National Library of Energy BETA

Sample records for house reactor components

  1. Reactor component automatic grapple

    DOE Patents [OSTI]

    Greenaway, Paul R.

    1982-01-01

    A grapple for handling nuclear reactor components in a medium such as liquid sodium which, upon proper seating and alignment of the grapple with the component as sensed by a mechanical logic integral to the grapple, automatically seizes the component. The mechanical logic system also precludes seizure in the absence of proper seating and alignment.

  2. Solid tags for identifying failed reactor components

    DOE Patents [OSTI]

    Bunch, Wilbur L.; Schenter, Robert E.

    1987-01-01

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

  3. Energy deposition in STARFIRE reactor components

    SciTech Connect (OSTI)

    Gohar, Y.; Brooks, J.N.

    1985-04-01

    The energy deposition in the STARFIRE commercial tokamak reactor was calculated based on detailed models for the different reactor components. The heat deposition and the 14 MeV neutron flux poloidal distributions in the first wall were obtained. The poloidal surface heat load distribution in the first wall was calculated from the plasma radiation. The Monte Carlo method was used for the calculation to allow an accurate modeling for the reactor geometry.

  4. Heavy Water Components Test Reactor Decommissioning - Major Component Removal

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2010-05-05

    The Heavy Water Components Test Reactor (HWCTR) facility (Figure 1) was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR facility is on high, well-drained ground, about 30 meters above the water table. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. It was not a defense-related facility like the materials production reactors at SRS. The reactor was moderated with heavy water and was rated at 50 megawatts thermal power. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In 1965, fuel assemblies were removed, systems that contained heavy water were drained, fluid piping systems were drained, deenergized and disconnected and the spent fuel basin was drained and dried. The doors of the reactor facility were shut and it wasn't until 10 years later that decommissioning plans were considered and ultimately postponed due to budget constraints. In the early 1990s, DOE began planning to decommission HWCTR again. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. The $1.6 billion allocation from the American Recovery and Reinvestment Act to SRS for site clean up at SRS has opened the doors to the HWCTR again - this time for final decommissioning. During the lifetime of HWCTR, 36 different fuel assemblies were tested in the facility. Ten of these

  5. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    SciTech Connect (OSTI)

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment

  6. Technological Assessment of Plasma Facing Components for DEMO Reactors |

    Office of Environmental Management (EM)

    Department of Energy Technological Assessment of Plasma Facing Components for DEMO Reactors Technological Assessment of Plasma Facing Components for DEMO Reactors Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. Technological Assessment of Plasma Facing Components for DEMO Reactors (1.99 MB) More Documents & Publications Tritium Plasma Experiment and Its Role in PHENIX Program Tritium research activities in Safety and Tritium

  7. Component failures that lead to reactor scrams. [PWR; BWR

    SciTech Connect (OSTI)

    Burns, E. T.; Wilson, R. J.; Lim, E. Y.

    1980-04-01

    This report summarizes the operating experience scram data compiled from 35 operating US light water reactors (LWRs) to identify the principal components/systems related to reactor scrams. The data base utilized to identify the scram causes is developed from a EPRI-utility sponsored survey conducted by SAI coupled with recent data from the USNRC Gray Books. The reactor population considered in this evaluation is limited to 23 PWRs and 12 BWRs because of the limited scope of the program. The population includes all the US NSSS vendors. It is judged that this population accurately characterizes the component-related scrams in LWRs over the first 10 years of plant operation.

  8. Austenitic alloy and reactor components made thereof

    DOE Patents [OSTI]

    Bates, John F.; Brager, Howard R.; Korenko, Michael K.

    1986-01-01

    An austenitic stainless steel alloy is disclosed, having excellent fast neutron irradiation swelling resistance and good post irradiation ductility, making it especially useful for liquid metal fast breeder reactor applications. The alloy contains: about 0.04 to 0.09 wt. % carbon; about 1.5 to 2.5 wt. % manganese; about 0.5 to 1.6 wt. % silicon; about 0.030 to 0.08 wt. % phosphorus; about 13.3 to 16.5 wt. % chromium; about 13.7 to 16.0 wt. % nickel; about 1.0 to 3.0 wt. % molybdenum; and about 0.10 to 0.35 wt. % titanium.

  9. LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BNL

    SciTech Connect (OSTI)

    P.C. Weaver

    2010-10-22

    5098-LR-01-0 -LETTER REPORT INDEPENDENT VERIFICATION OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT FAN HOUSE, BUILDING 704 BROOKHAVEN NATIONAL LABORATORY

  10. CHARACTERIZATION OF RADIOACTIVITY IN THE REACTOR VESSEL OF THE HEAVY WATER COMPONENT TEST REACTOR

    SciTech Connect (OSTI)

    Vinson, Dennis

    2010-06-01

    The Heavy Water Component Test Reactor (HWCTR) facility is a pressurized heavy water reactor that was used to test candidate fuel designs for heavy water power reactors. The reactor operated at nominal power of 50 MW{sub th}. The reactor coolant loop operated at 1200 psig and 250 C. Two isolated test loop were designed into the reactor to provide special test conditions. Fig. 1 shows a cut-away view of the reactor. The two loops are contained in four inch diameter stainless steel piping. The HWCTR was operated for only a short duration, from March 1962 to December 1964 in order to test the viability of test fuel elements and other reactor components for use in a heavy water power reactor. The reactor achieved 13,882 MWd of total power while testing 36 different fuel assemblies. In the course of operation, HWCTR experienced the cladding failures of 10 separate test fuel assemblies. In each case, the cladding was breached with some release of fuel core material into the isolated test loop, causing fission product and actinide contamination in the main coolant loop and the liquid and boiling test loops. Despite the contribution of the contamination from the failed fuel, the primary source of radioactivity in the HWCTR vessel and internals is the activation products in the thermal shields, and to a lesser degree, activation products in the reactor vessel walls and liner. A detailed facility characterization report of the HWCTR facility was completed in 1996. Many of the inputs and assumptions in the 1996 characterization report were derived from the HWCTR decommissioning plan published in 1975. The current paper provides an updated assessment of the radioisotopic characteristics of the HWCTR vessel and internals to support decommissioning activities on the facility.

  11. Hydraulic balancing of a control component within a nuclear reactor

    DOE Patents [OSTI]

    Marinos, D.; Ripfel, H.C.F.

    1975-10-14

    A reactor control component includes an inner conduit, for instance containing neutron absorber elements, adapted for longitudinal movement within an outer guide duct. A transverse partition partially encloses one end of the conduit and meets a transverse wall within the guide duct when the conduit is fully inserted into the reactor core. A tube piece extends from the transverse partition and is coaxially aligned to be received within a tubular receptacle which extends from the transverse wall. The tube piece and receptacle cooperate in engagement to restrict the flow and pressure of coolant beneath the transverse partition and thereby minimize upward forces tending to expel the inner conduit.

  12. Nuclear reactor spacer grid and ductless core component

    DOE Patents [OSTI]

    Christiansen, David W.; Karnesky, Richard A.

    1989-01-01

    The invention relates to a nuclear reactor spacer grid member for use in a liquid cooled nuclear reactor and to a ductless core component employing a plurality of these spacer grid members. The spacer grid member is of the egg-shell type and is constructed so that the walls of the cell members of the grid member are formed of a single thickness of metal to avoid tolerance problems. Within each cell member is a hydraulic spring which laterally constrains the nuclear material bearing rod which passes through each cell member against a hardstop in response to coolant flow through the cell member. This hydraulic spring is also suitable for use in a water cooled nuclear reactor. A core component constructed of, among other components, a plurality of these spacer grid members, avoids the use of a full length duct by providing spacer sleeves about the sodium tubes passing through the spacer grid members at locations between the grid members, thereby maintaining a predetermined space between adjacent grid members.

  13. Nuclear reactor heat transport system component low friction support system

    DOE Patents [OSTI]

    Wade, Elman E.

    1980-01-01

    A support column for a heavy component of a liquid metal fast breeder reactor heat transport system which will deflect when the pipes leading coolant to and from the heavy component expand or contract due to temperature changes includes a vertically disposed pipe, the pipe being connected to the heavy component by two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles and the pipe being supported through two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles, each of the cylindrical surfaces bearing on a flat and horizontal surface.

  14. Component failures at pressurized water reactors. Final report

    SciTech Connect (OSTI)

    Reisinger, M.F.

    1980-10-01

    Objectives of this study were to identify those systems having major impact on safety and availability (i.e. to identify those systems and components whose failures have historically caused the greatest number of challenges to the reactor protective systems and which have resulted in greatest loss of electric generation time). These problems were identified for engineering solutions and recommendations made for areas and programs where research and development should be concentrated. The program was conducted in three major phases: Data Analysis, Engineering Evaluation, Cost Benefit Analysis.

  15. Method of detecting leakage of reactor core components of liquid metal cooled fast reactors

    DOE Patents [OSTI]

    Holt, Fred E.; Cash, Robert J.; Schenter, Robert E.

    1977-01-01

    A method of detecting the failure of a sealed non-fueled core component of a liquid-metal cooled fast reactor having an inert cover gas. A gas mixture is incorporated in the component which includes Xenon-124; under neutron irradiation, Xenon-124 is converted to radioactive Xenon-125. The cover gas is scanned by a radiation detector. The occurrence of 188 Kev gamma radiation and/or other identifying gamma radiation-energy level indicates the presence of Xenon-125 and therefore leakage of a component. Similarly, Xe-126, which transmutes to Xe-127 and Kr-84, which produces Kr-85.sup.m can be used for detection of leakage. Different components are charged with mixtures including different ratios of isotopes other than Xenon-124. On detection of the identifying radiation, the cover gas is subjected to mass spectroscopic analysis to locate the leaking component.

  16. Generic component failure data base for light water and liquid sodium reactor PRAs (probabilistic risk assessments)

    SciTech Connect (OSTI)

    Eide, S.A.; Chmielewski, S.V.; Swantz, T.D.

    1990-02-01

    A comprehensive generic component failure data base has been developed for light water and liquid sodium reactor probabilistic risk assessments (PRAs). The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) and the Centralized Reliability Data Organization (CREDO) data bases were used to generate component failure rates. Using this approach, most of the failure rates are based on actual plant data rather than existing estimates. 21 refs., 9 tabs.

  17. Flow Components in a NaK Test Loop Designed to Simulate Conditions in a Nuclear Surface Power Reactor

    SciTech Connect (OSTI)

    Polzin, Kurt A.; Godfroy, Thomas J.

    2008-01-21

    A test loop using NaK as the working fluid is presently in use to study material compatibility effects on various components that comprise a possible nuclear reactor design for use on the lunar surface. A DC electromagnetic (EM) pump has been designed and implemented as a means of actively controlling the NaK flow rate through the system and an EM flow sensor is employed to monitor the developed flow rate. These components allow for the matching of the flow rate conditions in test loops with those that would be found in a full-scale surface-power reactor. The design and operating characteristics of the EM pump and flow sensor are presented. In the EM pump, current is applied to a set of electrodes to produce a Lorentz body force in the fluid. A measurement of the induced voltage (back-EMF) in the flow sensor provides the means of monitoring flow rate. Both components are compact, employing high magnetic field strength neodymium magnets thermally coupled to a water-cooled housing. A vacuum gap limits the heat transferred from the high temperature NaK tube to the magnets and a magnetically-permeable material completes the magnetic circuit. The pump is designed to produce a pressure rise of 34.5 kPa, and the flow sensor's predicted output is roughly 20 mV at the loop's nominal flow rate of 0.114 m{sup 3}/hr.

  18. An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components

    SciTech Connect (OSTI)

    Holcomb, David Eugene; Cetiner, Sacit M; Flanagan, George F; Peretz, Fred J; Yoder Jr, Graydon L

    2009-11-01

    This report provides guidance on the component testing necessary during the next phase of fluoride salt-cooled high temperature reactor (FHR) development. In particular, the report identifies and describes the reactor component performance and reliability requirements, provides an overview of what information is necessary to provide assurance that components will adequately achieve the requirements, and then provides guidance on how the required performance information can efficiently be obtained. The report includes a system description of a representative test scale FHR reactor. The reactor parameters presented in this report should only be considered as placeholder values until an FHR test scale reactor design is completed. The report focus is bounded at the interface between and the reactor primary coolant salt and the fuel and the gas supply and return to the Brayton cycle power conversion system. The analysis is limited to component level testing and does not address system level testing issues. Further, the report is oriented as a bottom-up testing requirements analysis as opposed to a having a top-down facility description focus.

  19. An Assessment of Remote Visual Methods to Detect Cracking in Reactor Components

    SciTech Connect (OSTI)

    Cumblidge, Stephen E.; Anderson, Michael T.; Doctor, Steven R.; Simonen, Fredric A.; Elliot, Anthony J.

    2008-01-01

    Recently, the U.S. nuclear industry has proposed replacing current volumetric and/or surface examinations of certain components in commercial nuclear power plants, as required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, “Inservice Inspection of Nuclear Power Plant Components,” with a simpler visual testing (VT) method. The advantages of VT are that these tests generally involve much less radiation exposure and time to perform the examination than do volumetric examinations such as ultrasonic testing. The issues relative to the reliability of VT in determining the structural integrity of reactor components were examined. Some piping and pressure vessel components in a nuclear power station are examined using VT as they are either in high radiation fields or component geometry precludes the use of ultrasonic testing (UT) methodology. Remote VT with radiation-hardened video systems has been used by nuclear utilities to find cracks in pressure vessel cladding in pressurized water reactors, core shrouds in boiling water reactors, and to investigate leaks in piping and reactor components. These visual tests are performed using a wide variety of procedures and equipment. The techniques for remote VT use submersible closed-circuit video cameras to examine reactor components and welds. PNNL conducted a parametric study that examined the important variables influencing the effectiveness of a remote visual test. Tested variables included lighting techniques, camera resolution, camera movement, and magnification. PNNL also conducted a limited laboratory test using a commercial visual testing camera system to experimentally determine the ability of the camera system to detect cracks of various widths under ideal conditions. The results of these studies and their implications are presented in this paper.

  20. Nuclear heat source component design considerations for HTGR process heat reactor plant concept

    SciTech Connect (OSTI)

    McDonald, C.F.; Kapich, D.; King, J.H.; Venkatesh, M.C.

    1982-05-01

    The coupling of a high-temperature gas-cooled reactor (HTGR) and a chemical process facility has the potential for long-term synthetic fuel production (i.e., oil, gasoline, aviation fuel, hydrogen, etc) using coal as the carbon source. Studies are in progress to exploit the high-temperature capability of an advanced HTGR variant for nuclear process heat. The process heat plant discussed in this paper has a 1170-MW(t) reactor as the heat source and the concept is based on indirect reforming, i.e., the high-temperature nuclear thermal energy is transported (via an intermediate heat exchanger (IHX)) to the externally located process plant by a secondary helium transport loop. Emphasis is placed on design considerations for the major nuclear heat source (NHS) components, and discussions are presented for the reactor core, prestressed concrete reactor vessel (PCRV), rotating machinery, and heat exchangers.

  1. Progress Towards Prognostic Health Management of Passive Components in Advanced Small Modular Reactors

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Ramuhalli, Pradeep; Hirt, Evelyn H.; Pardini, Allan F.; Suter, Jonathan D.; Prowant, Matthew S.

    2014-08-01

    Sustainable nuclear power to promote energy security and to reduce greenhouse gas emissions are two key national energy priorities. The development of deployable small modular reactors (SMRs) is expected to support these objectives by developing technologies that improve the reliability, sustain safety, and improve affordability of new reactors. Advanced SMRs (AdvSMRs) refer to a specific class of SMRs and are based on modularization of advanced reactor concepts. Prognostic health management (PHM) systems can benefit both the safety and economics of deploying AdvSMRs and can play an essential role in managing the inspection and maintenance of passive components in AdvSMR systems. This paper describes progress on development of a prototypic PHM system for AdvSMR passive components, with thermal creep chosen as the target degradation mechanism.

  2. Catalytic reactor

    DOE Patents [OSTI]

    Aaron, Timothy Mark; Shah, Minish Mahendra; Jibb, Richard John

    2009-03-10

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

  3. Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

    SciTech Connect (OSTI)

    Farmer, Mitchell T.; Bunt, R.; Corradini, M.; Ellison, Paul B.; Francis, M.; Gabor, John D.; Gauntt, R.; Henry, C.; Linthicum, R.; Luangdilok, W.; Lutz, R.; Paik, C.; Plys, M.; Rabiti, Cristian; Rempe, J.; Robb, K.; Wachowiak, R.

    2015-01-31

    The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy’s (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

  4. Requirements for Prognostic Health Management of Passive Components in Advanced Small Modular Reactors

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep

    2013-08-01

    Advanced small modular reactors (aSMRs), which are based on modularization of advanced reactor concepts, may provide a longer-term alternative to traditional light-water reactors and near term small modular reactors (SMRs), which are based on integral pressurized water reactor (iPWR) concepts. aSMRs are conceived for applications in remote locations and for diverse missions that include providing process or district heating, water desalination, and hydrogen production. Several challenges exist with respect to cost-effective operations and maintenance (O&M) of aSMRs, including the impacts of aggressive operating environments and modularity, and limiting these costs and staffing needs will be essential to ensuring the economic feasibility of aSMR deployment. In this regard, prognostic health management (PHM) systems have the potential to play a vital role in supporting the deployment of aSMR systems. This paper identifies requirements and technical gaps associated with implementation of PHM systems for passive aSMR components.

  5. Swelling in light water reactor internal components: Insights from computational modeling

    SciTech Connect (OSTI)

    Stoller, Roger E.; Barashev, Alexander V.; Golubov, Stanislav I.

    2015-08-01

    A modern cluster dynamics model has been used to investigate the materials and irradiation parameters that control microstructural evolution under the relatively low-temperature exposure conditions that are representative of the operating environment for in-core light water reactor components. The focus is on components fabricated from austenitic stainless steel. The model accounts for the synergistic interaction between radiation-produced vacancies and the helium that is produced by nuclear transmutation reactions. Cavity nucleation rates are shown to be relatively high in this temperature regime (275 to 325°C), but are sensitive to assumptions about the fine scale microstructure produced under low-temperature irradiation. The cavity nucleation rates observed run counter to the expectation that void swelling would not occur under these conditions. This expectation was based on previous research on void swelling in austenitic steels in fast reactors. This misleading impression arose primarily from an absence of relevant data. The results of the computational modeling are generally consistent with recent data obtained by examining ex-service components. However, it has been shown that the sensitivity of the model s predictions of low-temperature swelling behavior to assumptions about the primary damage source term and specification of the mean-field sink strengths is somewhat greater that that observed at higher temperatures. Further assessment of the mathematical model is underway to meet the long-term objective of this research, which is to provide a predictive model of void swelling at relevant lifetime exposures to support extended reactor operations.

  6. Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York

    SciTech Connect (OSTI)

    Harpeneau, Evan M.

    2011-06-24

    On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions.

  7. A review of the US joining technologies for plasma facing components in the ITER fusion reactor

    SciTech Connect (OSTI)

    Odegard, B.C. Jr.; Cadden, C.H.; Watson, R.D.; Slattery, K.T.

    1998-02-01

    This paper is a review of the current joining technologies for plasma facing components in the US for the International Thermonuclear Experimental Reactor (ITER) project. Many facilities are involved in this project. Many unique and innovative joining techniques are being considered in the quest to join two candidate armor plate materials (beryllium and tungsten) to a copper base alloy heat sink (CuNiBe, OD copper, CuCrZr). These techniques include brazing and diffusion bonding, compliant layers at the bond interface, and the use of diffusion barrier coatings and diffusion enhancing coatings at the bond interfaces. The development and status of these joining techniques will be detailed in this report.

  8. Facility Configuration Study of the High Temperature Gas-Cooled Reactor Component Test Facility

    SciTech Connect (OSTI)

    S. L. Austad; L. E. Guillen; D. S. Ferguson; B. L. Blakely; D. M. Pace; D. Lopez; J. D. Zolynski; B. L. Cowley; V. J. Balls; E.A. Harvego, P.E.; C.W. McKnight, P.E.; R.S. Stewart; B.D. Christensen

    2008-04-01

    A test facility, referred to as the High Temperature Gas-Cooled Reactor Component Test Facility or CTF, will be sited at Idaho National Laboratory for the purposes of supporting development of high temperature gas thermal-hydraulic technologies (helium, helium-Nitrogen, CO2, etc.) as applied in heat transport and heat transfer applications in High Temperature Gas-Cooled Reactors. Such applications include, but are not limited to: primary coolant; secondary coolant; intermediate, secondary, and tertiary heat transfer; and demonstration of processes requiring high temperatures such as hydrogen production. The facility will initially support completion of the Next Generation Nuclear Plant. It will secondarily be open for use by the full range of suppliers, end-users, facilitators, government laboratories, and others in the domestic and international community supporting the development and application of High Temperature Gas-Cooled Reactor technology. This pre-conceptual facility configuration study, which forms the basis for a cost estimate to support CTF scoping and planning, accomplishes the following objectives: • Identifies pre-conceptual design requirements • Develops test loop equipment schematics and layout • Identifies space allocations for each of the facility functions, as required • Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems • Identifies pre-conceptual utility and support system needs • Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

  9. A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water Reactor Cooling System Components

    Broader source: Energy.gov [DOE]

    In the United States currently there are approximately 104 operating light water reactors. Of these, 69 are pressurized water reactors (PWRs) and 35 are boiling water reactors (BWRs). In 2007, the...

  10. FEM calculation of eddy current losses and forces in thin conducting sheets of test facilities for fusion reactor components

    SciTech Connect (OSTI)

    Biro, O.; Preis, K.; Richter, K.R. ); Heller, R.; Komarek, P.; Maurer, W. )

    1992-03-01

    The eddy current carrying conducting parts in fusion reactor models are frequently relatively thin sheets. To avoid the associated numerical problems, the surface current density is represented in this paper by a scalar quantity and, as a novelty, the magnetic field is described overall by a magnetic vector potential to treat multiply connected conductors easily. The method is applied to several problems involving fusion reactor components.

  11. Technical Needs for Prototypic Prognostic Technique Demonstration for Advanced Small Modular Reactor Passive Components

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Coble, Jamie B.; Hirt, Evelyn H.; Ramuhalli, Pradeep; Mitchell, Mark R.; Wootan, David W.; Berglin, Eric J.; Bond, Leonard J.; Henager, Charles H.

    2013-05-17

    This report identifies a number of requirements for prognostics health management of passive systems in AdvSMRs, documents technical gaps in establishing a prototypical prognostic methodology for this purpose, and describes a preliminary research plan for addressing these technical gaps. AdvSMRs span multiple concepts; therefore a technology- and design-neutral approach is taken, with the focus being on characteristics that are likely to be common to all or several AdvSMR concepts. An evaluation of available literature is used to identify proposed concepts for AdvSMRs along with likely operational characteristics. Available operating experience of advanced reactors is used in identifying passive components that may be subject to degradation, materials likely to be used for these components, and potential modes of degradation of these components. This information helps in assessing measurement needs for PHM systems, as well as defining functional requirements of PHM systems. An assessment of current state-of-the-art approaches to measurements, sensors and instrumentation, diagnostics and prognostics is also documented. This state-of-the-art evaluation, combined with the requirements, may be used to identify technical gaps and research needs in the development, evaluation, and deployment of PHM systems for AdvSMRs. A preliminary research plan to address high-priority research needs for the deployment of PHM systems to AdvSMRs is described, with the objective being the demonstration of prototypic prognostics technology for passive components in AdvSMRs. Greater efficiency in achieving this objective can be gained through judicious selection of materials and degradation modes that are relevant to proposed AdvSMR concepts, and for which significant knowledge already exists. These selections were made based on multiple constraints including the analysis performed in this document, ready access to laboratory-scale facilities for materials testing and measurement, and

  12. Eddy current position indicating apparatus for measuring displacements of core components of a liquid metal nuclear reactor

    DOE Patents [OSTI]

    Day, Clifford K.; Stringer, James L.

    1977-01-01

    Apparatus for measuring displacements of core components of a liquid metal fast breeder reactor by means of an eddy current probe. The active portion of the probe is located within a dry thimble which is supported on a stationary portion of the reactor core support structure. Split rings of metal, having a resistivity significantly different than sodium, are fixedly mounted on the core component to be monitored. The split rings are slidably positioned around, concentric with the probe and symmetrically situated along the axis of the probe so that motion of the ring along the axis of the probe produces a proportional change in the probes electrical output.

  13. Physics-Based Multi-State Models of Passive Component Degradation for the R7 Reactor Simulation Environment

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Layton, Robert F.; Johnson, Kenneth I.; Lowry, Peter P.

    2012-06-25

    Abstract: The Next Generation Systems Analysis Code - referred to as R7 - is reactor systems simulation software being developed to support the Risk-Informed Safety Margin Characterization Pathway of the U.S. Department of Energy's Light Water Reactor Sustainability Program. It will provide an integrated multi-physics environment, implemented in an uncertainty quantification (UQ) framework that can produce risk and other performance insights on long-term reactor operations. An element of this simulation environment will be the performance of passive components and materials. Conventional models of component reliability are largely parametric, relying on plant service data to estimate component lifetimes and failure rates. This type of model has limited usefulness in the R7 environment where the intent is to explicitly determine the influence of physical stressors on component degradation. In this paper, we describe a new class of multi-state physics-based component models designed to be R7-compatible. These models capture the physics of materials degradation while also incorporating the effects of interventions and component rejuvenation. The models are implemented in a cumulative damage framework that allows the impact of an evolving physical environment to be addressed without recourse to resampling within the Monte Carlo-based UQ framework. The paper describes an application to stress corrosion cracking in dissimilar metal welds - a principal contributor to potential loss of coolant accidents. So while R7 will have the more conventional capability of reactor simulation codes to model the impact of degraded components and systems on plant performance, the methodology described here allows R7 to model the inverse effect; the impact of the physical environment on component degradation and performance.

  14. System Engineering Program Applicability for the High Temperature Gas-Cooled Reactor (HTGR) Component Test Capability (CTC)

    SciTech Connect (OSTI)

    Jeffrey Bryan

    2009-06-01

    This white paper identifies where the technical management and systems engineering processes and activities to be used in establishing the High Temperature Gas-cooled Reactor (HTGR) Component Test Capability (CTC) should be addressed and presents specific considerations for these activities under each CTC alternative

  15. Fundamental Understanding of Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors

    SciTech Connect (OSTI)

    Iouri I. Balachov; Takao Kobayashi; Francis Tanzella; Indira Jayaweera; Palitha Jayaweera; Petri Kinnunen; Martin Bojinov; Timo Saario

    2004-11-17

    This work contributes to the design of safe and economical Generation-IV Super-Critical Water Reactors (SCWRs) by providing a basis for selecting structural materials to ensure the functionality of in-vessel components during the entire service life. During the second year of the project, we completed electrochemical characterization of the oxide film properties and investigation of crack initiation and propagation for candidate structural materials steels under supercritical conditions. We ranked candidate alloys against their susceptibility to environmentally assisted degradation based on the in situ data measure with an SRI-designed controlled distance electrochemistry (CDE) arrangement. A correlation between measurable oxide film properties and susceptibility of austenitic steels to environmentally assisted degradation was observed experimentally. One of the major practical results of the present work is the experimentally proven ability of the economical CDE technique to supply in situ data for ranking candidate structural materials for Generation-IV SCRs. A potential use of the CDE arrangement developed ar SRI for building in situ sensors monitoring water chemistry in the heat transport circuit of Generation-IV SCWRs was evaluated and proved to be feasible.

  16. The Capabilities and Limitation of Remote Visual Methods to Detect Service-Induced Cracks in Reactor Components

    SciTech Connect (OSTI)

    Cumblidge, Stephen E.; Doctor, Steven R.; Anderson, Michael T.

    2006-11-01

    Since 1977, the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research has funded a multiyear program at the Pacific Northwest National Laboratory (PNNL) to evaluate the reliability and accuracy of nondestructive evaluation (NDE) techniques employed for inservice inspection (ISI). Recently, the U.S. nuclear industry proposed replacing current volumetric and/or surface examinations of certain components in commercial nuclear power plants, as required by ASME Boiler and Pressure Vessel Code Section XI, with a simpler visual testing (VT) method. The advantages of VT are that these tests generally involve much less radiation exposure and examination times than do volumetric examinations such as ultrasonic testing (UT). However, for industry to justify supplamenting volumetric metods with VT, and analysis of pertinent issues is needed to support the reliability of VT in determining the structural intefrity of reactor components. As piping and pressure vessel compoents in a nuclear power station are generally underwater and in high radiation field, they need to be examined by VT from a distance with radiation-hardened video systems. Remote visual testing has been used by nuclear utilities to find cracks in pressure vessel cladding in pressurized water reactors, for shrouds in boiling water reactors, and to investigate leaks in piping and reactor components. These visual tests are performed using a wide variety of procedures and equipment. The techniques for remote visual testing use submersible closed-circuit video cameras to examine reactor components and welds. PNNL has conducted a parametric study that examines the important variables that affect the effectiveness of a remote visual test. Tested variables include lighting techniques, camera resolution, camera movement, and magnification. PNNL has also conductrd a laboratory test using a commercial visual testing camera system to experimentally determine the ability of the camera system to

  17. Thermalhydraulic calculation for boiling water reactor and its natural circulation component

    SciTech Connect (OSTI)

    Trianti, Nuri Nurjanah,; Su’ud, Zaki; Arif, Idam; Permana, Sidik

    2015-09-30

    Thermalhydraulic of reactor core is the thermal study on fluids within the core reactor, i.e. analysis of the thermal energy transfer process produced by fission reaction from fuel to the reactor coolant. This study include of coolant temperature and reactor power density distribution. The purposes of this analysis in the design of nuclear power plant are to calculate the coolant temperature distribution and the chimney height so natural circulation could be occurred. This study was used boiling water reactor (BWR) with cylinder type reactor core. Several reactor core properties such as linear power density, mass flow rate, coolant density and inlet temperature has been took into account to obtain distribution of coolant density, flow rate and pressure drop. The results of calculation are as follows. Thermal hydraulic calculations provide the uniform pressure drop of 1.1 bar for each channels. The optimum mass flow rate to obtain the uniform pressure drop is 217g/s. Furthermore, from the calculation it could be known that outlet temperature is 288°C which is the saturated fluid’s temperature within the system. The optimum chimney height for natural circulation within the system is 14.88 m.

  18. DISMANTLING OF THE UPPER RPV COMPONENTS OF THE KARLSRUHE MULTI-PURPOSE RESEARCH REACTOR (MZFR), GERMANY

    SciTech Connect (OSTI)

    Prechtl, E.; Suessdorf, W.

    2003-02-27

    The Multi-purpose Research Reactor was a pressurized-water reactor cooled and moderated with heavy water. It was built from 1961 to 1966 and went critical for the first time on 29 September 1965. After nineteen years of successful operation, the reactor was de-activated on 3 May 1984. The reactor had a thermal output of 200 MW and an electrical output of 50 MW. The MZFR not only served to supply electrical power, but also as a test bed for: - research into various materials for reactor building (e. g. zirkaloy), - the manufacturing and operating industry to gain experience in erection and operation, - training scientific and technical reactor staff, and - power supply (first nuclear combined-heat-and-power system, 1979-1984). The experience gained in operating the MZFR was very helpful for the development and operation of power reactors. At first, safe containment and enclosure of the plant was planned, but then it was decided to dismantle the plant completely, step by step, in view o f the clear advantages of this approach. The decommissioning concept for the complete elimination of the plant down to a green-field site provides for eight steps. A separate decommissioning license is required for each step. As part of the dismantling, about 72,000 Mg [metric tons] of concrete and 7,200 Mg of metal (400 Mg RPV) must be removed. About 700 Mg of concrete (500 Mg biological shield) and 1300 Mg of metal must be classified as radioactive waste.

  19. Analytical Study of High Concentration PCB Paint at the Heavy Water Components Test Reactor

    SciTech Connect (OSTI)

    Lowry, N.J.

    1998-10-21

    This report provides results of an analytical study of high concentration PCB paint in a shutdown nuclear test reactor located at the US Department of Energy's Savannah River Site (SRS). The study was designed to obtain data relevant for an evaluation of potential hazards associated with the use of and exposure to such paints.

  20. Mechanical design of core components for a high performance light water reactor with a three pass core

    SciTech Connect (OSTI)

    Fischer, Kai; Schneider, Tobias; Redon, Thomas; Schulenberg, Thomas; Starflinger, Joerg

    2007-07-01

    Nuclear reactors using supercritical water as coolant can achieve more than 500 deg. C core outlet temperature, if the coolant is heated up in three steps with intermediate mixing to avoid hot streaks. This method reduces the peak cladding temperatures significantly compared with a single heat up. The paper presents an innovative mechanical design which has been developed recently for such a High Performance Light Water Reactor. The core is built with square assemblies of 40 fuel pins each, using wire wraps as grid spacers. Nine of these assemblies are combined to a cluster having a common head piece and a common foot piece. A downward flow of additional moderator water, separated from the coolant, is provided in gaps between the assemblies and in a water box inside each assembly. The cluster head and foot pieces and mixing chambers, which are key components for this design, are explained in detail. (authors)

  1. REACTOR

    DOE Patents [OSTI]

    Szilard, L.

    1963-09-10

    A breeder reactor is described, including a mass of fissionable material that is less than critical with respect to unmoderated neutrons and greater than critical with respect to neutrons of average energies substantially greater than thermal, a coolant selected from sodium or sodium--potassium alloys, a control liquid selected from lead or lead--bismuth alloys, and means for varying the quantity of control liquid in the reactor. (AEC)

  2. REACTOR

    DOE Patents [OSTI]

    Christy, R.F.

    1961-07-25

    A means is described for co-relating the essential physical requirements of a fission chain reaction in order that practical, compact, and easily controllable reactors can be built. These objects are obtained by employing a composition of fissionsble isotope and moderator in fluid form in which the amount of fissionsble isotcpe present governs the reaction. The size of the reactor is no longer a critical factor, the new criterion being the concentration of the fissionable isotope.

  3. INDEPENDENT CONFIRMATORY SURVEY REPORT FOR THE REACTOR BUILDING, HOT LABORATORY, PRIMARY PUMP HOUSE, AND LAND AREAS AT THE PLUM BROOK REACTOR FACILITY, SANDUSKY, OHIO

    SciTech Connect (OSTI)

    Erika N. Bailey

    2011-10-10

    In 1941, the War Department acquired approximately 9,000 acres of land near Sandusky, Ohio and constructed a munitions plant. The Plum Brook Ordnance Works Plant produced munitions, such as TNT, until the end of World War II. Following the war, the land remained idle until the National Advisory Committee for Aeronautics later called the National Aeronautics and Space Administration (NASA) obtained 500 acres to construct a nuclear research reactor designed to study the effects of radiation on materials used in space flight. The research reactor was put into operation in 1961 and was the first of fifteen test facilities eventually built by NASA at the Plum Brook Station. By 1963, NASA had acquired the remaining land at Plum Brook for these additional test facilities

  4. REACTOR

    DOE Patents [OSTI]

    Roman, W.G.

    1961-06-27

    A pressurized water reactor in which automatic control is achieved by varying the average density of the liquid moderator-cooiant is patented. Density is controlled by the temperature and power level of the reactor ftself. This control can be effected by the use of either plate, pellet, or tubular fuel elements. The fuel elements are disposed between upper and lower coolant plenum chambers and are designed to permit unrestricted coolant flow. The control chamber has an inlet opening communicating with the lower coolant plenum chamber and a restricted vapor vent communicating with the upper coolant plenum chamber. Thus, a variation in temperature of the fuel elements will cause a variation in the average moderator density in the chamber which directly affects the power level of the reactor.

  5. REACTORS

    DOE Patents [OSTI]

    Spitzer, L. Jr.

    1961-10-01

    Thermonuclear reactors, methods, and apparatus are described for controlling and confining high temperature plasma. Main axial confining coils in combination with helical windings provide a rotational transform that avoids the necessity of a figure-eight shaped reactor tube. The helical windings provide a multipolar helical magnetic field transverse to the axis of the main axial confining coils so as to improve the effectiveness of the confining field by counteracting the tendency of the more central lines of force in the stellarator tube to exchange positions with the magnetic lines of force nearer the walls of the tube. (AEC)

  6. Apparatus, components and operating methods for circulating fluidized bed transport gasifiers and reactors

    DOE Patents [OSTI]

    Vimalchand, Pannalal; Liu, Guohai; Peng, Wan Wang

    2015-02-24

    The improvements proposed in this invention provide a reliable apparatus and method to gasify low rank coals in a class of pressurized circulating fluidized bed reactors termed "transport gasifier." The embodiments overcome a number of operability and reliability problems with existing gasifiers. The systems and methods address issues related to distribution of gasification agent without the use of internals, management of heat release to avoid any agglomeration and clinker formation, specific design of bends to withstand the highly erosive environment due to high solid particles circulation rates, design of a standpipe cyclone to withstand high temperature gasification environment, compact design of seal-leg that can handle high mass solids flux, design of nozzles that eliminate plugging, uniform aeration of large diameter Standpipe, oxidant injection at the cyclone exits to effectively modulate gasifier exit temperature and reduction in overall height of the gasifier with a modified non-mechanical valve.

  7. Insights for aging management of light water reactor components: Metal containments. Volume 5

    SciTech Connect (OSTI)

    Shah, V.N.; Sinha, U.P.; Smith, S.K.

    1994-03-01

    This report evaluates the available technical information and field experience related to management of aging damage to light water reactor metal containments. A generic aging management approach is suggested for the effective and comprehensive aging management of metal containments to ensure their safe operation. The major concern is corrosion of the embedded portion of the containment vessel and detection of this damage. The electromagnetic acoustic transducer and half-cell potential measurement are potential techniques to detect corrosion damage in the embedded portion of the containment vessel. Other corrosion-related concerns include inspection of corrosion damage on the inaccessible side of BWR Mark I and Mark II containment vessels and corrosion of the BWR Mark I torus and emergency core cooling system piping that penetrates the torus, and transgranular stress corrosion cracking of the penetration bellows. Fatigue-related concerns include reduction in the fatigue life (a) of a vessel caused by roughness of the corroded vessel surface and (b) of bellows because of any physical damage. Maintenance of surface coatings and sealant at the metal-concrete interface is the best protection against corrosion of the vessel.

  8. Method for producing components with internal architectures, such as micro-channel reactors, via diffusion bonding sheets

    DOE Patents [OSTI]

    Alman, David E.; Wilson, Rick D.; Davis, Daniel L.

    2011-03-08

    This invention relates to a method for producing components with internal architectures, and more particularly, this invention relates to a method for producing structures with microchannels via the use of diffusion bonding of stacked laminates. Specifically, the method involves weakly bonding a stack of laminates forming internal voids and channels with a first generally low uniaxial pressure and first temperature such that bonding at least between the asperites of opposing laminates occurs and pores are isolated in interfacial contact areas, followed by a second generally higher isostatic pressure and second temperature for final bonding. The method thereby allows fabrication of micro-channel devices such as heat exchangers, recuperators, heat-pumps, chemical separators, chemical reactors, fuel processing units, and combustors without limitation on the fin aspect ratio.

  9. Protective structures on the surface of zirconium components of light water reactor cores: Formation, testing, and prototype equipment

    SciTech Connect (OSTI)

    Begrambekov, L. B.; Gordeev, A. A.; Evsin, A. E. Ivanova, S. V.; Kaplevsky, A. S.; Sadovskiy, Ya. A.

    2015-12-15

    The results of tests of plasma treatment of zirconium and deposition of protective yttrium coatings used as the methods of protection of zirconium components of light water reactor cores against hydrogenation are detailed. The amount of hydrogen in the treated sample exposed to superheated steam for 2500 h at temperature T = 400°C and pressure p = 1 atm was five times lower than the corresponding value for the untreated one. The amount of hydrogen in the sample coated with yttrium remained almost unchanged in 4000 h of exposure. A plasma method for rapid testing for hydrogen resistance is proposed. The hydrogenation rate provided by this method is 700 times higher than that in tests with superheated steam. The results of preliminary experiments confirm the possibility of constructing a unit for batch processing of the surfaces of fuel rod claddings.

  10. Balance of Plant System Analysis and Component Design of Turbo-Machinery for High Temperature Gas Reactor Systems

    SciTech Connect (OSTI)

    Ballinger, Ronald G.; Wang, Chun Yun; Kadak, Andrew; Todreas, Neil; Mirick, Bradley; Demetri, Eli; Koronowski, Martin

    2004-08-30

    The Modular Pebble Bed Reactor system (MPBR) requires a gas turbine cycle (Brayton cycle) as the power conversion system for it to achieve economic competitiveness as a Generation IV nuclear system. The availability of controllable helium turbomachinery and compact heat exchangers are thus the critical enabling technology for the gas turbine cycle. The development of an initial reference design for an indirect helium cycle has been accomplished with the overriding constraint that this design could be built with existing technology and complies with all current codes and standards. Using the initial reference design, limiting features were identified. Finally, an optimized reference design was developed by identifying key advances in the technology that could reasonably be expected to be achieved with limited R&D. This final reference design is an indirect, intercooled and recuperated cycle consisting of a three-shaft arrangement for the turbomachinery system. A critical part of the design process involved the interaction between individual component design and overall plant performance. The helium cycle overall efficiency is significantly influenced by performance of individual components. Changes in the design of one component, a turbine for example, often required changes in other components. To allow for the optimization of the overall design with these interdependencies, a detailed steady state and transient control model was developed. The use of the steady state and transient models as a part of an iterative design process represents a key contribution of this work. A dynamic model, MPBRSim, has been developed. The model integrates the reactor core and the power conversion system simultaneously. Physical parameters such as the heat exchangers; weights and practical performance maps such as the turbine characteristics and compressor characteristics are incorporated into the model. The individual component models as well as the fully integrated model of the

  11. The role of trace impurities in classification of in-core reactor components. Final report

    SciTech Connect (OSTI)

    Luksic, A.T.; Pauley, K.A.; Reid, B.d.

    1993-08-01

    Low-level radioactive waste is classified into three distinct categories under Title 10 of the Code of Federal Regulations Part 61 (10CFR61). These categories, Class A, B, and C, are determined by the concentrations of specified radionuclides, with Class C being the most restrictive. Waste which is determined to exceed the Class C limits is referred to as Greater Than Class C (GTCC) and is generally deemed to be unacceptable for disposal in a shallow land burial site. Under the Low-Level Waste Policy Act Amendments of 1985 (Public Law 99-240), the responsibility for disposal of waste classified as GTCC rests with the US government. To provide a better understanding of the elemental constituents that are present in nuclear fuel related materials, 41 samples of unirradiated materials used in the manufacture of fuel assembly hardware and nonfuel assembly components were obtained and analyzed. Particular emphasis was placed on evaluating the concentration of niobium in Zircaloy. The results of this work indicate that insignificant amounts of niobium are found in the current generation of Zircaloy. However, the reason for the inconsistency between the trace amounts of elemental niobium (<10 ppM) observed in the current analysis and the significant amounts (>100 ppM) that were observed in the previous analysis has not been identified.

  12. Reactor

    DOE Patents [OSTI]

    Evans, Robert M.

    1976-10-05

    1. A neutronic reactor having a moderator, coolant tubes traversing the moderator from an inlet end to an outlet end, bodies of material fissionable by neutrons of thermal energy disposed within the coolant tubes, and means for circulating water through said coolant tubes characterized by the improved construction wherein the coolant tubes are constructed of aluminum having an outer diameter of 1.729 inches and a wall thickness of 0.059 inch, and the means for circulating a liquid coolant through the tubes includes a source of water at a pressure of approximately 350 pounds per square inch connected to the inlet end of the tubes, and said construction including a pressure reducing orifice disposed at the inlet ends of the tubes reducing the pressure of the water by approximately 150 pounds per square inch.

  13. Argonne Liquid-Metal Advanced Burner Reactor : components and in-vessel system thermal-hydraulic research and testing experience - pathway forward.

    SciTech Connect (OSTI)

    Kasza, K.; Grandy, C.; Chang, Y.; Khalil, H.; Nuclear Engineering Division

    2007-06-30

    This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition from normal high

  14. Light Water Reactor Sustainability Technical Documents | Department...

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

    in Light Water Reactors: Life After 60 Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high...

  15. HWMA/RCRA CLOSURE PLAN FOR THE MATERIALS TEST REACTOR WING (TRA-604) LABORATORY COMPONENTS VOLUNTARY CONSENT ORDER ACTION PLAN VCO-5.8 D REVISION2

    SciTech Connect (OSTI)

    KIRK WINTERHOLLER

    2008-02-25

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the laboratory components of the Test Reactor Area Catch Tank System (TRA-630) that are located in the Materials Test Reactor Wing (TRA-604) at the Reactor Technology Complex, Idaho National Laboratory Site, to meet a further milestone established under Voluntary Consent Order Action Plan VCO-5.8.d. The TRA-604 laboratory components addressed in this closure plan were deferred from the TRA-630 Catch Tank System closure plan due to ongoing laboratory operations in the areas requiring closure actions. The TRA-604 laboratory components include the TRA-604 laboratory warm wastewater drain piping, undersink drains, subheaders, and the east TRA-604 laboratory drain header. Potentially contaminated surfaces located beneath the TRA-604 laboratory warm wastewater drain piping and beneath the island sinks located in Laboratories 126 and 128 (located in TRA-661) are also addressed in this closure plan. The TRA-604 laboratory components will be closed in accordance with the interim status requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, Subparts G and J. This closure plan presents the closure performance standards and the methods for achieving those standards.

  16. Energy House

    K-12 Energy Lesson Plans and Activities Web site (EERE)

    Students learn about energy conservation and efficiency by using various materials to insulate a cardboard house.

  17. Technical Letter Report, An Evaluation of Ultrasonic Phased Array Testing for Reactor Piping System Components Containing Dissimilar Metal Welds, JCN N6398, Task 2A

    SciTech Connect (OSTI)

    Diaz, Aaron A.; Cinson, Anthony D.; Crawford, Susan L.; Anderson, Michael T.

    2009-11-30

    Research is being conducted for the U.S. Nuclear Regulatory Commission at the Pacific Northwest National Laboratory to assess the effectiveness and reliability of advanced nondestructive examination (NDE) methods for the inspection of light-water reactor components. The scope of this research encom¬passes primary system pressure boundary materials including dissimilar metal welds (DMWs), cast austenitic stainless steels (CASS), piping with corrosion-resistant cladding, weld overlays, inlays and onlays, and far-side examinations of austenitic piping welds. A primary objective of this work is to evaluate various NDE methods to assess their ability to detect, localize, and size cracks in steel components that challenge standard and/or conventional inspection methodologies. This interim technical letter report provides a summary of a technical evaluation aimed at assessing the capabilities of phased-array (PA) ultrasonic testing (UT) methods as applied to the inspection of small-bore DMW components that exist in the reactor coolant systems (RCS) of pressurized water reactors (PWRs). Operating experience and events such as the circumferential cracking in the reactor vessel nozzle-to-RCS hot leg pipe at V.C. Summer nuclear power station, identified in 2000, show that in PWRs where primary coolant water (or steam) are present under normal operation, Alloy 82/182 materials are susceptible to pressurized water stress corrosion cracking. The extent and number of occurrences of DMW cracking in nuclear power plants (domestically and internationally) indicate the necessity for reliable and effective inspection techniques. The work described herein was performed to provide insights for evaluating the utility of advanced NDE approaches for the inspection of DMW components such as a pressurizer surge nozzle DMW, a shutdown cooling pipe DMW, and a ferritic (low-alloy carbon steel)-to-CASS pipe DMW configuration.

  18. Education Office Housing

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

    Education Office Housing Housing A housing forum and listings for housing in and around Los Alamos. Contact Postdoc Housing Email LANL Students' Association Email LANL postdoc...

  19. Nuclear reactor with low-level core coolant intake

    DOE Patents [OSTI]

    Challberg, Roy C.; Townsend, Harold E.

    1993-01-01

    A natural-circulation boiling-water reactor has skirts extending downward from control rod guide tubes to about 10 centimeters from the reactor vessel bottom. The skirts define annular channels about control rod drive housings that extend through the reactor vessel bottom. Recirculating water is forced in through the low-level entrances to these channels, sweeping bottom water into the channels in the process. The sweeping action prevents cooler water from accumulating at the bottom. This in turn minimizes thermal shock to bottom-dwelling components as would occur when accumulated cool water is swept away and suddenly replaced by warmer water.

  20. Steam Generator Component Model in a Combined Cycle of Power Conversion Unit for Very High Temperature Gas-Cooled Reactor

    SciTech Connect (OSTI)

    Oh, Chang H; Han, James; Barner, Robert; Sherman, Steven R

    2007-06-01

    The Department of Energy and the Idaho National Laboratory are developing a Next Generation Nuclear Plant (NGNP), Very High Temperature Gas-Cooled Reactor (VHTR) to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold 1) efficient low cost energy generation and 2) hydrogen production. Although a next generation plant could be developed as a single-purpose facility, early designs are expected to be dual-purpose. While hydrogen production and advanced energy cycles are still in its early stages of development, research towards coupling a high temperature reactor, electrical generation and hydrogen production is under way. A combined cycle is considered as one of the power conversion units to be coupled to the very high-temperature gas-cooled reactor (VHTR). The combined cycle configuration consists of a Brayton top cycle coupled to a Rankine bottoming cycle by means of a steam generator. A detailed sizing and pressure drop model of a steam generator is not available in the HYSYS processes code. Therefore a four region model was developed for implementation into HYSYS. The focus of this study was the validation of a HYSYS steam generator model of two phase flow correlations. The correlations calculated the size and heat exchange of the steam generator. To assess the model, those calculations were input into a RELAP5 model and its results were compared with HYSYS results. The comparison showed many differences in parameters such as the heat transfer coefficients and revealed the different methods used by the codes. Despite differences in approach, the overall results of heat transfer were in good agreement.

  1. Meadowlark House

    Broader source: Energy.gov [DOE]

    This poster describes the energy efficiency features and sustainable materials used in the Greensburg GreenTown Chain of Eco-Homes Meadowlark House in Greensburg, Kansas.

  2. " Million Housing Units, Final...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters ... Vacant housing units, seasonal units, second homes, military housing, and group quarters ...

  3. " Million Housing Units, Final"

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters ... Vacant housing units, seasonal units, second homes, military housing, and group quarters ...

  4. Open House Archive | Jefferson Lab

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

    Open House Archive 2014 Open House 2012 Open House 2010 Open House 2007 Open House 2005 Open House 2003 Open House 2001 Open House Back to the main Open House Page

  5. Student Housing

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

    In order to create a profile you will need a temporary access password. If you would like to take advantage of this housing resource you can request an access password at: ...

  6. Building America Case Study: Philadelphia Housing Authority Energy...

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

    Philadelphia Housing Authority Energy-Efficiency Turnover Protocols Philadelphia, Pennsylvania ... Building Component: Whole-building Application: Retrofit; multifamily Year Tested: ...

  7. Congressional Delegation visits Naval Reactors Facility | National...

    National Nuclear Security Administration (NNSA)

    Chuck Fleischmann of the House Appropriations Subcommittee on Energy and Water Development, visited the Naval Reactors Facility (NRF) at the Idaho National Laboratory (INL). ...

  8. Education Office Housing

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

    Education Office Housing Housing A housing forum and listings for housing in and around Los Alamos. Contact Postdoc Housing Email LANL Students' Association Email LANL postdoc program housing The Lab's postdoc program has a postdoc housing listing. If you are interested in posting a housing opportunity, send an email with the pertinent information to postdocprogram@lanl.gov. Housing listings will be posted for 1 month. If you wish for the listing to remain on the web site longer, please contact

  9. " Million Housing Units, Final...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Use of central air conditioning equipment for another housing unit also ...

  10. " Million Housing Units, Final...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Housing units are classified as urban or rural using definitions created by ...

  11. " Million Housing Units, Final...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Use of heating equipment for another housing unit also includes the use of ...

  12. " Million Housing Units, Final"

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Use of central air conditioning equipment for another housing unit also ...

  13. Forward House

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

    Space Heating and Ventilation Forward House UW-Madison UW-Milwaukee Faculty Advisors Professor Mark Keane | UW-Milwaukee Dr. Michael Cheadle | UW-Madison Professor Lesley Sager | UW-Madison Nic Dan Laura Jake Rob Jonnie Nasim Drew 1 2 Industry Partners Special Thanks to Professionals Professor Linda Keane | The School of the Art Institute of Chicago Cozette Moffatt | Interior Designer Students Emily Cruz | UW-Madison Marilyn Grace Cervantes | UW-Madison Rebecca Cohn | UW-Madison S t o r y A r c

  14. 1997 Housing Characteristics Tables Housing Unit Tables

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

    Million U.S. Households; 45 pages, 128 kb) Contents Pages HC1-1a. Housing Unit Characteristics by Climate Zone, Million U.S. Households, 1997 4 HC1-2a. Housing Unit Characteristics by Year of Construction, Million U.S. Households, 1997 4 HC1-3a. Housing Unit Characteristics by Household Income, Million U.S. Households, 1997 4 HC1-4a. Housing Unit Characteristics by Type of Housing Unit, Million U.S. Households, 1997 3 HC1-5a. Housing Unit Characteristics by Type of Owner-Occupied Housing Unit,

  15. Materials Degradation in Light Water Reactors: Life After 60

    Broader source: Energy.gov [DOE]

    Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field....

  16. Superinsulated houses

    SciTech Connect (OSTI)

    Shurcliff, W.A.

    1986-01-01

    Superinsulation is a direct response to the fast-rising cost of home heating. Of the many kinds of responses, superinsulation is proving to be the simplest and most cost-effective. Until the oil embargo of 1973 there was little interest in saving heat. When the oil shortage arrived and fuel costs doubled and redoubled, many architects responded, at first, by invoking solar energy. They examined the designs of existing solar-heated houses and proposed a great variety of new designs, most of which appeared - to the uninitiated - to have great promise. Most of the early designs were of the active type; some were of the passive type; a few were of the hybrid design.

  17. 1997 Housing Characteristics Tables Housing Unit Tables

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

    Percent of U.S. Households; 45 pages, 121 kb) Contents Pages HC1-1b. Housing Unit Characteristics by Climate Zone, Percent of U.S. Households, 1997 4 HC1-2b. Housing Unit Characteristics by Year of Construction, Percent of U.S. Households, 1997 4 HC1-3b. Housing Unit Characteristics by Household Income, Percent of U.S. Households, 1997 4 HC1-4b. Housing Unit Characteristics by Type of Housing Unit, Percent of U.S. Households, 1997 3 HC1-5b. Housing Unit Characteristics by Type of Owner-Occupied

  18. DOE ZERH Case Study: Mutual Housing California, Mutual Housing...

    Office of Scientific and Technical Information (OSTI)

    Housing California, Mutual Housing at Spring Lake, Woodland, CA Case study of a DOE 2015 Housing Innovation Award winning multifamily project of 62 affordable-housing...

  19. 2015 Arizona Housing Forum

    Broader source: Energy.gov [DOE]

    The 12th annual Arizona Housing Forum provides a platform for affordable housing professionals to network and share ideas to improve and create housing choices for Arizona. Registration is $350.

  20. Developing Alaskan Sustainable Housing

    Broader source: Energy.gov [DOE]

    The Association of Alaska Housing Authorities is holding a 3-day training event for housing development professionals titled Developing Alaskan Sustainable Housing (DASH). This is a unique...

  1. " Million Housing Units, Final...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Cooking includes fuels used by the major cooking equipment (ovens, cooktops, ...

  2. Advanced Nuclear Reactors | Department of Energy

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

    Advanced Nuclear Reactors Advanced Nuclear Reactors Turbulent Flow of Coolant in an Advanced Nuclear Reactor Visualizing Coolant Flow in Sodium Reactor Subassemblies Sodium-cooled Fast Reactor (SFR) Coolant Flow At the heart of a nuclear power plant is the reactor. The fuel assembly is placed inside a reactor vessel where all the nuclear reactions occur to produce the heat and steam used for power generation. Nonetheless, an entire power plant consists of many other support components and key

  3. Nuclear component horizontal seismic restraint

    DOE Patents [OSTI]

    Snyder, Glenn J.

    1988-01-01

    A nuclear component horizontal seismic restraint. Small gaps limit horizontal displacement of components during a seismic occurrence and therefore reduce dynamic loadings on the free lower end. The reactor vessel and reactor guard vessel use thicker section roll-forged rings welded between the vessel straight shell sections and the bottom hemispherical head sections. The inside of the reactor guard vessel ring forging contains local vertical dovetail slots and upper ledge pockets to mount and retain field fitted and installed blocks. As an option, the horizontal displacement of the reactor vessel core support cone can be limited by including shop fitted/installed local blocks in opposing alignment with the reactor vessel forged ring. Beams embedded in the wall of the reactor building protrude into apertures in the thermal insulation shell adjacent the reactor guard vessel ring and have motion limit blocks attached thereto to provide to a predetermined clearance between the blocks and reactor guard vessel ring.

  4. Protocol for House Parties

    Broader source: Energy.gov [DOE]

    Protocol for House Parties, from the Tool Kit Framework: Small Town University Energy Program (STEP).

  5. Reactor Materials Program - Baseline Material Property Handbook - Mechanical Properties of 1950's Vintage Stainless Steel Weldment Components, Task Number 89-23-A-1

    SciTech Connect (OSTI)

    Stoner, K.J.

    1999-11-05

    The Process Water System (primary coolant) piping of the nuclear production reactors constructed in the 1950''s at Savannah River Site is comprised primarily of Type 304 stainless steel with Type 308 stainless steel weld filler. A program to measure the mechanical properties of archival PWS piping and weld materials (having approximately six years of service at temperatures between 25 and 100 degrees C) has been completed. The results from the mechanical testing has been synthesized to provide a mechanical properties database for structural analyses of the SRS piping.

  6. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, Daniel L.

    1988-01-01

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

  7. AHFC Affordable Housing Summit

    Broader source: Energy.gov [DOE]

    The Alaska Housing Finance Corporation (AHFC) is hosting a summit to bring together Alaskans from across the state to identify the barriers and seek budget-neutral solutions to the numerous housing challenges facing Alaskans.

  8. " Million Housing Units, Final...

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

    Water Heating in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ... Units","5 or More Units","Mobile Homes" "Water Heating" "Total Homes",113.6,71.8,6.7,9,19...

  9. " Million Housing Units, Final...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Energy Star is a joint program of the U.S. Environmental Protection Agency ...

  10. 2015 Housing Innovation Awards

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy’s (DOE) Housing Innovation Awards recognize the very best in innovation on the path to zero energy ready homes. DOE Zero Energy Ready Home (ZERH) Housing Innovation...

  11. Energy efficient industrialized housing research program

    SciTech Connect (OSTI)

    Berg, R.; Brown, G.Z.; Finrow, J.; Kellett, R.; McDonald, M.; McGinn, B.; Ryan, P.; Sekiguchi, Tomoko . Center for Housing Innovation); Chandra, S.; Elshennawy, A.K.; Fairey, P.; Harrison, J.; Mazwell, L.; Roland, J.; Swart, W. )

    1989-12-01

    This document describes the research work completed in five areas in fiscal year 1989. (1) The analysis of the US industrialized housing industry includes statistics, definitions, a case study, and a code analysis. (2) The assessment of foreign technology reviews the current status of design, manufacturing, marketing, and installation of industrialized housing primarily in Sweden and Japan. (3) Assessment of industrialization applications reviews housing production by climate zone, has a cost and energy comparison of Swedish and US housing, and discusses future manufacturing processes and emerging components. (4) The state of computer use in the industry is described and a prototype design tool is discussed. (5) Side by side testing of industrialized housing systems is discussed.

  12. Insulator for laser housing

    DOE Patents [OSTI]

    Duncan, D.B.

    1992-12-29

    The present invention provides a heat-resistant electrical insulator adapted for joining laser housing portions, which insulator comprises: an annulus; a channel in the annulus traversing the circumference and length of the housing; at least two ports, each communicating with the channel and an outer surface of the housing; and an attachment for securely attaching each end of the annulus to a laser housing member. 3 figs.

  13. Nuclear reactor shutdown system

    DOE Patents [OSTI]

    Bhate, Suresh K.; Cooper, Martin H.; Riffe, Delmar R.; Kinney, Calvin L.

    1981-01-01

    An inherent shutdown system for a nuclear reactor having neutron absorbing rods affixed to an armature which is held in an upper position by a magnetic flux flowing through a Curie temperature material. The Curie temperature material is fixedly positioned about the exterior of an inner duct in an annular region through which reactor coolant flows. Elongated fuel rods extending from within the core upwardly toward the Curie temperature material are preferably disposed within the annular region. Upon abnormal conditions which result in high neutron flux and coolant temperature, the Curie material loses its magnetic permeability, breaking the magnetic flux path and allowing the armature and absorber rods to drop into the core, thus shutting down the fissioning reaction. The armature and absorber rods are retrieved by lowering the housing for the electromagnet forming coils which create a magnetic flux path which includes the inner duct wall. The coil housing then is raised, resetting the armature.

  14. Small Modular Nuclear Reactors: Parametric Modeling of Integrated...

    Office of Environmental Management (EM)

    Reactor Vessel Manufacturing Within a Factory Environment - Volume 1 This study focused on the learning process for the factory built components of the Integrated Reactor ...

  15. 1997 Housing Characteristics Tables Housing Unit Tables

    Gasoline and Diesel Fuel Update (EIA)

    Contact: Robert Latta, Survey Manager (rlatta@eia.doe.gov) World Wide Web: http:www.eia.doe.govemeuconsumption Table HC1-1a. Housing Unit Characteristics by Climate Zone, ...

  16. EcoHouse Program Overview

    Broader source: Energy.gov [DOE]

    Provides an overview of the Indianapolis Better Buildings program, the EcoHouse program, and Indianapolis Neighborhood Housing partnership (INHP).

  17. HIGH TEMPERATURE, HIGH POWER HETEROGENEOUS NUCLEAR REACTOR

    DOE Patents [OSTI]

    Hammond, R.P.; Wykoff, W.R.; Busey, H.M.

    1960-06-14

    A heterogeneous nuclear reactor is designed comprising a stationary housing and a rotatable annular core being supported for rotation about a vertical axis in the housing, the core containing a plurality of radial fuel- element supporting channels, the cylindrical empty space along the axis of the core providing a central plenum for the disposal of spent fuel elements, the core cross section outer periphery being vertically gradated in radius one end from the other to provide a coolant duct between the core and the housing, and means for inserting fresh fuel elements in the supporting channels under pressure and while the reactor is in operation.

  18. H. R. 1001: A Bill to authorize appropriations for the Reduced Enrichment Research and Test Reactors Program of the Department of Energy. Introduced in the House of Representatives, One Hundred Third Congress, First Session, February 18, 1993

    SciTech Connect (OSTI)

    Not Available

    1993-01-01

    This Act may be cited as the [open quotes]Bomb-Grade Uranium Export Substitution Act of 1993[close quotes]. The purpose of this Bill is to authorize appropriations for the Reduced Enrichment Research and Test Reactors Program of the Department of Energy. This document presents Congressional findings and a statement of authorization of appropriations.

  19. Detachable connection for a nuclear reactor fuel assembly

    DOE Patents [OSTI]

    Christiansen, David W.; Karnesky, Richard A.

    1986-01-01

    A locking connection for releasably attaching a handling socket to the duct tube of a fuel assembly for a nuclear reactor. The connection comprises a load pad housing mechanically attached to the duct tube and a handling socket threadably secured within the housing. A retaining ring is interposed between the housing and the handling socket and is formed with a projection and depression engageable within a cavity and groove of the housing and handling socket, respectively, to form a detachable interlocked connection assembly.

  20. Detachable connection for a nuclear reactor fuel assembly

    DOE Patents [OSTI]

    Christiansen, D.W.; Karnesky, R.A.

    1983-08-29

    A locking connection for releasably attaching a handling socket to the duct tube of a fuel assembly for a nuclear reactor. The connection comprises a load pad housing mechanically attached to the duct tube and a handling socket threadably secured within the housing. A retaining ring is interposed between the housing and the handling socket and is formed with a projection and depression engagable within a cavity and groove of the housing and handling socket, respectively, to form a detachable interlocked connection assembly.

  1. " Million Housing Units, Final...

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

    Characteristics of U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" "Structural and ...

  2. " Million Housing Units, Final...

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

    "Routine Service or Maintenance" "Performed on Main Heating Equipment3" ... 3Only includes routine service or maintenance performed in the last year. 4Housing ...

  3. " Million Housing Units, Final...

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

    ... "Routine Service or Maintenance" "Performed on Main Heating Equipment3" ... 3Only includes routine service or maintenance performed in the last year. 4Housing ...

  4. " Million Housing Units, Final...

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

    ... "Routine Service or Maintenance" "Performed on Main Heating Equipment4" ... 4Only includes routine service or maintenance performed in the last year. 5Housing ...

  5. " Million Housing Units, Final...

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

    4 Water Heating in U.S. Homes, by Number of Household Members, 2009" " Million Housing ... (millions)" ,,,,,,"5 or More Members" "Water Heating",,"1 Member","2 Members","3 ...

  6. Solar Affordable Housing Program

    Office of Environmental Management (EM)

    Solar Affordable Housing Program Why Solar for Tribes ... from a clean, renewable energy source Green jobs training ... with Other Tribal Communities The Great Plains Montana ...

  7. " Million Housing Units, Final...

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

    ... central air conditioning equipment for a business or farm building as well as another ... for Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in Buildings With" ...

  8. " Million Housing Units, Final...

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

    ... central air conditioning equipment for a business or farm building as well as another ... ,,"RSEs for Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ...

  9. Obama Administration Announces $450 Million to Design and Commercialize U.S. Small Modular Nuclear Reactors

    Broader source: Energy.gov [DOE]

    The White House announced new funding to advance the development of American-made small modular reactors (SMRs), an important element of the President’s energy strategy.

  10. Nuclear reactor

    DOE Patents [OSTI]

    Pennell, William E.; Rowan, William J.

    1977-01-01

    A nuclear reactor in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assmblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters and the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters and the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance.

  11. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Fermi, E.; Zinn, W.H.; Anderson, H.L.

    1958-09-16

    Means are presenied for increasing the reproduction ratio of a gaphite- moderated neutronic reactor by diminishing the neutron loss due to absorption or capture by gaseous impurities within the reactor. This means comprised of a fluid-tight casing or envelope completely enclosing the reactor and provided with a valve through which the casing, and thereby the reactor, may be evacuated of atmospheric air.

  12. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Martin Peng, Y.K.M.

    1985-10-03

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

  13. Nuclear reactor

    DOE Patents [OSTI]

    Yant, Howard W.; Stinebiser, Karl W.; Anzur, Gregory C.

    1977-01-01

    A nuclear reactor, particularly a liquid-metal breeder reactor, whose upper internals include outlet modules for channeling the liquid-metal coolant from selected areas of the outlet of the core vertically to the outlet plenum. The modules are composed of a highly-refractory, high corrosion-resistant alloy, for example, INCONEL-718. Each module is disposed to confine and channel generally vertically the coolant emitted from a subplurality of core-component assemblies. Each module has a grid with openings, each opening disposed to receive the coolant from an assembly of the subplurality. The grid in addition serves as a holdown for the assemblies of the corresponding subplurality preventing their excessive ejection upwardly from the core. In the region directly over the core the outlet modules are of such peripheral form that they nest forming a continuum over the core-component assemblies whose outlet coolant they confine. Each subassembly includes a chimney which confines the coolant emitted by its corresponding subassemblies to generally vertical flow between the outlet of the core and the outlet plenum. Each subplurality of assemblies whose emitted coolant is confined by an outlet module includes assemblies which emit lower-temperature coolant, for example, a control-rod assembly, or fertile assemblies, and assemblies which emit coolant of substantially higher temperature, for example, fuel-rod assemblies. The coolants of different temperatures are mixed in the chimneys reducing the effect of stripping (hot-cold temperature fluctuations) on the remainder of the upper internals which are composed typically of AISI-304 or AISI-316 stainless steel.

  14. Multiple pump housing

    DOE Patents [OSTI]

    Donoho, II, Michael R.; Elliott; Christopher M.

    2010-03-23

    A fluid delivery system includes a first pump having a first drive assembly, a second pump having a second drive assembly, and a pump housing. At least a portion of each of the first and second pumps are located in the housing.

  15. ,"Housing Units1","Average Square Footage Per Housing Unit",...

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

    ... includes households that occupy their primary housing unit without payment of rent. ... includes households that occupy their primary housing unit without payment of rent. ...

  16. ,"Housing Units1","Average Square Footage Per Housing Unit",...

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

    ... Vacant housing units, seasonal units, second homes, military housing, and group quarters are excluded. 2Total square footage includes all basements, finished or conditioned (heated ...

  17. Housing And Mounting Structure

    DOE Patents [OSTI]

    Anderson, Gene R.; Armendariz, Marcelino G.; Baca, Johnny R.F.; Bryan, Robert P.; Carson, Richard F.; Duckett, III, Edwin B.; McCormick, Frederick B.; Miller, Gregory V.; Peterson, David W.; Smith, Terrance T.

    2005-03-08

    This invention relates to an optical transmitter, receiver or transceiver module, and more particularly, to an apparatus for connecting a first optical connector to a second optical connector. The apparatus comprises: (1) a housing having at least a first end and at least a second end, the first end of the housing capable of receiving the first optical connector, and the second end of the housing capable of receiving the second optical connector; (2) a longitudinal cavity extending from the first end of the housing to the second end of the housing; and (3) an electromagnetic shield comprising at least a portion of the housing. This invention also relates to an apparatus for housing a flexible printed circuit board, and this apparatus comprises: (1) a mounting structure having at least a first surface and a second surface; (2) alignment ridges along the first and second surfaces of the mounting structure, the alignment ridges functioning to align and secure a flexible printed circuit board that is wrapped around and attached to the first and second surfaces of the mounting structure; and (3) a series of heat sink ridges adapted to the mounting structure, the heat sink ridges functioning to dissipate heat that is generated from the flexible printed circuit board.

  18. Developing Alaskan Sustainable Housing Training

    Broader source: Energy.gov [DOE]

    Hosted by the Association of Alaska Housing Authorities (AAHA), this three-day training event covers strategies and technical issues related to sustainable housing development.

  19. Whole-House Systems Approach

    Broader source: Energy.gov [DOE]

    A whole-house systems approach considers the house as an energy system with interdependent parts, each of which affects the performance of the entire system.

  20. Transducer for downhole drilling components

    DOE Patents [OSTI]

    Hall, David R; Fox, Joe R

    2006-05-30

    A robust transmission element for transmitting information between downhole tools, such as sections of drill pipe, in the presence of hostile environmental conditions, such as heat, dirt, rocks, mud, fluids, lubricants, and the like. The transmission element maintains reliable connectivity between transmission elements, thereby providing an uninterrupted flow of information between drill string components. A transmission element is mounted within a recess proximate a mating surface of a downhole drilling component, such as a section of drill pipe. The transmission element may include an annular housing forming a trough, an electrical conductor disposed within the trough, and an MCEI material disposed between the annular housing and the electrical conductor.

  1. " Million Housing Units, Final...

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

    3 Space Heating in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to ...

  2. " Million Housing Units, Final...

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

    3 Appliances in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to 1949","1950 ...

  3. " Million Housing Units, Final...

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

    Water Heating in U.S. Homes, by Census Region, 2009" " Million Housing Units, Final" ,,"Census Region" ,"Total U.S.1 (millions)" ,,"Northeast","Midwest","South","West" "Water ...

  4. " Million Housing Units, Final...

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

    3 Water Heating in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, ... to 1989","1990 to 1999","2000 to 2009" "Water Heating" "Total Homes",113.6,14.4,5.2,13.5...

  5. " Million Housing Units, Final...

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

    2 Water Heating in U.S. Homes, by OwnerRenter Status, 2009" " Million Housing Units, ...","Own","Rent","Own","Rent","Own","Rent" "Water Heating" "Total Homes",113.6,76.5,37.1,63....

  6. " Million Housing Units, Final...

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

    6 Water Heating in U.S. Homes, by Climate Region, 2009" " Million Housing Units, Final" ... Cold","Mixed- Humid","Mixed-Dry" "Water Heating",,"Cold",,"Hot-Dry","Hot-Humid","M...

  7. " Million Housing Units, Final...

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

    5 Water Heating in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ... to 119,999","120,000 or More" "Water Heating" "Total Homes",113.6,23.7,27.5,21....

  8. " Million Housing Units, Final...

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

    ... the use of the heating equipment for a business or farm building as well as another ... for Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in Buildings With" ...

  9. " Million Housing Units, Final...

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

    ... the use of the heating equipment for a business or farm building as well as another ... ,,"RSEs for Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ...

  10. " Million Housing Units, Final"

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

    ...",37.1,13.7,10.9,6,3.2,1.6,0.6,1.1,10.1 "Payment Method for Energy Bills" "All Paid by ... their primary housing unit without payment of rent. 4Participation in assistance ...

  11. Hood River Passive House

    SciTech Connect (OSTI)

    Hales, D.

    2013-03-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project.

  12. High flux reactor

    DOE Patents [OSTI]

    Lake, James A.; Heath, Russell L.; Liebenthal, John L.; DeBoisblanc, Deslonde R.; Leyse, Carl F.; Parsons, Kent; Ryskamp, John M.; Wadkins, Robert P.; Harker, Yale D.; Fillmore, Gary N.; Oh, Chang H.

    1988-01-01

    A high flux reactor is comprised of a core which is divided into two symetric segments housed in a pressure vessel. The core segments include at least one radial fuel plate. The spacing between the plates functions as a coolant flow channel. The core segments are spaced axially apart such that a coolant mixing plenum is formed between them. A channel is provided such that a portion of the coolant bypasses the first core section and goes directly into the mixing plenum. The outlet coolant from the first core segment is mixed with the bypass coolant resulting in a lower inlet temperature to the lower core segment.

  13. Repair welding of fusion reactor components

    SciTech Connect (OSTI)

    Chin, B.A.

    1993-05-15

    Experiments have shown that irradiated Type 316 stainless steel is susceptible to heat-affected-zone (HAZ) cracking upon cooling when welded using the gas tungsten arc (GTA) process under lateral constraint. The cracking has been hypothesized to be caused by stress-assisted helium bubble growth and rupture at grain boundaries. This study utilized an experimental welding setup which enabled different compressive stresses to be applied to the plates during welding. Autogenous GTA welds were produced in Type 316 stainless steel doped with 256 appm helium. The application of a compressive stress, 55 MPa, during welding suppressed the previously observed catastrophic cracking. Detailed examinations conducted after welding showed a dramatic change in helium bubble morphology. Grain boundary bubble growth along directions parallel to the weld was suppressed. Results suggest that stress-modified welding techniques may be used to suppress or eliminate helium-induced cracking during joining of irradiated materials.

  14. Bathtub Row Houses

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

    Bathtub Row Houses Manhattan Project in Los Alamos: Bathtub Row Houses Los Alamos was where efforts of the Manhattan Project came together to discover the science necessary to succeed-inventing the technical processes then producing and testing two nuclear devices. In Los Alamos, the park experience is a partnership among the Department of Energy, the National Park Service, private landowners, and Los Alamos County. Guest Cottage, Los Alamos Ranch School, 1942 6. Historical Museum Built as the

  15. BOILING REACTORS

    DOE Patents [OSTI]

    Untermyer, S.

    1962-04-10

    A boiling reactor having a reactivity which is reduced by an increase in the volume of vaporized coolant therein is described. In this system unvaporized liquid coolant is extracted from the reactor, heat is extracted therefrom, and it is returned to the reactor as sub-cooled liquid coolant. This reduces a portion of the coolant which includes vaporized coolant within the core assembly thereby enhancing the power output of the assembly and rendering the reactor substantially self-regulating. (AEC)

  16. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, D.L.

    1987-09-04

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

  17. Nuclear reactor construction with bottom supported reactor vessel

    DOE Patents [OSTI]

    Sharbaugh, John E.

    1987-01-01

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

  18. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Daniels, F.

    1959-10-27

    A reactor in which at least a portion of the moderator is in the form of movable refractory balls is described. In addition to their moderating capacity, these balls may serve as carriers for fissionable material or fertile material, or may serve in a coolant capacity to remove heat from the reactor. A pneumatic system is used to circulate the balls through the reactor.

  19. Data transmission element for downhole drilling components

    DOE Patents [OSTI]

    Hall, David R.; Hall, Jr., H. Tracy; Pixton, David S.; Dahlgren, Scott; Fox, Joe; Sneddon, Cameron; Briscoe, Michael

    2006-01-31

    A robust data transmission element for transmitting information between downhole components, such as sections of drill pipe, in the presence of hostile environmental conditions, such as heat, dirt, rocks, mud, fluids, lubricants, and the like. The data transmission element components include a generally U-shaped annular housing, a generally U-shaped magnetically conductive, electrically insulating element such as ferrite, and an insulated conductor. Features on the magnetically conducting, electrically insulating element and the annular housing create a pocket when assembled. The data transmission element is filled with a polymer to retain the components within the annular housing by filling the pocket with the polymer. The polymer can bond with the annular housing and the insulated conductor but preferably not the magnetically conductive, electrically insulating element. A data transmission element is mounted within a recess proximate a mating surface of a downhole drilling component, such as a section of drill pipe.

  20. CONVECTION REACTOR

    DOE Patents [OSTI]

    Hammond, R.P.; King, L.D.P.

    1960-03-22

    An homogeneous nuclear power reactor utilizing convection circulation of the liquid fuel is proposed. The reactor has an internal heat exchanger looated in the same pressure vessel as the critical assembly, thereby eliminating necessity for handling the hot liquid fuel outside the reactor pressure vessel during normal operation. The liquid fuel used in this reactor eliminates the necessity for extensive radiolytic gas rocombination apparatus, and the reactor is resiliently pressurized and, without any movable mechanical apparatus, automatically regulates itself to the condition of criticality during moderate variations in temperature snd pressure and shuts itself down as the pressure exceeds a predetermined safe operating value.

  1. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Bassett, C.H.

    1961-05-16

    A fuel element particularly adapted for use in nuclear reactors of high power density is offered. It has fissionable fuel pellet segments mounted in a tubular housing and defining a central passage in the fuel element. A burnable poison element extends through the central passage, which is designed to contain more poison material at the median portion than at the end portions thereby providing a more uniform hurnup and longer reactivity life.

  2. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Fraas, A.P.; Mills, C.B.

    1961-11-21

    A neutronic reactor in which neutron moderation is achieved primarily in its reflector is described. The reactor structure consists of a cylindrical central "island" of moderator and a spherical moderating reflector spaced therefrom, thereby providing an annular space. An essentially unmoderated liquid fuel is continuously passed through the annular space and undergoes fission while contained therein. The reactor, because of its small size, is particularly adapted for propulsion uses, including the propulsion of aircraft. (AEC)

  3. REACTOR COOLING

    DOE Patents [OSTI]

    Quackenbush, C.F.

    1959-09-29

    A nuclear reactor with provisions for selectively cooling the fuel elements is described. The reactor has a plurality of tubes extending throughout. Cylindrical fuel elements are disposed within the tubes and the coolant flows through the tubes and around the fuel elements. The fuel elements within the central portion of the reactor are provided with roughened surfaces of material. The fuel elements in the end portions of the tubes within the reactor are provlded with low conduction jackets and the fuel elements in the region between the central portion and the end portions are provided with smooth surfaces of high heat conduction material.

  4. In-situ Condition Monitoring of Components in Small Modular Reactors Using Process and Electrical Signature Analysis. Final report, volume 1. Development of experimental flow control loop, data analysis and plant monitoring

    SciTech Connect (OSTI)

    Upadhyaya, Belle; Hines, J. Wesley; Damiano, Brian; Mehta, Chaitanya; Collins, Price; Lish, Matthew; Cady, Brian; Lollar, Victor; de Wet, Dane; Bayram, Duygu

    2015-12-15

    The research and development under this project was focused on the following three major objectives: Objective 1: Identification of critical in-vessel SMR components for remote monitoring and development of their low-order dynamic models, along with a simulation model of an integral pressurized water reactor (iPWR). Objective 2: Development of an experimental flow control loop with motor-driven valves and pumps, incorporating data acquisition and on-line monitoring interface. Objective 3: Development of stationary and transient signal processing methods for electrical signatures, machinery vibration, and for characterizing process variables for equipment monitoring. This objective includes the development of a data analysis toolbox. The following is a summary of the technical accomplishments under this project: - A detailed literature review of various SMR types and electrical signature analysis of motor-driven systems was completed. A bibliography of literature is provided at the end of this report. Assistance was provided by ORNL in identifying some key references. - A review of literature on pump-motor modeling and digital signal processing methods was performed. - An existing flow control loop was upgraded with new instrumentation, data acquisition hardware and software. The upgrading of the experimental loop included the installation of a new submersible pump driven by a three-phase induction motor. All the sensors were calibrated before full-scale experimental runs were performed. - MATLAB-Simulink model of a three-phase induction motor and pump system was completed. The model was used to simulate normal operation and fault conditions in the motor-pump system, and to identify changes in the electrical signatures. - A simulation model of an integral PWR (iPWR) was updated and the MATLAB-Simulink model was validated for known transients. The pump-motor model was interfaced with the iPWR model for testing the impact of primary flow perturbations (upsets) on

  5. Hood River Passive House

    SciTech Connect (OSTI)

    Hales, David

    2014-01-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to "reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project. The design includes high R-Value assemblies, extremely tight construction, high performance doors and windows, solar thermal DHW, heat recovery ventilation, moveable external shutters and a high performance ductless mini-split heat pump. Cost analysis indicates that many of the measures implemented in this project did not meet the BA standard for cost neutrality. The ductless mini-split heat pump, lighting and advanced air leakage control were the most cost effective measures. The future challenge will be to value engineer the performance levels indicated here in modeling using production based practices at a significantly lower cost.

  6. Hood River Passive House

    SciTech Connect (OSTI)

    Hales, D.

    2014-01-01

    The Hood River Passive Project was developed by Root Design Build of Hood River Oregon using the Passive House Planning Package (PHPP) to meet all of the requirements for certification under the European Passive House standards. The Passive House design approach has been gaining momentum among residential designers for custom homes and BEopt modeling indicates that these designs may actually exceed the goal of the U.S. Department of Energy's (DOE) Building America program to reduce home energy use by 30%-50% (compared to 2009 energy codes for new homes). This report documents the short term test results of the Shift House and compares the results of PHPP and BEopt modeling of the project. The design includes high R-Value assemblies, extremely tight construction, high performance doors and windows, solar thermal DHW, heat recovery ventilation, moveable external shutters and a high performance ductless mini-split heat pump. Cost analysis indicates that many of the measures implemented in this project did not meet the BA standard for cost neutrality. The ductless mini-split heat pump, lighting and advanced air leakage control were the most cost effective measures. The future challenge will be to value engineer the performance levels indicated here in modeling using production based practices at a significantly lower cost.

  7. Nuclear reactor sealing system

    DOE Patents [OSTI]

    McEdwards, James A.

    1983-01-01

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

  8. " Million U.S. Housing Units"

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

    Unit" ,"Housing Units (millions)","Single-Family Units",,"Apartments in Buildings ... Housing Unit" ,"RSEs for Housing Units ","Single-Family Units",,"Apartments in Buildings ...

  9. " Million U.S. Housing Units"

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

    Housing Unit Characteristics by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to 1949","1950 ...

  10. THE WHITE HOUSE | Department of Energy

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

    THE WHITE HOUSE THE WHITE HOUSE THE WHITE HOUSE (13.56 KB) More Documents & Publications Audit Report: IG-0473 Lapse Documents Inspection Report: IG-0397

  11. OPEN HOUSE - Climate Prisms: Arctic

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

    OPEN HOUSE - Climate Prisms: Arctic OPEN HOUSE - Climate Prisms: Arctic WHEN: Jul 17, 2015 12:00 PM - 1:00 PM WHERE: Bradbury Science Museum 1350 Central Ave, Los Alamos, NM 87544, ...

  12. Manhattan Project: The "Big House"

    Office of Scientific and Technical Information (OSTI)

    The "Big House" was the dormitory for the Los Alamos Boys Ranch School. Students slept year-round on its unheated porches. During the Manhattan Project, the Big House contained, ...

  13. White House Tribal Youth Gathering

    Broader source: Energy.gov [DOE]

    The White House will host the first-ever White House Tribal Youth Gathering to provide American Indian and Alaska Native youth from across the country the opportunity to interact directly with senior Administration officials and the White House Council on Native American Affairs. Registration is due May 8, 2015.

  14. Housing characteristics 1993

    SciTech Connect (OSTI)

    1995-06-01

    This report, Housing Characteristics 1993, presents statistics about the energy-related characteristics of US households. These data were collected in the 1993 Residential Energy Consumption Survey (RECS) -- the ninth in a series of nationwide energy consumption surveys conducted since 1978 by the Energy Information Administration of the US Department of Energy. Over 7 thousand households were surveyed, representing 97 million households nationwide. A second report, to be released in late 1995, will present statistics on residential energy consumption and expenditures.

  15. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Moore, R.V.; Bowen, J.H.; Dent, K.H.

    1958-12-01

    A heterogeneous, natural uranium fueled, solid moderated, gas cooled reactor is described, in which the fuel elements are in the form of elongated rods and are dlsposed within vertical coolant channels ln the moderator symmetrically arranged as a regular lattice in groups. This reactor employs control rods which operate in vertical channels in the moderator so that each control rod is centered in one of the fuel element groups. The reactor is enclosed in a pressure vessel which ls provided with access holes at the top to facilitate loading and unloadlng of the fuel elements, control rods and control rod driving devices.

  16. House Simulation Protocols (Building America Benchmark) - Building...

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

    House Simulation Protocols (Building America Benchmark) - Building America Top Innovation House Simulation Protocols (Building America Benchmark) - Building America Top Innovation ...

  17. Strengthening Relationships Between Energy Programs and Housing...

    Energy Savers [EERE]

    Relationships Between Energy Programs and Housing Programs Strengthening Relationships Between Energy Programs and Housing Programs Better Buildings Residential Network Multifamily ...

  18. Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges

    Broader source: Energy.gov [DOE]

    The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR...

  19. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Hurwitz, H. Jr.; Brooks, H.; Mannal, C.; Payne, J.H.; Luebke, E.A.

    1959-03-24

    A reactor of the heterogeneous, liquid cooled type is described. This reactor is comprised of a central region of a plurality of vertically disposed elongated tubes surrounded by a region of moderator material. The central region is comprised of a central core surrounded by a reflector region which is surrounded by a fast neutron absorber region, which in turn is surrounded by a slow neutron absorber region. Liquid sodium is used as the primary coolant and circulates through the core which contains the fuel elements. Control of the reactor is accomplished by varying the ability of the reflector region to reflect neutrons back into the core of the reactor. For this purpose the reflector is comprised of moderator and control elements having varying effects on reactivity, the control elements being arranged and actuated by groups to give regulation, shim, and safety control.

  20. NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Wigner, E.P.

    1960-11-22

    A nuclear reactor is described wherein horizontal rods of thermal- neutron-fissionable material are disposed in a body of heavy water and extend through and are supported by spaced parallel walls of graphite.

  1. REACTOR SHIELD

    DOE Patents [OSTI]

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  2. Reactor apparatus

    DOE Patents [OSTI]

    Echtler, J. Paul

    1981-01-01

    A reactor apparatus for hydrocracking a polynuclear aromatic hydrocarbonaceous feedstock to produce lighter hydrocarbon fuels by contacting the hydrocarbonaceous feedstock with hydrogen in the presence of a molten metal halide catalyst.

  3. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  4. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Fermi, E.

    1960-04-01

    A nuclear reactor is described consisting of blocks of graphite arranged in layers, natural uranium bodies disposed in holes in alternate layers of graphite blocks, and coolant tubes disposed in the layers of graphite blocks which do not contain uranium.

  5. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  6. Islip Housing Authority Energy Efficiency Turnover Protocols, Islip, New York (Fact Sheet), Building America Case Study: Whole-House Solutions for Existing Homes, Building Technologies Office (BTO)

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

    Islip Housing Authority Energy Efficiency Turnover Protocols Islip, New York PROJECT INFORMATION Project Name: Islip Housing Authority Unit Turnover Retrofit Program Location: Islip, NY Partners: Islip Housing Authority, http://www.rhaonline.com/ Advanced Residential Integrated Solutions Collaborative (ARIES), http://levypartnership.com/ Building Component: Whole building Application: Retrofit; single and multifamily Year Tested: 2013 Applicable Climate Zone(s): All PERFORMANCE DATA Cost of

  7. Gas Reactor Plant Analyzer and Simulator for Hydrogen Production

    Energy Science and Technology Software Center (OSTI)

    2004-01-01

    This software is used to study and analyze various configurations of plant equipment for gas cooled nuclear reactor applications. The user of this software would likely be interested in optimizing the economic, safety, and operating performance of this type of reactor. The code provides the capability for the user through his input to configure networks of nuclear reactor components. The components available include turbine, compressor, heat exchanger, reactor core, coolers, bypass valves, and control systems.

  8. NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Vernon, H.C.

    1959-01-13

    A neutronic reactor of the heterogeneous, fluid cooled tvpe is described. The reactor is comprised of a pressure vessel containing the moderator and a plurality of vertically disposed channels extending in spaced relationship through the moderator. Fissionable fuel material is placed within the channels in spaced relationship thereto to permit circulation of the coolant fluid. Separate means are provided for cooling the moderator and for circulating a fluid coolant thru the channel elements to cool the fuel material.

  9. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  10. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Breden, C.R.; Dietrich, J.R.

    1961-06-20

    A water-soluble non-volatile poison may be introduced into a reactor to nullify excess reactivity. The poison is removed by passing a side stream of the water containing the soluble poison to an evaporation chamber. The vapor phase is returned to the reactor to decrease the concentration of soluble poison and the liquid phase is returned to increase the concentration of soluble poison.

  11. Performance House -- A Cold Climate Challenge Home

    SciTech Connect (OSTI)

    Puttagunta, S.; Grab, J.; Williamson, J.

    2013-08-01

    Working with builder partners on a test homes allows for vetting of whole-house building strategies to eliminate any potential unintended consequences prior to implementing these solution packages on a production scale. To support this research, CARB partnered with Preferred Builders Inc. on a high-performance test home in Old Greenwich, CT. The philosophy and science behind the 2,700 ft2 'Performance House' was based on the premise that homes should be safe, healthy, comfortable, durable, efficient, and adapt with the homeowners. The technologies and strategies used in the 'Performance House' were not cutting-edge, but simply 'best practices practiced'. The focus was on simplicity in construction, maintenance, and operation. When seeking a 30% source energy savings targets over a comparable 2009 IECC code-built home in the cold climate zone, nearly all components of a home must be optimized. Careful planning and design are critical. To help builders and architects seeking to match the performance of this home, a step-by-step guide through the building shell components of DOE's Challenge Home are provided in a pictorial story book. The end result was a DOE Challenge Home that achieved a HERS Index Score of 20 (43 without PV, the minimum target was 55 for compliance). This home was also awarded the 2012 HOBI for Best Green Energy Efficient Home from the Home Builders & Remodelers Association of Connecticut.

  12. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Grebe, J.J.

    1959-07-14

    High temperature reactors which are uniquely adapted to serve as the heat source for nuclear pcwered rockets are described. The reactor is comprised essentially of an outer tubular heat resistant casing which provides the main coolant passageway to and away from the reactor core within the casing and in which the working fluid is preferably hydrogen or helium gas which is permitted to vaporize from a liquid storage tank. The reactor core has a generally spherical shape formed entirely of an active material comprised of fissile material and a moderator material which serves as a diluent. The active material is fabricated as a gas permeable porous material and is interlaced in a random manner with very small inter-connecting bores or capillary tubes through which the coolant gas may flow. The entire reactor is divided into successive sections along the direction of the temperature gradient or coolant flow, each section utilizing materials of construction which are most advantageous from a nuclear standpoint and which at the same time can withstand the operating temperature of that particular zone. This design results in a nuclear reactor characterized simultaneously by a minimum critiral size and mass and by the ability to heat a working fluid to an extremely high temperature.

  13. Underground house book

    SciTech Connect (OSTI)

    Campbell, S.

    1980-01-01

    Aesthetics, attitudes, and acceptance of earth-covered buildings are examined initially, followed by an examination of land, money, water, earth, design, heat, and interior factors. Contributions made by architect Frank Lloyd Wright are discussed and reviewed. Contemporary persons, mostly designers, who contribute from their experiences with underground structures are Andy Davis; Rob Roy; Malcolm Wells; John Barnard, Jr.; Jeff Sikora; and Don Metz. A case study to select the site, design, and prepare to construct Earthtech 6 is described. Information is given in appendices on earth-protected buildings and existing basements; financing earth-sheltered housing; heating-load calculations and life-cycle costing; and designer names and addresses. (MCW)

  14. CAMDOpenHouse2016

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

    Center for Advanced Microstructures and Devices OPEN HOUSE FREE & open to the public Hands on Science Demonstrations Tours of the Laboratory LSU CAMD 6980 Jefferson Hwy Baton Rouge, LA 70806 Phone: 225.578.8887 Fax: 225.578.6954 E-mail:evstev@lsu.edu Website: www.camd.lsu.edu *Located between College Drive and Corporate Boulevard Activities for all ages S a t u r d a y O c t o b e r 1 5 , 2 0 1 6 1 0 A . M . - 2 P . M .

  15. Passive heat transfer means for nuclear reactors

    DOE Patents [OSTI]

    Burelbach, James P.

    1984-01-01

    An improved passive cooling arrangement is disclosed for maintaining adjacent or related components of a nuclear reactor within specified temperature differences. Specifically, heat pipes are operatively interposed between the components, with the vaporizing section of the heat pipe proximate the hot component operable to cool it and the primary condensing section of the heat pipe proximate the other and cooler component operable to heat it. Each heat pipe further has a secondary condensing section that is located outwardly beyond the reactor confinement and in a secondary heat sink, such as air ambient the containment, that is cooler than the other reactor component. Means such as shrouding normally isolated the secondary condensing section from effective heat transfer with the heat sink, but a sensor responds to overheat conditions of the reactor to open the shrouding, which thereby increases the cooling capacity of the heat pipe. By having many such heat pipes, an emergency passive cooling system is defined that is operative without electrical power.

  16. Development of Basic Housing Systems for Maximum Affordability

    SciTech Connect (OSTI)

    Aglan, H.; Gibbons, A.; McQueen, T.M.; Morris, C.; Raines, J.; Wendt, R.L.

    1999-04-19

    The ability to provide safe, habitable, comfortable housing for very low income residents within the target budget of $10,000 presents unique design and construction challenges. However, a number of preliminary conclusions have been inferred as being important concepts relative to the study of affordable housing. The term affordable housing can have many meanings and research is needed to define this explicitly. As it is most often used, affordable housing refers to an economic relationship between the price of housing, household income and current interest rates available from a lending institution. There is no direct relationship between architectural style, construction technology or user needs and the concept of affordability. For any home to be affordable, the home owner must balance the combination of housing needs and desires within the limits of an actual budget. There are many misconceptions that affordable housing must be defined as housing for those who cannot afford the free-market price. The concept of affordable housing must also include a component that recognizes the quality of the housing as an important element of the design and construction. In addition, responses to local climate impacts are necessary and are always part of a regional expression of architectural design. By using careful planning and design it may be possible to construct a limited dwelling unit today for a sum of approximately $10,000. Since the organization of the construction process must involve the owner/occupants as well as other volunteers, the project must not only be well conceived, but well developed and coordinated.

  17. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Ohlinger, L.A.; Wigner, E.P.; Weinberg, A.M.; Young, G.J.

    1958-09-01

    This patent relates to neutronic reactors of the heterogeneous water cooled type, and in particular to a fuel element charging and discharging means therefor. In the embodiment illustrated the reactor contains horizontal, parallel coolant tubes in which the fuel elements are disposed. A loading cart containing a magnzine for holding a plurality of fuel elements operates along the face of the reactor at the inlet ends of the coolant tubes. The loading cart is equipped with a ram device for feeding fuel elements from the magazine through the inlot ends of the coolant tubes. Operating along the face adjacent the discharge ends of the tubes there is provided another cart means adapted to receive irradiated fuel elements as they are forced out of the discharge ends of the coolant tubes by the incoming new fuel elements. This cart is equipped with a tank coataining a coolant, such as water, into which the fuel elements fall, and a hydraulically operated plunger to hold the end of the fuel element being discharged. This inveation provides an apparatus whereby the fuel elements may be loaded into the reactor, irradiated therein, and unloaded from the reactor without stopping the fiow of the coolant and without danger to the operating personnel.

  18. Nuclear Reactors and Technology

    SciTech Connect (OSTI)

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

    1992-01-01

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

  19. SURE HOUSE | Department of Energy

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

    blend in its Efficient, Affordable, Solar, Innovation--or EASI--House. Learn More AGGIE SOL The University of California, Davis, has strong pedigrees in both sustainable projects...

  20. High Performance Factory Built Housing

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

    Performance Factory Built Housing 2015 Building Technologies Office Peer Review Jordan Dentz, jdentz@levypartnership.com ARIES The Levy Partnership, Inc. Project Summary ...

  1. Nuclear reactor shield including magnesium oxide

    DOE Patents [OSTI]

    Rouse, Carl A.; Simnad, Massoud T.

    1981-01-01

    An improvement in nuclear reactor shielding of a type used in reactor applications involving significant amounts of fast neutron flux, the reactor shielding including means providing structural support, neutron moderator material, neutron absorber material and other components as described below, wherein at least a portion of the neutron moderator material is magnesium in the form of magnesium oxide either alone or in combination with other moderator materials such as graphite and iron.

  2. POWER REACTOR

    DOE Patents [OSTI]

    Zinn, W.H.

    1958-07-01

    A fast nuclear reactor system ls described for producing power and radioactive isotopes. The reactor core is of the heterogeneous, fluid sealed type comprised of vertically arranged elongated tubular fuel elements having vertical coolant passages. The active portion is surrounded by a neutron reflector and a shield. The system includes pumps and heat exchangers for the primary and secondary coolant circuits. The core, primary coolant pump and primary heat exchanger are disposed within an irapenforate tank which is filled with the primary coolant, in this case a liquid metal such as Na or NaK, to completely submerge these elements. The tank is completely surrounded by a thick walled concrete shield. This reactor system utilizes enriched uranium or plutonium as the fissionable material, uranium or thorium as a diluent and thorium or uranium containing less than 0 7% of the U/sup 235/ isotope as a fertile material.

  3. REACTOR CONTROL

    DOE Patents [OSTI]

    Fortescue, P.; Nicoll, D.

    1962-04-24

    A control system employed with a high pressure gas cooled reactor in which a control rod is positioned for upward and downward movement into the neutron field from a position beneath the reactor is described. The control rod is positioned by a coupled piston cylinder releasably coupled to a power drive means and the pressurized coolant is directed against the lower side of the piston. The coolant pressure is offset by a higher fiuid pressure applied to the upper surface of the piston and means are provided for releasing the higher pressure on the upper side of the piston so that the pressure of the coolant drives the piston upwardly, forcing the coupled control rod into the ncutron field of the reactor. (AEC)

  4. Bioconversion reactor

    DOE Patents [OSTI]

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

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

  5. NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Wigner, E.P.; Young, G.J.

    1958-10-14

    A method is presented for loading and unloading rod type fuel elements of a neutronic reactor of the heterogeneous, solld moderator, liquid cooled type. In the embodiment illustrated, the fuel rods are disposed in vertical coolant channels in the reactor core. The fuel rods are loaded and unloaded through the upper openings of the channels which are immersed in the coolant liquid, such as water. Unloading is accomplished by means of a coffer dam assembly having an outer sleeve which is placed in sealing relation around the upper opening. A radiation shield sleeve is disposed in and reciprocable through the coffer dam sleeve. A fuel rod engaging member operates through the axial bore in the radiation shield sleeve to withdraw the fuel rod from its position in the reactor coolant channel into the shield, the shield snd rod then being removed. Loading is accomplished in the reverse procedure.

  6. (Reactor dosimetry)

    SciTech Connect (OSTI)

    West, C.D.

    1990-09-13

    The lead in most aspects of research reactor design and use passed from the USA about 15 years ago, soon after the construction of the HFIR and HFBR. The Europeans have consistently upgraded and improved their existing facilities and have built new ones including the HFR at Grenoble and ORPHEE at Saclay. They studied ultra-high flux concepts ({approximately}10{sup 20}/m{sup {minus}2}{center dot}s{sup {minus}1}) about 10 years ago, and are in the design phase of a new, highly efficient medium flux reactor to be built at Garching, near Munich in Germany. A visit was made to Interatom, the firm -- the equivalent of the Architect/Engineer for the ANS project -- responsible, under contract to the Technical University of Munich, for the new Munich reactor design. There are many similarities to the ANS design, and we reviewed and discussed technical and safety aspects of the two reactors. A request was made for some new, hitherto proprietary, experimental data on reactor thermal hydraulics and cooling that will be very valuable to the ANS project. I presented a seminar on the ANS project. A visit was made to Kernforschungszentrum Karlsruhe and knowledge was gained from Dr. Kuchle, a true pioneer of ultra-high flux reactor concepts, of their work. Dr. Kuchle kindly reviewed the ANS reference core and cooling system design (with favorable conclusions). I then talked with researchers working on materials irradiation damage and activation of structural materials by neutron irradiation, both key issues for the ANS. I was shown some new techniques they have developed for testing materials irradiation effects at high fluences, in a short time, using accelerated particle beams.

  7. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Fermi, E.; Szilard, L.

    1957-09-24

    Reactors of the type employing plates of natural uranium in a moderator are discussed wherein the plates are um-formly disposed in parallel relationship to each other thereby separating the moderator material into distinct and individual layers. Each plate has an uninterrupted sunface area substantially equal to the cross-sectional area of the active portion of the reactor, the particular size of the plates and the volume ratio of moderator to uranium required to sustain a chain reaction being determinable from the known purity of these materials and other characteristics such as the predictable neutron losses due to the formation of radioactive elements of extremely high neutron capture cross section.

  8. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  9. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Young, G.

    1963-01-01

    This patent covers a power-producing nuclear reactor in which fuel rods of slightly enriched U are moderated by heavy water and cooled by liquid metal. The fuel rods arranged parallel to one another in a circle are contained in a large outer closed-end conduit that extends into a tank containing the heavy water. Liquid metal is introduced into the large conduit by a small inner conduit that extends within the circle of fuel rods to a point near the lower closed end of the outer conduit. (AEC) Production Reactors

  10. FUEL ELEMENT FOR NUCLEAR REACTORS

    DOE Patents [OSTI]

    Bassett, C.H.

    1961-05-01

    A nuclear reactor fuel element comprising high density ceramic fissionable material enclosed in a tubular cladding of corrosion-resistant material is described. The fissionable material is in the form of segments of a tube which have cooperating tapered interfaces which produce outward radial displacement when the segments are urged axially together. A resilient means is provided within the tubular housing to constantly urge the fuel segments axially. This design maintains the fuel material in tight contacting engagement against the inner surface of the outer cladding tube to eliminate any gap therebetween which may be caused by differential thermal expansion between the fuel material and the material of the tube.

  11. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Peng, Yueng-Kay M.

    1989-04-04

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

  12. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Peng, Yueng-Kay M.

    1989-01-01

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

  13. Preliminary LOCA analysis of the westinghouse small modular reactor using the WCOBRA/TRAC-TF2 thermal-hydraulics code

    SciTech Connect (OSTI)

    Liao, J.; Kucukboyaci, V. N.; Nguyen, L.; Frepoli, C.

    2012-07-01

    The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (> 225 MWe) integral pressurized water reactor (iPWR) with all primary components, including the steam generator and the pressurizer located inside the reactor vessel. The reactor core is based on a partial-height 17x17 fuel assembly design used in the AP1000{sup R} reactor core. The Westinghouse SMR utilizes passive safety systems and proven components from the AP1000 plant design with a compact containment that houses the integral reactor vessel and the passive safety systems. A preliminary loss of coolant accident (LOCA) analysis of the Westinghouse SMR has been performed using the WCOBRA/TRAC-TF2 code, simulating a transient caused by a double ended guillotine (DEG) break in the direct vessel injection (DVI) line. WCOBRA/TRAC-TF2 is a new generation Westinghouse LOCA thermal-hydraulics code evolving from the US NRC licensed WCOBRA/TRAC code. It is designed to simulate PWR LOCA events from the smallest break size to the largest break size (DEG cold leg). A significant number of fluid dynamics models and heat transfer models were developed or improved in WCOBRA/TRAC-TF2. A large number of separate effects and integral effects tests were performed for a rigorous code assessment and validation. WCOBRA/TRAC-TF2 was introduced into the Westinghouse SMR design phase to assist a quick and robust passive cooling system design and to identify thermal-hydraulic phenomena for the development of the SMR Phenomena Identification Ranking Table (PIRT). The LOCA analysis of the Westinghouse SMR demonstrates that the DEG DVI break LOCA is mitigated by the injection and venting from the Westinghouse SMR passive safety systems without core heat up, achieving long term core cooling. (authors)

  14. Nuclear Reactors and Technology; (USA)

    SciTech Connect (OSTI)

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

    1991-01-01

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

  15. Large Component Removal/Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.

    2002-02-27

    This paper describes the removal and disposal of the large components from Maine Yankee Atomic Power Plant. The large components discussed include the three steam generators, pressurizer, and reactor pressure vessel. Two separate Exemption Requests, which included radiological characterizations, shielding evaluations, structural evaluations and transportation plans, were prepared and issued to the DOT for approval to ship these components; the first was for the three steam generators and one pressurizer, the second was for the reactor pressure vessel. Both Exemption Requests were submitted to the DOT in November 1999. The DOT approved the Exemption Requests in May and July of 2000, respectively. The steam generators and pressurizer have been removed from Maine Yankee and shipped to the processing facility. They were removed from Maine Yankee's Containment Building, loaded onto specially designed skid assemblies, transported onto two separate barges, tied down to the barges, th en shipped 2750 miles to Memphis, Tennessee for processing. The Reactor Pressure Vessel Removal Project is currently under way and scheduled to be completed by Fall of 2002. The planning, preparation and removal of these large components has required extensive efforts in planning and implementation on the part of all parties involved.

  16. Neutronic reactor

    DOE Patents [OSTI]

    Wende, Charles W. J.; Babcock, Dale F.; Menegus, Robert L.

    1983-01-01

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

  17. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Starr, C.

    1963-01-01

    This patent relates to a combination useful in a nuclear reactor and is comprised of a casing, a mass of graphite irapregnated with U compounds in the casing, and at least one coolant tube extending through the casing. The coolant tube is spaced from the mass, and He is irtroduced irto the space between the mass and the coolant tube. (AEC)

  18. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Creutz, E.C.; Ohlinger, L.A.; Weinberg, A.M.; Wigner, E.P.; Young, G.J.

    1959-10-27

    BS>A reactor cooled by water, biphenyl, helium, or other fluid with provision made for replacing the fuel rods with the highest plutonium and fission product content without disassembling the entire core and for promptly cooling the rods after their replacement in order to prevent build-up of heat from fission product activity is described.

  19. Neutronic reactor

    DOE Patents [OSTI]

    Wende, Charles W. J.

    1976-08-17

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield.

  20. Neutronic reactor

    DOE Patents [OSTI]

    Carleton, John T.

    1977-01-25

    A graphite-moderated nuclear reactor includes channels between blocks of graphite and also includes spacer blocks between adjacent channeled blocks with an axis of extension normal to that of the axis of elongation of the channeled blocks to minimize changes in the physical properties of the graphite as a result of prolonged neutron bombardment.

  1. NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Anderson, H.L.

    1958-10-01

    The design of control rods for nuclear reactors are described. In this design the control rod consists essentially of an elongated member constructed in part of a neutron absorbing material and having tube means extending therethrough for conducting a liquid to cool the rod when in use.

  2. Removable check valve for use in a nuclear reactor

    DOE Patents [OSTI]

    Dunn, Charlton (Calabasas, CA); Gutzmann, Edward A. (Simi Valley, CA)

    1988-01-01

    A removable check valve for interconnecting the discharge duct of a pump and an inlet coolant duct of a reactor core in a pool-type nuclear reactor. A manifold assembly is provided having an outer periphery affixed to and in fluid communication with the discharge duct of the pump and has an inner periphery having at least one opening therethrough. A housing containing a check valve is located within the inner periphery of the manifold. The upper end of the housing has an opening in alignment with the opening in the manifold assembly, and seals are provided above and below the openings. The lower end of the housing is adapted for fluid communication with the inlet duct of the reactor core.

  3. Laser housing having integral mounts and method of manufacturing same

    DOE Patents [OSTI]

    Herron, Michael Alan; Brickeen, Brian Keith

    2004-10-19

    A housing adapted to position, support, and facilitate aligning various components, including an optical path assembly, of a laser. In a preferred embodiment, the housing is constructed from a single piece of material and broadly comprises one or more through-holes; one or more cavities; and one or more integral mounts, wherein the through-holes and the cavities cooperate to define the integral mounts. Securement holes machined into the integral mounts facilitate securing components within the integral mounts using set screws, adhesive, or a combination thereof. In a preferred method of making the housing, the through-holes and cavities are first machined into the single piece of material, with at least some of the remaining material forming the integral mounts.

  4. A system analysis computer model for the High Flux Isotope Reactor (HFIRSYS Version 1)

    SciTech Connect (OSTI)

    Sozer, M.C.

    1992-04-01

    A system transient analysis computer model (HFIRSYS) has been developed for analysis of small break loss of coolant accidents (LOCA) and operational transients. The computer model is based on the Advanced Continuous Simulation Language (ACSL) that produces the FORTRAN code automatically and that provides integration routines such as the Gear`s stiff algorithm as well as enabling users with numerous practical tools for generating Eigen values, and providing debug outputs and graphics capabilities, etc. The HFIRSYS computer code is structured in the form of the Modular Modeling System (MMS) code. Component modules from MMS and in-house developed modules were both used to configure HFIRSYS. A description of the High Flux Isotope Reactor, theoretical bases for the modeled components of the system, and the verification and validation efforts are reported. The computer model performs satisfactorily including cases in which effects of structural elasticity on the system pressure is significant; however, its capabilities are limited to single phase flow. Because of the modular structure, the new component models from the Modular Modeling System can easily be added to HFIRSYS for analyzing their effects on system`s behavior. The computer model is a versatile tool for studying various system transients. The intent of this report is not to be a users manual, but to provide theoretical bases and basic information about the computer model and the reactor.

  5. Statement on Defense Nuclear Nonproliferation and Naval Reactors Activities

    National Nuclear Security Administration (NNSA)

    before the House Committee on Appropriations Subcommittee on Energy & Water Development | National Nuclear Security Administration | (NNSA) Defense Nuclear Nonproliferation and Naval Reactors Activities before the House Committee on Appropriations Subcommittee on Energy & Water Development February 26, 2013 INTRODUCTION Chairman Frelinghuysen, Ranking Member Kaptur, and distinguished members of the Subcommittee, thank you for having me here today to discuss the National Nuclear

  6. TA-2 Water Boiler Reactor Decommissioning Project

    SciTech Connect (OSTI)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

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

  7. DOE Zero Energy Ready Home Case Study: Mutual Housing California...

    Energy Savers [EERE]

    Mutual Housing California, Mutual Housing at Spring Lake, Woodland, CA DOE Zero Energy Ready Home Case Study: Mutual Housing California, Mutual Housing at Spring Lake, Woodland, CA ...

  8. Multi-Family Housing Loans and Grants

    Broader source: Energy.gov [DOE]

    Multi-family housing programs offer rural rental housing loans to provide affordable multi-family rental housing for very low-, low-, and moderate-income families, the elderly, and persons with...

  9. Energetic component treatability study

    SciTech Connect (OSTI)

    Gildea, P.D.; Brandon, S.L.; Brown, B.G. [and others

    1997-11-01

    The effectiveness of three environmentally sound processes for small energetic component disposal was examined experimentally in this study. The three destruction methods, batch reactor supercritical water oxidation, sodium hydroxide base hydrolysis and calcium carbonate cookoff were selected based on their potential for producing a clean solid residue and minimum release of toxic gases after component detonation. The explosive hazard was destroyed by all three processes. Batch supercritical water oxidation destroyed both the energetics and organics. Further development is desired to optimize process parameters. Sodium hydroxide base hydrolysis and calcium carbonate cookoff results indicated the potential for scrubbing gaseous detonation products. Further study and testing are needed to quantify the effectiveness of these later two processes for full-scale munition destruction. The preliminary experiments completed in this study have demonstrated the promise of these three processes as environmentally sound technologies for energetic component destruction. Continuation of these experimental programs is strongly recommended to optimize batch supercritical water oxidation processing, and to fully develop the sodium hydroxide base hydrolysis and calcium carbonate cookoff technologies.

  10. Fast Reactor Technology Preservation

    SciTech Connect (OSTI)

    Wootan, David W.; Omberg, Ronald P.

    2008-01-11

    There is renewed worldwide interest in developing and implementing a new generation of advanced fast reactors. International cooperative efforts are underway such as the Global Nuclear Energy Partnership (GNEP). Advanced computer modeling and simulation efforts are a key part of these programs. A recognized and validated set of Benchmark Cases are an essential component of such modeling efforts. Testing documentation developed during the operation of the Fast Flux Test Facility (FFTF) provide the information necessary to develop a very useful set of Benchmark Cases.

  11. Closed Brayton cycle power conversion systems for nuclear reactors :

    SciTech Connect (OSTI)

    Wright, Steven A.; Lipinski, Ronald J.; Vernon, Milton E.; Sanchez, Travis

    2006-04-01

    This report describes the results of a Sandia National Laboratories internally funded research program to study the coupling of nuclear reactors to gas dynamic Brayton power conversion systems. The research focused on developing integrated dynamic system models, fabricating a 10-30 kWe closed loop Brayton cycle, and validating these models by operating the Brayton test-loop. The work tasks were performed in three major areas. First, the system equations and dynamic models for reactors and Closed Brayton Cycle (CBC) systems were developed and implemented in SIMULINKTM. Within this effort, both steady state and dynamic system models for all the components (turbines, compressors, reactors, ducting, alternators, heat exchangers, and space based radiators) were developed and assembled into complete systems for gas cooled reactors, liquid metal reactors, and electrically heated simulators. Various control modules that use proportional-integral-differential (PID) feedback loops for the reactor and the power-conversion shaft speed were also developed and implemented. The simulation code is called RPCSIM (Reactor Power and Control Simulator). In the second task an open cycle commercially available Capstone C30 micro-turbine power generator was modified to provide a small inexpensive closed Brayton cycle test loop called the Sandia Brayton test-Loop (SBL-30). The Capstone gas-turbine unit housing was modified to permit the attachment of an electrical heater and a water cooled chiller to form a closed loop. The Capstone turbine, compressor, and alternator were used without modification. The Capstone systems nominal operating point is 1150 K turbine inlet temperature at 96,000 rpm. The annular recuperator and portions of the Capstone control system (inverter) and starter system also were reused. The rotational speed of the turbo-machinery is controlled by adjusting the alternator load by using the electrical grid as the load bank. The SBL-30 test loop was operated at

  12. REACTOR MONITORING

    DOE Patents [OSTI]

    Bugbee, S.J.; Hanson, V.F.; Babcock, D.F.

    1959-02-01

    A neutron density inonitoring means for reactors is described. According to this invention a tunnel is provided beneath and spaced from the active portion of the reactor and extends beyond the opposite faces of the activc portion. Neutron beam holes are provided between the active portion and the tunnel and open into the tunnel near the middle thereof. A carriage operates back and forth in the tunnel and is adapted to convey a neutron detector, such as an ion chamber, and position it beneath one of the neutron beam holes. This arrangement affords convenient access of neutron density measuring instruments to a location wherein direct measurement of neutron density within the piles can be made and at the same time affords ample protection to operating personnel.

  13. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Treshow, M.

    1958-08-19

    A neuclear reactor is described of the heterogeneous type and employing replaceable tubular fuel elements and heavy water as a coolant and moderator. A pluraltty of fuel tubesa having their axes parallel, extend through a tank type pressure vessel which contatns the liquid moderator. The fuel elements are disposed within the fuel tubes in the reaetive portion of the pressure vessel during normal operation and the fuel tubes have removable plug members at each end to permit charging and discharging of the fuel elements. The fuel elements are cylindrical strands of jacketed fissionable material having helical exterior ribs. A bundle of fuel elements are held within each fuel tube with their longitudinal axes parallel, the ribs serving to space them apart along their lengths. Coolant liquid is circulated through the fuel tubes between the spaced fuel elements. Suitable control rod and monitoring means are provided for controlling the reactor.

  14. REACTOR UNLOADING

    DOE Patents [OSTI]

    Leverett, M.C.

    1958-02-18

    This patent is related to gas cooled reactors wherein the fuel elements are disposed in vertical channels extending through the reactor core, the cooling gas passing through the channels from the bottom to the top of the core. The invention is a means for unloading the fuel elements from the core and comprises dump values in the form of flat cars mounted on wheels at the bottom of the core structure which support vertical stacks of fuel elements. When the flat cars are moved, either manually or automatically, for normal unloading purposes, or due to a rapid rise in the reproduction ratio within the core, the fuel elements are permtted to fall by gravity out of the core structure thereby reducing the reproduction ratio or stopping the reaction as desired.

  15. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Wade, E.J.

    1958-09-16

    This patent relates to a reflector means for a neutronic reactor. A reflector comprised of a plurality of vertically movable beryllium control members is provided surrounding the sides of the reactor core. An absorber of fast neutrons comprised of natural uramum surrounds the reflector. An absorber of slow neutrons surrounds the absorber of fast neutrons and is formed of a plurality of beryllium blocks having natural uranium members distributcd therethrough. in addition, a movable body is positioned directly below the core and is comprised of a beryllium reflector and an absorbing member attached to the botiom thereof, the absorbing member containing a substance selected from the goup consisting of natural urantum and Th/sup 232/.

  16. Nuclear reactor

    DOE Patents [OSTI]

    Wade, Elman E.

    1979-01-01

    A nuclear reactor including two rotatable plugs and a positive top core holddown structure. The top core holddown structure is divided into two parts: a small core cover, and a large core cover. The small core cover, and the upper internals associated therewith, are attached to the small rotating plug, and the large core cover, with its associated upper internals, is attached to the large rotating plug. By so splitting the core holddown structures, under-the-plug refueling is accomplished without the necessity of enlarging the reactor pressure vessel to provide a storage space for the core holddown structure during refueling. Additionally, the small and large rotating plugs, and their associated core covers, are arranged such that the separation of the two core covers to permit rotation is accomplished without the installation of complex lifting mechanisms.

  17. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Grebe, J.J.

    1959-12-15

    A reactor which is particularly adapted tu serve as a heat source for a nuclear powered alrcraft or rocket is described. The core of this reactor consists of a porous refractory modera;or body which is impregnated with fissionable nuclei. The core is designed so that its surface forms tapered inlet and outlet ducts which are separated by the porous moderator body. In operation a gaseous working fluid is circulated through the inlet ducts to the surface of the moderator, enters and passes through the porous body, and is heated therein. The hot gas emerges into the outlet ducts and is available to provide thrust. The principle advantage is that tremendous quantities of gas can be quickly heated without suffering an excessive pressure drop.

  18. NUCLEAR REACTORS

    DOE Patents [OSTI]

    Long, E.; Ashby, J.W.

    1958-09-16

    ABS>A graphite moderator structure is presented for a nuclear reactor compriscd of an assembly of similarly orientated prismatic graphite blocks arranged on spaced longitudinal axes lying in common planes wherein the planes of the walls of the blocks are positioned so as to be twisted reintive to the planes of said axes so thatthe unlmpeded dtrect paths in direction wholly across the walls of the blocks are limited to the width of the blocks plus spacing between the blocks.

  19. Neutronic reactor

    DOE Patents [OSTI]

    Lewis, Warren R.

    1978-05-30

    A graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels.

  20. NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  1. ,"Housing Units1","Average Square Footage Per Housing Unit",...

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

    ... U.S. Department of Energy's Office of Energy and Efficiency and Renewable Energy (EERE). 5Rented includes households that occupy their primary housing unit without payment of rent. ...

  2. ,"Housing Units1","Average Square Footage Per Housing Unit",...

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

    ... Unconditioned and unfinished areas in attics and attached garages are excluded. 3Housing units are classified as urban or rural using definitions created by the U.S. Census Bureau, ...

  3. Recycling in public housing: The Syracuse Housing Authority

    SciTech Connect (OSTI)

    Foote, K.C.; DeVoe, J.F.

    1997-01-01

    The mission of the Syracuse Housing Authority (SHA, Syracuse, N.Y.) is to provide clean, safe, and affordable housing for low-income citizens of the city of Syracuse. In doing so, it has worked to be innovative. SHA owns and manages 12 federally funded housing developments and one New York state-funded project, in addition to managing two buildings owned by the city. After nearly 60 years of success in providing affordable housing in the Syracuse area, the pioneering SHA took on another daunting mission in the 1990s: modernization of waste collection and recycling. By the beginning of 1990, SHA was facing two mandates: to initiate a recycling program by July 1, as mandated by Onondaga County law, and to reduce its trash bill significantly.

  4. REACTOR CONTROL

    DOE Patents [OSTI]

    Ruano, W.J.

    1957-12-10

    This patent relates to nuclear reactors of the type which utilize elongited rod type fuel elements immersed in a liquid moderator and shows a design whereby control of the chain reaction is obtained by varying the amount of moderator or reflector material. A central tank for containing liquid moderator and fuel elements immersed therein is disposed within a surrounding outer tank providing an annular space between the two tanks. This annular space is filled with liquid moderator which functions as a reflector to reflect neutrons back into the central reactor tank to increase the reproduction ratio. Means are provided for circulating and cooling the moderator material in both tanks and additional means are provided for controlling separately the volume of moderator in each tank, which latter means may be operated automatically by a neutron density monitoring device. The patent also shows an arrangement for controlling the chain reaction by injecting and varying an amount of poisoning material in the moderator used in the reflector portion of the reactor.

  5. Travois Indian Country Affordable Housing & Economic Development...

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

    Travois Indian Country Affordable Housing & Economic Development Conference Travois Indian Country Affordable Housing & Economic Development Conference April 4, 2016 8:00AM CDT to ...

  6. 2015 Housing Innovation Awards Application Form | Department...

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

    Housing Innovation Awards Application Form 2015 Housing Innovation Awards Application Form ... The 2015 ceremony will take place at the EEBA Excellence in Building Conference & Expo ...

  7. " Million U.S. Housing Units"

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

    0 Home Appliances Usage Indicators by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  8. " Million U.S. Housing Units"

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

    5 Space Heating Usage Indicators by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  9. " Million U.S. Housing Units"

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

    7 Air-Conditioning Usage Indicators by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  10. " Million U.S. Housing Units"

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

    2 Living Space Characteristics by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  11. " Million U.S. Housing Units"

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

    4 Space Heating Characteristics by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  12. " Million U.S. Housing Units"

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

    2 Home Electronics Usage Indicators by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  13. " Million U.S. Housing Units"

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

    6 Air Conditioning Characteristics by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  14. Peoria Tribe: Housing Authority- 2010 Project

    Broader source: Energy.gov [DOE]

    The Housing Authority of the Peoria Tribe of Indians of Oklahoma (Peoria Housing Authority or PHA) will conduct the "PHA Weatherization Training Project."

  15. Funding Opportunity: Building America High Performance Housing...

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

    Opportunity: Building America High Performance Housing Innovation Funding Opportunity: Building America High Performance Housing Innovation November 19, 2015 - 11:51am Addthis The ...

  16. Grandma's House (Weatherization) | Department of Energy

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

    Grandma's House (Weatherization) Grandma's House (Weatherization) Addthis When you weatherize a home it needs to work as a system. Learn more here

  17. " Million U.S. Housing Units"

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

    Units" ,,"UrbanRural Location (as Self-Reported)" ,"Housing Units (millions)" "Space ... ,,"RSEs for UrbanRural Location (as Self-Reported)" ,"RSEs for Housing Units " "Space ...

  18. " Million U.S. Housing Units"

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

    Units" ,,"UrbanRural Location (as Self-Reported)" ,"Housing Units (millions)" "Living ... ,,"RSEs for UrbanRural Location (as Self-Reported)" ,"RSEs for Housing Units (millions)" ...

  19. Total U.S. Housing Units...................................

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

    ... Space Heating Usage Indicators Million U.S. Housing Units Detached Attached Energy Information Administration 2005 Residential Energy Consumption Survey: Preliminary Housing ...

  20. Energy Efficiency Upgrades in Multifamily Housing | Department...

    Energy Savers [EERE]

    Upgrades in Multifamily Housing Energy Efficiency Upgrades in Multifamily Housing Better Buildings Residential Network Case Study: Energy Efficiency Upgrades in Multifamily ...

  1. " Million U.S. Housing Units"

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

    Water Heating Characteristics by UrbanRural Location, 2005" " Million U.S. Housing Units" ,,"UrbanRural Location (as Self-Reported)" ,"Housing Units (millions)" "Water Heating ...

  2. " Million U.S. Housing Units"

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

    8 Water Heating Characteristics by Type of Housing Unit, 2005" " Million U.S. Housing ... Units",,"Apartments in Buildings With--" "Water Heating Characteristics",,"Detached","Atta...

  3. Total U.S. Housing Units.................................

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

    At Home Behavior Home Used for Business Yes......Type of Owner-Occupied Housing Unit Housing Units (millions) Single-Family Units ...

  4. Cold worked ferritic alloys and components

    DOE Patents [OSTI]

    Korenko, Michael K.

    1984-01-01

    This invention relates to liquid metal fast breeder reactor and steam generator precipitation hardening fully ferritic alloy components which have a microstructure substantially free of the primary precipitation hardening phase while having cells or arrays of dislocations of varying population densities. It also relates to the process by which these components are produced, which entails solution treating the alloy followed by a final cold working step. In this condition, the first significant precipitation hardening of the component occurs during high temperature use.

  5. Maximizing Residential Energy Savings: Net Zero Energy House (ZEH) Technology Pathways

    SciTech Connect (OSTI)

    Anderson, R.; Roberts, D.

    2008-11-01

    To meet current U.S. Department of Energy zero-energy home performance goals, new technologies and solutions must increase whole-house efficiency savings by an additional 40% relative to those provided by best available components and systems.

  6. Low-temperature hermetic sealing of optical fiber components

    SciTech Connect (OSTI)

    Kramer, D.P.

    1995-12-31

    A method for manufacturing low-temperature hermetically sealed optical fiber components is provided. The method comprises the steps of: inserting an optical fiber into a housing, the optical fiber having a glass core, a glass cladding and a protective buffer layer disposed around the core and cladding; heating the housing to a predetermined temperature, the predetermined temperature being below a melting point for the protective buffer layer and above a melting point of a solder; placing the solder in communication with the heated housing to allow the solder to form an eutectic and thereby fill a gap between the interior of the housing and the optical fiber; and cooling the housing to allow the solder to form a hermetic compression seal between the housing and the optical fiber.

  7. Low-temperature hermetic sealing of optical fiber components

    DOE Patents [OSTI]

    Kramer, Daniel P. (Centerville, OH)

    1996-10-22

    A method for manufacturing low-temperature hermetically sealed optical fi components is provided. The method comprises the steps of: inserting an optical fiber into a housing, the optical fiber having a glass core, a glass cladding and a protective buffer layer disposed around the core and cladding; heating the housing to a predetermined temperature, the predetermined temperature being below a melting point for the protective buffer layer and above a melting point of a solder; placing the solder in communication with the heated housing to allow the solder to form an eutectic and thereby fill a gap between the interior of the housing and the optical fiber; and cooling the housing to allow the solder to form a hermetic compression seal between the housing and the optical fiber.

  8. Low-temperature hermetic sealing of optical fiber components

    DOE Patents [OSTI]

    Kramer, D.P.

    1996-10-22

    A method for manufacturing low-temperature hermetically sealed optical fiber components is provided. The method comprises the steps of: inserting an optical fiber into a housing, the optical fiber having a glass core, a glass cladding and a protective buffer layer disposed around the core and cladding; heating the housing to a predetermined temperature, the predetermined temperature being below a melting point for the protective buffer layer and above a melting point of a solder; placing the solder in communication with the heated housing to allow the solder to form an eutectic and thereby fill a gap between the interior of the housing and the optical fiber; and cooling the housing to allow the solder to form a hermetic compression seal between the housing and the optical fiber. 5 figs.

  9. State space modeling of reactor core in a pressurized water reactor

    SciTech Connect (OSTI)

    Ashaari, A.; Ahmad, T.; M, Wan Munirah W.; Shamsuddin, Mustaffa; Abdullah, M. Adib

    2014-07-10

    The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

  10. Benefits of Small Modular Reactors (SMRs) | Department of Energy

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

    Benefits of Small Modular Reactors (SMRs) Benefits of Small Modular Reactors (SMRs) Small modular reactors offer a lower initial capital investment, greater scalability, and siting flexibility for locations unable to accommodate more traditional larger reactors. They also have the potential for enhanced safety and security compared to earlier designs. Modularity: The term "modular" in the context of SMRs refers to the ability to fabricate major components of the nuclear steam supply

  11. SURE HOUSE | Department of Energy

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

    just yet, but the ultra-efficient Alf House could soon change that. Learn More CASA DEL SOL With the 2015 Solar Decathlon taking place in Irvine, California, Team Orange County --...

  12. ALF HOUSE | Department of Energy

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

    was looking for a way to represent its home territory. They found their inspiration in nature: the golden poppy, California's state flower. Learn More DURA URBAN HOUSE People from...

  13. Public Housing Project Performance Benchmarks

    Broader source: Energy.gov [DOE]

    Reports five major performance metrics that can be used to benchmark proposed energy service company projects within public housing, disaggregated and reported by major retrofit strategy. Author: U.S. Department of Energy

  14. Important notice about using /house

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

    using house July 6, 2012 Description There have been a lot of issues recently with NFS hangs on the gpint machines. The origin of the gpint hanging has been determined to be...

  15. Synfuel production in nuclear reactors

    DOE Patents [OSTI]

    Henning, C.D.

    Apparatus and method for producing synthetic fuels and synthetic fuel components by using a neutron source as the energy source, such as a fusion reactor. Neutron absorbers are disposed inside a reaction pipe and are heated by capturing neutrons from the neutron source. Synthetic fuel feedstock is then placed into contact with the heated neutron absorbers. The feedstock is heated and dissociates into its constituent synfuel components, or alternatively is at least preheated sufficiently to use in a subsequent electrolysis process to produce synthetic fuels and synthetic fuel components.

  16. NNSS Hosts Groundwater Open House

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

    Survey of the Bay Area NNSS Hosts Groundwater Open House A RSL helicopter spent part of August conducting aerial radiation flyovers in the California Bay Area. The team rocked the competition and chiseled out an impressive second place finish recently in the Security Protection Officer competition. Groundwater was the topic of discussion at a recent open house. See page 12. See page 5. See page 8. Enterprise Publication "ONEVOICE" Replaces Spotlight and SiteLines The Nevada National

  17. Open House with Environmental Scientists

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

    Open House with Environmental Scientists Open House with Environmental Scientists WHEN: Apr 23, 2015 12:00 PM - 1:00 PM WHERE: Bradbury Science Museum 1350 Central Ave, Los Alamos, NM 87544, USA CONTACT: Jessica Privette 505 667-0375 CATEGORY: Bradbury INTERNAL: Calendar Login Laboratory Environmental Research and Monitoring Event Description Ask Laboratory biologists and anthropologists your natural resource questions. In honor of Earth Week, Los Alamos National Laboratory's Environmental

  18. B Reactor | Department of Energy

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

    Operational Management History Manhattan Project Signature Facilities B Reactor B Reactor B Reactor Completed in September 1944, the B Reactor was the world's first ...

  19. Materials and Components Technology Division research summary, 1991

    SciTech Connect (OSTI)

    Not Available

    1991-04-01

    This division has the purpose of providing a R and D capability for design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs are in support of the Integral Fast Reactor, life extension for light water reactors, fuels development for the new production reactor and research and test reactors, fusion reactor first-wall and blanket technology, safe shipment of hazardous materials, fluid mechanics/materials/instrumentation for fossile energy systems, and energy conservation and renewables (including tribology, high- temperature superconductivity). Separate abstracts have been prepared for the data base.

  20. NUCLEAR REACTORS

    DOE Patents [OSTI]

    Long, E.; Ashley, J.W.

    1958-12-16

    A graphite moderator structure is described for a gas-cooled nuclear reactor having a vertical orlentation wherein the structure is physically stable with regard to dlmensional changes due to Wigner growth properties of the graphite, and leakage of coolant gas along spaces in the structure is reduced. The structure is comprised of stacks of unlform right prismatic graphite blocks positioned in layers extending in the direction of the lengths of the blocks, the adjacent end faces of the blocks being separated by pairs of tiles. The blocks and tiles have central bores which are in alignment when assembled and are provided with cooperatlng keys and keyways for physical stability.

  1. Photocatalytic reactor

    DOE Patents [OSTI]

    Bischoff, B.L.; Fain, D.E.; Stockdale, J.A.D.

    1999-01-19

    A photocatalytic reactor is described for processing selected reactants from a fluid medium comprising at least one permeable photocatalytic membrane having a photocatalytic material. The material forms an area of chemically active sites when illuminated by light at selected wavelengths. When the fluid medium is passed through the illuminated membrane, the reactants are processed at these sites separating the processed fluid from the unprocessed fluid. A light source is provided and a light transmitting means, including an optical fiber, for transmitting light from the light source to the membrane. 4 figs.

  2. The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474

    SciTech Connect (OSTI)

    Halliwell, Chris

    2012-07-01

    the various decommissioning campaigns. The use of low force compaction for insulation and soft wastes provided a simple, robust and cost effective solution as did the direct encapsulation of LLW steel components in the later stages of reactor decommissioning. Progress through early campaigns was good, often bettering the baseline schedule, especially when undertaking the repetitive tasks seen during Neutron Shield and Graphite Core decommissioning, once the operators had become experienced with the equipment, though delays became more pronounced, mainly as a result of increased failures due to the age and maintainability of the RDM and associated equipment. Extensive delays came about as a result of the unsupported insulation falling away from the pressure vessel during removal and the inability of the ventilation system to manage the sub micron particulate generated during IPOPI cutting operations, though the in house development of revised and new methodologies ultimately led to the successful completion of PV and I removal. In a programme spanning over 12 years, the decommissioning of the reactor pressure vessel and core led to the production 110 ILW and 75 LLW WAGR boxes, with 20 LLW ISO freight containers of primary reactor wastes, resulting in an overall packaged volume of approximately 2500 cubic metres containing the estimated 460 cubic metres of the reactor structure. (authors)

  3. Inside the White House: Solar Panels | Department of Energy

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

    Inside the White House: Solar Panels Inside the White House: Solar Panels

  4. Hybrid adsorptive membrane reactor

    DOE Patents [OSTI]

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    2011-03-01

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

  5. H Reactor - Hanford Site

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

    About Us Projects & Facilities H Reactor About Us About Hanford Cleanup Hanford History ... 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and ...

  6. C Reactor - Hanford Site

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

    C Reactor About Us About Hanford Cleanup Hanford History Hanford Site Wide Programs ... 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and ...

  7. F Reactor - Hanford Site

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

    About Us Projects & Facilities F Reactor About Us About Hanford Cleanup Hanford History ... 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and ...

  8. N Reactor - Hanford Site

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

    Projects & Facilities N Reactor About Us About Hanford Cleanup Hanford History Hanford ... 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and ...

  9. Housing Innovation Awards | Department of Energy

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

    Zero Energy Ready Home » Housing Innovation Awards Housing Innovation Awards HIA Awards.JPG Since 2013, The U.S. Department of Energy's (DOE) Housing Innovation Awards has recognized the very best in innovation on the path to zero energy ready homes. The Housing Innovation Awards recognize forward-thinking builders for delivering American homebuyers with the home of the future, today. Explore these award winning homes on the Tour of Zero. The 2016 Housing Innovation Awards will be held

  10. 2016 Housing Innovation Awards | Department of Energy

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

    2016 Housing Innovation Awards 2016 Housing Innovation Awards The U.S. Department of Energy's (DOE) Housing Innovation Awards recognize the very best in innovation on the path to zero energy ready homes. DOE Zero Energy Ready Home (ZERH) Housing Innovation Award Winners are selected for each of five categories: custom buyer, custom spec, production, multifamily, and affordable homes. One DOE ZERH Grand Housing Innovation Award Winner will be announced from among the winners in each of these

  11. Million U.S. Housing Units Total............................................................................

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

    Attached 2 to 4 Units Table HC2.12 Home Electronics Usage Indicators by Type of Housing Unit, 2005 5 or More Units Mobile Homes Type of Housing Unit Housing Units (millions) Single-Family Units Apartments in Buildings With-- Home Electronics Usage Indicators Detached Energy Information Administration: 2005 Residential Energy Consumption Survey: Preliminary Housing Characteristics Tables Million U.S. Housing Units Attached 2 to 4 Units Table HC2.12 Home Electronics Usage Indicators by Type of

  12. Control Means for Reactor

    DOE Patents [OSTI]

    Manley, J. H.

    1961-06-27

    An apparatus for controlling a nuclear reactor includes a tank just below the reactor, tubes extending from the tank into the reactor, and a thermally expansible liquid neutron absorbent material in the tank. The liquid in the tank is exposed to a beam of neutrons from the reactor which heats the liquid causing it to expand into the reactor when the neutron flux in the reactor rises above a predetermincd danger point. Boron triamine may be used for this purpose.

  13. Ceramic tile expansion engine housing

    DOE Patents [OSTI]

    Myers, B.

    1995-04-11

    An expandable ceramic tile housing for a high temperature engine is disclosed wherein each tile is independently supported in place in an interlocking matrix by retention mechanisms which mechanically couple the individual ceramic tiles to an outer metal support housing while maintaining thermal isolation of the metal housing from the ceramic tiles. The ceramic tiles are formed with either an octagonal front face portion and a square shank portion or a square front face portion with an octagonal shank portion. The length of the sides of the octagonal front face portion on one tile is equal to the length of the sides of the square front face portion of adjoining tiles to permit formation of an interlocking matrix. Fibrous ceramic sealing material may be placed between radial and tangential facing surfaces of adjacent tiles to limit radial gas flow there between. Labyrinth-sealed pressure-controlled compartments may be established between the tile housing and the outer metal support housing to control radial gas flow. 8 figures.

  14. Ceramic tile expansion engine housing

    DOE Patents [OSTI]

    Myers, Blake

    1995-01-01

    An expandable ceramic tile housing for a high temperature engine is disclosed wherein each tile is independently supported in place in an interlocking matrix by retention mechanisms which mechanically couple the individual ceramic tiles to an outer metal support housing while maintaining thermal isolation of the metal housing from the ceramic tiles. The ceramic tiles are formed with either an octagonal front face portion and a square shank portion or a square front face portion with an octagonal shank portion. The length of the sides of the octagonal front face portion on one tile is equal to the length of the sides of the square front face portion of adjoining tiles to permit formation of an interlocking matrix. Fibrous ceramic sealing material may be placed between radial and tangential facing surfaces of adjacent tiles to limit radial gas flow therebetween. Labyrinth-sealed pressure-controlled compartments may be established between the tile housing and the outer metal support housing to control radial gas flow.

  15. Power Burst Facility (PBF) Reactor Reactor Decommissioning

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

    Click here to view Click here to view Reactor Decommissioning Click on an image to enlarge A crane removes the reactor vessel from the Power Burst Facility (top), then places it ...

  16. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Stewart, H.B.

    1958-12-23

    A nuclear reactor of the type speclfically designed for the irradiation of materials is discussed. In this design a central cyllndrical core of moderating material ls surrounded by an active portlon comprlsed of an annular tank contalning fissionable material immersed ln a liquid moderator. The active portion ls ln turn surrounded by a reflector, and a well ls provided in the center of the core to accommodate the materlals to be irradiated. The over-all dimensions of the core ln at least one plane are equal to or greater than twice the effective slowing down length and equal to or less than twlce the effective diffuslon length for neutrons in the core materials.

  17. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Daniels, F.

    1962-12-18

    A power plant is described comprising a turbine and employing round cylindrical fuel rods formed of BeO and UO/sub 2/ and stacks of hexagonal moderator blocks of BeO provided with passages that loosely receive the fuel rods so that coolant may flow through the passages over the fuels to remove heat. The coolant may be helium or steam and fiows through at least one more heat exchanger for producing vapor from a body of fluid separate from the coolant, which fluid is to drive the turbine for generating electricity. By this arrangement the turbine and directly associated parts are free of particles and radiations emanating from the reactor. (AEC)

  18. NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Wigner, E.P.

    1957-09-17

    A reactor of the type having coolant liquid circulated through clad fuel elements geometrically arranged in a solid moderator, such as graphite, is described. The core is enclosed in a pressure vessel and suitable shielding, wherein means is provided for circulating vapor through the core to superheat the same. This is accomplished by drawing off the liquid which has been heated in the core due to the fission of the fuel, passing it to a nozzle within a chamber where it flashes into a vapor, and then passing the vapor through separate tubes extending through the moderator to pick up more heat developed in the core due to the fission of the fuel, thereby producing superheated vapor.

  19. Important notice about using /house

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

    Important notice about using /house Important notice about using /house July 6, 2012 Description There have been a lot of issues recently with NFS hangs on the gpint machines. The origin of the gpint hanging has been determined to be a defect in the Isilon filesystem software, and happens when a file being written is simultaneously opened for reading on the same host. This most frequently happens when people tail files being written by the same machine. E.g.: DO NOT DO THIS: gpint17 $

  20. Vanadium recycling for fusion reactors

    SciTech Connect (OSTI)

    Dolan, T.J.; Butterworth, G.J.

    1994-04-01

    Very stringent purity specifications must be applied to low activation vanadium alloys, in order to meet recycling goals requiring low residual dose rates after 50--100 years. Methods of vanadium production and purification which might meet these limits are described. Following a suitable cooling period after their use, the vanadium alloy components can be melted in a controlled atmosphere to remove volatile radioisotopes. The aim of the melting and decontamination process will be the achievement of dose rates low enough for ``hands-on`` refabrication of new reactor components from the reclaimed metal. The processes required to permit hands-on recycling appear to be technically feasible, and demonstration experiments are recommended. Background information relevant to the use of vanadium alloys in fusion reactors, including health hazards, resources, and economics, is provided.

  1. Reactor and method of operation

    DOE Patents [OSTI]

    Wheeler, John A.

    1976-08-10

    A nuclear reactor having a flattened reactor activity curve across the reactor includes fuel extending over a lesser portion of the fuel channels in the central portion of the reactor than in the remainder of the reactor.

  2. RSMASS: A simple model for estimating reactor and shield masses

    SciTech Connect (OSTI)

    Marshall, A.C.; Aragon, J.; Gallup, D.

    1987-01-01

    A simple mathematical model (RSMASS) has been developed to provide rapid estimates of reactor and shield masses for space-based reactor power systems. Approximations are used rather than correlations or detailed calculations to estimate the reactor fuel mass and the masses of the moderator, structure, reflector, pressure vessel, miscellaneous components, and the reactor shield. The fuel mass is determined either by neutronics limits, thermal/hydraulic limits, or fuel damage limits, whichever yields the largest mass. RSMASS requires the reactor power and energy, 24 reactor parameters, and 20 shield parameters to be specified. This parametric approach should be applicable to a very broad range of reactor types. Reactor and shield masses calculated by RSMASS were found to be in good agreement with the masses obtained from detailed calculations.

  3. Nuclear Reactor Safety Design Criteria

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

    1993-01-19

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Supersedes DOE 5480.1, dated 1-19-93. Certified 11-18-10.

  4. DOE Tour of Zero: Mutual Housing at Spring Lake by Mutual Housing

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

    California | Department of Energy Mutual Housing at Spring Lake by Mutual Housing California DOE Tour of Zero: Mutual Housing at Spring Lake by Mutual Housing California 1 of 14 Mutual Housing built this 62-unit multifamily affordable housing development near Sacramento, California, to the performance criteria of the U.S. Department of Energy Zero Energy Ready Home (ZERH) program. 2 of 14 In addition to DOE Zero Energy Ready Home, the high-efficiency construction meets the requirements of

  5. Shielded fluid stream injector for particle bed reactor

    DOE Patents [OSTI]

    Notestein, John E.

    1993-01-01

    A shielded fluid-stream injector assembly is provided for particle bed reactors. The assembly includes a perforated pipe injector disposed across the particle bed region of the reactor and an inverted V-shaped shield placed over the pipe, overlapping it to prevent descending particles from coming into direct contact with the pipe. The pipe and shield are fixedly secured at one end to the reactor wall and slidably secured at the other end to compensate for thermal expansion. An axially extending housing aligned with the pipe and outside the reactor and an in-line reamer are provided for removing deposits from the inside of the pipe. The assembly enables fluid streams to be injected and distributed uniformly into the particle bed with minimized clogging of injector ports. The same design may also be used for extraction of fluid streams from particle bed reactors.

  6. Light Water Reactor Sustainability (LWRS) Program | Department...

    Energy Savers [EERE]

    Nuclear Reactor Technologies Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) Program Light Water Reactor Sustainability (LWRS) ...

  7. SRS Small Modular Reactors

    ScienceCinema (OSTI)

    None

    2014-05-21

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

  8. Reactor safety method

    DOE Patents [OSTI]

    Vachon, Lawrence J.

    1980-03-11

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

  9. Support arrangement for core modules of nuclear reactors

    DOE Patents [OSTI]

    Bollinger, Lawrence R.

    1987-01-01

    A support arrangement is provided for the core modules of a nuclear reactor which provides support access through the control drive mechanisms of the reactor. This arrangement provides axial support of individual reactor core modules from the pressure vessel head in a manner which permits attachment and detachment of the modules from the head to be accomplished through the control drive mechanisms after their leadscrews have been removed. The arrangement includes a module support nut which is suspended from the pressure vessel head and screw threaded to the shroud housing for the module. A spline lock prevents loosening of the screw connection. An installation tool assembly, including a cell lifting and preloading tool and a torquing tool, fits through the control drive mechanism and provides lifting of the shroud housing while disconnecting the spline lock, as well as application of torque to the module support nut.

  10. Support arrangements for core modules of nuclear reactors. [PWR

    DOE Patents [OSTI]

    Bollinger, L.R.

    1983-11-03

    A support arrangement is provided for the core modules of a nuclear reactor which provides support access through the control drive mechanisms of the reactor. This arrangement provides axial support of individual reactor core modules from the pressure vessel head in a manner which permits attachment and detachment of the modules from the head to be accomplished through the control drive mechanisms after their leadscrews have been removed. The arrangement includes a module support nut which is suspended from the pressure vessel head and screw threaded to the shroud housing for the module. A spline lock prevents loosening of the screw connection. An installation tool assembly, including a cell lifting and preloading tool and a torquing tool, fits through the control drive mechanism and provides lifting of the shroud housing while disconnecting the spline lock, as well as application of torque to the module support nut.

  11. Nuclear reactor

    DOE Patents [OSTI]

    Thomson, Wallace B.

    2004-03-16

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

  12. Low-temperature Swelling in LWR Internal Components: Current Data and Modeling Assessment

    Broader source: Energy.gov [DOE]

    Recent experimental observations have made it clear that cavity formation can occur in light-water reactor internal components fabricated from austenitic stainless during the course of their...

  13. Occupancy Simulation in Three Residential Research Houses

    SciTech Connect (OSTI)

    Boudreaux, Philip R; Gehl, Anthony C; Christian, Jeffrey E

    2012-01-01

    Three houses of similar floor plan are being compared for energy consumption. The first house is a typical builder house of 2400 ft2 (223 m2) in east Tennessee. The second house contains retrofits available to a home owner such as energy efficient appliances, windows and HVAC, as well as an insulated attic which contains HVAC duct work. The third house was built using optimum-value framing construction with photovoltaic modules and solar water heating. To consume energy researchers have set up appliances, lights, and plug loads to turn on and off automatically according to a schedule based on the Building America Research Benchmark Definition. As energy efficiency continues to be a focus for protecting the environment and conserving resources, experiments involving whole house energy consumption will be done. In these cases it is important to understand how to simulate occupancy so that data represents only house performance and not human behavior. The process for achieving automated occupancy simulation will be discussed. Data comparing the energy use of each house will be presented and it will be shown that the third house used 66% less and the second house used 36% less energy than the control house in 2010. The authors will discuss how energy prudent living habits can further reduce energy use in the third house by 23% over the average American family living in the same house.

  14. Buildings Energy Data Book: 2.7 Industrialized Housing (IH)

    Buildings Energy Data Book [EERE]

    5 2004 Number of Industrialized Housing Manufacturers Versus Production (Stick-Builders) Companies Type Panelized Modular (1) HUD-Code Production Builders Component Manufacturers Special (Commercial) Units Note(s): Source(s): 170 1) 170 of these companies also produce panelized homes. Automated Builder Magazine, Mar. 2005, p. 34-35; Automated Builder Magazine, Jan. 2004, p. 16. Number of Companies 3,500 200 90 7,000 2,200

  15. MHTool User's Guide - Software for Manufactured Housing Structural Design

    SciTech Connect (OSTI)

    W. D. Richins

    2005-07-01

    Since the late 1990s, the Department of Energy's Idaho National Laboratory (INL) has worked with the US Department of Housing and Urban Development (HUD), the Manufactured Housing Institute (MHI), the National Institute of Standards and Technology (NIST), the National Science Foundation (NSF), and an industry committee to measure the response of manufactured housing to both artificial and natural wind loads and to develop a computational desktop tool to optimize the structural performance of manufactured housing to HUD Code loads. MHTool is the result of an 8-year intensive testing and verification effort using single and double section homes. MHTool is the first fully integrated structural analysis software package specifically designed for manufactured housing. To use MHTool, industry design engineers will enter information (geometries, materials, connection types, etc.) describing the structure of a manufactured home, creating a base model. Windows, doors, and interior walls can be added to the initial design. Engineers will input the loads required by the HUD Code (wind, snow loads, interior live loads, etc.) and run an embedded finite element solver to find walls or connections where stresses are either excessive or very low. The designer could, for example, substitute a less expensive and easier to install connection in areas with very low stress, then re-run the analysis for verification. If forces and stresses are still within HUD Code requirements, construction costs would be saved without sacrificing quality. Manufacturers can easily change geometries or component properties to optimize designs of various floor plans then submit MHTool input and output in place of calculations for DAPIA review. No change in the regulatory process is anticipated. MHTool, while not yet complete, is now ready for demonstration. The pre-BETA version (Build-16) was displayed at the 2005 National Congress & Expo for Manufactured & Modular Housing. Additional base models and an

  16. Nuclear reactor I

    DOE Patents [OSTI]

    Ference, Edward W.; Houtman, John L.; Waldby, Robert N.

    1977-01-01

    A nuclear reactor, particularly a liquid-metal breeder reactor whose upper internals include provision for channeling the liquid metal flowing from the core-component assemblies to the outlet plenum in vertical paths in direction generally along the direction of the respective assemblies. The metal is channeled by chimneys, each secured to, and extending from, a grid through whose openings the metal emitted by a plurality of core-component assemblies encompassed by the grid flows. To reduce the stresses resulting from structural interaction, or the transmissive of thermal strains due to large temperature differences in the liquid metal emitted from neighboring core-component assemblies, throughout the chimneys and the other components of the upper internals, the grids and the chimneys are supported from the heat plate and the core barrel by support columns (double portal support) which are secured to the head plate at the top and to a member, which supports the grids and is keyed to the core barrel, at the bottom. In addition to being restrained from lateral flow by the chimneys, the liquid metal is also restrained from flowing laterally by a peripheral seal around the top of the core. This seal limits the flow rate of liquid metal, which may be sharply cooled during a scram, to the outlet nozzles. The chimneys and the grids are formed of a highly-refractory, high corrosion-resistant nickel-chromium-iron alloy which can withstand the stresses produced by temperature differences in the liquid metal. The chimneys are supported by pairs of plates, each pair held together by hollow stubs coaxial with, and encircling, the chimneys. The plates and stubs are a welded structure but, in the interest of economy, are composed of stainless steel which is not weld compatible with the refractory metal. The chimneys and stubs are secured together by shells of another nickel-chromium-iron alloy which is weld compatible with, and is welded to, the stubs and has about the same

  17. 2014 Housing Innovation Awards DOE Challenge Home Application...

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

    Housing Innovation Awards DOE Challenge Home Application 2014 Housing Innovation Awards DOE Challenge Home Application The U.S. Department of Energy's Housing Innovation Awards ...

  18. Efficient Solutions for New Homes Case Study: Demonstration House...

    Energy Savers [EERE]

    Demonstration House of Cold-Climate Solutions for Affordable Housing Efficient Solutions for New Homes Case Study: Demonstration House of Cold-Climate Solutions for Affordable ...

  19. Before the Subcommittee on Water and Power - House Natural Resources...

    Energy Savers [EERE]

    House Natural Resources Committee Before the Subcommittee on Water and Power - House ... More Documents & Publications Before The Subcommittee on Water and Power - House Energy ...

  20. Before House Committee on Oversight and Government Reform | Department...

    Office of Environmental Management (EM)

    House Committee on Oversight and Government Reform Before House Committee on Oversight and Government Reform Before House Committee on Oversight and Government Reform By: Secretary...

  1. Open House | Photosynthetic Antenna Research Center

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

    Open House Open House In early 2015, PARC moved it's adminstration offices to Siegle Hall 4th floor on Washington University in St. Louis' campus. In celebration of this move, we...

  2. " Million U.S. Housing Units"

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

    HC5.9 Home Appliances Characteristics by Year of Construction, 2005" " Million U.S. Housing Units" ,,"Year of Construction" ,"Housing Units (millions)" ,,"Before 1940","1940 to ...

  3. PARC Open House | Photosynthetic Antenna Research Center

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

    PARC Open House PARC Open House Join us for food and refreshments April 10, 2015 - 4:00pm to 6:00pm Washington University in St. Louis, Seigle Hall 4th Floor, Suite 435 We welcome...

  4. Native American Housing: Obstacles and Opportunities

    Broader source: Energy.gov [DOE]

    Hosted by the U.S. Department of Housing and Urban Development (HUD), this event will cover tribal housing and how to develop and implement programs based on and conducive to local conditions and...

  5. Whole-House Ventilation | Department of Energy

    Office of Environmental Management (EM)

    - 2:37pm Addthis A whole-house ventilation system with dedicated ducting in a new energy-efficient home. | Photo courtesy of iStockphotobrebca. A whole-house ventilation...

  6. DOE-HUD Initiative on Energy Efficiency in Housing: A federal partnership. Program summary report

    SciTech Connect (OSTI)

    Brinch, J.

    1996-06-01

    One of the primary goals of the US Department of Housing and urban Development (HUD) is the expansion of home ownership and affordable housing opportunities. Recognizing that energy efficiency is a key component in an affordable housing strategy, HUD and the US Department of Energy (DOE) created the DOE-HUD Initiative on Energy Efficiency in Housing. The DOE-HUD Initiative was designed to share the results of DOE research with housing providers throughout the nation, to reduce energy costs in federally-subsidized dwelling units and improve their affordability and comfort. This Program Summary Report provides an overview of the DOE-HUD Initiative and detailed project descriptions of the twenty-seven projects carried out with Initiative funding.

  7. Advanced House Framing | Department of Energy

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

    Design » Design for Efficiency » Advanced House Framing Advanced House Framing Two-story home using advanced framing techniques. Two-story home using advanced framing techniques. Advanced house framing, sometimes called optimum value engineering (OVE), refers to framing techniques designed to reduce the amount of lumber used and waste generated in the construction of a wood-framed house. These techniques boost energy efficiency by replacing lumber with insulation material while maintaining the

  8. FUSED REACTOR FUELS

    DOE Patents [OSTI]

    Mayer, S.W.

    1962-11-13

    This invention relates to a nuciear reactor fuel composition comprising (1) from about 0.01 to about 50 wt.% based on the total weight of said composition of at least one element selected from the class consisting of uranium, thorium, and plutonium, wherein said eiement is present in the form of at least one component selected from the class consisting of oxides, halides, and salts of oxygenated anions, with components comprising (2) at least one member selected from the class consisting of (a) sulfur, wherein the sulfur is in the form of at least one entity selected irom the class consisting of oxides of sulfur, metal sulfates, metal sulfites, metal halosulfonates, and acids of sulfur, (b) halogen, wherein said halogen is in the form of at least one compound selected from the class of metal halides, metal halosulfonates, and metal halophosphates, (c) phosphorus, wherein said phosphorus is in the form of at least one constituent selected from the class consisting of oxides of phosphorus, metal phosphates, metal phosphites, and metal halophosphates, (d) at least one oxide of a member selected from the class consisting of a metal and a metalloid wherein said oxide is free from an oxide of said element in (1); wherein the amount of at least one member selected from the class consisting of halogen and sulfur is at least about one at.% based on the amount of the sum of said sulfur, halogen, and phosphorus atom in said composition; and wherein the amount of said 2(a), 2(b) and 2(c) components in said composition which are free from said elements of uranium, thorium, arid plutonium, is at least about 60 wt.% based on the combined weight of the components of said composition which are free from said elements of uranium, thorium, and plutonium. (AEC)

  9. Fifth Annual Native American Housing Conference

    Broader source: Energy.gov [DOE]

    The Fifth Annual Native American Housing Conference will be held in conjunction with the Native American Economic Development Conference. Attendees will hear from top experts in the housing field on the state of housing in Native America and what programs are available to assist you in taking the next step.

  10. THE WHITE HOUSE | Department of Energy

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

    THE WHITE HOUSE THE WHITE HOUSE THE WHITE HOUSE (66.14 KB) More Documents & Publications FACT SHEET: U.S.-China Clean Energy Cooperation Announcements US-China Clean Energy Cooperation Progress Report on U.S.-China Energy Cooperation

  11. Chicagoland Single-Family Housing Characterization

    SciTech Connect (OSTI)

    Spanier, J.; Scheu, R.; Brand, L.; Yang, J.

    2012-06-01

    In this report, the PARR team identifies housing characteristics and energy use for fifteen housing types (groups) in the Chicagoland (Cook County, Illinois) region and specifies measure packages that provide an optimum level of energy savings based on a BEopt analysis. The analysis is based on assessor data and actual energy consumption data on 432,605 houses representing approximately 30% of the population.

  12. Chicagoland Single-Family Housing Characterization

    SciTech Connect (OSTI)

    Spanier, J.; Scheu, R.; Brand, L.; Yang, J.

    2012-06-01

    In this report, the PARR team identifies housing characteristics and energy use for fifteen housing types in the Chicagoland (Cook County, Illinois) region and specifies measure packages that provide an optimum level of energy savings based on a BEopt analysis. The analysis is based on assessor data and actual energy consumption data on 432,605 houses representing approximately 30% of the population.

  13. Federal Housing Administration's Energy Efficient Mortgage Program

    Broader source: Energy.gov [DOE]

    Describes the U.S. Department of Housing and Urban Development Energy Efficient Mortgage Program which helps homebuyers or homeowners save money on utility bills by enabling them to finance the cost of adding energy efficiency features to new or existing housing. Authors: U.S. Department of Housing and Urban Development

  14. White House Forum on Minorites in Energy

    Office of Energy Efficiency and Renewable Energy (EERE)

    On November 13, 2013, the Department of Energy and the White House Office of Science and Technology Policy, the Council for Environmental Quality, and the White House Office of Public Engagement co-hosted the White House Forum on Minorities in Energy. The event included the announcement of the Ambassadors for the Minorities in Energy Initiative.

  15. Remotely serviced filter and housing

    DOE Patents [OSTI]

    Ross, M.J.; Zaladonis, L.A.

    1987-07-22

    A filter system for a hot cell comprises a housing adapted for input of air or other gas to be filtered, flow of the air through a filter element, and exit of filtered air. The housing is tapered at the top to make it easy to insert a filter cartridge holds the filter element while the air or other gas is passed through the filter element. Captive bolts in trunnion nuts are readily operated by electromechanical manipulators operating power wrenches to secure and release the filter cartridge. The filter cartridge is adapted to make it easy to change a filter element by using a master-slave manipulator at a shielded window station. 6 figs.

  16. Remotely serviced filter and housing

    DOE Patents [OSTI]

    Ross, Maurice J.; Zaladonis, Larry A.

    1988-09-27

    A filter system for a hot cell comprises a housing adapted for input of air or other gas to be filtered, flow of the air through a filter element, and exit of filtered air. The housing is tapered at the top to make it easy to insert a filter cartridge using an overhead crane. The filter cartridge holds the filter element while the air or other gas is passed through the filter element. Captive bolts in trunnion nuts are readily operated by electromechanical manipulators operating power wrenches to secure and release the filter cartridge. The filter cartridge is adapted to make it easy to change a filter element by using a master-slave manipulator at a shielded window station.

  17. Green Future Double Barrel House

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

    University Green Future Double Barrel House DOE Race to Zero Student Competition 2016 Sean Benson Team Leader - Net Zero Energy Design I & II Bachelor of Science in Architecture, Dec 2016 Alexis Borman Net Zero Energy Design II Bachelor of Science in Architecture, May 2016 Christopher Brown AIA COTE, Net Zero Energy Design I & II Bachelor of Science in Architecture, May 2016 Devonta Magee Net Zero Energy Design II Bachelor of Science in Architecture, Aug 2016 Yasmine Parker Net Zero

  18. Building America House Simulation Protocols

    SciTech Connect (OSTI)

    Hendron, Robert; Engebrecht, Cheryn

    2010-09-01

    The House Simulation Protocol document was developed to track and manage progress toward Building America's multi-year, average whole-building energy reduction research goals for new construction and existing homes, using a consistent analytical reference point. This report summarizes the guidelines for developing and reporting these analytical results in a consistent and meaningful manner for all home energy uses using standard operating conditions.

  19. Public Housing Project Performance Benchmarks

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

    Public Housing Project Performance Benchmarks (All ASHRAE Zones) We define an ESCO as a company that provides energy efficiency-related and other value-added services and that employs performance contracting as a core part of its energy efficiency services business. 1 For projects with electricity savings, we assume site energy conversion (1 kWh = 3,412 Btu). We did not estimate avoided Btus from gallons of water conserved. In general, we followed the analytical approach documented in Hopper et

  20. Catalytic reactor for low-Btu fuels

    DOE Patents [OSTI]

    Smith, Lance; Etemad, Shahrokh; Karim, Hasan; Pfefferle, William C.

    2009-04-21

    An improved catalytic reactor includes a housing having a plate positioned therein defining a first zone and a second zone, and a plurality of conduits fabricated from a heat conducting material and adapted for conducting a fluid therethrough. The conduits are positioned within the housing such that the conduit exterior surfaces and the housing interior surface within the second zone define a first flow path while the conduit interior surfaces define a second flow path through the second zone and not in fluid communication with the first flow path. The conduit exits define a second flow path exit, the conduit exits and the first flow path exit being proximately located and interspersed. The conduits define at least one expanded section that contacts adjacent conduits thereby spacing the conduits within the second zone and forming first flow path exit flow orifices having an aggregate exit area greater than a defined percent of the housing exit plane area. Lastly, at least a portion of the first flow path defines a catalytically active surface.

  1. The house of the future

    ScienceCinema (OSTI)

    None

    2010-09-01

    Learn what it will take to create tomorrow's net-zero energy home as scientists reveal the secrets of cool roofs, smart windows, and computer-driven energy control systems. The net-zero energy home: Scientists are working to make tomorrow's homes more than just energy efficient -- they want them to be zero energy. Iain Walker, a scientist in the Lab's Energy Performance of Buildings Group, will discuss what it takes to develop net-zero energy houses that generate as much energy as they use through highly aggressive energy efficiency and on-site renewable energy generation. Talking back to the grid: Imagine programming your house to use less energy if the electricity grid is full or price are high. Mary Ann Piette, deputy director of Berkeley Lab's building technology department and director of the Lab's Demand Response Research Center, will discuss how new technologies are enabling buildings to listen to the grid and automatically change their thermostat settings or lighting loads, among other demands, in response to fluctuating electricity prices. The networked (and energy efficient) house: In the future, your home's lights, climate control devices, computers, windows, and appliances could be controlled via a sophisticated digital network. If it's plugged in, it'll be connected. Bruce Nordman, an energy scientist in Berkeley Lab's Energy End-Use Forecasting group, will discuss how he and other scientists are working to ensure these networks help homeowners save energy.

  2. Spent nuclear fuel discharges from U.S. reactors 1994

    SciTech Connect (OSTI)

    1996-02-01

    Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year`s report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs.

  3. Whole-House Ventilation | Department of Energy

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

    Ventilation » Whole-House Ventilation Whole-House Ventilation A whole-house ventilation system with dedicated ducting in a new energy-efficient home. | Photo courtesy of ©iStockphoto/brebca. A whole-house ventilation system with dedicated ducting in a new energy-efficient home. | Photo courtesy of ©iStockphoto/brebca. Energy-efficient homes -- both new and existing -- require mechanical ventilation to maintain indoor air quality. There are four basic mechanical whole-house ventilation

  4. Monument Valley Open House | Department of Energy

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

    Monument Valley Open House Monument Valley Open House July 18, 2016 - 12:22pm Addthis What does this project do? Goal 6. Engage the public, governments, and interested parties Monument Valley Open House 01.jpg An open house was held at Monument Valley High School in Utah. The U.S. Department of Energy Office of Legacy Management (LM) hosted the Uranium Issues Open House on Saturday, April 9, 2016, at Monument Valley High School in Monument Valley, Utah. Multiple federal agencies and their Navajo

  5. NHI Component Technical Readiness Evaluation System

    SciTech Connect (OSTI)

    Steven R. Sherman; Dane F. Wilson; Steven J. Pawel

    2007-09-01

    A decision process for evaluating the technical readiness or maturity of components (i.e., heat exchangers, chemical reactors, valves, etc.) for use by the U.S. DOE Nuclear Hydrogen Initiative is described. This system is used by the DOE NHI to assess individual components in relation to their readiness for pilot-scale and larger-scale deployment and to drive the research and development work needed to attain technical maturity. A description of the evaluation system is provided, and examples are given to illustrate how it is used to assist in component R&D decisions.

  6. Self-actuating and locking control for nuclear reactor

    DOE Patents [OSTI]

    Chung, Dong K. (Chatsworth, CA)

    1982-01-01

    A self-actuating, self-locking flow cutoff valve particularly suited for use in a nuclear reactor of the type which utilizes a plurality of fluid support neutron absorber elements to provide for the safe shutdown of the reactor. The valve comprises a substantially vertical elongated housing and an aperture plate located in the housing for the flow of fluid therethrough, a substantially vertical elongated nozzle member located in the housing and affixed to the housing with an opening in the bottom for receiving fluid and apertures adjacent a top end for discharging fluid. The nozzle further includes two sealing means, one located above and the other below the apertures. Also located in the housing and having walls surrounding the nozzle is a flow cutoff sleeve having a fluid opening adjacent an upper end of the sleeve, the sleeve being moveable between an upper open position wherein the nozzle apertures are substantially unobstructed and a closed position wherein the sleeve and nozzle sealing surfaces are mated such that the flow of fluid through the apertures is obstructed. It is a particular feature of the present invention that the valve further includes a means for utilizing any increase in fluid pressure to maintain the cutoff sleeve in a closed position. It is another feature of the invention that there is provided a means for automatically closing the valve whenever the flow of fluid drops below a predetermined level.

  7. The Absent House: The Ecological House of Puerto Rico

    High Performance Buildings Database

    Vega Alta, PR The Absent House takes advantage of the benevolent climate of the humid tropics of Puerto Rico to play with the ambiguity of interior and exterior spaces. Main spaces include: a kitchenette and master bathroom suite; a guest tower with a bedroom, bathroom, and small library; an open, public pavilion for cooking, dining, and porch activities; a bathroom for visitors; an infrastructure pavilion for electricity and water consumption management; and an organic garden. The Patio of the Sun and the Stars, the most important s

  8. Attrition reactor system

    DOE Patents [OSTI]

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

    1993-09-28

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

  9. Attrition reactor system

    DOE Patents [OSTI]

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

    1993-01-01

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

  10. Hybrid plasmachemical reactor

    SciTech Connect (OSTI)

    Lelevkin, V. M. Smirnova, Yu. G.; Tokarev, A. V.

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  11. Nuclear reactor insulation and preheat system

    DOE Patents [OSTI]

    Wampole, Nevin C.

    1978-01-01

    An insulation and preheat system for preselected components of a fluid cooled nuclear reactor. A gas tight barrier or compartment of thermal insulation surrounds the selected components and includes devices to heat the internal atmosphere of the compartment. An external surface of the compartment or enclosure is cooled, such as by a circulating fluid. The heating devices provide for preheating of the components, as well as maintenance of a temperature sufficient to ensure that the reactor coolant fluid will not solidify during shutdown. The external cooling limits the heat transferred to other plant structures, such as supporting concrete and steel. The barrier is spaced far enough from the surrounded components so as to allow access for remote or manual inspection, maintenance, and repair.

  12. Reactor System Transient Code.

    Energy Science and Technology Software Center (OSTI)

    1999-07-14

    RELAP3B describes the behavior of water-cooled nuclear reactors during postulated accidents or power transients, such as large reactivity excursions, coolant losses or pump failures. The program calculates flows, mass and energy inventories, pressures, temperatures, and steam qualities along with variables associated with reactor power, reactor heat transfer, or control systems. Its versatility allows one to describe simple hydraulic systems as well as complex reactor systems.

  13. Period meter for reactors

    DOE Patents [OSTI]

    Rusch, Gordon K.

    1976-01-06

    An improved log N amplifier type nuclear reactor period meter with reduced probability for noise-induced scrams is provided. With the reactor at low power levels a sampling circuit is provided to determine the reactor period by measuring the finite change in the amplitude of the log N amplifier output signal for a predetermined time period, while at high power levels, differentiation of the log N amplifier output signal provides an additional measure of the reactor period.

  14. NEUTRONIC REACTOR POWER PLANT

    DOE Patents [OSTI]

    Metcalf, H.E.

    1962-12-25

    This patent relates to a nuclear reactor power plant incorporating an air-cooled, beryllium oxide-moderated, pebble bed reactor. According to the invention means are provided for circulating a flow of air through tubes in the reactor to a turbine and for directing a sidestream of the circu1ating air through the pebble bed to remove fission products therefrom as well as assist in cooling the reactor. (AEC)

  15. The Performance House - A Cold Climate Challenge Home

    SciTech Connect (OSTI)

    Puttagunta, S.; Grab, J.; Williamson, J.

    2013-08-01

    Working with builder partners on test homes allows for vetting of whole-house building strategies to eliminate any potential unintended consequences prior to implementing these solution packages on a production scale. To support this research, CARB partnered with Preferred Builders Inc. on a high-performance test home in Old Greenwich, CT. The philosophy and science behind the 2,700 ft2 "Performance House" was based on the premise that homes should be safe, healthy, comfortable, durable, efficient, and adapt with the homeowners. The technologies and strategies used in the "Performance House" were not cutting-edge, but simply "best practices practiced". The focus was on simplicity in construction, maintenance, and operation. When seeking a 30% source energy savings targets over a comparable 2009 IECC code-built home in the cold climate zone, nearly all components of a home must be optimized. Careful planning and design are critical. To help builders and architects seeking to match the performance of this home, a step-by-step guide through the building shell components of DOE's Challenge Home are provided in a pictorial story book. The end result was a DOE Challenge Home that achieved a HERS Index Score of 20 (43 without PV, the minimum target was 55 for compliance). This home was also awarded the 2012 HOBI for Best Green Energy Efficient Home from the Home Builders & Remodelers Association of Connecticut.

  16. Variable flow control for a nuclear reactor control rod

    DOE Patents [OSTI]

    Carleton, Richard D.; Bhattacharyya, Ajay

    1978-01-01

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

  17. Containment system for supercritical water oxidation reactor

    DOE Patents [OSTI]

    Chastagner, P.

    1994-07-05

    A system is described for containment of a supercritical water oxidation reactor in the event of a rupture of the reactor. The system includes a containment for housing the reaction vessel and a communicating chamber for holding a volume of coolant, such as water. The coolant is recirculated and sprayed to entrain and cool any reactants that might have escaped from the reaction vessel. Baffles at the entrance to the chamber prevent the sprayed coolant from contacting the reaction vessel. An impact-absorbing layer is positioned between the vessel and the containment to at least partially absorb momentum of any fragments propelled by the rupturing vessel. Remote, quick-disconnecting fittings exterior to the containment, in cooperation with shut-off valves, enable the vessel to be isolated and the system safely taken off-line. Normally-closed orifices throughout the containment and chamber enable decontamination of interior surfaces when necessary. 2 figures.

  18. Containment system for supercritical water oxidation reactor

    DOE Patents [OSTI]

    Chastagner, Philippe

    1994-01-01

    A system for containment of a supercritical water oxidation reactor in the event of a rupture of the reactor. The system includes a containment for housing the reaction vessel and a communicating chamber for holding a volume of coolant, such as water. The coolant is recirculated and sprayed to entrain and cool any reactants that might have escaped from the reaction vessel. Baffles at the entrance to the chamber prevent the sprayed coolant from contacting the reaction vessel. An impact-absorbing layer is positioned between the vessel and the containment to at least partially absorb momentum of any fragments propelled by the rupturing vessel. Remote, quick-disconnecting fittings exterior to the containment, in cooperation with shut-off valves, enable the vessel to be isolated and the system safely taken off-line. Normally-closed orifices throughout the containment and chamber enable decontamination of interior surfaces when necessary.

  19. Healthy and Affordable Housing: Practical Recommendations for Building, Renovating and Maintaining Housing: Read This Before You Move In

    SciTech Connect (OSTI)

    2001-09-06

    This document provides advice for healthy and affordable housing: practical recommendations for building, renovating, and maintaining housing.

  20. NEUTRONIC REACTOR SHIELDING

    DOE Patents [OSTI]

    Borst, L.B.

    1961-07-11

    A special hydrogenous concrete shielding for reactors is described. In addition to Portland cement and water, the concrete essentially comprises 30 to 60% by weight barytes aggregate for enhanced attenuation of fast neutrons. The biological shields of AEC's Oak Ridge Graphite Reactor and Materials Testing Reactor are particular embodiments.

  1. Advanced Test Reactor Tour

    ScienceCinema (OSTI)

    Miley, Don

    2013-05-28

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

  2. High solids fermentation reactor

    DOE Patents [OSTI]

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

    1993-01-01

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

  3. High solids fermentation reactor

    DOE Patents [OSTI]

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

    1993-03-02

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

  4. Improved vortex reactor system

    DOE Patents [OSTI]

    Diebold, James P.; Scahill, John W.

    1995-01-01

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

  5. Advanced Test Reactor Tour

    SciTech Connect (OSTI)

    Miley, Don

    2011-01-01

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

  6. NUCLEAR REACTOR CONTROL SYSTEM

    DOE Patents [OSTI]

    Epler, E.P.; Hanauer, S.H.; Oakes, L.C.

    1959-11-01

    A control system is described for a nuclear reactor using enriched uranium fuel of the type of the swimming pool and other heterogeneous nuclear reactors. Circuits are included for automatically removing and inserting the control rods during the course of normal operation. Appropriate safety circuits close down the nuclear reactor in the event of emergency.

  7. EM Removes Radioactive Components from Former Reactor at Oak...

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

    ... The items were moved by long-handled tools into a container that was placed in the pool. Then, the container was retrieved and moved by a crane into an 80,000-pound, ...

  8. Repair welding of fusion reactor components. Second year technical report

    SciTech Connect (OSTI)

    Chin, B.A.

    1993-05-15

    Experiments have shown that irradiated Type 316 stainless steel is susceptible to heat-affected-zone (HAZ) cracking upon cooling when welded using the gas tungsten arc (GTA) process under lateral constraint. The cracking has been hypothesized to be caused by stress-assisted helium bubble growth and rupture at grain boundaries. This study utilized an experimental welding setup which enabled different compressive stresses to be applied to the plates during welding. Autogenous GTA welds were produced in Type 316 stainless steel doped with 256 appm helium. The application of a compressive stress, 55 MPa, during welding suppressed the previously observed catastrophic cracking. Detailed examinations conducted after welding showed a dramatic change in helium bubble morphology. Grain boundary bubble growth along directions parallel to the weld was suppressed. Results suggest that stress-modified welding techniques may be used to suppress or eliminate helium-induced cracking during joining of irradiated materials.

  9. NGNP Reactor Coolant Chemistry Control Study

    SciTech Connect (OSTI)

    Brian Castle

    2010-11-01

    The main focus of this paper is to identify the most desirable ranges of impurity levels in the primary coolant to optimize component life in the primary circuit of the Next Generation Nuclear Plant (NGNP), which will either be a prismatic block or pebble bed reactor.

  10. Reactor vessel support system

    DOE Patents [OSTI]

    Golden, Martin P.; Holley, John C.

    1982-01-01

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

  11. Nuclear reactor overflow line

    DOE Patents [OSTI]

    Severson, Wayne J.

    1976-01-01

    The overflow line for the reactor vessel of a liquid-metal-cooled nuclear reactor includes means for establishing and maintaining a continuous bleed flow of coolant amounting to 5 to 10% of the total coolant flow through the overflow line to prevent thermal shock to the overflow line when the reactor is restarted following a trip. Preferably a tube is disposed concentrically just inside the overflow line extending from a point just inside the reactor vessel to an overflow tank and a suction line is provided opening into the body of liquid metal in the reactor vessel and into the annulus between the overflow line and the inner tube.

  12. B Reactor - Hanford Site

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

    Reactor About Us About Hanford Cleanup Hanford History Hanford Site Wide Programs Contact Us 100 Area 118-K-1 Burial Ground 200 Area 222-S Laboratory 242-A Evaporator 300 Area 324 Building 325 Building 400 Area/Fast Flux Test Facility 618-10 and 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and Interim Storage Area Canyon Facilities Cold Test Facility D and DR Reactors Effluent Treatment Facility Environmental Restoration Disposal Facility F Reactor H

  13. DOE ZERH Case Study: Mutual Housing California, Mutual Housing at Spring

    Office of Scientific and Technical Information (OSTI)

    Lake, Woodland, CA () | SciTech Connect : DOE ZERH Case Study: Mutual Housing California, Mutual Housing at Spring Lake, Woodland, CA Citation Details In-Document Search Title: DOE ZERH Case Study: Mutual Housing California, Mutual Housing at Spring Lake, Woodland, CA Case study of a DOE 2015 Housing Innovation Award winning multifamily project of 62 affordable-housing apartment home in the hot-dry climate that exceeded CA Title 24-2008 by 35%, with 2x4 16" on center walls with R-21

  14. Evaluation of aging degradation of structural components

    SciTech Connect (OSTI)

    Chopra, O.K.; Shack, W.J.

    1992-03-01

    Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport reactor, as well as thermal embrittlement of CF-8 cast stainless steel components from the Shippingport and KRB reactors, has been characterized. Increases in Charpy transition temperature (CTT), yield stress, and hardness of the NST material in the low-temperature low-flux environment are consistent with the test reactor data for irradiations at < 232{degrees}C. The shift in CTT is not as severe as that observed in surveillance samples from the High Flux Isotope Reactor (HFIR): however, it shows very good agreement with the results for HFIR A212-B steel irradiated in the Oak Ridge Research Reactor. The results indicate that fluence rate has not effect on radiation embrittlement at rates as low as 2 {times} 10{sup 8} n/cm{sup 2}{center dot}s at the low operating temperature of the Shippingport NST, i.e., 55{degrees}C. This suggest that radiation damage in Shippingport NST and HFIR surveillance samples may be different because of the neutron spectra and/or Cu and Ni content of the two materials. Cast stainless steel components show relatively modest decreases in fracture toughness and Charpy-impact properties and a small increase in tensile strength. Correlations for estimating mechanical properties of cast stainless steels predict accurate or slightly conservative values for Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of the materials. The kinetics of thermal embrittlement and degree of embrittlement at saturation, i.e., the minimum impact energy achieved after long-term aging, were established from materials that were aged further in the laboratory. The results were consistent with the estimates. The correlations successfully predict the mechanical properties of the Ringhals 2 reactor hot- and crossover-leg elbows (CF-8M steel) after service of {approx}15 y.

  15. Evaluation of aging degradation of structural components

    SciTech Connect (OSTI)

    Chopra, O.K.; Shack, W.J.

    1992-03-01

    Irradiation embrittlement of the neutron shield tank (NST) A212 Grade B steel from the Shippingport reactor, as well as thermal embrittlement of CF-8 cast stainless steel components from the Shippingport and KRB reactors, has been characterized. Increases in Charpy transition temperature (CTT), yield stress, and hardness of the NST material in the low-temperature low-flux environment are consistent with the test reactor data for irradiations at < 232{degrees}C. The shift in CTT is not as severe as that observed in surveillance samples from the High Flux Isotope Reactor (HFIR): however, it shows very good agreement with the results for HFIR A212-B steel irradiated in the Oak Ridge Research Reactor. The results indicate that fluence rate has not effect on radiation embrittlement at rates as low as 2 {times} 10{sup 8} n/cm{sup 2}{center_dot}s at the low operating temperature of the Shippingport NST, i.e., 55{degrees}C. This suggest that radiation damage in Shippingport NST and HFIR surveillance samples may be different because of the neutron spectra and/or Cu and Ni content of the two materials. Cast stainless steel components show relatively modest decreases in fracture toughness and Charpy-impact properties and a small increase in tensile strength. Correlations for estimating mechanical properties of cast stainless steels predict accurate or slightly conservative values for Charpy-impact energy, tensile flow stress, fracture toughness J-R curve, and J{sub IC} of the materials. The kinetics of thermal embrittlement and degree of embrittlement at saturation, i.e., the minimum impact energy achieved after long-term aging, were established from materials that were aged further in the laboratory. The results were consistent with the estimates. The correlations successfully predict the mechanical properties of the Ringhals 2 reactor hot- and crossover-leg elbows (CF-8M steel) after service of {approx}15 y.

  16. Spinning fluids reactor

    DOE Patents [OSTI]

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

    2012-11-20

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

  17. Reactor water cleanup system

    DOE Patents [OSTI]

    Gluntz, Douglas M.; Taft, William E.

    1994-01-01

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

  18. Reactor water cleanup system

    DOE Patents [OSTI]

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

    1994-12-20

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

  19. Fission reactors and materials

    SciTech Connect (OSTI)

    Frost, B.R.T.

    1981-12-01

    The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions.

  20. DETECTION OF COATING FAILURES IN A NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Snell, A.H.; Allison, S.K.

    1958-02-11

    This patent relates to water-cooled reactor systems and discloses a means to detect leaks in the jackets of jacketed fuel elements comprising a neutron detector located in the cooling water discharge pipe,the pipe being provided with an enlarged portion for housing the detector so that the latter is completely surrounded by the water in its passage through the pipe, said enlarged portion and detector being shielded from the reactor for the purpose of detecting only those delayed neutrons emitted in the cooling water and due to the latter picking up fission fragments from the defective fuel elements.

  1. Jacking mechanism for upper internals structure of a liquid metal nuclear reactor

    DOE Patents [OSTI]

    Gillett, James E.; Wineman, Arthur L.

    1984-01-01

    A jacking mechanism for raising the upper internals structure of a liquid metal nuclear reactor which jacking mechanism uses a system of gears and drive shafts to transmit force from a single motor to four mechanically synchronized ball jacks to raise and lower support columns which support the upper internals structure. The support columns have a pin structure which rides up and down in a slot in a housing fixed to the reactor head. The pin has two locking plates which can be rotated around the pin to bring bolt holes through the locking plates into alignment with a set of bolt holes in the housing, there being a set of such housing bolt holes corresponding to both a raised and a lowered position of the support column. When the locking plate is so aligned, a surface of the locking plate mates with a surface in the housing such that the support column is then supported by the locking plate and not by the ball jacks. Since the locking plates are to be installed and bolted to the housing during periods of reactor operation, the ball jacks need not be sized to react the large forces which occur or potentially could occur on the upper internals structure of the reactor during operation. The locking plates react these loads. The ball jacks, used only during refueling, can be smaller, which enable conventionally available equipment to fulfill the precision requirements for the task within available space.

  2. Sandia National Laboratories: Intern Housing Resources

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

    CA Intern Candidates Pre-Employment Instructions NM Employee Candidates CA Employee Candidates NM Intern Candidates CA Intern Candidates Step 1: Complete Your Application Step 2: Accept Your Offer Step 3: Prepare to Start Step 4: Report to Work Your Benefits Your Pay Intern Housing Resources Contacts Pre-Employment_Instructions Intern Housing Resources Livermore, California Before you commit to any housing agreement, be sure to ask about short-term (2-4 months) leasing options and any additional

  3. Sandia National Laboratories: Intern Housing Resources

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

    NM Intern Candidates Pre-Employment Instructions NM Employee Candidates CA Employee Candidates NM Intern Candidates Step 1: Complete Your Application Step 2: Accept Your Offer Step 3: Prepare to Start Step 4: Report to Work Your Benefits Your Pay Intern Housing Resources Contacts CA Intern Candidates Pre-Employment_Instructions Intern Housing Resources Albuquerque, New Mexico All housing arrangements need to be made on your own. Unfortunately, Sandia's Student Internship Program is unable to

  4. Emergency heat removal system for a nuclear reactor

    DOE Patents [OSTI]

    Dunckel, Thomas L.

    1976-01-01

    A heat removal system for nuclear reactors serving as a supplement to an Emergency Core Cooling System (ECCS) during a Loss of Coolant Accident (LOCA) comprises a plurality of heat pipes having one end in heat transfer relationship with either the reactor pressure vessel, the core support grid structure or other in-core components and the opposite end located in heat transfer relationship with a heat exchanger having heat transfer fluid therein. The heat exchanger is located external to the pressure vessel whereby excessive core heat is transferred from the above reactor components and dissipated within the heat exchanger fluid.

  5. DURA URBAN HOUSE | Department of Energy

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

    blend in its Efficient, Affordable, Solar, Innovation--or EASI--House. Learn More AGGIE SOL The University of California, Davis, has strong pedigrees in both sustainable projects...

  6. The White House's Week of Making

    Broader source: Energy.gov [DOE]

    The White House's Week of Making from June 12-18 will coincide with a National Maker Faire event in Washington, D.C.

  7. Testimony before the House Appropriations Committee, Subcommittee...

    National Nuclear Security Administration (NNSA)

    Testimony before the House Appropriations Committee, Subcommittee on Energy and Water ... for Atomic Energy (Rosatom), and Rostekhnadzor, the Russian nuclear regulatory agency. ...

  8. Energy Conservation Standards for Manufactured Housing. Notice...

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

    ... The IECC was first published in 1998, and it has been updated continuously since that ... the National Fire Protection Association (NFPA) Standard on Manufactured Housing in ...

  9. " Million U.S. Housing Units"

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

    8 Water Heating Characteristics by Year of Construction, 2005" " Million U.S. Housing ... to 1989","1990 to 1999","2000 to 2005" "Water Heating Characteristics" ...

  10. Stewards of Affordable Housing for the Future

    Broader source: Energy.gov [DOE]

    Better Buildings Multifamily Peer Exchange Call Featuring: Stewards of Affordable Housing for the Future, call slides and discussion summary, April 7, 2011.

  11. Federal Housing Administration's Energy Efficient Mortgage Program...

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

    Mortgage Program Describes the U.S. Department of Housing and Urban Development Energy Efficient Mortgage Program which helps homebuyers or homeowners save money on utility...

  12. Total U.S. Housing Units..................................

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

    At Home Behavior Home Used for Business Yes......Apartments in Buildings With-- Housing Units (millions) Single-Family Units Detached ...

  13. Fayette Country, Pennsylvania, Housing Market Analysis

    Broader source: Energy.gov [DOE]

    This is a document from the Fayette County Housing Consortium posted to the website of the U.S. Department of Energy's Better Buildings Neighborhood Program.

  14. Please transfer ALL data off house

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

    Please transfer ALL data off /house before 12/1/2013 Please transfer ALL data off house September 3, 2013 by Kjiersten Fagnan We are happy to announce that all the file systems: /global/projectb, /global/dna and /webfs are available for use. We now strongly encourage users to begin the data transfer process from /house to the other file systems. House will retire on December 20, 2013! For more information on the best ways to transfer data and what each file system should be used for, check this

  15. NNSA Administrator Testifies Before the House Appropriations...

    National Nuclear Security Administration (NNSA)

    Subcommittee on Energy and Water Development May 21, 2009 NNSA Administrator Testifies Before the House Appropriations Subcommittee on Energy and Water Development ...

  16. Design for energy efficiency: Energy efficient industrialized housing research program. Progress report

    SciTech Connect (OSTI)

    Kellett, R.; Berg, R.; Paz, A.; Brown, G.Z.

    1991-03-01

    Since 1989, the U.S. Department of Energy has sponsored the Energy Efficient Industrialized Housing research program (EEIH) to improve the energy efficiency of industrialized housing. Two research centers share responsibility for this program: The Center for Housing Innovation at the University of Oregon and the Florida Solar Energy Center, a research institute of the University of Central Florida. Additional funding is provided through the participation of private industry, state governments and utilities. The program is guided by a steering committee comprised of industry and government representatives. This report summarizes Fiscal Year (FY) 1990 activities and progress, and proposed activities for FY 1991 in Task 2.1 Design for Energy Efficiency. This task establishes a vision of energy conservation opportunities in critical regions, market segments, climate zones and manufacturing strategies significant to industrialized housing in the 21st Century. In early FY 1990, four problem statements were developed to define future housing demand scenarios inclusive of issues of energy efficiency, housing design and manufacturing. Literature surveys were completed to assess seven areas of influence for industrialized housing and energy conservation in the future. Fifty-five future trends were identified in computing and design process; manufacturing process; construction materials, components and systems; energy and environment; demographic context; economic context; and planning policy and regulatory context.

  17. Passive heat-transfer means for nuclear reactors. [LMFBR

    DOE Patents [OSTI]

    Burelbach, J.P.

    1982-06-10

    An improved passive cooling arrangement is disclosed for maintaining adjacent or related components of a nuclear reactor within specified temperature differences. Specifically, heat pipes are operatively interposed between the components, with the vaporizing section of the heat pipe proximate the hot component operable to cool it and the primary condensing section of the heat pipe proximate the other and cooler component operable to heat it. Each heat pipe further has a secondary condensing section that is located outwardly beyond the reactor confinement and in a secondary heat sink, such as air ambient the containment, that is cooler than the other reactor component. By having many such heat pipes, an emergency passive cooling system is defined that is operative without electrical power.

  18. Self-adjustable supplemental support system for a cylindrical container in a housing

    DOE Patents [OSTI]

    Blaushild, Ronald M.

    1987-01-01

    A self-adjustable supplementary support system for a cylindrical container coaxially disposed in a cylindrical housing by upper flanged supports has a plurality of outwardly extending bracket units on the external surface of the container which coact with inwardly extending resiliently outwardly extending bracket units on the inner wall of the cylindrical housing. The bracket units have flanges which form a concave surface that seats on support bars, attached by links to torsion bars that are secured to ring segments annularly spaced about the inner wall of the cylindrical housing and the bracket units and support bars coact with each other to radially position and support the container in the housing during movement of the two components from a vertical to a horizontal position, and during transportation of the same.

  19. Self-adjustable supplemental support system for a cylindrical container in a housing

    DOE Patents [OSTI]

    Blaushild, R.M.

    1987-01-30

    A self-adjustable supplementary support system for a cylindrical container coaxially disposed in a cylindrical housing by upper flanged supports has a plurality of outwardly extending bracket units on the external surface of the container which coact with inwardly extending resiliently outwardly extending bracket units on the inner wall of the cylindrical housing. The bracket units have flanges which form a concave surface that seats on support bars, attached by links to torsion bars that are secured to ring segments annularly spaced about the inner wall of the cylindrical housing and the bracket units and support bars coact with each other to radially position and support the container in the housing during movement of the two components from a vertical to a horizontal position, and during transportation of the same. 14 figs.

  20. Prospects for Tokamak Fusion Reactors

    SciTech Connect (OSTI)

    Sheffield, J.; Galambos, J.

    1995-04-01

    This paper first reviews briefly the status and plans for research in magnetic fusion energy and discusses the prospects for the tokamak magnetic configuration to be the basis for a fusion power plant. Good progress has been made in achieving fusion reactor-level, deuterium-tritium (D-T) plasmas with the production of significant fusion power in the Joint European Torus (up to 2 MW) and the Tokamak Fusion Test Reactor (up to 10 MW) tokamaks. Advances on the technologies of heating, fueling, diagnostics, and materials supported these achievements. The successes have led to the initiation of the design phases of two tokamaks, the International Thermonuclear Experimental Reactor (ITER) and the US Toroidal Physics Experiment (TPX). ITER will demonstrate the controlled ignition and extended bum of D-T plasmas with steady state as an ultimate goal. ITER will further demonstrate technologies essential to a power plant in an integrated system and perform integrated testing of the high heat flux and nuclear components required to use fusion energy for practical purposes. TPX will complement ITER by testing advanced modes of steady-state plasma operation that, coupled with the developments in ITER, will lead to an optimized demonstration power plant.

  1. Cool Energy House - An Intro to the Cool Energy House Retrofit

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

    Demonstration Project Webinar | Department of Energy Cool Energy House - An Intro to the Cool Energy House Retrofit Demonstration Project Webinar Cool Energy House - An Intro to the Cool Energy House Retrofit Demonstration Project Webinar Slides from the Building America webinar on November 14, 2011. webinar_cool_ehouse_20111130.pdf (8.94 MB) More Documents & Publications Building America Overview - 2014 BTO Peer Review Building America Roadmap to High Performance Homes Automated Sealing

  2. Building America Whole-House Solutions for Existing Homes: Islip Housing

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

    Authority Energy Efficiency Turnover Protocols, Islip, New York | Department of Energy Islip Housing Authority Energy Efficiency Turnover Protocols, Islip, New York Building America Whole-House Solutions for Existing Homes: Islip Housing Authority Energy Efficiency Turnover Protocols, Islip, New York In this project, ARIES worked with two public housing authorities (PHA) to develop packages of energy efficiency retrofit measures the PHAs can cost effectively implement at the time when units

  3. Method to Reduce Neutron Production in Small Clean Fusion Reactors Inventor

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

    --- Samuel A. Cohen | Princeton Plasma Physics Lab Method to Reduce Neutron Production in Small Clean Fusion Reactors Inventor --- Samuel A. Cohen This invention describes a method to reduce neutron production of D-3He-fueled, steady state, small FRC fusion reactors using periodic, co-streaming, energetic ion beams generated by RF. Use of this method will lessen damage to and activation of reactor components and, in doing so, can advance the development of fusion reactors for electrical

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

    SciTech Connect (OSTI)

    Soldevilla, M.; Salmons, S.; Espinosa, B.

    2013-07-01

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

  5. NEUTRONIC REACTOR SYSTEM

    DOE Patents [OSTI]

    Goett, J.J.

    1961-01-24

    A system is described which includes a neutronic reactor containing a dispersion of fissionable material in a liquid moderator as fuel and a conveyor to which a portion of the dispersion may be passed and wherein the self heat of the slurry evaporates the moderator. Means are provided for condensing the liquid moderator and returning it to the reactor and for conveying the dried fissionable material away from the reactor.

  6. THERMAL NEUTRONIC REACTOR

    DOE Patents [OSTI]

    Spinrad, B.I.

    1960-01-12

    A novel thermal reactor was designed in which a first reflector formed from a high atomic weight, nonmoderating material is disposed immediately adjacent to the reactor core. A second reflector composed of a moderating material is disposed outwardly of the first reflector. The advantage of this novel reflector arrangement is that the first reflector provides a high slow neutron flux in the second reflector, where irradiation experiments may be conducted with a small effect on reactor reactivity.

  7. Improved vortex reactor system

    DOE Patents [OSTI]

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

    1995-05-09

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

  8. Small Modular Reactors (SMRs) | Department of Energy

    Energy Savers [EERE]

    Reactor Technologies Small Modular Reactors (SMRs) Small Modular Reactors (SMRs) ... to the NRC by late-2016 Complete reactor module final design by mid-2019 For more ...

  9. White House | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    White House White House Honors Four Early-Career Sandia Researchers Sandia National Laboratories researchers Matthew Brake, Adrian Chavez, Seth Root and Daniel Stick have been named by President Barack Obama as recipients of the Presidential Early Career Award for Scientists and Engineers (PECASE). The PECASE is the highest honor the U.S. government gives

  10. Tokamak reactor first wall

    DOE Patents [OSTI]

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

    1984-11-20

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

  11. Small Modular Reactors - SRSCRO

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

    smr Small Modular Reactors The Savannah River National Laboratory (SRNL) has announced several partnerships to bring refrigerator-sized modular nuclear reactors, known as Small Modular Reactors or SMRs, to the Savannah River Site facility and jump start development of the U.S. Energy Freedom CenterTM. Currently, all large commercial power reactors in the United States and most in the rest of the world are based on "light water" designs - that is, they use uranium fuel and ordinary

  12. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, Juhani

    1996-01-01

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

  13. Pressurized fluidized bed reactor

    DOE Patents [OSTI]

    Isaksson, J.

    1996-03-19

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

  14. HOMOGENEOUS NUCLEAR POWER REACTOR

    DOE Patents [OSTI]

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  15. Experimental Study on Flow Optimization in Upper Plenum of Reactor Vessel for a Compact Sodium-Cooled Fast Reactor

    SciTech Connect (OSTI)

    Kimura, Nobuyuki; Hayashi, Kenji; Kamide, Hideki; Itoh, Masami; Sekine, Tadashi

    2005-11-15

    An innovative sodium-cooled fast reactor has been investigated in a feasibility study of fast breeder reactor cycle systems in Japan. A compact reactor vessel and a column-type upper inner structure with a radial slit for an arm of a fuel-handling machine (FHM) are adopted. Dipped plates are set in the reactor vessel below the free surface to prevent gas entrainment. We performed a one-tenth-scaled model water experiment for the upper plenum of the reactor vessel. Gas entrainment was not observed in the experiment under the same velocity condition as the reactor. Three vortex cavitations were observed near the hot-leg inlet. A vertical rib on the reactor vessel wall was set to restrict the rotating flow near the hot leg. The vortex cavitation between the reactor vessel wall and the hot leg was suppressed by the rib under the same cavitation factor condition as in the reactor. The cylindrical plug was installed through the hole in the dipped plates for the FHM to reduce the flow toward the free surface. It was effective when the plug was submerged into the middle height in the upper plenum. This combination of two components had a possibility to optimize the flow in the compact reactor vessel.

  16. New Whole-House Solutions Case Study: The Performance House: A Cold Climate Challenge Home, Old Greenwich, Connecticut

    SciTech Connect (OSTI)

    2013-11-01

    By working with builder partners on test homes, researchers from the U.S. Department of Energys Building America program can vet whole-house building strategies and avoid potential unintended consequences of implementing untested solution packages on a production scale. To support this research, Building America team Consortium for Advanced Residential Buildings (CARB) partnered with Preferred Builders Inc. on a high-performance test home in Old Greenwich, Connecticut. The philosophy and science behind the 2,700 ft2 Performance House was based on the premise that homes should be safe, healthy, comfortable, durable, efficient, and adaptable to the needs of homeowners. The technologies and strategies used in the Performance House were best practices rather than cutting edge, with a focus on simplicity in construction, maintenance, and operation. Achieving 30% source energy savings compared with a home built to the 2009 International Energy Conservation Code in the cold climate zone requires that nearly all components and systems be optimized. Careful planning and design are critical. The end result was a DOE Challenge Home that achieved a Home Energy Rating System (HERS) Index Score of 20 (43 without photovoltaics [PV]).

  17. Inductive coupler for downhole components and method for making same

    DOE Patents [OSTI]

    Hall, David R.; Hall, Jr., H. Tracy; Pixton, David S.; Dahlgren, Scott; Briscoe, Michael A.; Sneddon, Cameron; Fox, Joe

    2006-05-09

    The present invention includes a method of making an inductive coupler for downhole components. The method includes providing an annular housing, preferably made of steel, the housing having a recess. A conductor, preferably an insulated wire, is also provided along with a plurality of generally U-shaped magnetically conducting, electrically insulating (MCEI) segments. Preferably, the MCEI segments comprise ferrite. An assembly is formed by placing the plurality of MCEI segments within the recess in the annular housing. The segments are aligned to form a generally circular trough. A first portion of the conductor is placed within the circular trough. This assembly is consolidated with a meltable polymer which fills spaces between the segments, annular housing and the first portion of the conductor. The invention also includes an inductive coupler including an annular housing having a recess defined by a bottom portion and two opposing side wall portions. At least one side wall portion includes a lip extending toward but not reaching the other side wall portion. A plurality of generally U-shaped MCEI segments, preferably comprised of ferrite, are disposed in the recess and aligned so as to form a circular trough. The coupler further includes a conductor disposed within the circular trough and a polymer filling spaces between the segments, the annular housing and the conductor.

  18. New Whole-House Solutions Case Study: Low-Cost Evaluation of Energy Savings at the Community Scale - Fresno, California

    SciTech Connect (OSTI)

    2014-10-01

    In this project, IBACOS partnered with builder Wathen-Castanos Hybrid Homes to develop a simple and low-cost methodology by which community-scale energy savings can be evaluated based on results at the occupied test house level.Research focused on the builder and trade implementation of a whole-house systems integrated measures package and the actual utility usage in the houses at the community scale of production. Five occupants participated in this community-scale research by providing utility bills and information on occupancy and miscellaneous gas and electric appliance use for their houses. IBACOS used these utility data and background information to analyze the actual energy performance of the houses. Verification with measured data is an important component in predictive energy modeling. The actual utility bill readings were compared to projected energy consumption using BEopt with actual weather and thermostat set points for normalization.

  19. Design, Test and Demonstration of Saturable Reactor High-Temperature Superconductor Fault Current Limiters

    SciTech Connect (OSTI)

    Frank Darmann; Robert Lombaerde; Franco Moriconi; Albert Nelson

    2011-10-31

    Zenergy Power has successfully designed, built, tested, and installed in the US electrical grid a saturable reactor Fault Current Limiter. Beginning in 2007, first as SC Power Systems and from 2008 as Zenergy Power, Inc., ZP used DOE matching grant and ARRA funds to help refine the design of the saturated reactor fault current limiter. ZP ultimately perfected the design of the saturated reactor FCL to the point that ZP could reliably design a suitable FCL for most utility applications. Beginning with a very basic FCL design using 1G HTS for a coil housed in a LN2 cryostat for the DC bias magnet, the technology progressed to a commercial system that was offered for sale internationally. Substantial progress was made in two areas. First, the cryogenics cooling system progressed from a sub-cooled liquid nitrogen container housing the HTS coils to cryostats utilizing dry conduction cooling and reaching temperatures down to less than 20 degrees K. Large, round cryostats with “warm bore” diameters of 1.7 meters enabled the design of large tanks to hold the AC components. Second, the design of the AC part of the FCL was refined from a six legged “spider” design to a more compact and lighter design with better fault current limiting capability. Further refinement of the flux path and core shape led to an efficient saturated reactor design requiring less Ampere-turns to saturate the core. In conclusion, the development of the saturable reactor FCL led to a more efficient design not requiring HTS magnets and their associated peripheral equipment, which yielded a more economical product in line with the electric utility industry expectations. The original goal for the DOE funding of the ZP project “Design, Test and Demonstration of Saturable Reactor High-Temperature Superconductor Fault Current Limiters” was to stimulate the HTS wire industry with, first 1G, then 2G, HTS wire applications. Over the approximately 5 years of ZP’s product

  20. Brookhaven Graphite Research Reactor Workshop

    Broader source: Energy.gov [DOE]

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

  1. 10th Annual North American Passive House Conference

    Broader source: Energy.gov [DOE]

    Hosted by the Passive House Institute US, this five-day conference will target both multifamily and single family housing design, engineering, and development along with Passive House certification.

  2. Whole-House Systems Approach | Department of Energy

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

    Design Design for Efficiency Whole-House Systems Approach Whole-House Systems Approach The whole-house systems approach used to design this ultra-efficient home at Lone Star ...

  3. Energy Showcase Open House 2012 | Argonne National Laboratory

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

    Energy Showcase Open House 2012 Energy Showcase Open House 2012 1 of 65 Energy Showcase Open House 2012 A visitor peers inside to see an ion trap in the 203 Physics Building. View ...

  4. NEUTRONIC REACTOR BURIAL ASSEMBLY

    DOE Patents [OSTI]

    Treshow, M.

    1961-05-01

    A burial assembly is shown whereby an entire reactor core may be encased with lead shielding, withdrawn from the reactor site and buried. This is made possible by a five-piece interlocking arrangement that may be easily put together by remote control with no aligning of bolt holes or other such close adjustments being necessary.

  5. NEUTRONIC REACTOR SYSTEM

    DOE Patents [OSTI]

    Treshow, M.

    1959-02-10

    A reactor system incorporating a reactor of the heterogeneous boiling water type is described. The reactor is comprised essentially of a core submerged adwater in the lower half of a pressure vessel and two distribution rings connected to a source of water are disposed within the pressure vessel above the reactor core, the lower distribution ring being submerged adjacent to the uppcr end of the reactor core and the other distribution ring being located adjacent to the top of the pressure vessel. A feed-water control valve, responsive to the steam demand of the load, is provided in the feedwater line to the distribution rings and regulates the amount of feed water flowing to each distribution ring, the proportion of water flowing to the submerged distribution ring being proportional to the steam demand of the load. This invention provides an automatic means exterior to the reactor to control the reactivity of the reactor over relatively long periods of time without relying upon movement of control rods or of other moving parts within the reactor structure.

  6. Light water reactor program

    SciTech Connect (OSTI)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  7. REFLECTOR FOR NEUTRONIC REACTORS

    DOE Patents [OSTI]

    Fraas, A.P.

    1963-08-01

    A reflector for nuclear reactors that comprises an assembly of closely packed graphite rods disposed with their major axes substantially perpendicular to the interface between the reactor core and the reflector is described. Each graphite rod is round in transverse cross section at (at least) its interface end and is provided, at that end, with a coaxial, inwardly tapering hole. (AEC)

  8. Probabilistic Safety Assessment of Tehran Research Reactor

    SciTech Connect (OSTI)

    Hosseini, Seyed Mohammad Hadi; Nematollahi, Mohammad Reza; Sepanloo, Kamran

    2004-07-01

    Probabilistic Safety Assessment (PSA) application is found to be a practical tool for research reactor safety due to intense involvement of human interactions in an experimental facility. In this paper the application of the Probabilistic Safety Assessment to the Tehran Research Reactor (TRR) is presented. The level 1 PSA application involved: Familiarization with the plant, selection of accident initiators, mitigating functions and system definitions, event tree constructions and quantification, fault tree constructions and quantification, human reliability, component failure data base development and dependent failure analysis. Each of the steps of the analysis given above is discussed with highlights from the selected results. Quantification of the constructed models is done using SAPHIRE software. This Study shows that the obtained core damage frequency for Tehran Research Reactor (8.368 E-6 per year) well meets the IAEA criterion for existing nuclear power plants (1E-4). But safety improvement suggestions are offered to decrease the most probable accidents. (authors)

  9. Major Components of Lending

    Broader source: Energy.gov [DOE]

    The major components of a clean energy financing program are described below, centered around the characteristics and sources of capital.

  10. Symposium on electroslag component casting: proceedings

    SciTech Connect (OSTI)

    Judkins, R.R.; Hobday, J.M.

    1984-03-01

    The US Department of Energy (DOE), Office of Fossil Energy, Office of Surface Coal Gasification, has established a Materials Program to develop and apply appropriate materials to coal gasification plant components. The overall goals of the Surface Gasification Materials Program (SGMP) are to improve operational reliability and system durability and to reduce fabrication and operating costs of coal gasification plant components. The SGMP Electroslag Component Casting Project is directed to the development of electroslag casting (ESC) technology for use in coal conversion components such as valve bodies, pump housings, and pipe fittings. The aim is to develop a sufficient data base to permit ESC to become an ASME Code-accepted process. It is also intended to transfer the ESC process technology to private industry. This symposium was planned to discuss not only the SGMP Electroslag Component Casting Project but the activities and experiences of other organizations as well. The symposium addressed descriptions of electroslag processes; a worldwide perspective on the status of ESC technology; and details of production, mechanical properties, economics, and use of ESC for coal gasification components. Ten papers were presented, and a panel discussion was held to provide participants an opportunity to express their opinions and to offer recommendations on the content of the DOE program. This document constitutes the proceedings of that symposium. The papers included here are minimally edited transcripts of the presentations made at the symposium. All papers have been processed for inclusion in the Energy Data Base.

  11. $50 and up underground house book

    SciTech Connect (OSTI)

    Oehler, M.

    1981-01-01

    Earth-sheltered housing can be livable, compatible with nature, and inexpensive. Plans and designs for low-cost houses that are integrated with their environment make up most of this book. The author begins by outlining 23 advantages of underground housing and describing the histories of several unconventional buildings in the $50 to $500 price range. He also suggests where building materials can be bought and scrounged, describes construction techniques, and explains how to cope with building codes. Sketches, floorplans, and photographs illustrate the text. 8 references, 4 tables. (DCK)

  12. " Million Housing Units, Final"

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

    Air Conditioning in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ,"Total U.S.1 (millions)" ,," Detached"," Attached"," 2 to 4 Units","5 or More Units","Mobile Homes" "Air Conditioning" "Total Homes",113.6,71.8,6.7,9,19.1,6.9 "Air Conditioning Equipment"

  13. " Million Housing Units, Final"

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

    Appliances in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ,"Total U.S.1 (millions)" ,,,,,"5 or More Units","Mobile Homes" "Appliances",,"Detached","Attached","2 to 4 Units" "Total Homes",113.6,71.8,6.7,9,19.1,6.9 "Cooking Appliances" "Stoves (Units With

  14. Peoria Tribal Housing Authority: Weatherization Training Project

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

    Program 2009 Program Review Denver Colorado  Jason Dollarhide, Second Chief  Peoria Tribe of Indians of Oklahoma  Deputy Director, Housing Authority of the Peoria Tribe  The Peoria Tribe is located in Miami, Oklahoma  We currently have an enrollment of 2,900 Tribal members  The Peoria Tribal operations and Housing Authority employ 39 persons.  The Peoria Tribe and Housing Authority work in partnership with the Ottawa Tribe of Oklahoma. We manage 127 low-rent units in various

  15. Some Aspects of Reactor Theory

    DOE R&D Accomplishments [OSTI]

    Weinberg, Alvin M.

    1952-10-10

    Some general remarks are made on reactor theory, particularly the asymptotic theory and multigroup methods. Unsolved reactor problems are also briefly discussed. (B.J.H.)

  16. Reactor Materials | Department of Energy

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

    reactor materials crosscut effort will enable the development of innovative and ... Research into specific degradation modes or material needs unique to a particular reactor ...

  17. Two component-three dimensional catalysis

    DOE Patents [OSTI]

    Schwartz, Michael; White, James H.; Sammells, Anthony F.

    2002-01-01

    This invention relates to catalytic reactor membranes having a gas-impermeable membrane for transport of oxygen anions. The membrane has an oxidation surface and a reduction surface. The membrane is coated on its oxidation surface with an adherent catalyst layer and is optionally coated on its reduction surface with a catalyst that promotes reduction of an oxygen-containing species (e.g., O.sub.2, NO.sub.2, SO.sub.2, etc.) to generate oxygen anions on the membrane. The reactor has an oxidation zone and a reduction zone separated by the membrane. A component of an oxygen containing gas in the reduction zone is reduced at the membrane and a reduced species in a reactant gas in the oxidation zone of the reactor is oxidized. The reactor optionally contains a three-dimensional catalyst in the oxidation zone. The adherent catalyst layer and the three-dimensional catalyst are selected to promote a desired oxidation reaction, particularly a partial oxidation of a hydrocarbon.

  18. Before the House Energy and Commerce Committee | Department of...

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

    Committee Before the House Energy and Commerce Committee Before the House Energy and Commerce Committee By: Secretary Steven Chu Subject: American Clean Energy and Security Act of...

  19. Before the Subcommittee on Environment and the Economy - House...

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

    House Energy and Commerce Committee Before the Subcommittee on Environment and the Economy - House Energy and Commerce Committee Testimony of Ernest Moniz, Secretary of Energy...

  20. Before the Subcommittee on Oversight and Investigations - House...

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

    Oversight and Investigations - House Energy and Commerce Committee Before the Subcommittee on Oversight and Investigations - House Energy and Commerce Committee Testimony of Daniel...

  1. Testimony Before the House Energy and Commerce Subcommittee on...

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

    Energy and Commerce Subcommittee on Energy and Environment Testimony Before the House Energy and Commerce Subcommittee on Energy and Environment Before the House Energy and...

  2. Before The Subcommittee on Oversight and Investigations - House...

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

    The Subcommittee on Oversight and Investigations - House Committee on Energy and Commerce Before The Subcommittee on Oversight and Investigations - House Committee on Energy and...

  3. Before House Subcommittee on Oversight and Investigations - Committee...

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

    House Subcommittee on Oversight and Investigations - Committee on Energy and Commerce Before House Subcommittee on Oversight and Investigations - Committee on Energy and Commerce...

  4. Before the Subcommittee on Energy and Power -- House Energy and...

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

    - House Energy and Commerce Committee Before the Subcommittee on Energy and Power -- House Energy and Commerce Committee Testimony of Ernest Moniz, Secretary of Energy Before the...

  5. Before House Subcommittee on Energy and Power - Committee on...

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

    - Committee on Energy and Commerce Before House Subcommittee on Energy and Power - Committee on Energy and Commerce Before House Subcommittee on Energy and Power - Committee on...

  6. Before the House Subcommittee on Energy - Committee on Science...

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

    Before the House Science and Technology Subcommittee on Energy and Environment Microsoft Word - Second ITER Council Press Release.doc Before the House Committee on Space, Science, ...

  7. 2014 HAC Rural Housing Conference: Retool, Rebuild, Renew

    Broader source: Energy.gov [DOE]

    The biennial HAC Rural Housing Conference brings together stakeholders in the field of rural affordable housing from local nonprofits, federal agencies, Congress, state and local governments, and...

  8. Stewards of Affordable Housing for the Future | Department of...

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

    Stewards of Affordable Housing for the Future Stewards of Affordable Housing for the Future Better Buildings Multifamily Peer Exchange Call Featuring: Stewards of Affordable...

  9. Housing and Construction Holding Company | Open Energy Information

    Open Energy Info (EERE)

    Housing and Construction Holding Company Jump to: navigation, search Name: Housing and Construction Holding Company Place: Ramat-Gan, Israel Zip: 52215 Product: Israel-based...

  10. Before the House Subcommittee on Energy, Committee on Science...

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

    Before the House Subcommittee on Energy, Committee on Science, Space and Technology Testimony of Dr. Peter Lyons, Assistant Secretary for Nuclear Energy Before the House ...

  11. Before the House Small Business Subcommittee on Contracting and...

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

    Subcommittee on Contracting and Technology Before the House Small Business Subcommittee on Contracting and Technology Before the House Small Business Subcommittee on Contracting...

  12. The Subcommittee on Water, Power, and Oceans House Committee...

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

    The Subcommittee on Water, Power, and Oceans House Committee on Natural Resources The Subcommittee on Water, Power, and Oceans House Committee on Natural Resources Testimony of ...

  13. Before the House Natural Resources Subcommittee on Water and...

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

    (71.99 KB) More Documents & Publications Before the House Natural Resources Subcommittee on Water and Power Before the House Natural Resources Subcommittee on Water and Power

  14. Before the Subcommittee on Water, Power, and Oceans House Natural...

    Office of Environmental Management (EM)

    House Natural Resources Committee Before the Subcommittee on Water, Power, and Oceans House Natural Resources Committee Testimony of Elliot E. Mainzer, Administrator, Bonneville...

  15. Before the House Natural Resources Subcommittee on Water and...

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

    More Documents & Publications Before the House Natural Resources Subcommittee on Water and Power Before House Subcommittee on Water and Power - Committee on Natural...

  16. Building America Whole-House Solutions for New Homes: Northwest...

    Energy Savers [EERE]

    High-Performance Test Homes Building America Whole-House Solutions for New Homes: Northwest Energy Efficient Manufactured Housing Program High-Performance Test Homes This project ...

  17. Building America Whole-House Solutions for Existing Homes: Cascade...

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

    Building America Whole-House Solutions for Existing Homes: Cascade Apartments - Deep Energy Multifamily Retrofit (Fact Sheet) Building America Whole-House Solutions for Existing...

  18. Before the House Science and Technology Subcommittee on Energy...

    Energy Savers [EERE]

    Science and Technology Subcommittee on Energy and Environment Before the House Science and Technology Subcommittee on Energy and Environment Before the House Science and Technology ...

  19. Before the House Science and Technology Subcommittee on Investigations...

    Energy Savers [EERE]

    Before the House Science and Technology Subcommittee on Investigations and Oversight Before the House Science and Technology Subcommittee on Investigations and Oversight By: ...

  20. Before the House Committee on Armed Services - Subcommittee on...

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

    Before the House Committee on Armed Services - Subcommittee on Strategic Forces Testimony of Gen. Frank G. Klotz (Ret.) Before the House Committee on Armed Services - Subcommittee ...

  1. Building America Whole-House Solutions for Existing Homes: Performance...

    Energy Savers [EERE]

    Stockton, California (Fact Sheet) Building America Whole-House Solutions for Existing Homes: Performance of a Hot-Dry Climate Whole-House Retrofit, Stockton, California (Fact ...

  2. Before the House Subcommittee on Energy and Environment - Committee...

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

    Transportation Before the House Subcommittee on Energy and Environment - Committee on Science, Space, and Transportation Before the House Subcommittee on Energy and Environment -...

  3. Before the House Science and Technology Subcommittee on Energy...

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

    Subcommittee on Energy and Environment Before the House Science and Technology Subcommittee on Energy and Environment Before the House Science and Technology Subcommittee on Energy...

  4. Project Reports for Peoria Tribe: Housing Authority- 2010 Project

    Broader source: Energy.gov [DOE]

    The Housing Authority of the Peoria Tribe of Indians of Oklahoma (Peoria Housing Authority or PHA) will conduct the "PHA Weatherization Training Project."

  5. Sandia Energy - White House Business Council Roundtable on Water

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

    Protected: White House Business Council Roundtable on Water Home Climate Water Security Protected: White House Business Council Roundtable on Water Previous Next Protected: White...

  6. Vale Slaughter House Space Heating Low Temperature Geothermal...

    Open Energy Info (EERE)

    Slaughter House Space Heating Low Temperature Geothermal Facility Jump to: navigation, search Name Vale Slaughter House Space Heating Low Temperature Geothermal Facility Facility...

  7. Before the Subcommittee on Environment and the Economy -- House...

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

    Environment and the Economy -- House Energy and Commerce Committee Before the Subcommittee on Environment and the Economy -- House Energy and Commerce Committee Testimony of Peter ...

  8. Before the House Committee on Energy and Commerce Subcommittee...

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

    Before the House Committee on Energy and Commerce Subcommittee on Oversight and ... Oversight and Investigations Energy and Commerce Committee U.S. House of Representatives ...

  9. Before the House Subcommittee on Energy and Power - Committee...

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

    Energy and Power - Committee on Energy and Commerce Before the House Subcommittee on Energy and Power - Committee on Energy and Commerce Before the House Subcommittee on Energy and ...

  10. Before the House Committee on Energy and Commerce - Subcommittee...

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

    Before the House Committee on Energy and Commerce - Subcommittee on Environment and ... Before the House Committee on Energy and Commerce - Subcommittee on Environment and ...

  11. Tribal Leaders Provide White House with Input on Bolstering Climate...

    Office of Environmental Management (EM)

    Leaders Provide White House with Input on Bolstering Climate Resilience Tribal Leaders Provide White House with Input on Bolstering Climate Resilience January 7, 2015 - 10:29am ...

  12. Before House Committee on Science, Space, and Technology - Subcommitte...

    Energy Savers [EERE]

    House Committee on Science, Space, and Technology - Subcommittees on Environment and Energy Before House Committee on Science, Space, and Technology - Subcommittees on Environment ...

  13. Before the House Science, Space, and Technology Subcommittee...

    Energy Savers [EERE]

    Technology Laboratory Before the House Science, Space, and Technology Subcommittee on ... the Subcommittee on Energy -- House Science, Space, and Technology Committee Before ...

  14. White House Leadership Summit on Women, Climate and Energy |...

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

    White House Leadership Summit on Women, Climate and Energy White House Leadership Summit on Women, Climate and Energy Addthis Topic Energy Efficiency Energy Usage Science & ...

  15. Team New Jersey's Beach House Approaches Sustainable Design from...

    Energy Savers [EERE]

    Team New Jersey's Beach House Approaches Sustainable Design from a Different Angle Team New Jersey's Beach House Approaches Sustainable Design from a Different Angle April 28, 2011...

  16. Before the House Science, Space, and Technology Subcommittee...

    Energy Savers [EERE]

    House Science, Space, and Technology Subcommittee on Investigations and Oversight Before the House Science, Space, and Technology Subcommittee on Investigations and Oversight...

  17. Buffalo Pushes Energy-Efficient Affordable Housing in New York...

    Energy Savers [EERE]

    Buffalo Pushes Energy-Efficient Affordable Housing in New York Buffalo Pushes Energy-Efficient Affordable Housing in New York Better Buildings Residential Network member PUSH ...

  18. White House Announces New Executive Order To Reduce Greenhouse...

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

    White House Announces New Executive Order To Reduce Greenhouse Gas Emissions in the Federal Government White House Announces New Executive Order To Reduce Greenhouse Gas Emissions ...

  19. Building America Case Study: Demonstration House of Cold-Climate...

    Energy Savers [EERE]

    Demonstration House of Cold-Climate Solutions for Affordable Housing Minneapolis, ... America (BA) team that conducted a demonstration project to help nonproft developers ...

  20. Low-Cost Ventilation in Production Housing - Building America...

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

    Low-Cost Ventilation in Production Housing (845.94 KB) More Documents & Publications Building America Whole-House Solutions for New Homes: Green Coast Enterprises, New Orleans, ...

  1. CHIP House Takes Design to Different Heights (Literally)

    Broader source: Energy.gov [DOE]

    Check out the SCI-Arc/Caltech 2011 Solar Decathlon team's house to find out more about their net-zero energy use home -- the CHIP House.

  2. Building America Whole-House Solutions for Existing Homes: Cascade...

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

    More Documents & Publications Building America Whole-House Solutions for Existing Homes: Conway Street Apartments - Greenfield, Massachusetts Building America Whole-House Solutions ...

  3. Building America Whole-House Solutions for Existing Homes: Multifamily...

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

    Building America Whole-House Solutions for New Homes: Shaw Construction, Aspen, Colorado Building America Whole-House Solutions for Existing Homes: Conway Street Apartments - ...

  4. Before the Subcommittee on Water and Power - House Natural Resources...

    Energy Savers [EERE]

    the Subcommittee on Water and Power - House Natural Resources Committee Before the Subcommittee on Water and Power - House Natural Resources Committee Testimony of Christopher M. ...

  5. Before the Subcommittee on Water, Power, and Oceans - House Natural...

    Energy Savers [EERE]

    Water, Power, and Oceans - House Natural Resources Committee Before the Subcommittee on Water, Power, and Oceans - House Natural Resources Committee Testimony of Kenneth E. Legg, ...

  6. Before The Subcommittee on Water and Power - House Energy and...

    Energy Savers [EERE]

    The Subcommittee on Water and Power - House Energy and Natural Resources Committee Before The Subcommittee on Water and Power - House Energy and Natural Resources Committee ...

  7. Before the House Science and Technology Subcommittee on Oversight...

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

    Oversight and Investigations Before the House Science and Technology Subcommittee on Oversight and Investigations Before the House Science and Technology Subcommittee on Oversight...

  8. Before the House Energy and Commerce Subcommittee on Oversight...

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

    Oversight and Investigations Before the House Energy and Commerce Subcommittee on Oversight and Investigations Before the House Energy and Commerce Subcommittee on Oversight and ...

  9. Before House Subcommittee on Energy and Power and Subcommittee...

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

    on Energy and Commerce Before House Subcommittee on Energy and Power and Subcommittee on Oversight and Investigations - Committee on Energy and Commerce Before House ...

  10. Before the House Committee on Energy and Commerce Subcommittee...

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

    on Oversight and Investigations Energy and Commerce Committee U.S. House of Representatives WIPP Public Hearing June 2016 Before the House Committee on Energy and Commerce ...

  11. Before the Subcommittee on Energy - House Committee on Science...

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

    Before the Subcommittee on Energy - House Committee on Science, Space, and Technology Before the Subcommittee on Energy - House Committee on Science, Space, and Technology ...

  12. Hearing Before the House Science, Space, and Technology Subcommittee...

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

    House Science, Space, and Technology Subcommittee on Energy, and Subcommittee on Oversight Hearing Before the House Science, Space, and Technology Subcommittee on Energy, and ...

  13. Before the Subcommittee on Strategic Forces - House Armed Services...

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

    - House Armed Services Committee Before the Subcommittee on Strategic Forces - House Armed Services Committee Testimony of Daniel B. Poneman, Deputy Secretary of Energy Before the ...

  14. Before the Subcommittee on Oversight and Investigations - House...

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

    Oversight and Investigations - House Committee on Energy and Commerce Before the Subcommittee on Oversight and Investigations - House Committee on Energy and Commerce Testimony of ...

  15. Houses are Dumb without Smart Ventilation (Technical Report)...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Houses are Dumb without Smart Ventilation Citation Details In-Document Search Title: Houses are Dumb without Smart Ventilation You are accessing a document ...

  16. Energy Department Announces Winners of Housing Innovation Awards...

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

    ... Energy Department Announces Winners of Housing Innovation Awards Energy Department Announces Winners of Housing Innovation Awards One Sky Homes, San Jose, CA, Custom Builder, Grand ...

  17. 2016 Argonne Open House Program | Argonne National Laboratory

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

    6 Argonne Open House Program Seventy Years of Discovery May 21, 2016 9 a.m. - 4 p.m. PDF icon 2016_Argonne_Open_House_Program

  18. Housing Energy Efficiency: AHFC Energy Programs and Resources

    Office of Environmental Management (EM)

    1981 to supplement HUD Indian Housing Development funds Funds are used for: *Water and ... meet BEES Supplemental Housing Development Grant Program 8 Health and Safety ...

  19. Oversight Hearing Before the House Natural Resources Subcommittee...

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

    Oversight Hearing Before the House Natural Resources Subcommittee on Water, Power, and Oceans Oversight Hearing Before the House Natural Resources Subcommittee on Water, Power, and ...

  20. Los Angeles County's Green Idea House Achieves Efficient Goals...

    Energy Savers [EERE]

    County's Green Idea House Achieves Efficient Goals Los Angeles County's Green Idea House Achieves Efficient Goals Photo of an energy-efficient home with modern architecture. The ...

  1. Obama Administration Announces $450 Million to Design and Commercialize U.S. Small Modular Nuclear Reactors

    Broader source: Energy.gov [DOE]

    Today, as President Obama went to Ohio State University to discuss the all-out, all-of-the-above strategy for American energy, the White House announced new funding to advance the development of American-made small modular reactors (SMRs).

  2. Inductive coupler for downhole components and method for making same

    DOE Patents [OSTI]

    Hall, David R.; Hall, Jr., H. Tracy; Pixton, David S.; Dahlgren, Scott; Sneddon, Cameron; Fox, Joe; Briscoe, Michael A.

    2006-10-03

    An inductive coupler for downhole components. The inductive coupler includes an annular housing having a recess defined by a bottom portion and two opposing side wall portions. At least one side wall portion includes a lip extending toward but not reaching the other side wall portion. A plurality of generally U-shaped MCEI segments, preferably comprised of ferrite, are disposed in the recess and aligned so as to form a circular trough. The coupler further includes a conductor disposed within the circular trough and a polymer filling spaces between the segments, the annular housing and the conductor.

  3. Annual Performance Evaluation of a Pair of Energy Efficient Houses (WC3 and WC4) in Oak Ridge, TN

    SciTech Connect (OSTI)

    Biswas, Kaushik; Christian, Jeffrey E; Gehl, Anthony C; Jackson, Roderick K; Boudreaux, Philip R

    2012-04-01

    Beginning in 2008, two pairs of energy-saver houses were built at Wolf Creek in Oak Ridge, TN. These houses were designed to maximize energy efficiency using new ultra-high-efficiency components emerging from ORNL s Cooperative Research and Development Agreement (CRADA) partners and others. The first two houses contained 3713 square feet of conditioned area and were designated as WC1 and WC2; the second pair consisted of 2721 square feet conditioned area with crawlspace foundation and they re called WC3 and WC4. This report is focused on the annual energy performance of WC3 and WC4, and how they compare against a previously benchmarked maximum energy efficient house of a similar footprint. WC3 and WC4 are both about 55-60% more efficient than traditional new construction. Each house showcases a different envelope system: WC3 is built with advanced framing featured cellulose insulation partially mixed with phase change materials (PCM); and WC4 house has cladding composed of an exterior insulation and finish system (EIFS). The previously benchmarked house was one of three built at the Campbell Creek subdivision in Knoxville, TN. This house (CC3) was designed as a transformation of a builder house (CC1) with the most advanced energy-efficiency features, including solar electricity and hot water, which market conditions are likely to permit within the 2012 2015 period. The builder house itself was representative of a standard, IECC 2006 code-certified, all-electric house built by the builder to sell around 2005 2008.

  4. Risk Management for Sodium Fast Reactors.

    SciTech Connect (OSTI)

    Denman, Matthew R; Groth, Katrina; Cardoni, Jeffrey N; Wheeler, Timothy A.

    2015-01-01

    Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of self - correcting, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the syste m's design to manage the accident. While inherently and passively safe designs are laudable, extreme boundary conditions can interfere with the design attributes which facilitate inherent safety , thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a beyond design basis seismic event with the intend of exploring two issues : (1) can human intervention either improve or worsen the potential end states and (2) can a Bayes ian Network be constructed to infer the state of the reactor to inform (1). ACKNOWLEDGEMENTS The author s would like to acknowledge the U.S. Department of E nergy's Office of Nuclear Energy for funding this research through Work Package SR - 14SN100303 under the Advanced Reactor Concepts program. The authors also acknowledge the PRA teams at A rgonne N ational L aborator y , O ak R idge N ational L aborator y , and I daho N ational L aborator y for their continue d contributions to the advanced reactor PRA mission area.

  5. Nuclear reactor control column

    DOE Patents [OSTI]

    Bachovchin, Dennis M.

    1982-01-01

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

  6. Slurry reactor design studies

    SciTech Connect (OSTI)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. ); Akgerman, A. ); Smith, J.M. )

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  7. Reactor Safety Research Programs

    SciTech Connect (OSTI)

    Edler, S. K.

    1981-07-01

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

  8. " Million U.S. Housing Units" ,,"2005...

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

    2 Living Space Characteristics by Household Income, 2005" " Million U.S. Housing Units" ... to 79,999","80,000 or More" "Living Space Characteristics" "Total",111.1,26.7,28.8,2...

  9. House Care Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Care Co Ltd Jump to: navigation, search Name: House Care Co Ltd Place: Tokyo, Tokyo, Japan Zip: 163-1431 Sector: Solar Product: Japanese insulation and roofing installer which...

  10. 2014 White House Tribal Nations Conference

    Broader source: Energy.gov [DOE]

    On Wednesday, December 3, President Obama will host the 2014 White House Tribal Nations Conference at the Capital Hilton in Washington, DC. The conference will provide leaders from the 566...

  11. History of Electricity at the White House

    Broader source: Energy.gov [DOE]

    The White House has only been electrified for a little over a century. Check out our timeline to read more about what it takes to power 1600 Pennsylvania Avenue.

  12. Retrofitting the Southeast. The Cool Energy House

    SciTech Connect (OSTI)

    Zoeller, W.; Shapiro, C.; Vijayakumar, G.; Puttagunta, S.

    2013-02-01

    The Consortium for Advanced Residential Buildings research team has provided the technical engineering and building science support for a highly visible demonstration home that was unveiled at the National Association of Home Builders' International Builders Show on Feb. 9, 2012, in Orlando, FL. The two previous projects, the Las Vegas net-zero ReVISION House and the 2011 VISION and ReVISION Houses in Orlando, met goals for energy efficiency, cost effectiveness, and information dissemination through multiple web-based venues. This report describes the deep energy retrofit of the Cool Energy House (CEH), which began as a mid-1990s two-story traditional specification house of about 4,000 ft2 in the upscale Orlando suburb of Windermere.

  13. Retrofitting the Southeast: The Cool Energy House

    SciTech Connect (OSTI)

    Zoeller, W.; Shapiro, C.; Vijayakumar, G.; Puttagunta, S.

    2013-02-01

    The Consortium for Advanced Residential Buildings has provided the technical engineering and building science support for a highly visible demonstration home in connection with the National Association of Home Builders' International Builders Show. The two previous projects, the Las Vegas net-zero ReVISION House and the 2011 VISION and ReVISION Houses in Orlando, met goals for energy efficiency, cost effectiveness, and information dissemination through multiple web-based venues. This project, which was unveiled at the 2012 International Builders Show in Orlando on February 9, is the deep energy retrofit Cool Energy House (CEH). The CEH began as a mid-1990s two-story traditional specification house of about 4,000 ft2 in the upscale Orlando suburb of Windermere.

  14. Advanced House Framing | Department of Energy

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

    called optimum value engineering (OVE), refers to framing techniques designed to reduce the amount of lumber used and waste generated in the construction of a wood-framed house. ...

  15. Alaska Housing Finance Corporation Energy Efficiency Programs...

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

    + 89-91 5 Star 92-94 5 Star + 95-100 6 Star 7,000 rebate for 5 Star Plus Established 1981 to supplement HUD Indian Housing Development funds Funds are used for: *Water and sewer ...

  16. Ceramic pressure housing with metal endcaps

    DOE Patents [OSTI]

    Downing, J.P. Jr.; DeRoos, B.G.; Hackman, D.J.

    1995-06-27

    A housing is disclosed for the containment of instrumentation in a high pressure fluid environment that consists of a metallic endcap and ceramic cylinder bonded together. The improvement comprises a structure which results in the improved sealing of said housing as the fluid pressure increases. The cylindrical ceramic tube and endcap are dimensioned such that mechanical failure does not occur when exposed to the desired external operating pressures which includes up to 36,000 feet of water. The housing is designed to withstand the external operating pressures without being subject to mechanical failure or excessive deformation which results in the loss of pressure housing integrity via cracking or deformation of the ceramic tube, deformation of the endcap, or from failure of the bonding agent. 9 figs.

  17. Green House Gases | The Ames Laboratory

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

    Green House Gases Did You Know? If it were not for naturally occurring greenhouse gases, the Earth would be too cold to support life as we know it. Without the greenhouse effect,...

  18. Webinar: Leadership Recognition with Housing Innovation Awards

    Broader source: Energy.gov [DOE]

    Title: Leadership Recognition with Housing Innovation Awards             Date: Wednesday, May 21, 2014Time: 12:00PM - 1:00 PM EST

  19. Team Ontario 2009 Solar Decathlon House

    Broader source: Energy.gov [DOE]

    This photograph features Team Ontario/BC's solar-powered house that glows at night during the Lighting Design contest at the U.S. Department of Energy Solar Decathlon on the National Mall. Team...

  20. house of representatives | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Congressmen tour Y-12 facilities During a recent visit to the Y-12 National Security Complex, Rep. Mike Simpson (R-Idaho), chairman of the House Energy and Water Appropriations ...