boiling Water Reactor Concept With Superheated Steam

    SciTech Connect (OSTI)

    Tsiklauri, G.; Newman, D.; Meriwether, G.; Korolev, V. [Pacific Northwest National Laboratory, P.O. Box 999 Richland, WA 99352 (United States)

    2002-07-01

    An Advanced Nuclear Reactor concept is presented which extends Boiling Water Reactor technology with micro-fuel elements (MFE) and produces superheated steam. A nuclear plant with MFE is highly efficient and safe, due to ceramic-clad nuclear fuel. Water is used as both moderator and coolant. The fuel consists of spheres of about 1.5 mm diameter of UO{sub 2} with several external coatings of different carbonaceous materials. The outer coating of the particles is SiC, manufactured with chemical vapor disposition (CVD) technology. Endurance of the integrity of the SiC coating in water, air and steam has been demonstrated experimentally in Germany, Russia and Japan. This paper describes a result of a preliminary design and analysis of 3750 MWt (1500 MWe) plant with standard pressure of 16 MPa, which is widely achieved in the vessel of pressurized-water type reactors. The superheated steam outlet temperature of 550 deg. C elevates the steam cycle to high thermal efficiency of 42%. (authors)

  2. Use Steam Jet Ejectors or Thermocompressors to Reduce Venting of

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

    Low-Pressure Steam | Department of Energy Steam Jet Ejectors or Thermocompressors to Reduce Venting of Low-Pressure Steam Use Steam Jet Ejectors or Thermocompressors to Reduce Venting of Low-Pressure Steam This tip sheet on steam jet ejectors and thermocompressors provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies. STEAM TIP SHEET #29 Use Steam Jet Ejectors or Thermocompressors to Reduce Venting of Low-Pressure Steam (January 2012)

  3. TRANSISTOR HIGH VOLTAGE POWER SUPPLY

    DOE Patents [OSTI]

    Driver, G.E.

    1958-07-15

    High voltage, direct current power supplies are described for use with battery powered nuclear detection equipment. The particular advantages of the power supply described, are increased efficiency and reduced size and welght brought about by the use of transistors in the circuit. An important feature resides tn the employment of a pair of transistors in an alternatefiring oscillator circuit having a coupling transformer and other circuit components which are used for interconnecting the various electrodes of the transistors.

  4. Minimize Boiler Blowdown, Energy Tips: STEAM, Steam Tip Sheet...

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

    may lead to carryover of boiler water into the steam, or the formation of deposits. ... 108,696 - 106,383 2,313 lbhr Enthalpy of Boiler Water 338.5 Btulb; for ...

  5. Steam reformer with catalytic combustor

    DOE Patents [OSTI]

    Voecks, Gerald E.

    1990-03-20

    A steam reformer is disclosed having an annular steam reforming catalyst bed formed by concentric cylinders and having a catalytic combustor located at the center of the innermost cylinder. Fuel is fed into the interior of the catalytic combustor and air is directed at the top of the combustor, creating a catalytic reaction which provides sufficient heat so as to maintain the catalytic reaction in the steam reforming catalyst bed. Alternatively, air is fed into the interior of the catalytic combustor and a fuel mixture is directed at the top. The catalytic combustor provides enhanced radiant and convective heat transfer to the reformer catalyst bed.

  6. Trends in packaged steam generators

    SciTech Connect (OSTI)

    Ganapathy, V. [ABCO Industries, Abilene, TX (United States)

    1996-09-01

    Oil and gas-fired packaged steam generators are used in many industrial plants. They generate saturated or superheated steam up to 250,000 lb/hr, 1000 psig, and 950 F. They may be used for continuous steam generation or as standby boilers in cogeneration systems. Numerous variables affect the design of this equipment. A few important considerations should be addressed at an early point by the plant engineer specifying or evaluating equipment options. These considerations include trends such as customized designs that minimize operating costs and ensure emissions regulations are met. The paper discusses efficiency considerations first.

  7. Development and Transient Analysis of a Helical-coil Steam Generator for High Temperature Reactors

    SciTech Connect (OSTI)

    Nathan V. Hoffer; Nolan A. Anderson; Piyush Sabharwall

    2011-08-01

    A high temperature gas-cooled reactor (HTGR) is under development by the Next Generation Nuclear Plant (NGNP) Project at the Idaho National Laboratory (INL). Its design emphasizes electrical power production which may potentially be coupled with process heat for hydrogen production and other industrial applications. NGNP is considering a helical-coil steam generator for the primary heat transport loop heat exchanger based on its increased heat transfer and compactness when compared to other steam generators. The safety and reliability of the helical-coil steam generator is currently under evaluation as part of the development of NGNP. Transients, such as loss of coolant accidents (LOCA), are of interest in evaluating the safety of steam generators. In this study, a complete steam generator inlet pipe break (double ended pipe break) LOCA was simulated by an exponential loss of primary side pressure. For this analysis, a model of the helical-coil steam generator was developed using RELAP5-3D, an INL inhouse systems analysis code. The steam generator model behaved normally during the transient simulating the complete steam generator inlet pipe break LOCA. Further analysis is required to comprehensively evaluate the safety and reliability of the helical-coil steam generator design in the NGNP setting.

  8. Potential failure of steam generator tubes following a station blackout

    SciTech Connect (OSTI)

    Ward, L.W.; Palmrose, D.E.

    1994-12-31

    The U.S. Nuclear Regulatory Commission is considering changes to pressurized water reactor (PWR) requirements relating to steam generator tube plugging and repair criteria, including leakage monitoring. The proposed changes are known as the alternate tube plugging criteria (APC) and are intended to permit PWRs to operate with through-wall cracks in steam generator tubes subject to meeting a specified limit on predicted primary to secondary leakage under accident conditions. To assess the consequences of the alternate plugging criteria, analyses were performed for a station blackout sequence in which the reactor core melts while the reactor coolant system (RCS) remains at high pressure. Evaluations were conducted to investigate the potential for tube failure with and without secondary system depressurization. The excessive heat coupled with the high-pressure differentials across the steam generator tubes could result in creep rupture failure of the tubes during a severe accident, which could lead to a radiological release directly to the environment. In order to assess the safety significance of the APC, it is important to identify the level of steam generator tube leakage that can occur without challenging the previous study conclusions that steam generator creep failure will not occur prior to a surge line or hot-leg failure. To assess the effect of leakage on steam generator tube integrity during a core melt sequence with the RCS at high pressure and the secondary side of the steam generators pressurized and depressurized, an analysis was performed for a core melt event resulting from an unmitigated station blackout to identify the total steamenerator and tube leakage flow rates that could induce tube ruptures prior to other RCS boudary faliures that could depressurize the RCS.

  9. Guide to Orifice Plate Steam Traps

    SciTech Connect (OSTI)

    Oland, C.B.

    2001-01-11

    This guide was prepared to serve as a foundation for making informed decisions about when orifice plate steam traps should be considered for use in new or existing steam systems. It presents background information about different types of steam traps and defines their unique functional and operational characteristics. The advantages and disadvantages associated with using orifice plate steam traps are provided to highlight their capabilities and limitations. Finally, recommendations for using orifice plate steam traps are presented, and possible applications are identified.

  10. Steam System Modeler | Department of Energy

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

    Steam System Modeler Steam System Modeler April 17, 2014 - 11:34am Addthis There is often flexibility in the operational conditions and requirements of any steam system. In order to optimize performance, the impacts of potential adjustments need to be understood individually and collectively. The Steam System Modeler allows you to create up to a 3-pressure-header basic model of your current steam system. A second model can then be created by adjusting a series of characteristics simulating

  11. Thermostatic steam trap

    SciTech Connect (OSTI)

    Anderson, A.H.; Mac Nicol, A.E.

    1987-03-03

    A thermostatic trap is described for a heating system having a feed pipe connected to a source of steam and a discharge pipe for discharge of condensate and comprising: housing means defining a volume and comprising a bowl shaped body, a removable cover therefor, a housing inlet pipe portion projecting from a side wall portion of the body and adapted for connection to the discharge pipe. A housing outlet pipe portion projects from a bottom wall portion of the body, and an outlet orifice defined by the bottom wall portion and extends between the volume and the outlet pipe portion; a valve body means retained within the volume and comprising an end wall, a side wall and a retaining ring portion that together define a valve chamber. The end wall defines a valve inlet opening communicating with the chamber and an annular valve seat within the chamber and encircling the valve inlet opening. The valve body means comprises a valve outlet pipe that defines a valve outlet opening axially aligned with the valve inlet opening and communicating with the chamber, the outlet pipe being fixed in the outlet orifice; a resilient, annular seal means disposed within the valve chamber and encircling the valve inlet opening; and a bi-metallic disc disposed within the valve chamber between the annular seal means and the outlet opening and having an outer peripheral portion retained by the retaining ring portion of the valve body means.

  12. Steam reforming catalyst

    DOE Patents [OSTI]

    Kramarz, Kurt W.; Bloom, Ira D.; Kumar, Romesh; Ahmed, Shabbir; Wilkenhoener, Rolf; Krumpelt, Michael

    2001-01-01

    A method of forming a hydrogen rich gas from a source of hydrocarbon fuel. A vapor of the hydrocarbon fuel and steam is brought in contact with a two-part catalyst having a dehydrogenation powder portion and an oxide-ion conducting powder portion at a temperature not less than about 770.degree.C. for a time sufficient to generate the hydrogen rich. The H.sub.2 content of the hydrogen gas is greater than about 70 percent by volume. The dehydrogenation portion of the catalyst includes a group VIII metal, and the oxide-ion conducting portion is selected from a ceramic oxide from the group crystallizing in the fluorite or perovskite structure and mixtures thereof. The oxide-ion conducting portion of the catalyst is a ceramic powder of one or more of ZrO.sub.2, CeO.sub.2, Bi.sub.2 O.sub.3, (BiVO).sub.4, and LaGaO.sub.3.

  13. NNSA TRITIUM SUPPLY CHAIN

    SciTech Connect (OSTI)

    Wyrick, Steven; Cordaro, Joseph; Founds, Nanette; Chambellan, Curtis

    2013-08-21

    Savannah River Site plays a critical role in the Tritium Production Supply Chain for the National Nuclear Security Administration (NNSA). The entire process includes: • Production of Tritium Producing Burnable Absorber Rods (TPBARs) at the Westinghouse WesDyne Nuclear Fuels Plant in Columbia, South Carolina • Production of unobligated Low Enriched Uranium (LEU) at the United States Enrichment Corporation (USEC) in Portsmouth, Ohio • Irradiation of TPBARs with the LEU at the Tennessee Valley Authority (TVA) Watts Bar Reactor • Extraction of tritium from the irradiated TPBARs at the Tritium Extraction Facility (TEF) at Savannah River Site • Processing the tritium at the Savannah River Site, which includes removal of nonhydrogen species and separation of the hydrogen isotopes of protium, deuterium and tritium.

  14. Inspect and Repair Steam Traps | Department of Energy

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

    Inspect and Repair Steam Traps Inspect and Repair Steam Traps This tip sheet on inspecting and repairing steam traps provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies. STEAM TIP SHEET #1 Inspect and Repair Steam Traps (January 2012) (393.77 KB) More Documents & Publications Flash High-Pressure Condensate to Regenerate Low-Pressure Steam Steam Pressure Reduction: Opportunities and Issues Use Steam Jet Ejectors or Thermocompressors

  15. Consider Steam Turbine Drives for Rotating Equipment, Energy...

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

    1 Consider Steam Turbine Drives for Rotating Equipment Steam turbines are well suited as ... This service generally calls for a backpressure noncondensing steam turbine. The ...

  16. Best Management Practice #8: Steam Boiler Systems | Department...

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

    8: Steam Boiler Systems Best Management Practice 8: Steam Boiler Systems Steam boilers are commonly used in large heating systems, institutional kitchens, or in facilities where ...

  17. Steam Pressure Reduction, Opportunities, and Issues

    SciTech Connect (OSTI)

    Berry, Jan; Griffin, Mr. Bob; Wright, Anthony L

    2006-01-01

    Steam pressure reduction has the potential to reduce fuel consumption for a minimum capital investment. When the pressure at the boiler is reduced, fuel and steam are saved as a result of changes in the high-pressure side of the steam system from the boiler through the condensate return system. In the boiler plant, losses from combustion, boiler blowdown, radiation, and steam venting from condensate receivers would be reduced by reducing steam pressure. Similarly, in the steam distribution system, losses from radiation, flash steam vented from condensate receivers, and component and steam trap leakage would also be reduced. There are potential problems associated with steam pressure reduction, however. These may include increased boiler carryover, boiler water circulation problems in watertube boilers, increased steam velocity in piping, loss of power in steam turbines, and issues with pressure reducing valves. This paper is based a Steam Technical Brief sponsored by the U.S. Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy and Enbridge Gas Distribution, Inc. (5). An example illustrates the use of DOE BestPractices Steam System Assessment Tool to model changes in steam, fuel, electricity generation, and makeup water and to estimate resulting economic benefits.

  18. Equips Nucleares SA | Open Energy Information

    Open Energy Info (EERE)

    SA Place: Madrid, Spain Zip: 28006 Sector: Services Product: ENSA is a Spanish nuclear components and nuclear services supply company. References: Equips Nucleares, SA1...

  19. How three smart managers control steam costs

    SciTech Connect (OSTI)

    Kendall, R.

    1982-11-01

    Three steam-intensive companies report innovative ways to reduce steam-production costs. Goodyear Tire and Rubber Co. concentrated on regular maintenance, process modifications, and heat recovery, but also has an on-going policy of seeking further cost savings. Future efforts will explore computer-based boiler controls. Zenith Radio Corporation's color picture tube-making process uses 12% less steam after 700 mechanical steam traps were replaced with fixed-orifice traps. Petro-Tex Chemical Corp. reduced steam costs by monitoring and optimizing process units and by making capital investments to improve steam management. (DCK)

  20. Use Steam Jet Ejectors or Thermoscompressors to Reduce Venting of Low-Pressure Steam - Steam Tip Sheet #29

    SciTech Connect (OSTI)

    2012-01-01

    This revised AMO tip sheet on steam jet ejectors and thermocompressors provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  1. Overview of steam generator tube degradation and integrity issues

    SciTech Connect (OSTI)

    Diercks, D.R.; Shack, W.J.; Muscara, J.

    1996-10-01

    The degradation of steam generator tubes in pressurized water nuclear reactors continues to be a serious problem. Primary water stress corrosion cracking is commonly observed at the roll transition zone at U-bends, at tube denting locations, and occasionally in plugs and sleeves. Outer-diameter stress corrosion cracking and intergranular attack commonly occur near the tube support plate crevice, near the tube sheet in crevices or under sludge piles, and occasionally in the free span. A particularly troubling recent trend has been the increasing occurrence of circumferential cracking at the RTZ on both the primary and secondary sides. Segmented axial cracking at the tubes support plate crevices is also becoming more common. Despite recent advances in in-service inspection technology, a clear need still exists for quantifying and improving the reliability of in- service inspection methods with respect to the probability of detection of the various types of flaws and their accurate sizing. Improved inspection technology and the increasing occurrence of such degradation modes as circumferential cracking, intergranular attack, and discontinuous axial cracking have led to the formulation of a new performance-based steam generator rule. This new rule would require the development and implementation of a steam generator management program that monitors tube condition against accepted performance criteria to ensure that the tubes perform the required safety function over the next operating cycle. The new steam generator rule will also be applied to severe accident conditions to determine the continued serviceability of a steam generator with degraded tubes in the event of a severe accident. Preliminary analyses are being performed for a hypothetical severe accident scenario to determine whether failure will occur first in the steam generator tubes, which would lead to containment bypass, or instead in the hot leg nozzle or surge line, which would not.

  2. Fast fluidized bed steam generator

    DOE Patents [OSTI]

    Bryers, Richard W. (Flemington, NJ); Taylor, Thomas E. (Bergenfield, NJ)

    1980-01-01

    A steam generator in which a high-velocity, combustion-supporting gas is passed through a bed of particulate material to provide a fluidized bed having a dense-phase portion and an entrained-phase portion for the combustion of fuel material. A first set of heat transfer elements connected to a steam drum is vertically disposed above the dense-phase fluidized bed to form a first flow circuit for heat transfer fluid which is heated primarily by the entrained-phase fluidized bed. A second set of heat transfer elements connected to the steam drum and forming the wall structure of the furnace provides a second flow circuit for the heat transfer fluid, the lower portion of which is heated by the dense-phase fluidized bed and the upper portion by the entrained-phase fluidized bed.

  3. Los Alamos National Laboratory Steam Plant Project Kickoff Meeting |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) Kickoff Meeting ESPC KICK OFF MEET_ANDY 8_22_FINAL VERSION_2.pptx ESPC KICK OFF MEET_JOE 8_22_16_V2 (002).pptx Updated on 8/26/2016. Related Topics Acquisition & Project Management apm lanl Los alamos national laboratory Related News On Womens Equality Day, we celebrate NNSA's talented Women in STEM Los Alamos National Laboratory Steam Plant Project Reports and Analysis

  4. Development of the first demonstration CFB boiler for gas and steam cogeneration

    SciTech Connect (OSTI)

    Fang, M; Luo, Z.; Li, X.; Wang, Q.; Shi, Z.; Ni, M.; Cen, K.

    1997-12-31

    To solve the shortage of gas and steam supply in the small towns of the country, a new gas steam cogeneration system has been developed. On the basis of the fundamental research on the system, a demonstration gas steam cogeneration system has been designed. As the phase 1 of the project, a 75t/h demonstration CFB boiler for gas steam cogeneration has been erected and operated at Yangzhong Thermal Power Plant of China. This paper introduces the first 75t/h demonstration CFB boiler for gas steam cogeneration. Due to the need of gas steam cogeneration process, the boiler has the features of high temperature cyclone separation, high solid recycle ratio, staged combustion and an external heat exchanger adjusting bed temperature and heat load. The operation results show that the boiler has wide fuel adaptability and the heating value of the coal changes from 14MJ/Kg to 25MJ/Kg. The heat load changes from 85t/h to 28t/h while steam parameter is maintained at the normal conditions. The combustion efficiency of the boiler attain 98%. The boiler design and operation experiences may be a guide to the design and operation of larger CFB units in the future.

  5. Clean Firetube Boiler Waterside Heat Transfer Surfaces, Energy Tips: STEAM, Steam Tip Sheet #7 (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-04-01

    A steam energy tip sheet for the Advanced Manufacturing Office (AMO). The prevention of scale formation in firetube boilers can result in substantial energy savings. Scale deposits occur when calcium, magnesium, and silica, commonly found in most water supplies, react to form a continuous layer of material on the waterside of the boiler heat exchange tubes. Scale creates a problem because it typically possesses a thermal conductivity, an order of magnitude less than the corresponding value for bare steel. Even thin layers of scale serve as an effective insulator and retard heat transfer. The result is overheating of boiler tube metal, tube failures, and loss of energy efficiency. Fuel consumption may increase by up to 5% in firetube boilers because of scale. The boilers steam production may be reduced if the firing rate cannot be increased to compensate for the decrease in combustion efficiency. Energy losses as a function of scale thickness and composition are given. Any scale in a boiler is undesirable. The best way to deal with scale is not to let it form in the first place. Prevent scale formation by: (1) Pretreating of boiler makeup water (using water softeners, demineralizers, and reverse osmosis to remove scale-forming minerals); (2) Injecting chemicals into the boiler feedwater; and (3) Adopting proper boiler blowdown practices.

  6. Foreign Research Reactor Spent Nuclear Fuel Acceptance Program

    National Nuclear Security Administration (NNSA)

    * Complete reactor control rod system. * Note: Does not include the steam turbine generator portion of the power plant. - Sensitive nuclear technology: Any information...

  7. Save Energy Now in Your Steam Systems

    Broader source: Energy.gov [DOE]

    This brief outlines typical ways to increase steam system efficiency through changes in distribution, generation, and recovery.

  8. Hierarchically structured catalysts for cascade and selective steam reforming/hydrodeoxygenation reactions

    SciTech Connect (OSTI)

    Sun, Junming; Karim, Ayman M.; Li, Xiaohong S.; Rainbolt, James E.; Kovarik, Libor; Shin, Yongsoon; Wang, Yong

    2015-09-29

    We report a hierarchically structured catalyst with steam reforming and hydrodeoxygenation functionalities being deposited in the micropores and macropores, respectively. The catalyst is highly efficient to upgrade the pyrolysis vapors of pine forest product residual, resulting in a dramatically decreased acid content and increased hydrocarbon yield without external H2 supply.

  9. Best Management Practice #8: Steam Boiler Systems

    Office of Energy Efficiency and Renewable Energy (EERE)

    Boilers and steam generators are commonly used in large heating systems, institutional kitchens, or in facilities where large amounts of process steam are used. This equipment consumes varying amounts of water depending on system size, the amount of steam used, and the amount of condensate returned.

  10. Materials Performance in USC Steam

    SciTech Connect (OSTI)

    G. R. Holcomb, P. Wang, P. D. Jablonski, and J. A. Hawk

    2010-05-01

    The proposed steam inlet temperature in the Advanced Ultra Supercritical (A-USC) steam turbine is high enough (760 °C) that traditional turbine casing and valve body materials such as ferritic/martensitic steels will not suffice due to temperature limitations of this class of materials. Cast versions of several traditionally wrought Ni-based superalloys were evaluated for use as casing or valve components for the next generation of industrial steam turbines. The full size castings are substantial: 2-5,000 kg each half and on the order of 100 cm thick. Experimental castings were quite a bit smaller, but section size was retained and cooling rate controlled to produce equivalent microstructures. A multi-step homogenization heat treatment was developed to better deploy the alloy constituents. The most successful of these cast alloys in terms of creep strength (Haynes 263, Haynes 282, and Nimonic 105) were subsequently evaluated by characterizing their microstructure as well as their steam oxidation resistance (at 760 and 800 °C).

  11. ENERGY SUPPLY SECURITY 2014

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

    Sustainable Together ENERGY SUPPLY SECURITY 2014 Emergency Response of IEA Countries Secure Sustainable Together ENERGY SUPPLY SECURITY 2014 Emergency Response of IEA Countries ...

  12. School Supply Drive

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

    backpacks filled with school supplies. September 16, 2013 Del Norte Credit Union's Baxter Bear takes a moment to pose with some of the backpacks filled with school supplies...

  13. TWR Bench-Scale Steam Reforming Demonstration

    SciTech Connect (OSTI)

    D. W. Marshall; N. R. Soelberg

    2003-05-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a "road ready" waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrate residues were about 400 ppm in the product and NOx destruction exceeded 86%. The demonstration was successful.

  14. TWR Bench-Scale Steam Reforming Demonstration

    SciTech Connect (OSTI)

    Marshall, D.W.; Soelberg, N.R.

    2003-05-21

    The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a ''road ready'' waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrate residues were about 400 ppm in the product and NOx destruction exceeded 86%. The demonstration was successful.

  15. Closed loop steam cooled airfoil

    SciTech Connect (OSTI)

    Widrig, Scott M.; Rudolph, Ronald J.; Wagner, Gregg P.

    2006-04-18

    An airfoil, a method of manufacturing an airfoil, and a system for cooling an airfoil is provided. The cooling system can be used with an airfoil located in the first stages of a combustion turbine within a combined cycle power generation plant and involves flowing closed loop steam through a pin array set within an airfoil. The airfoil can comprise a cavity having a cooling chamber bounded by an interior wall and an exterior wall so that steam can enter the cavity, pass through the pin array, and then return to the cavity to thereby cool the airfoil. The method of manufacturing an airfoil can include a type of lost wax investment casting process in which a pin array is cast into an airfoil to form a cooling chamber.

  16. Steam System Energy Conservation Measures

    Energy Science and Technology Software Center (OSTI)

    2010-12-31

    This software requires inputs of simple system inventory information and calculates the energy and cost benefits of various retrofit opportunities. This tool includes energy conservation measures for: fixing steam leaks. This tool calculates energy savings, demand reduction, cost savings, and building life cycle costs including: simple payback, discounted payback, net-present value, and savings to investment ratio. In addition this tool also displays the environmental benefits of a project.

  17. Heavy oil. upgrading integrated with steam drive

    SciTech Connect (OSTI)

    Van Driesen, R.; Viens, C.H.; Fornoff, L.L.

    1980-01-01

    A study of the upgrading of heavy oil from a representative Venezuelan Jobo crude (9.2/sup 0/API, 4.1% sulfur, and 500 ppm total metals) from the Orinoco area involved 110 computer simulations based on a modified C-E Lummus Refinery Linear Program model on the assumptions of a 125,000 bbl/day refinery built, starting at 1979 prices, for completion by 1986 near the producing field to supply the fuel oil needed to provide oil field steam. All of the upgrading systems were economically attractive; the per cent return-on-investment (ROI) before taxes for the methods studied were: for Lummus LC-Fining, 135.9%; for Exxon's FLEXICOKING, 132.4%; for delayed coking, 119.2%; and for deasphalting, 106.5%. LC-Fining provided the best over-all combination of flexibility, product yield, product quality, and return on investment. The economics favored upgrading to the maximum extent possible; there was a reduction in the ROI for all the upgrading systems when product specifications were lowered from the premium base case (1.2% SO/sub 2/ emitted per million Btu fired). The premium upgraded heavy crude oils should be worth $3.00-$3.50/bbl more than comparable conventional crude oils, could be of up to 27/sup 0/API, and could be substituted, at up to 50%, for conventional crude oils in a typical U.S. refinery.

  18. Consider Steam Turbine Drives for Rotating Equipment | Department of Energy

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

    Steam Turbine Drives for Rotating Equipment Consider Steam Turbine Drives for Rotating Equipment This tip sheet outlines the benefits of steam turbine drives for rotating equipment as part of optimized steam systems. STEAM TIP SHEET #21 Consider Steam Turbine Drives for Rotating Equipment (January 2012) (398.66 KB) More Documents & Publications Improving Steam System Performance: A Sourcebook for Industry, Second Edition Adjustable Speed Drive Part-Load Efficiency Benchmark the Fuel Cost of

  19. Insulate Steam Distribution and Condensate Return Lines | Department of

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

    Energy Insulate Steam Distribution and Condensate Return Lines Insulate Steam Distribution and Condensate Return Lines This tip sheet on insulating steam distribution and condensate return lines provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies. STEAM TIP SHEET #2 Insulate Steam Distribution and Condensate Return Lines (January 2012) (385.81 KB) More Documents & Publications Use a Vent Condenser to Recover Flash Steam Energy

  20. Significant Silica Solubility in Geothermal Steam

    SciTech Connect (OSTI)

    James, Russell

    1986-01-21

    Although it is widely believed that silica solubility in low pressure (5 to 10 bar) geothermal steam is negligible, when one takes into account steam flows exceeding 10 million tonnes a year--at Wairakei, for instance--it is found that the amount transmitted in the vapor has the potential to give significant deposits on turbine nozzles and blades. A 150 MWe power station, when based on flows from a hot water reservoir at (a) 250 C or (b) 315 C, and with separator pressures of 6 bar, is found to carry about 100 and 200 kg/year respectively in the steam phase. In the case of a similar sized station exploiting a dry steam reservoir such as The Geysers, equivalent silica flows are obtained, dissolved in steam and carried as dust--the latter as solid particles precipitating from the vapor en route from source to turbine, and not preexisting in the formations as is commonly considered. Choking or coating of subterranean rock near such dry steam wells due to exsolving silica, may be the principal cause of declining steam discharge under production. Silica from completely dry or superheated steam can also seal the cap and sides of steam reservoirs when expanding below the criticus temperature (236 C) in a way previously thought possible only by hot water or wet steam.

  1. Technical evaluation: 300 Area steam line valve accident

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    On June 7, 1993, a journeyman power operator (JPO) was severely burned and later died as a result of the failure of a 6-in. valve that occurred when he attempted to open main steam supply (MSS) valve MSS-25 in the U-3 valve pit. The pit is located northwest of Building 331 in the 300 Area of the Hanford Site. Figure 1-1 shows a layout of the 300 Area steam piping system including the U-3 steam valve pit. Figure 1-2 shows a cutaway view of the approximately 10- by 13- by 16-ft-high valve pit with its various steam valves and connecting piping. Valve MSS-25, an 8-in. valve, is located at the bottom of the pit. The failed 6-in. valve was located at the top of the pit where it branched from the upper portion of the 8-in. line at the 8- by 8- by 6-in. tee and was then ``blanked off`` with a blind flange. The purpose of this technical evaluation was to determine the cause of the accident that led to the failure of the 6-in. valve. The probable cause for the 6-in. valve failure was determined by visual, nondestructive, and destructive examination of the failed valve and by metallurgical analysis of the fractured region of the valve. The cause of the accident was ultimately identified by correlating the observed failure mode to the most probable physical phenomenon. Thermal-hydraulic analyses, component stress analyses, and tests were performed to verify that the probable physical phenomenon could be reasonably expected to produce the failure in the valve that was observed.

  2. Optical steam quality measurement system and method

    SciTech Connect (OSTI)

    Davidson, James R.; Partin, Judy K.

    2006-04-25

    An optical measurement system is presented that offers precision on-line monitoring of the quality of steam. Multiple wavelengths of radiant energy are passed through the steam from an emitter to a detector. By comparing the amount of radiant energy absorbed by the flow of steam for each wavelength, a highly accurate measurement of the steam quality can be determined on a continuous basis in real-time. In an embodiment of the present invention, the emitter, comprises three separate radiant energy sources for transmitting specific wavelengths of radiant energy through the steam. In a further embodiment, the wavelengths of radiant energy are combined into a single beam of radiant energy for transmission through the steam using time or wavelength division multiplexing. In yet a further embodiment, the single beam of radiant energy is transmitted using specialized optical elements.

  3. Steam Technical Brief: How to Calculate the True Cost of Steam

    SciTech Connect (OSTI)

    2010-06-25

    This BestPractice Steam Technical Brief helps you calculate the true cost of steam. Knowing the correct cost is important for many reasons and all of them have to do with improving the company's bottom line.

  4. Benchmark the Fuel Cost of Steam Generation - Steam Tip Sheet #15

    SciTech Connect (OSTI)

    2012-01-01

    This revised AMO tip sheet on benchmarking the fuel cost of steam provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  5. Use a Vent Condenser to Recover Flash Steam Energy - Steam Tip Sheet #13

    SciTech Connect (OSTI)

    2012-01-31

    This revised AMO tip sheet on vent condenser to recover flash steam energy provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  6. Insulate Steam Distribution and Condensate Return Lines - Steam Tip Sheet #2

    SciTech Connect (OSTI)

    2012-01-31

    This revised AMO tip sheet on insulating steam distribution and condensate return lines provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  7. Method of steam reforming methanol to hydrogen

    DOE Patents [OSTI]

    Beshty, Bahjat S. (Lower Makefield, PA)

    1990-01-01

    The production of hydrogen by the catalyzed steam reforming of methanol is accomplished using a reformer of greatly reduced size and cost wherein a mixture of water and methanol is superheated to the gaseous state at temperatures of about 800.degree. to about 1,100.degree. F. and then fed to a reformer in direct contact with the catalyst bed contained therein, whereby the heat for the endothermic steam reforming reaction is derived directly from the superheated steam/methanol mixture.

  8. Steam Systems, Retrofit Measure Packages, Hydronic Systems

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

    Program www.buildingamerica.gov Decker Homes Buildings Technologies Program Steam Systems, Retrofit Measure Packages, Hydronic Systems Russell Ruch Elevate Energy Peter Ludwig Elevate Energy July 16, 2014 Building America Webinar: Retrofitting Central Space Conditioning Strategies for Multifamily Buildings Contents * Retrofit Measure Packages for steam and hydronic MF buildings that save 25-30% * System Balancing * Steam * Hydronic 2 | Building America Program www.buildingamerica.gov Background

  9. Huntsman-Enron close supply deals

    SciTech Connect (OSTI)

    1996-08-14

    Huntsman Corp. and Enron Liquid Services has signed ethylene supply agreements with consumers for their joint 1.5-billion lbs/year steam cracker. Huntsman says participants will be announced next week. Initial plans call for the unit to be built at Huntsman`s Port Arthur, TX complex, with startup scheduled for 1999. Huntsman says engineering, procurement, and financing should be in place by the end of the year. The unit will supply Huntsman`s growing internal needs for ethylene and propylene and bolster its position in the Gulf merchant market and will increase Huntsman`s ethylene capacity to more than 3.3 billion lbs/year. Enron`s extensive pipeline system will provide feedstock and be used as a distribution network for ethylene customers.

  10. Steam Technical Brief: Industrial Heat Pumps for Steam and Fuel Savings

    SciTech Connect (OSTI)

    2010-06-25

    The purpose of this Steam Techcial Brief is to introduce heat-pump technology and its applicaiton in industrial processes.

  11. Covered Product Category: Commercial Steam Cookers

    Broader source: Energy.gov [DOE]

    The Federal Energy Management Program (FEMP) provides acquisition guidance for commercial steam cookers, which are covered by the ENERGY STAR program.

  12. Greenville Steam Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    2006 Database Retrieved from "http:en.openei.orgwindex.php?titleGreenvilleSteamBiomassFacility&oldid397532" Feedback Contact needs updating Image needs updating...

  13. Achieve Steam System Excellence: Industrial Technologies Program...

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

    ... equipment. * The IAC Steam Tool Benchmarking Report project tested and validated ... system against well-documented industry best practices. * 3E Plus software evaluates and ...

  14. Warm or Steaming Ground | Open Energy Information

    Open Energy Info (EERE)

    causing steam to form when water is present. Other definitions:Wikipedia Reegle Modern Geothermal Features Typical list of modern geothermal features Hot Springs Fumaroles...

  15. Standard Steam Trust LLC | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name: Standard Steam Trust LLC Place: Denver, Colorado Sector: Geothermal energy Product: Subsidiary of Denver-based geothermal project developer, Terra...

  16. Minimize Boiler Blowdown - Steam Tip Sheet #9

    SciTech Connect (OSTI)

    2012-01-31

    This revised AMO tip sheet on minimizing boiler blowdown provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  17. Pre-In-Plant Training Webinar (Steam)

    Office of Energy Efficiency and Renewable Energy (EERE)

    This pre-In-Plant training webinar for the Better Plants Program covers how to find energy savings in steam systems.

  18. Steam Turbine Materials and Corrosion

    SciTech Connect (OSTI)

    Holcomb, G.H.; Hsu, D.H.

    2008-07-01

    Ultra-supercritical (USC) power plants offer the promise of higher efficiencies and lower emissions. Current goals of the U.S. Department of Energy’s Advanced Power Systems Initiatives include coal generation at 60% efficiency, which would require steam temperatures of up to 760 °C. In prior years this project examined the steamside oxidation of alloys for use in high- and intermediate-pressure USC turbines. This steamside oxidation research is continuing and progress is presented, with emphasis on chromia evaporation.

  19. Designing an ultrasupercritical steam turbine

    SciTech Connect (OSTI)

    Klotz, H.; Davis, K.; Pickering, E.

    2009-07-15

    Carbon emissions produced by the combustion of coal may be collected and stored in the future, but a better approach is to reduce the carbon produced through efficient combustion technologies. Increasing the efficiency of new plants using ultrasupercritical (USC) technology will net less carbon released per megawatt-hour using the world's abundant coal reserves while producing electricity at the lowest possible cost. The article shows how increasing the steam turbine operating conditions for a new USC project in the USA and quantify the potential CO{sub 2} reduction this advanced design makes possible. 7 figs., 3 tabs.

  20. Steam turbine materials and corrosion

    SciTech Connect (OSTI)

    Holcomb, G.R.; Alman, D.E.; Dogan, O.N.; Rawers, J.C.; Schrems, K.K.; Ziomek-Moroz, M.

    2007-12-01

    Ultra-supercritical (USC) power plants offer the promise of higher efficiencies and lower emissions. Current goals of the U.S. Department of Energys Advanced Power Systems Initiatives include power generation from coal at 60% efficiency, which would require steam temperatures of up to 760C. This project examines the steamside oxidation of candidate alloys for use in USC systems, with emphasis placed on applications in high- and intermediate-pressure turbines. As part of this research a concern has arisen about the possibility of high chromia evaporation rates of protective scales in the turbine. A model to calculate chromia evaporation rates is presented.

  1. Evaluation and field validation of Eddy-Current array probes for steam generator tube inspection

    SciTech Connect (OSTI)

    Dodd, C.V.; Pate, J.R.

    1996-07-01

    The objective of the Improved Eddy-Current ISI for Steam Generator Tubing program is to upgrade and validate eddy-current inspections, including probes, instrumentation, and data processing techniques for inservice inspection of new, used, and repaired steam generator tubes; to improve defect detection, classification, and characterization as affected by diameter and thickness variations, denting, probe wobble, tube sheet, tube supports, copper and sludge deposits, even when defect types and other variables occur in combination; to transfer this advanced technology to NRC`s mobile NDE laboratory and staff. This report describes the design of specialized high-speed 16-coil eddy-current array probes. Both pancake and reflection coils are considered. Test results from inspections using the probes in working steam generators are given. Computer programs developed for probe calculations are also supplied.

  2. Benchmark the Fuel Cost of Steam Generation | Department of Energy

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

    Benchmark the Fuel Cost of Steam Generation Benchmark the Fuel Cost of Steam Generation This tip sheet on benchmarking the fuel cost of steam provides how-to advice for improving...

  3. Feedstock Supply System Logistics

    SciTech Connect (OSTI)

    2006-06-01

    Feedstock supply is a significant cost component in the production of biobased fuels, products, and power. The uncertainty of the biomass feedstock supply chain and associated risks are major barriers to procuring capital funding for start-up biorefineries.

  4. Review of Orifice Plate Steam Traps | Department of Energy

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

    Orifice Plate Steam Traps Review of Orifice Plate Steam Traps This guide was prepared to serve as a foundation for making informed decisions about when orifice plate steam traps should be considered for use in new or existing steam systems. It presents background information about different types of steam traps and defines their unique functional and operational characteristics. The advantages and disadvantages associated with using orifice plate steam traps are provided to highlight their

  5. Steam Pressure Reduction: Opportunities and Issues | Department of Energy

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

    Pressure Reduction: Opportunities and Issues Steam Pressure Reduction: Opportunities and Issues This brief details industrial steam generation systems best practices and opportunities for reducing steam system operating pressure. Steam Pressure Reduction: Opportunities and Issues (November 2005) (1.18 MB) More Documents & Publications Steam System Survey Guide Improving Steam System Performance: A Sourcebook for Industry, Second Edition Install an Automatic Blowdown-Control System

  6. Process steam production from cotton gin trash

    SciTech Connect (OSTI)

    LePori, W.A.; Carney, D.B.; Lalk, T.R.; Anthony, R.G.

    1981-01-01

    A steam producing system based on fluidized-bed gasification of biomass materials is discussed. Limited experimental results are discussed and show that steam has been produced at rates of 334.3 kg/hr. (737 lbs/hr.) with 2.8 kg of stream produced for each kilogram of cotton gin trash (2.8 lb/lb.). ref.

  7. Feedstock Supply & Logistics Feedstock Supply System Integration

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

    ... LOGTOF 36.95 60.22 Urban and mill wood wastes MRESUU 4.56 7.79 Potential feedstock supply (Totals) 164.4 267.67 Resource Agricultural Residues Energy Crops Forest Resources ...

  8. Geothermal Steam Act of 1970 | Open Energy Information

    Open Energy Info (EERE)

    Geothermal Steam Act of 1970 Jump to: navigation, search To encourage the development of geothermal energy, the United States government passed the Geothermal Steam Act in 1970...

  9. Paducah Package Steam Boilers to Provide Efficiency, Environmental Benefits

    Broader source: Energy.gov [DOE]

    PADUCAH, Ky. – Five modern, modular steam boilers have replaced three larger coal-fired boilers that comprised the steam plant at EM’s Paducah Site.

  10. Insulate Steam Distribution and Condensate Return Lines, Energy...

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

    and help ensure proper steam pressure at plant equipment. Any surface over 120F should be insulated, including boiler surfaces, steam and condensate return piping, and fttings. ...

  11. Integrated vacuum absorption steam cycle gas separation (Patent...

    Office of Scientific and Technical Information (OSTI)

    vacuum absorption steam cycle gas separation Citation Details In-Document Search Title: Integrated vacuum absorption steam cycle gas separation Methods and systems for separating ...

  12. Building America Expert Meeting: Multifamily Hydronic and Steam...

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

    Multifamily Hydronic and Steam Heating Controls and Distribution Retrofits Building America Expert Meeting: Multifamily Hydronic and Steam Heating Controls and Distribution ...

  13. Y-12 Steam Plant Project Received National Recognition for Project...

    National Nuclear Security Administration (NNSA)

    Steam Plant Project Received National Recognition for Project Management Excellence March 23, 2011 Y-12 steam plant project receives national recognition for project management ...

  14. Boiler Upgrades and Decentralizing Steam Systems Save Water and...

    Energy Savers [EERE]

    Boiler Upgrades and Decentralizing Steam Systems Save Water and Energy at Naval Air Station Oceana Boiler Upgrades and Decentralizing Steam Systems Save Water and Energy at Naval ...

  15. Use a Vent Condenser to Recover Flash Steam Energy | Department...

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

    Use a Vent Condenser to Recover Flash Steam Energy (January 2012) (374.64 KB) More Documents & Publications Recover Heat from Boiler Blowdown Deaerators in Industrial Steam Systems ...

  16. Use Vapor Recompression to Recover Low-Pressure Waste Steam

    Broader source: Energy.gov [DOE]

    This tip sheet on recovering low-pressure waste steam provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  17. Water-Efficient Technology Opportunity: Steam Sterilizer Condensate...

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

    Steam Sterilizer Condensate Retrofit Kit Water-Efficient Technology Opportunity: Steam ... sterilizer condensate retrofit kits as a water-saving technology that is relevant to the ...

  18. Paducah Package Steam Boilers to Provide Efficiency, Environmental...

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

    PADUCAH, Ky. - Five modern, modular steam boilers have replaced three larger coal-fired boilers that comprised the steam plant at EM's Paducah Site. Moving to the more ...

  19. Steam drying of products containing solvent mixtures

    SciTech Connect (OSTI)

    Pothmann, E.; Schluender, E.U. [Univ. Karlsruhe (Germany). Inst. fuer Thermische Verfahrenstechnik

    1995-12-31

    Drying experiments with single, porous spheres wetted with mixtures of 2-propanol and water were performed using superheated steam, air, or steam-air mixtures as drying agent. Both the drying rate and the moisture composition were determined experimentally for different temperatures and compositions of the drying agent and for different initial compositions of the moisture. It is shown that evaporation of 2-propanol is enhanced by using superheated steam as drying agent instead of air due to steam condensing on the sample. While the overall drying rate increases with rising steam temperature, the evaporation rate of 2-propanol is hardly affected. When drying samples containing mixtures of 2-propanol and water, internal boiling can occur depending on the vapor-liquid equilibrium. Vapor generated inside the sample may cause mechanical dewatering of the sample which greatly increases the drying rate.

  20. Mist/steam cooling in a heated horizontal tube -- Part 1: Experimental system

    SciTech Connect (OSTI)

    Guo, T.; Wang, T.; Gaddis, J.L.

    2000-04-01

    To improve the airfoil cooling significantly for the future generation of advanced turbine systems (ATS), a fundamental experimental program has been developed to study the heat transfer mechanisms of mist/steam cooling under highly superheated wall temperatures. The mist/steam mixture was obtained by blending fine water droplets (3 {approximately} 15 {micro}m in diameter) with the saturated steam at 1.5 bars. Two mist generation systems were tested by using the pressure atomizer and the steam-assisted pneumatic atomizer, respectively. The test section, heated directly by a DC power supply, consisted of a thin-walled ({approximately} 0.9 mm), circular stainless steel tube with an ID of 20 mm and a length of 203 mm. Droplet size and distribution were measured by a phase Doppler particle analyzer (PDPA) system through view ports grafted at the inlet and the outlet of the test section. Mist transportation and droplet dynamics were studied in addition to the heat transfer measurements. The experiment was conducted with steam Reynolds numbers ranging from 10,000 to 35,000, wall superheat up to 300 C, and droplet mass ratios ranging from 1 {approximately} 6%.

  1. Nuclear Fuel Cycle | Department of Energy

    Energy Savers [EERE]

    ... In a fuel fabrication plant great care is taken with the size and shape of processing ... Generation of electricity in a nuclear reactor is similar to a coal-fired steam station. The ...

  2. Identifying and bounding uncertainties in nuclear reactor thermal power calculations

    SciTech Connect (OSTI)

    Phillips, J.; Hauser, E.; Estrada, H.

    2012-07-01

    Determination of the thermal power generated in the reactor core of a nuclear power plant is a critical element in the safe and economic operation of the plant. Direct measurement of the reactor core thermal power is made using neutron flux instrumentation; however, this instrumentation requires frequent calibration due to changes in the measured flux caused by fuel burn-up, flux pattern changes, and instrumentation drift. To calibrate the nuclear instruments, steam plant calorimetry, a process of performing a heat balance around the nuclear steam supply system, is used. There are four basic elements involved in the calculation of thermal power based on steam plant calorimetry: The mass flow of the feedwater from the power conversion system, the specific enthalpy of that feedwater, the specific enthalpy of the steam delivered to the power conversion system, and other cycle gains and losses. Of these elements, the accuracy of the feedwater mass flow and the feedwater enthalpy, as determined from its temperature and pressure, are typically the largest contributors to the calorimetric calculation uncertainty. Historically, plants have been required to include a margin of 2% in the calculation of the reactor thermal power for the licensed maximum plant output to account for instrumentation uncertainty. The margin is intended to ensure a cushion between operating power and the power for which safety analyses are performed. Use of approved chordal ultrasonic transit-time technology to make the feedwater flow and temperature measurements (in place of traditional differential-pressure- based instruments and resistance temperature detectors [RTDs]) allows for nuclear plant thermal power calculations accurate to 0.3%-0.4% of plant rated power. This improvement in measurement accuracy has allowed many plant operators in the U.S. and around the world to increase plant power output through Measurement Uncertainty Recapture (MUR) up-rates of up to 1.7% of rated power, while also

  3. Petroleum Supply Annual

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

    Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 248,959 - - - - 235,269 8,443 10,330 474,643 7,698 0

  4. Petroleum Supply Annual

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

    0.PDF Table 10. PAD District 4 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 573 - - - - 309

  5. Petroleum Supply Annual

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

    1.PDF Table 11. PAD District 5 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 35,538 -

  6. Petroleum Supply Annual

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

    2.PDF Table 12. PAD District 5 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,146 - - - -

  7. Petroleum Supply Annual

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

    .PDF Table 2. U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 8,031 - - - - 7,589 272 333 15,311 248 0 Natural Gas Plant

  8. Petroleum Supply Annual

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

    .PDF Table 3. PAD District 1 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,408 - -

  9. Petroleum Supply Annual

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

    TABLE4.PDF Table 4. PAD District 1 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 45 - - - -

  10. Petroleum Supply Annual

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

    TABLE5.PDF Table 5. PAD District 2 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil .............................................................

  11. Petroleum Supply Annual

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

    TABLE6.PDF Table 6. PAD District 2 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,529 - - -

  12. Petroleum Supply Annual

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

    TABLE7.PDF Table 7. PAD District 3 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................

  13. Petroleum Supply Annual

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

    TABLE8.PDF Table 8. PAD District 3 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................ 4,737 - - -

  14. Petroleum Supply Annual

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

    TABLE9.PDF Table 9. PAD District 4 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January 2014 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil .............................................................

  15. Petroleum Supply Monthly

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

    June 2016 Table 1. U.S. Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 261,028 - - - - 228,320 3,220 -11,881 492,960

  16. Petroleum Supply Monthly

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

    5 June 2016 Table 10. PAD District 2 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  17. Petroleum Supply Monthly

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

    6 June 2016 Table 11. PAD District 2 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 1,673 - - - -

  18. Petroleum Supply Monthly

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

    7 June 2016 Table 12. PAD District 2 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  19. Petroleum Supply Monthly

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

    8 June 2016 Table 13. PAD District 3 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................

  20. Petroleum Supply Monthly

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

    9 June 2016 Table 14. PAD District 3 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  1. Petroleum Supply Monthly

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

    0 June 2016 Table 15. PAD District 3 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................ 5,357 - - -

  2. Petroleum Supply Monthly

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

    1 June 2016 Table 16. PAD District 3 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  3. Petroleum Supply Monthly

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

    2 June 2016 Table 17. PAD District 4 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6 ............................................................

  4. Petroleum Supply Monthly

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

    3 June 2016 Table 18. PAD District 4 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil 6

  5. Petroleum Supply Monthly

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

    4 June 2016 Table 19. PAD District 4 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 643 - - - -

  6. Petroleum Supply Monthly

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

    June 2016 Table 2. U.S. Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports Adjust- ments 1 Stock Change 2 Refinery and Blender Net Inputs Exports Products Supplied 3 Crude Oil 4 ............................................................ 1,639,778 - - - - 1,420,355

  7. Petroleum Supply Monthly

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

    5 June 2016 Table 20. PAD District 4 - Year-to-Date Daily Average Supply and Disposition of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  8. Petroleum Supply Monthly

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

    6 June 2016 Table 21. PAD District 5 - Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil .............................................................

  9. Petroleum Supply Monthly

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

    7 June 2016 Table 22. PAD District 5 - Year-to-Date Supply, Disposition, and Ending Stocks of Crude Oil and Petroleum Products, January-June 2016 (Thousand Barrels) Commodity Supply Disposition Ending Stocks Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil

  10. Petroleum Supply Monthly

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

    8 June 2016 Table 23. PAD District 5 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, June 2016 (Thousand Barrels per Day) Commodity Supply Disposition Field Production Renewable Fuels and Oxygenate Plant Net Production Refinery and Blender Net Production Imports (PADD of Entry) 1 Net Receipts 2 Adjust- ments 3 Stock Change 4 Refinery and Blender Net Inputs Exports Products Supplied 5 Crude Oil ............................................................. 983 - - - -