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1

Solid tags for identifying failed reactor components  

DOE Patents [OSTI]

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.

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

1987-01-01T23:59:59.000Z

2

James P. Mosquera Director, Reactor Plant Components  

E-Print Network [OSTI]

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

3

Heavy Water Components Test Reactor Decommissioning - Major Component Removal  

SciTech Connect (OSTI)

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 experienced cladding failures as operational capabilities of the different designs were being established. In addition, numerous spills of heavy water occurred within the facility. Currently, radiation and radioactive contamination levels are low within HWCTR with most of the radioactivity contained within the reactor vessel. There are no known insults to the environment, however with the increasing deterioration of the facility, the possibility exists that contamination could spread outside the facility if it is not decommissioned. An interior panoramic view of the ground floor elevation taken in August 2009 is shown in Figure 2. The foreground shows the transfer coffin followed by the reactor vessel and control rod drive platform in the center. Behind the reactor vessel is the fuel pool. Above the ground level are the polar crane and the emergency deluge tank at the top of the dome. Note the considerable rust and degradation of the components and the interior of the containment building. Alternative studies have concluded that the most environmentally safe, cost effective option for final decommissioning is to remove the reactor vessel, steam generators, and all equipment above grade including the dome. Characterization studies along with transport models have concluded that the remaining below grade equipment that is left in place including the transfer coffin will not contribute any significant contamination to the environment in the future. The below grade space will be grouted in place. A concrete cover will be placed over the remaining footprint and the groundwater will be monitored for an indefinite period to ensure compliance with environmental regulations. The schedule for completion of decommissioning is late FY2011. This paper describes the concepts planned in order to remove the major components including the dome, the reactor vessel (RV), the two steam generators (SG), and relocating the transfer coffin (TC).

Austin, W.; Brinkley, D.

2010-05-05T23:59:59.000Z

4

HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING  

SciTech Connect (OSTI)

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 including the dome was removed, a concrete cover was to be placed over the remaining footprint and the groundwater monitored for an indefinite period to ensure compliance with environmental regulations.

Austin, W.; Brinkley, D.

2011-10-13T23:59:59.000Z

5

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

SciTech Connect (OSTI)

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.

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

1980-04-01T23:59:59.000Z

6

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

SciTech Connect (OSTI)

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

P.C. Weaver

2010-10-22T23:59:59.000Z

7

Austenitic alloy and reactor components made thereof  

DOE Patents [OSTI]

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.

Bates, John F. (Ogden, UT); Brager, Howard R. (Richland, WA); Korenko, Michael K. (Wexford, PA)

1986-01-01T23:59:59.000Z

8

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

SciTech Connect (OSTI)

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.

Vinson, Dennis

2010-06-01T23:59:59.000Z

9

Nuclear reactor spacer grid and ductless core component  

DOE Patents [OSTI]

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.

Christiansen, David W. (Kennewick, WA); Karnesky, Richard A. (Richland, WA)

1989-01-01T23:59:59.000Z

10

Prognostics Health Management for Advanced Small Modular Reactor Passive Components  

SciTech Connect (OSTI)

In the United States, sustainable nuclear power to promote energy security is a key national energy priority. Advanced small modular reactors (AdvSMR), which are based on modularization of advanced reactor concepts using non-light-water reactor (LWR) coolants such as liquid metal, helium, or liquid salt may provide a longer-term alternative to more conventional LWR-based concepts. The economics of AdvSMRs will be impacted by the reduced economy-of-scale savings when compared to traditional LWRs and the controllable day-to-day costs of AdvSMRs are expected to be dominated by operations and maintenance costs. Therefore, achieving the full benefits of AdvSMR deployment requires a new paradigm for plant design and management. In this context, prognostic health management of passive components in AdvSMRs can play a key role in enabling the economic deployment of AdvSMRs. In this paper, the background of AdvSMRs is discussed from which requirements for PHM systems are derived. The particle filter technique is proposed as a prognostics framework for AdvSMR passive components and the suitability of the particle filter technique is illustrated by using it to forecast thermal creep degradation using a physics-of-failure model and based on a combination of types of measurements conceived for passive AdvSMR components.

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

2013-10-18T23:59:59.000Z

11

Nuclear reactor heat transport system component low friction support system  

DOE Patents [OSTI]

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.

Wade, Elman E. (Ruffs Dale, PA)

1980-01-01T23:59:59.000Z

12

Repair welding of fusion reactor components. Final technical report  

SciTech Connect (OSTI)

The exposure of metallic materials, such as structural components of the first wall and blanket of a fusion reactor, to neutron irradiation will induce changes in both the material composition and microstructure. Along with these changes can come a corresponding deterioration in mechanical properties resulting in premature failure. It is, therefore, essential to expect that the repair and replacement of the degraded components will be necessary. Such repairs may require the joining of irradiated materials through the use of fusion welding processes. The present ITER (International Thermonuclear Experimental Reactor) conceptual design is anticipated to have about 5 km of longitudinal welds and ten thousand pipe butt welds in the blanket structure. A recent study by Buende et al. predict that a failure is most likely to occur in a weld. The study is based on data from other large structures, particularly nuclear reactors. The data used also appear to be consistent with the operating experience of the Fast Flux Test Facility (FFTF). This reactor has a fuel pin area comparable with the area of the ITER first wall and has experienced one unanticipated fuel pin failure after two years of operation. The repair of irradiated structures using fusion welding will be difficult due to the entrapped helium. Due to its extremely low solubility in metals, helium will diffuse and agglomerate to form helium bubbles after being trapped at point defects, dislocations, and grain boundaries. Welding of neutron-irradiated type 304 stainless steels has been reported with varying degree of heat-affected zone cracking (HAZ). The objectives of this study were to determine the threshold helium concentrations required to cause HAZ cracking and to investigate techniques that might be used to eliminate the HAZ cracking in welding of helium-containing materials.

Chin, B.A.; Wang, C.A.

1997-09-30T23:59:59.000Z

13

Component failures at pressurized water reactors. Final report  

SciTech Connect (OSTI)

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.

Reisinger, M.F.

1980-10-01T23:59:59.000Z

14

Design of an aluminum differential housing and driveline components for high performance applications  

E-Print Network [OSTI]

The purpose of the study was to design a lightweight aluminum differential housing to replace the cast-iron housing used in the Torsenģ T-1. The redesigned housing was destined for use in the 2004 MIT Formula SAE vehicle, ...

James, Richard A. (Richard Alexander), 1982-

2004-01-01T23:59:59.000Z

15

Impact of conversion to mixed-oxide fuels on reactor structural components  

SciTech Connect (OSTI)

The use of mixed-oxide (MOX) fuel to replace conventional uranium fuel in commercial light-water power reactors will result in an increase in the neutron flux. The impact of the higher flux on the structural integrity of reactor structural components must be evaluated. This report briefly reviews the effects of radiation on the mechanical properties of metals. Aging degradation studies and reactor operating experience provide a basis for determining the areas where conversion to MOX fuels has the potential to impact the structural integrity of reactor components.

Yahr, G.T.

1997-04-01T23:59:59.000Z

16

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

SciTech Connect (OSTI)

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.

Polzin, Kurt A.; Godfroy, Thomas J. [NASA Marshall Space Flight Center Propulsion Research and Technology Applications Branch/ER24, MSFC, AL 35812 (United States)

2008-01-21T23:59:59.000Z

17

Catalytic reactor  

DOE Patents [OSTI]

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.

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

2009-03-10T23:59:59.000Z

18

Comparison of thorium-based fuels with different fissile components in existing boiling water reactors  

E-Print Network [OSTI]

Comparison of thorium-based fuels with different fissile components in existing boiling water, SE-412 96 Göteborg, Sweden Keywords: Thorium BWR Neutronics a b s t r a c t With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Water Reactor) with thorium

Demazière, Christophe

19

Potential Application of Electrical Signature Analysis Methods for Monitoring Small Modular Reactor Components  

SciTech Connect (OSTI)

This paper will describe the technical basis behind ESA and why we consider it a viable SMR condition monitoring technology. Concepts are presented of how ESA could be applied to monitor two candidate small modular reactor components: the main coolant pumps and the control rod drives. We believe the general health of these two components can be monitored and trended over time, using ESA methods. Our optimism is based on over two decades of ESA development and testing on a wide variety of components and systems, many of which have similar operational features to the main coolant pumps and control rod drives.

Damiano, Brian [ORNL] [ORNL; Tucker Jr, Raymond W [ORNL] [ORNL; Haynes, Howard D [ORNL] [ORNL

2010-01-01T23:59:59.000Z

20

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

SciTech Connect (OSTI)

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.

Harpeneau, Evan M. [Oak Ridge Institute for Science and Education, Oak Ridge, TN (United States). Independent Environmental Assessment and Verification Program

2011-06-24T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Modeling of reactor components using FIDAP: a finite element computer code  

E-Print Network [OSTI]

of MASTER OF SCIENCE May 1989 Major Subject: Nuclear Engineering MODELING OF REACTOR COMPONENTS USING FIDAP - A FINITE ELEMENT COMPUTER CODE A Thesis by ANAND GANGADHARAN Approved as to style and content by. assin A. Hassan (Chair of Committee... of Nuclear Engineering, Texas ASM University. I feel elated in placing on record, my direct and totally involved interaction with the Chairman of my committee, Prof. Y. A. Hassan. I am grateful to him for his constant and unreserved encouragement...

Gangadharan, Anand

1989-01-01T23:59:59.000Z

22

Methods for nondestructive testing of austenitic high-temperature gas-cooled reactor components  

SciTech Connect (OSTI)

Safety-relevant components of high-temperature gas-cooled reactor components are mostly fabricated in nickel-based alloys and austenitic materials like Inconel-617, Hastelloy-X, Nimonic-86, or Incoloy-800H. Compared to ferritic steels, these austenitic materials can have a coarse-grained microstructure, especially in weldments and castings. Coarse-grained or elastic anisotropic materials are difficult to inspect with ultrasonics due to strong attenuation, high noise level (scattering, ''grass'' indications), and sound beam distortions (skewing, splitting, and mode conversion). Only few results dealing with the nondestructive testing of nickel-based alloys are known. The problem area, solutions, and first experiences are reported.

Gobbels, K.; Kapitza, H.

1984-09-01T23:59:59.000Z

23

COMPONENT DEGRADATION SUSCEPTIBILITIES AS THE BASES FOR MODELING REACTOR AGING RISK  

SciTech Connect (OSTI)

The extension of nuclear power plant operating licenses beyond 60 years in the United States will be necessary if we are to meet national energy needs while addressing the issues of carbon and climate. Characterizing the operating risks associated with aging reactors is problematic because the principal tool for risk-informed decision-making, Probabilistic Risk Assessment (PRA), is not ideally-suited to addressing aging systems. The components most likely to drive risk in an aging reactor - the passives - receive limited treatment in PRA, and furthermore, standard PRA methods are based on the assumption of stationary failure rates: a condition unlikely to be met in an aging system. A critical barrier to modeling passives aging on the wide scale required for a PRA is that there is seldom sufficient field data to populate parametric failure models, and nor is there the availability of practical physics models to predict out-year component reliability. The methodology described here circumvents some of these data and modeling needs by using materials degradation metrics, integrated with conventional PRA models, to produce risk importance measures for specific aging mechanisms and component types. We suggest that these measures have multiple applications, from the risk-screening of components to the prioritization of materials research.

Unwin, Stephen D.; Lowry, Peter P.; Toyooka, Michael Y.

2010-07-18T23:59:59.000Z

24

Method for fabricating wrought components for high-temperature gas-cooled reactors and product  

DOE Patents [OSTI]

A method and alloys for fabricating wrought components of a high-temperature gas-cooled reactor are disclosed. These wrought, nickel-based alloys, which exhibit strength and excellent resistance to carburization at elevated temperatures, include aluminum and titanium in amounts and ratios to promote the growth of carburization resistant films while preserving the wrought character of the alloys. These alloys also include substantial amounts of molybdenum and/or tungsten as solid-solution strengtheners. Chromium may be included in concentrations less than 10% to assist in fabrication. Minor amounts of carbon and one or more carbide-forming metals also contribute to high-temperature strength.

Thompson, Larry D. (San Diego, CA); Johnson, Jr., William R. (San Diego, CA)

1985-01-01T23:59:59.000Z

25

Mechanical properties of welds in commercial alloys for high-temperature gas-cooled reactor components  

SciTech Connect (OSTI)

Weld properties of Hastelloy-X, Incoloy alloy 800H (with and without Inconel-82 cladding), and 2 1/4 Cr-1 Mo are being studied to provide design data to support the development of steam generator, core auxiliary heat exchanger, and metallic thermal barrier components of the high-temperature gas-cooled reactor (HTGR) steam cycle/cogeneration plant. Tests performed include elevated-temperature creep rupture tests and tensile tests. So far, data from the literature and from relatively short-term tests at GA Technologies Inc. indicate that the weldments are satisfactory for HTGR application.

Lindgren, J.R.; Li, C.C.; Ryder, R.H.; Thurgood, B.E.

1984-07-01T23:59:59.000Z

26

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

SciTech Connect (OSTI)

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: ē Identifies pre-conceptual design requirements ē Develops test loop equipment schematics and layout ē Identifies space allocations for each of the facility functions, as required ē Develops a pre-conceptual site layout including transportation, parking and support structures, and railway systems ē Identifies pre-conceptual utility and support system needs ē Establishes pre-conceptual electrical one-line drawings and schedule for development of power needs.

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

2008-04-01T23:59:59.000Z

27

Induced Radioactivity and Waste Classification of Reactor Zone Components of the Chernobyl Nuclear Power Plant Unit 1 After Final Shutdown  

SciTech Connect (OSTI)

The dismantlement of the reactor core materials and surrounding structural components is a major technical concern for those planning closure and decontamination and decommissioning of the Chernobyl Nuclear Power Plant (NPP). Specific issues include when and how dismantlement should be accomplished and what the radwaste classification of the dismantled system would be at the time it is disassembled. Whereas radiation levels and residual radiological characteristics of the majority of the plant systems are directly measured using standard radiation survey and radiochemical analysis techniques, actual measurements of reactor zone materials are not practical due to high radiation levels and inaccessibility. For these reasons, neutron transport analysis was used to estimate induced radioactivity and radiation levels in the Chernobyl NPP Unit 1 reactor core materials and structures.Analysis results suggest that the optimum period of safe storage is 90 to 100 yr for the Unit 1 reactor. For all of the reactor components except the fuel channel pipes (or pressure tubes), this will provide sufficient decay time to allow unlimited worker access during dismantlement, minimize the need for expensive remote dismantlement, and allow for the dismantled reactor components to be classified as low- or medium-level radioactive waste. The fuel channel pipes will remain classified as high-activity waste requiring remote dismantlement for hundreds of years due to the high concentration of induced {sup 63}Ni in the Zircaloy pipes.

Bylkin, Boris K. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Davydova, Galina B. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Zverkov, Yuri A. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Krayushkin, Alexander V. [Russian Research Center 'Kurchatov Institute' (Russian Federation); Neretin, Yuri A. [Chernobyl Nuclear Power Plant (Ukraine); Nosovsky, Anatoly V. [Slavutych Division of the International Chernobyl Center (Ukraine); Seyda, Valery A. [Chernobyl Nuclear Power Plant (Ukraine); Short, Steven M. [Pacific Northwest National Laboratory (United States)

2001-10-15T23:59:59.000Z

28

NUHOWS - Storage and Transportation of Irradiated Reactor Components in Large Packages - 13439  

SciTech Connect (OSTI)

Most irradiated reactor components (hardware such as Control Rod Blades, Fuel Channels, Poison Curtains, etc.) generated at reactors previously required significant processing for size reduction due to the available transportation casks not being physically capable of containing unprocessed material. As of July 1, 2008, disposal for this typical waste class (B and C) became inaccessible (for the major part of the nation) due to the Barnwell, SC disposal facility being closed to all but its three compact states (CT, NJ and SC). Currently in the United States, most facilities are storing their irradiated hardware on-site in the spent fuel pools. Until recently with the opening of the Waste Control Specialists' Texas disposal facility, utilities faced the challenges of spent fuel pool space and capacity management. However, even with WCS's disposal availability, the site currently has annual Curie limitations for disposal, which will continue to promote interim on-site storage until such time as disposal is available. In response, Transnuclear Inc., (TN) an AREVA company, proceeded with designing a new large Radioactive Waste Container (RWC) that can be used to package irradiated hardware without the need for significant processing. The design features of the RWC allows for intermittent loadings of the hardware for better packaging efficiency, higher packaging density, space savings and reduced cost. This RWC is also compatible with TN's on-site modular vault storage system. Once completely loaded, the RWC can be transported to an on-site storage facility, an off-site storage facility and/or an available disposal facility. To accommodate the transportation, TN has designed a large transportation cask, the MP197HB. As the original design was for transporting fuel, it contains the necessary shielding to allow for the transport of unprocessed irradiated reactor components, while significantly reducing the amount of irradiated hardware shipments required with the use of the new RWC. This paper provides information on the unique design features of the RWC, storage module vaults, MP197HB Transportation Cask and cost saving benefits of using the large RWC for packaging, storage, transport and disposal. (authors)

Rae, Glen A. [Transnuclear, Inc., 7135 Minstrel Way, Columbia, MD 21045 (United States)] [Transnuclear, Inc., 7135 Minstrel Way, Columbia, MD 21045 (United States)

2013-07-01T23:59:59.000Z

29

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

SciTech Connect (OSTI)

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 potential synergies with other national laboratory and university partners.

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.

2013-05-17T23:59:59.000Z

30

Radiation Hardness of Passive Fibre Optic Components for the Future Thermonuclear Fusion Reactor  

E-Print Network [OSTI]

thermon uclearfusion reactor ITER will require remote-hanA#0 equipmen t to monNNfl its operation an to allow hazard-freemand-freexAN durin itsfrequen tmain ten3# periods. Heavy shielded umbilicals will be required tocon5N3 thesen2A5 an the actuators with theirinrx0flNj tation Multiplexin sen#0 signfl3 turn out to beessen tial to ease the umbilicalmancalx5 t. We arecon33NxF0# fibre optic technxfljN , with its in trinfl# wavelenflfl multiplexin (WDM) capabilities, tohanA5 these ITER multiplexin issues. We propose anA anAN2 data lin design for low-banjxF0N sennj an actuators basedon commercialo #-the-shelf (COTS) fiber optic compon5 ts. We relyon passive compon0 ts such as WDM couplersan fibre Bragggratin2 (FBG) to build a radiationfl0#NxnN t an5#j datalin0 WDM couplers remain operationx up to a 13 MGy gamma total dose. Aradiation53AxnA chan#/ drift is observed. The refractive inflNN han3 un33 ion33jj radiation is proposed as the degradation mechan30j FBG filters con tin ue to operate satisfactorily up to a 150 MGy total gamma dosean an505/3 fluen2 of about 10 15nx0 2 . Our resultson these COTS all-fibre passive compon5 ts open perspectives to build a radiation#A2/xn t an/5/ optical data lin compatible with the ITERrequiremen ts.

A. Fernandez Fernandez F. Berghmans; A. Fern; Ez Fern; M. Decrťton; P. Mťgret; M. Blondel; A. Delchambre; Ez A; F. Berghmans A; B. Brichard; M. Van Uffelen

2001-01-01T23:59:59.000Z

31

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

SciTech Connect (OSTI)

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.

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

2012-06-25T23:59:59.000Z

32

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

SciTech Connect (OSTI)

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.

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

2004-11-17T23:59:59.000Z

33

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

SciTech Connect (OSTI)

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.

Prechtl, E.; Suessdorf, W.

2003-02-27T23:59:59.000Z

34

Analysis of removal alternatives for the Heavy Water Components Test Reactor at the Savannah River Site. Revision 1  

SciTech Connect (OSTI)

This engineering study evaluates different alternatives for decontamination and decommissioning of the Heavy Water Components Test Reactor (HWCTR). Cooled and moderated with pressurized heavy water, this uranium-fueled nuclear reactor was designed to test fuel assemblies for heavy water power reactors. It was operated for this purpose from march of 1962 until December of 1964. Four alternatives studied in detail include: (1) dismantlement, in which all radioactive and hazardous contaminants would be removed, the containment dome dismantled and the property restored to a condition similar to its original preconstruction state; (2) partial dismantlement and interim safe storage, where radioactive equipment except for the reactor vessel and steam generators would be removed, along with hazardous materials, and the building sealed with remote monitoring equipment in place to permit limited inspections at five-year intervals; (3) conversion for beneficial reuse, in which most radioactive equipment and hazardous materials would be removed and the containment building converted to another use such as a storage facility for radioactive materials, and (4) entombment, which involves removing hazardous materials, filling the below-ground structure with concrete, removing the containment dome and pouring a concrete cap on the tomb. Also considered was safe storage, but this approach, which has, in effect, been followed for the past 30 years, did not warrant detailed evaluation. The four other alternatives were evaluate, taking into account factors such as potential effects on the environment, risks, effectiveness, ease of implementation and cost. The preferred alternative was determined to be dismantlement. This approach is recommended because it ranks highest in the comparative analysis, would serve as the best prototype for the site reactor decommissioning program and would be most compatible with site property reuse plans for the future.

Owen, M.B.

1997-04-01T23:59:59.000Z

35

Prioritization of reactor control components susceptible to fire damage as a consequence of aging  

SciTech Connect (OSTI)

The Fire Vulnerability of Aged Electrical Components Test Program is to identify and assess issues of plant aging that could lead to an increase in nuclear power plant risk because of fires. Historical component data and prior analyses are used to prioritize a list of components with respect to aging and fire vulnerability and the consequences of their failure on plant safety systems. The component list emphasizes safety system control components, but excludes cables, large equipment, and devices encompassed in the Equipment Qualification (EQ) program. The test program selected components identified in a utility survey and developed test and fire conditions necessary to maximize the effectiveness of the test program. Fire damage considerations were limited to purely thermal effects.

Lowry, W.; Vigil, R. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Nowlen, S. [Sandia National Labs., Albuquerque, NM (United States)

1994-01-01T23:59:59.000Z

36

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)

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

Erika N. Bailey

2011-10-10T23:59:59.000Z

37

Intact and Degraded Component Criticality Calculations of N Reactors Spent Nuclear Fuel  

SciTech Connect (OSTI)

The objective of this calculation is to perform intact and degraded mode criticality evaluations of the Department of Energy's (DOE) N Reactor Spent Nuclear Fuel codisposed in a 2-Defense High-Level Waste (2-DHLW)/2-Multi-Canister Overpack (MCO) Waste Package (WP) and emplaced in a monitored geologic repository (MGR) (see Attachment I). The scope of this calculation is limited to the determination of the effective neutron multiplication factor (k{sub eff}) for both intact and degraded mode internal configurations of the codisposal waste package. This calculation will support the analysis that will be performed to demonstrate the technical viability for disposing of U-metal (N Reactor) spent nuclear fuel in the potential MGR.

L. Angers

2001-01-31T23:59:59.000Z

38

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

SciTech Connect (OSTI)

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-flow operation to natural circulation. Low-flow coolant events are the most difficult to design for because they involve the most complex thermal-hydraulic behavior induced by the dominance of thermal-buoyancy forces acting on the coolants. Such behavior can cause multiple-component flow interaction phenomena, which are not adequately understood or appreciated by reactor designers as to their impact on reactor performance and safety. Since the early 1990s, when DOE canceled the U.S. Liquid Metal Fast Breeder Reactor (LMFBR) program, little has been done experimentally to further understand the importance of the complex thermal-buoyancy phenomena and their impact on reactor design or to improve the ability of three-dimensional (3-D) transient computational fluid dynamics (CFD) and structures codes to model the phenomena. An improved experimental data base and the associated improved validated codes would provide needed design tools to the reactor community. The improved codes would also facilitate scale-up from small-scale testing to prototype size and would facilitate comparing performance of one reactor/component design with another. The codes would also have relevance to the design and safety of water-cooled reactors. To accomplish the preceding, it is proposed to establish a national GNEP-LMR research and development center at Argonne having as its foundation state-of-art science-based infrastructure consisting of: (a) thermal-hydraulic experimental capabilities for conducting both water and sodium testing of individual reactor components and complete reactor in-vessel models and (b) a computational modeling development and validation capability that is strongly interfaced with the experimental facilities. The proposed center would greatly advance capabilities for reactor development by establishing the validity of high-fidelity (i.e., close to first principles) models and tools. Such tools could be used directly for reactor design or for qualifying/tuning of lower-fidelity models, which now require costly experimental qualification for each different type of design

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

2007-06-30T23:59:59.000Z

39

Time-dependent tritium inventories and flow rates in fuel cycle components of a tokamak fusion reactor  

SciTech Connect (OSTI)

The dynamic behavior of the fuel cycle in a fusion reactor is of crucial importance due to the need to keep track of the large amount of tritium being constantly produced, transported, and processed in the reactor system. Because tritium is a source of radioactivity, loss and exhaust to the environment must be kept to a minimum. With ITER advancing to its Engineering Design phase, there is a need to accurately predict the dynamic tritium inventories and flow rates throughout the fuel cycle and to study design variations to meet the demands of low tritium inventory. In this paper, time-dependent inventories and flow rates for several components of the fuel cycle are modeled and studied through the use of a new modular-type model for the dynamic simulation of the fuel cycle in a fusion reactor. The complex dynamic behavior in the modeled subsystems is analyzed using this new model. Previous dynamic models focusing on the fuel cycle dealt primarily with a residence time parameter ({tau}{sub res}) defining each subsystem of the model. In this modular model, this residence time approach is avoided in favor of a more accurate and flexible model that utilizes real design parameters and operating schedules of the various subsystems modeled.

Kuan, W.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Willms, R.S. [Los Alamos National Lab., NM (United States)

1994-12-31T23:59:59.000Z

40

Acoustic Emission and Guided Ultrasonic Waves for Detection and Continuous Monitoring of Cracks in Light Water Reactor Components  

SciTech Connect (OSTI)

Acoustic emission (AE) and guided ultrasonic waves (GUW) are considered for continuous monitoring and detection of cracks in Light Water Reactor (LWR) components. In this effort, both techniques are applied to the detection and monitoring of fatigue crack growth in a full scale pipe component. AE results indicated crack initiation and rapid growth in the pipe, and significant GUW responses were observed in response to the growth of the fatigue crack. After initiation, the crack growth was detectable with AE for approximately 20,000 cycles. Signals associated with initiation and rapid growth where distinguished based on total rate of activity and differences observed in the centroid frequency of hits. An intermediate stage between initiation and rapid growth was associated with significant energy emissions, though few hits. GUW exhibit a nearly monotonic trend with crack length with an exception of measurements obtained at 41 mm and 46 mm.

Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep; Watson, Bruce E.; Cumblidge, Stephen E.; Doctor, Steven R.; Bond, Leonard J.

2012-06-28T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Unsteady momentum fluxes in two-phase flow and the vibration of nuclear reactor components  

E-Print Network [OSTI]

The steady and unsteady components of the momentum flux in a twophase flow have been measured at the exit of a vertical pipe. Measured momentum flux data has been machine processed by standard random vibration techniques ...

Yih, Tien Sieh

1968-01-01T23:59:59.000Z

42

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

SciTech Connect (OSTI)

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 power conversion system have been verified with an industry-standard general thermal-fluid code Flownet. With respect to the dynamic model, bypass valve control and inventory control have been used as the primary control methods for the power conversion system. By performing simulation using the dynamic model with the designed control scheme, the combination of bypass and inventory control was optimized to assure system stability within design temperature and pressure limits. Bypass control allows for rapid control system response while inventory control allows for ultimate steady state operation at part power very near the optimum operating point for the system. Load transients simulations show that the indirect, three-shaft arrangement gas turbine power conversion system is stable and controllable. For the indirect cycle the intermediate heat exchanger (IHX) is the interface between the reactor and the turbomachinery systems. As a part of the design effort the IHX was identified as the key component in the system. Two technologies, printed circuit and compact plate-fin, were investigated that have the promise of meeting the design requirements for the system. The reference design incorporates the possibility of using either technology although the compact plate-fin design was chosen for subsequent analysis. The thermal design and parametric analysis with an IHX and recuperator using the plate-fin configuration have been performed. As a three-shaft arrangement, the turbo-shaft sets consist of a pair of turbine/compressor sets (high pressure and low pressure turbines with same-shaft compressor) and a power turbine coupled with a synchronous generator. The turbines and compressors are all axial type and the shaft configuration is horizontal. The core outlet/inlet temperatures are 900/520 C, and the optimum pressure ratio in the power conversion cycle is 2.9. The design achieves a plant net efficiency of approximately 48%.

Ronald G. Ballinger Chunyun Wang Andrew Kadak Neil Todreas

2004-08-30T23:59:59.000Z

43

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

DOE Patents [OSTI]

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.

Alman, David E. (Corvallis, OR); Wilson, Rick D. (Corvallis, OR); Davis, Daniel L. (Albany, OR)

2011-03-08T23:59:59.000Z

44

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

SciTech Connect (OSTI)

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.

Shah, V.N.; Sinha, U.P. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Smith, S.K. [Ogden Environmental and Energy Services, Southfield, MI (United States)

1994-03-01T23:59:59.000Z

45

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)

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.

KIRK WINTERHOLLER

2008-02-25T23:59:59.000Z

46

Proposed and existing passive and inherent safety-related structures, systems, and components (building blocks) for advanced light-water reactors  

SciTech Connect (OSTI)

A nuclear power plant is composed of many structures, systems, and components (SSCs). Examples include emergency core cooling systems, feedwater systems, and electrical systems. The design of a reactor consists of combining various SSCs (building blocks) into an integrated plant design. A new reactor design is the result of combining old SSCs in new ways or use of new SSCs. This report identifies, describes, and characterizes SSCs with passive and inherent features that can be used to assure safety in light-water reactors. Existing, proposed, and speculative technologies are described. The following approaches were used to identify the technologies: world technical literature searches, world patent searches, and discussions with universities, national laboratories and industrial vendors. 214 refs., 105 figs., 26 tabs.

Forsberg, C.W.; Moses, D.L.; Lewis, E.B.; Gibson, R.; Pearson, R.; Reich, W.J.; Murphy, G.A.; Staunton, R.H.; Kohn, W.E.

1989-10-01T23:59:59.000Z

47

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)

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.

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

2009-11-30T23:59:59.000Z

48

Nuclear reactor with low-level core coolant intake  

DOE Patents [OSTI]

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.

Challberg, Roy C. (Livermore, CA); Townsend, Harold E. (Campbell, CA)

1993-01-01T23:59:59.000Z

49

Meadowlark House  

Office of Energy Efficiency and Renewable Energy (EERE)

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

50

Arctic house  

E-Print Network [OSTI]

Currently available housing in the Arctic is limited to solutions that have been adapted from designs for less severe climates. This thesis has developed a new manner of residential construction designed specifically for ...

Turkel, Joel A. (Joel Abram), 1969-

1999-01-01T23:59:59.000Z

51

Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors  

E-Print Network [OSTI]

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

Terrani, Kurt Amir

2010-01-01T23:59:59.000Z

52

Postdoc Housing  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar Home Design Passive SolarCenterYouPortsmouth/PaducahNREL's useHousing

53

Student Housing  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatus TomAbout ¬Ľ Staff125,849|Structures forStudent Housing Student

54

" Million Housing Units, Final...  

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

Computers and Other Electronics in U.S. Homes, by Housing Unit Type, 2009" " Million Housing Units, Final" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings...

55

" 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...

56

" 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" ,,"Housing Unit Type" ,,"Single-Family Units",,"Apartments in Buildings With" ,"Total...

57

Housing policy in China  

E-Print Network [OSTI]

In the last three decades, the People's Republic of China (PRC) has managed to replace its welfare-based urban housing system with a market-based housing provision scheme. With such significant housing policy changes, the ...

Gao, Lu, S.M. Massachusetts Institute of Technology

2011-01-01T23:59:59.000Z

58

House Energy and Water Development FY 2007 Appropriations Passed by House Appropriations Committee May 17, 2006, Status: sent to House  

E-Print Network [OSTI]

May 17, 2006, Status: sent to House Fusion Energy Sciences ­ Office of Science The Committee recommendation for fusion energy sciences is $318,950,000, the same as the budget request. The Committee in the International Thermonuclear Experimental Reactor (ITER) Project without doing so at the expense of domestic

59

Protocol for House Parties  

Broader source: Energy.gov [DOE]

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

60

Housing and Residential Life  

E-Print Network [OSTI]

1 Housing and Residential Life Guidebook 2014-2015 LivingCampus #12;2 fau.edu/housing Welcome! The Housing & Residential Life staff is excited that you've moved home! Florida Atlantic University residence halls and apartments are your home for the 2014-2015 school year. The Housing & Residential Life staff

Fernandez, Eduardo

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

House Rules [ 2010 2011  

E-Print Network [OSTI]

The following items are prohibited in student housing: coffee makers, rice cookers, toaster ovens, air

Aalberts, Daniel P.

62

Overview of the US stellarator reactor study  

SciTech Connect (OSTI)

This study, which uses a cost-minimization code that incorporates the ARIES costing and reactor component models with a I-D energy transport calculation, shows that a torsatron reactor could be competitive with a tokamak reactor.

Lyon, J.F. [Oak Ridge National Lab., TN (United States); Gulec, K. [Univ. of Tennessee, Knoxville, TN (United States); Miller, R.L. [Los Alamos National Lab., NM (United States); El-Guebaly, L. [Univ. of Wisconsin, Madison, WI (United States)

1993-12-31T23:59:59.000Z

63

Energy efficient industrialized housing research program  

SciTech Connect (OSTI)

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.

Berg, R.; Brown, G.Z.; Finrow, J.; Kellett, R.; McDonald, M.; McGinn, B.; Ryan, P.; Sekiguchi, Tomoko (Oregon Univ., Eugene, OR (USA). Center for Housing Innovation); Chandra, S.; Elshennawy, A.K.; Fairey, P.; Harrison, J.; Mazwell, L.; Roland, J.; Swart, W. (Florida Solar Energy Center, Cape Canaveral, FL (USA))

1989-12-01T23:59:59.000Z

64

Nuclear component horizontal seismic restraint  

DOE Patents [OSTI]

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.

Snyder, Glenn J. (Lynchburg, VA)

1988-01-01T23:59:59.000Z

65

Leaching of radionuclides from furfural-based polymers used to solidify reactor compartments and components disposed of in the Arctic Kara Sea  

SciTech Connect (OSTI)

Within the course of operating its nuclear navy, the former Soviet Union (FSU) disposed of reactor vessels and spent nuclear fuel (SNF) in three fjords on the east coast of Novaya Zemlya and in the open Kara Sea within the Novaya Zemlya Trough during the period 1965 to 1988. The dumping consisted of 16 reactors, six of which contained SNF and one special container that held ca. 60% of the damaged SNF and the screening assembly from the No. 2 reactor of the atomic icebreaker Lenin. At the time, the FSU considered dumping of decommissioned nuclear submarines with damaged cores in the bays of and near by the Novaya Zemlya archipelago in the Arctic Kara Sea to be acceptable. To provide an additional level of safety, a group of Russian scientists embarked upon a course of research to develop a solidification agent that would provide an ecologically safe barrier. The barrier material would prevent direct contact of seawater with the SNF and the resultant leaching and release of radionuclides. The solidification agent was to be introduced by flooding the reactors vessels and inner cavities. Once introduced the agent would harden and form an impermeable barrier. This report describes the sample preparation of several ``Furfurol'' compositions and their leach testing using cesium 137 as tracer.

HEISER,J.H.; SIVINTSEV,Y.; ALEXANDROV,V.P.; DYER,R.S.

1999-09-01T23:59:59.000Z

66

" Million Housing Units, Final...  

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

2 Computers and Other Electronics in U.S. Homes, by OwnerRenter Status, 2009" " Million Housing Units, Final" ,,,,"Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in...

67

" Million Housing Units, Final...  

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

2 Air Conditioning in U.S. Homes, by OwnerRenter Status, 2009" " Million Housing Units, Final" ,,,,"Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in Buildings With"...

68

" 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, Final" ,,,,"Housing Unit Type" ,,,,"Single-Family Units",,,,"Apartments in Buildings With"...

69

100% petroleum house  

E-Print Network [OSTI]

I am designing a Case Study House to be sponsored by Royal Dutch Shell which utilizes the by-product of oil extraction, petroleum gas, to produce a zero waste, 100% petroleum based house. The motivation of the Case Study ...

Costanza, David (David Nicholas)

2013-01-01T23:59:59.000Z

70

Westinghouse Small Modular Reactor nuclear steam supply system design  

SciTech Connect (OSTI)

The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the first in a series of four papers which describe the design and functionality of the Westinghouse SMR. Also described in this series are the key drivers influencing the design of the Westinghouse SMR and the unique passive safety features of the Westinghouse SMR. Several critical motivators contributed to the development and integration of the Westinghouse SMR design. These design driving motivators dictated the final configuration of the Westinghouse SMR to varying degrees, depending on the specific features under consideration. These design drivers include safety, economics, AP1000{sup R} reactor expertise and experience, research and development requirements, functionality of systems and components, size of the systems and vessels, simplicity of design, and licensing requirements. The Westinghouse SMR NSSS consists of an integral reactor vessel within a compact containment vessel. The core is located in the bottom of the reactor vessel and is composed of 89 modified Westinghouse 17x17 Robust Fuel Assemblies (RFA). These modified fuel assemblies have an active core length of only 2.4 m (8 ft) long, and the entirety of the core is encompassed by a radial reflector. The Westinghouse SMR core operates on a 24 month fuel cycle. The reactor vessel is approximately 24.4 m (80 ft) long and 3.7 m (12 ft) in diameter in order to facilitate standard rail shipping to the site. The reactor vessel houses hot and cold leg channels to facilitate coolant flow, control rod drive mechanisms (CRDM), instrumentation and cabling, an intermediate flange to separate flow and instrumentation and facilitate simpler refueling, a pressurizer, a straight tube, recirculating steam generator, and eight reactor coolant pumps (RCP). The containment vessel is 27.1 m (89 ft) long and 9.8 m (32 ft) in diameter, and is designed to withstand pressures up to 1.7 MPa (250 psi). It is completely submerged in a pool of water serving as a heat sink and radiation shield. Housed within the containment are four combined core makeup tanks (CMT)/passive residual heat removal (PRHR) heat exchangers, two in-containment pools (ICP), two ICP tanks and four valves which function as the automatic depressurization system (ADS). The PRHR heat exchangers are thermally connected to two different ultimate heat sink (UHS) tanks which provide transient cooling capabilities. (authors)

Memmott, M. J.; Harkness, A. W.; Van Wyk, J. [Westinghouse Electric Company LLC, 600 Cranberry Woods Drive, Cranberry Twp. PA 16066 (United States)

2012-07-01T23:59:59.000Z

71

Insulator for laser housing  

DOE Patents [OSTI]

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.

Duncan, D.B.

1992-12-29T23:59:59.000Z

72

Insulator for laser housing  

DOE Patents [OSTI]

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.

Duncan, David B. (Auburn, CA)

1992-01-01T23:59:59.000Z

73

Residential Learning University Housing  

E-Print Network [OSTI]

Residential Learning & University Housing Handbook 2008 - 2009 A Guide for Residential Living on the Campus of Rowan University #12;Welcome to Residential Learning & University Housing! The primary purpose of the Office of Residential Life & University Housing is to assist and support students in the pursuit

Rusu, Adrian

74

Fusion reactor pumped laser  

DOE Patents [OSTI]

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.

Jassby, Daniel L. (Princeton, NJ)

1988-01-01T23:59:59.000Z

75

Effects of housing policies on intra-urban inequality in transitioning China  

E-Print Network [OSTI]

In the People's Republic of China, housing reform was launched in the 1980s as a component of the overall economic reform. In the 1990s, housing policies, privatization and subsidies combined, were found to contribute to ...

Xu, Yi, M.C.P. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

76

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)

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.

Stoner, K.J.

1999-11-05T23:59:59.000Z

77

Detachable connection for a nuclear reactor fuel assembly  

DOE Patents [OSTI]

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.

Christiansen, David W. (Kennewick, WA); Karnesky, Richard A. (Richland, WA)

1986-01-01T23:59:59.000Z

78

" Million Housing Units, Final...  

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

9 Fuels Used and End Uses in Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

79

" Million Housing Units, Final...  

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

1 Computers and Other Electronics in Homes in West Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"West Census Region" ,,,"Mountain Census...

80

" Million Housing Units, Final...  

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

0 Computers and Other Electronics in Homes in South Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"South Census Region" ,,,"South Atlantic Census...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

" Million Housing Units, Final...  

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

9 Computers and Other Electronics in Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

82

" Million Housing Units, Final...  

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

8 Computers and Other Electronics in Homes in Northeast Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Northeast Census Region" ,,,"New England Census...

83

" Million Housing Units, Final...  

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

1 Air Conditioning in Homes in West Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"West Census Region" ,,,"Mountain Census Division",,,"Pacific Census...

84

" Million Housing Units, Final...  

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

8 Air Conditioning in Homes in Northeast Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Northeast Census Region" ,,,"New England Census Division",,,"Middle...

85

" Million Housing Units, Final...  

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

0 Air Conditioning in Homes in South Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"South Census Region" ,,,"South Atlantic Census Division",,,,,,"East...

86

" Million Housing Units, Final"  

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

9 Air Conditioning in Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

87

" Million Housing Units, Final...  

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

9 Water Heating in U.S. Homes in Midwest Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Midwest Census Region" ,,,"East North Central Census...

88

" Million Housing Units, Final...  

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

0 Water Heating in U.S. Homes in South Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"South Census Region" ,,,"South Atlantic Census Division",,,,,,"East...

89

" Million Housing Units, Final...  

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

11 Water Heating in U.S. Homes in West Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"West Census Region" ,,,"Mountain Census Division",,,"Pacific...

90

" Million Housing Units, Final...  

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

8 Water Heating in U.S. Homes in Northeast Region, Divisions, and States, 2009" " Million Housing Units, Final" ,,"Northeast Census Region" ,,,"New England Census...

91

" Million U.S. Housing Units"  

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

7 Air Conditioning Usage Indicators by Type of Housing Unit, 2005" " Million U.S. Housing Units" ,,"Type of Housing Unit" ,"Housing Units (millions)","Single-Family...

92

Caribbean House Nicole Meadows  

E-Print Network [OSTI]

1 Caribbean House Nicole Meadows OVERVIEW The Caribbean House is a program that will educate UVM students and the community around them on the different cultures within the Caribbean. Throughout that embodies the Caribbean. This program welcomes all individuals of different backgrounds, cultures

Hayden, Nancy J.

93

Summer Housing Contract INTRODUCTION  

E-Print Network [OSTI]

the pamphlet Protect Your Family from Lead In Your Home. The pa must have completed their move out. Failure to adhere to these dates will lead to administrative are not identified. See Physical Pland Housing Guidelines for more detail. LEAD PAINT DISCLOSURE Housing built before

Devoto, Stephen H.

94

Multiple pump housing  

DOE Patents [OSTI]

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.

Donoho, II, Michael R. (Edelstein, IL); Elliott, Christopher M. (Metamora, IL)

2010-03-23T23:59:59.000Z

95

Reactor Physics  

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

Reactor Physics Reactor and nuclear physics is a key area of research at INL. Much of the research done in reactor physics can be separated into one of three categories:...

96

Energy Efficient Industrialized Housing Research Program  

SciTech Connect (OSTI)

Six area reported progress in the Energy Efficient Industrialized Housing Research Program during FY 1991. As part of Industry Guidance, meetings were held with steering and technical committees in computers, housing design and manufacturing. This task area enables the program to benefit from the expertise of industry representatives and communicate research results directly to them. As part of the Design Process performance specifications were being developed for the future housing system designed last year. These house designs coordinate and optimize predicted and desirable advances in computerized design processes, materials, components, and manufacturing automation to achieve energy efficiency at reduced first cost. Energy design software were being developed for CAD systems, stressed skin insulating core panel manufacturers; and a prototype energy sales tool. A prototype design was to be developed to integrate one or more subsystems with the building skin. As part of the Manufacturing Process we are developing a manufacturing process simulation and data base to help current and new entrants to the industrialized housing industry in assessing the impact of implementing new manufacturing techniques. For Evaluation we are developing testing plans for six units of housing on the UO campus and the stressed skin insulating core house to be constructed in Oregon. The DOW Chemical test structure will be retrofitted with a tile roof and retested to compare to the dome and conventional construction structures. Calibration of the wind tunnel will be completed so that laboratory tests can be conducted to simulate the ventilation cooling efficiency of houses in design. Research utilization and program management were either aspects of this program.

Not Available

1992-03-01T23:59:59.000Z

97

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.

98

Spherical torus fusion reactor  

DOE Patents [OSTI]

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.

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

99

US House of Representatives Appropriation Committee Report May 18, 2005  

E-Print Network [OSTI]

US House of Representatives Appropriation Committee Report May 18, 2005 Fusion Energy Sciences The Committee recommendation for fusion energy sciences is $295,155,000, an increase of $5,605,000 over that two-thirds of the proposed increase for the International Thermonuclear Experimental Reactor (ITER

100

Atrium House solar revitalization  

E-Print Network [OSTI]

The idea behind the Atrium House Solar Revitalization project, may be briefly presented as: energy conserving, low rise, high density, related- to- the-sky residences. The proposed system consists of a reticulate grid - ...

Malamuceanu, Dan Roland

1984-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

" Million Housing Units, Final...  

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

6 Televisions in U.S. Homes, by Climate Region, 2009" " Million Housing Units, Final" ,,"Climate Region2" ,"Total U.S.1 (millions)" ,,"Very Cold","Mixed- Humid","Mixed-Dry"...

102

" Million Housing Units, Final...  

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

" Million Housing Units, Final" ,,"Climate Region2" ,"Total U.S.1 (millions)" ,,"Very Cold","Mixed- Humid","Mixed-Dry" "Fuels Used and End Uses",,"Cold",,"Hot-Dry","Hot-Humid...

103

" Million Housing Units, Preliminary"  

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

Computers and Other Electronics in U.S. Homes, By Number of Household Members, 2009" " Million Housing Units, Preliminary" ,,"Number of Household Members" ,"Total U.S.1 (millions)"...

104

" Million Housing Units, Final...  

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

3 Computers and Other Electronics in U.S. Homes, by Year of Construction, 2009" " Million Housing Units, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before...

105

" Million Housing Units, Final...  

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

7 Computers and Other Electronics in U.S. Homes, by Census Region, 2009" " Million Housing Units, Final" ,,"Census Region" ,"Total U.S.1 (millions)" ,,"Northeast","Midwest","South"...

106

" Million Housing Units, Final"  

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

5 Computers and Other Electronics in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty...

107

" Million Housing Units, Final...  

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

4 Air Conditioning in U.S. Homes, by Number of Household Members, 2009" " Million Housing Units, Final" ,,"Number of Household Members" ,"Total U.S.1 (millions)" ,,,,,,"5 or More...

108

" Million Housing Units, Final...  

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

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

109

" Million Housing Units, Final...  

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

3 Air Conditioning 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...

110

" Million Housing Units, Final"  

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

5 Air Conditioning in U.S. Homes, by Household Income, 2009" " Million Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty Line2" ,,"Less...

111

Hood River Passive House  

SciTech Connect (OSTI)

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.

Hales, D.

2013-03-01T23:59:59.000Z

112

Indian Housing Training Conference  

Broader source: Energy.gov [DOE]

This four-day conference will provide housing professionals with the tools to maintain good homes, build affordable homes, improve public safety, and provide essential building blocks to a healthy...

113

" 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...

114

" Million Housing Units, Final...  

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

3 Televisions 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...

115

" Million Housing Units, Final...  

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

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

116

" 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" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty Line2" ,,"Less than...

117

" 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, Final" ,,"Year of Construction" ,"Total U.S.1 (millions)" ,,"Before 1940","1940 to...

118

" 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" ,,"Climate Region2" ,"Total U.S.1 (millions)" ,,"Very Cold","Mixed- Humid","Mixed-Dry"...

119

" Million Housing Units, Final...  

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

7 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...

120

" 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 Units, Final" ,,"Number of Household Members" ,"Total U.S.1 (millions)" ,,,,,,"5 or More...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

" Million Housing Units, Final...  

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

Housing Units, Final" ,,"Household Income" ,"Total U.S.1 (millions)",,,"Below Poverty Line2" ,,"Less than 20,000","20,000 to 39,999","40,000 to 59,999","60,000 to...

122

" Million Housing Units, Final...  

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

by the U.S. Department of Energy's Office of Energy and Efficiency and Renewable Energy (EERE). 3Housing units are classified as urban or rural using definitions created...

123

Transducer for downhole drilling components  

DOE Patents [OSTI]

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.

Hall, David R; Fox, Joe R

2006-05-30T23:59:59.000Z

124

Special No. 9 House  

High Performance Buildings Database

New Orleans, LA The Special No. 9 House was designed for the Make It Right Foundation to provide storm-resistant, affordable, and sustainable housing options for the residents of New Orleans' Lower Ninth Ward displaced by Hurricane Katrina. To support Make It Right's goal of building 150 homes in the Lower Ninth Ward, this single-family home is poised for mass production, anticipating a shift from on-site to off-site fabrication as more homes are scheduled for construction.

125

Ron Thompson Director of Housing  

E-Print Network [OSTI]

Vinings Community Assistant Vinings Custodial Supervisor Tina Roach South Housing Custodial Supervisor

126

Data transmission element for downhole drilling components  

DOE Patents [OSTI]

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.

Hall, David R. (Provo, UT); Hall, Jr., H. Tracy (Provo, UT); Pixton, David S. (Lehi, UT); Dahlgren, Scott (Provo, UT); Fox, Joe (Spanish Fork, UT); Sneddon, Cameron (Provo, UT); Briscoe, Michael (Lehi, UT)

2006-01-31T23:59:59.000Z

127

Fusion reactor pumped laser  

DOE Patents [OSTI]

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.

Jassby, D.L.

1987-09-04T23:59:59.000Z

128

Nuclear reactor construction with bottom supported reactor vessel  

DOE Patents [OSTI]

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

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

1987-01-01T23:59:59.000Z

129

House, home, and community : good models for graduate student housing  

E-Print Network [OSTI]

This thesis explores the planning and design of on-campus housing for graduate students in urban context. This study reviews the prevailing models of on-campus housing nationally and discusses the new concepts of future ...

Han, Jienan, 1978-

2004-01-01T23:59:59.000Z

130

Fayette Country, Pennsylvania, Housing Market Analysis | Department...  

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

Fayette Country, Pennsylvania, Housing Market Analysis Fayette Country, Pennsylvania, Housing Market Analysis This is a document from the Fayette County Housing Consortium posted...

131

Controlling House Sparrows  

E-Print Network [OSTI]

T he English or house sparrow is a very common resident in urban and suburban areas. Introduced from Europe, the sparrow has spread over the entire United States and is found almost everywhere in Texas. It is an aggressive, adaptable bird that nests...

Texas Wildlife Services

2008-04-15T23:59:59.000Z

132

Hood River Passive House  

SciTech Connect (OSTI)

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.

Hales, D.

2014-01-01T23:59:59.000Z

133

Housing services Zinfandel Hall  

E-Print Network [OSTI]

resources, the library, and the Internet. The Community has its own dining hall, swimming pools, study roomsHousing services Zinfandel Hall (707) 664-2541 Fax: (707) 664-4158 e-mail: ssu hall suites and campus apartments, all located just seconds from the main campus classroom buildings

Ravikumar, B.

134

Systems Science Harder House  

E-Print Network [OSTI]

Systems Science Harder House 1604 SW 10th Avenue 503-725-4960 www.sysc.pdx.edu/ M.S. Ph.D. Systems governing systems of widely differing types. Systems concepts and techniques are used extensively for both who are skilled in modern methods of decision making and systems design and who are capable

135

The emotional economy of housing  

E-Print Network [OSTI]

This paper offers an interpretation of the role of emotions in animating housing markets which complements more traditional economic and behavioural studies of locally based house-price inflation. Looking to debates within ...

Christie, H.; Smith, S.J.; Munro, M.

2008-10-01T23:59:59.000Z

136

Queens College Louis Armstrong House  

E-Print Network [OSTI]

Queens College Louis Armstrong House Louis Armstrong House Museum "From a humble, two-room shack Armstrong. Armstrong lived for nearly three decades in the modest, brick-fronted Corona, Queens home that today is the Louis Armstrong House Museum, which is partnered with Queens College, and open

Rosen, Jay

137

Passive retrofits for Navy housing  

SciTech Connect (OSTI)

A project to assess and initiate passive solar energy retrofits to US Navy family housing is described. The current data base for Navy housing (ECOP), and its enhancement for passive solar purposes options proposed for Navy housing are explained. The analysis goals and methods to evaluate the retrofits are discussed. An educational package to explain the retrofits is described.

Hibbert, R.; Miles, C.; Jones, R.; Peck, C.; Anderson, J.; Jacobson, V.; Dale, A.M.

1985-01-01T23:59:59.000Z

138

Housing characteristics 1993  

SciTech Connect (OSTI)

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.

NONE

1995-06-01T23:59:59.000Z

139

Performance House -- A Cold Climate Challenge Home  

SciTech Connect (OSTI)

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.

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

2013-08-01T23:59:59.000Z

140

Mobile-component housing and solar energy : the possibilities  

E-Print Network [OSTI]

This paper is part of a body of work directed at enhancing the acceptance of photovoltaics in various sectors of the U.S. economy. The focus here is on residential applications. The work is funded by the U.S. Department ...

Nutt-Powell, Thomas E.

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

House Testimony | Jefferson Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun withconfinement plasmas inPortalAll NERSCResearchInstitute /House

142

THE WHITE HOUSE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign Object DamageSystemsU.S. TALKS1THE WHITE HOUSE Office

143

THE WHITE HOUSE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign Object DamageSystemsU.S. TALKS1THE WHITE HOUSE

144

THE WHITE HOUSE  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign Object DamageSystemsU.S. TALKS1THE WHITE HOUSE

145

Education Office Housing  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area. TheEPSCI Home It is the missionEducation Office Housing

146

Open House | Jefferson Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratorySpeeding access1 TechnicalOilOnline Application ¬ĽOpen House

147

Terrace housing : providing quality in higher-density housing  

E-Print Network [OSTI]

The higher demand of higher-density housing in Bangkok due to the rapid growth of the economy and the use of high-performance materials and modern construction methods has changed the forms of housing from low-rise buildings ...

Atthakor, Songpol

1992-01-01T23:59:59.000Z

148

Housing Workshop I Some Questions on Housing Quality  

E-Print Network [OSTI]

but most importantly the environmental conditions are poor and energy guzzling, with controls than no one new housing schemes in terms of: · Community ­ to what extent does the development create a sense of community? · Connectivity ­ how well connected is any new housing development to the existing communities

Reading, University of

149

Passive heat transfer means for nuclear reactors  

DOE Patents [OSTI]

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.

Burelbach, James P. (Glen Ellyn, IL)

1984-01-01T23:59:59.000Z

150

Caribbean House Hilory Thomas, `14  

E-Print Network [OSTI]

Caribbean House Hilory Thomas, `14 College of Arts and Sciences Biochemistry #12;Overview of the Program The aim of the Caribbean House is to better inform and enhance individual's knowledge about the Caribbean islands and their characteristics. The program also aims to bring together diverse individuals

Hayden, Nancy J.

151

Software and House Requirements Engineering  

E-Print Network [OSTI]

a requirements engineer who puts her knowledge of software construction together with her creativity to come upSoftware and House Requirements Engineering: Lessons Learned in Combatting Requirements Creep creativity to try to come up with a plan for a house that will meet the customer's requirements. The customer

Berry, Daniel M.

152

The Resource Conservation Research House  

SciTech Connect (OSTI)

The Resource Conservation Research House, built by the NAHB Research Center and opened in 1992, was constructed with materials that conserve the nation`s resources. The house is designed to stimulate interest in resource conservation in home building among home builders, home buyers, public officials, civic groups, and the media. In addition to products made from recycled materials, products and systems used to build the house are made from less costly materials, more durable materials, and materials that contribute to energy conservation during the lifetime of the house. A principal purpose of building the house was to test and demonstrate resource-conserving products and systems that now exist only in prototype or that are on the fringes of the market, and to help to move useful, cost-effective products of this type toward the marketplace mainstream.

Bowles, L.K. [NAHB Research Center, Inc., Upper Marlboro, MD (United States)

1994-12-31T23:59:59.000Z

153

Higher occupancy humanism : the trade-offs for encouraging middle income housing in a global city  

E-Print Network [OSTI]

In high density urban areas where the land acquisition and construction cost components are significant relative to total development costs, the market typically supplies a high-income housing product in order to justify ...

Konishi, Ryunosuke, 1975-

2003-01-01T23:59:59.000Z

154

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

SciTech Connect (OSTI)

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.

Anderson, R.; Roberts, D.

2008-11-01T23:59:59.000Z

155

Removable check valve for use in a nuclear reactor  

DOE Patents [OSTI]

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.

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

1988-01-01T23:59:59.000Z

156

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

SciTech Connect (OSTI)

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.

Sozer, M.C.

1992-04-01T23:59:59.000Z

157

Nuclear reactor engineering  

SciTech Connect (OSTI)

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

Glasstone, S.; Sesonske, A.

1981-01-01T23:59:59.000Z

158

Nuclear reactor shield including magnesium oxide  

DOE Patents [OSTI]

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.

Rouse, Carl A. (Del Mar, CA); Simnad, Massoud T. (La Jolla, CA)

1981-01-01T23:59:59.000Z

159

Energy Efficient Industrialized Housing Research Program. Annual report, FY 1991  

SciTech Connect (OSTI)

Six area reported progress in the Energy Efficient Industrialized Housing Research Program during FY 1991. As part of Industry Guidance, meetings were held with steering and technical committees in computers, housing design and manufacturing. This task area enables the program to benefit from the expertise of industry representatives and communicate research results directly to them. As part of the Design Process performance specifications were being developed for the future housing system designed last year. These house designs coordinate and optimize predicted and desirable advances in computerized design processes, materials, components, and manufacturing automation to achieve energy efficiency at reduced first cost. Energy design software were being developed for CAD systems, stressed skin insulating core panel manufacturers; and a prototype energy sales tool. A prototype design was to be developed to integrate one or more subsystems with the building skin. As part of the Manufacturing Process we are developing a manufacturing process simulation and data base to help current and new entrants to the industrialized housing industry in assessing the impact of implementing new manufacturing techniques. For Evaluation we are developing testing plans for six units of housing on the UO campus and the stressed skin insulating core house to be constructed in Oregon. The DOW Chemical test structure will be retrofitted with a tile roof and retested to compare to the dome and conventional construction structures. Calibration of the wind tunnel will be completed so that laboratory tests can be conducted to simulate the ventilation cooling efficiency of houses in design. Research utilization and program management were either aspects of this program.

Not Available

1992-03-01T23:59:59.000Z

160

" 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...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

" Million U.S. Housing Units"  

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

7 Air-Conditioning Usage Indicators by Number of Household Members, 2005" " Million U.S. Housing Units" ,,"Number of Households With --" ,"Housing Units (millions)" ,,"1 Member","2...

162

" 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...

163

" 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...

164

Housing and Urban Development Multifamily Properties Eligible...  

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

DOE's income eligibility requirement, which is currently set at 200% of the federal poverty level. Note that a public housing, assisted housing, and LIHTC building that does not...

165

Research reactors - an overview  

SciTech Connect (OSTI)

A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

West, C.D.

1997-03-01T23:59:59.000Z

166

Nuclear Reactors and Technology  

SciTech Connect (OSTI)

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.

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

1992-01-01T23:59:59.000Z

167

Light Water Reactor Sustainability  

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

3 Light Water Reactor Sustainability Program ACCOMPLISHMENTS REPORT 2013 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

168

Light Water Reactor Sustainability  

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

4 Light Water Reactor Sustainability ACCOMPLISHMENTS REPORT 2014 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

169

Public housing renovation : an opportunity for a better housing environment  

E-Print Network [OSTI]

The central hypothesis of this study is that the current renovation program of public housing projects is based on a predominantly physical perspective. Understanding the administrative and implementation aspects of the ...

JordŠn F., Pablo (JordŠn Fuchs)

1984-01-01T23:59:59.000Z

170

Customizing mass housing : a discursive grammar for Siza's Malagueira houses  

E-Print Network [OSTI]

This thesis proposes a process of providing mass-customized housing based on computer-aided design and production systems. It focuses on the design part, which mainly consists of an interactive system for the generation ...

Duarte, Josť Pinto

2001-01-01T23:59:59.000Z

171

Housing Market Information and the Benefit of Housing Programs  

E-Print Network [OSTI]

~ Kain, John F. and Quigley, John M. , "Measuring theKain, John F. and Quigley, John M. , "Evaluating theKain, John F. and Quigley, John M. , Housing Markets and

Quigley, John M.

1986-01-01T23:59:59.000Z

172

Low-temperature hermetic sealing of optical fiber components  

DOE Patents [OSTI]

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.

Kramer, Daniel P. (Centerville, OH)

1996-10-22T23:59:59.000Z

173

Bioconversion reactor  

DOE Patents [OSTI]

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.

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

1992-01-01T23:59:59.000Z

174

Nuclear Reactors and Technology; (USA)  

SciTech Connect (OSTI)

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.

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

1991-01-01T23:59:59.000Z

175

University Reactor Matching Grants Program  

SciTech Connect (OSTI)

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

John Valentine; Farzad Rahnema; Said Abdel-Khalik

2003-02-14T23:59:59.000Z

176

Spherical torus fusion reactor  

DOE Patents [OSTI]

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.

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

1989-01-01T23:59:59.000Z

177

Residential Handbook Welcome to your University of Pittsburgh housing accommodations.  

E-Print Network [OSTI]

housing. Upon electronically signing your Housing and Dining Services Contract (Contract), you agreed to

Sibille, Etienne

178

House Appropriations Committee'Report FY04 Energy and Water Development Act  

E-Print Network [OSTI]

House Appropriations Committee'Report FY04 Energy and Water Development Act Fusion-relevant Sections "FUSION ENERGY SCIENCES "The Committee recommendation for fusion energy sciences is $268 of the Administration's proposal to re-engage in the International Thermonuclear Experimental Reactor (ITER) project

179

Optimizing Manufactured Housing Energy Use  

E-Print Network [OSTI]

Heater 40 gallon capacity Solar Water Heater ? 66 gallon capacity Duct Joints Industry Standard Sealed with Mastic Duct System Perimeter Duct System Main Trunk Line House Leakage ACH 50 = 10 ACH 50 = 9 Figure 1 Floor Plan...

McGinley, W. M.; Jones, A.; Turner, C.; Chandra, S.; Beal, D.; Parker, D. S.; Moyer, N.; McIlvaine, J.

2004-01-01T23:59:59.000Z

180

White House Tribal Nations Conference  

Broader source: Energy.gov [DOE]

On December 5, 2012, President Obama will host representatives invited from each of the 566 federally recognized American Indian tribes, and Alaska Native Villages, at the 2012 White House Tribal...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Transactions Costs and Housing Markets  

E-Print Network [OSTI]

1989: 282-294. Quigley, John M. , ďInterest Rate Variations,69(4), 1987: 636-643. Quigley, John M. , ďHomeowner MobilityAND HOUSING MARKETS By John M. Quigley February 2004 These

Quigley, John M.

2002-01-01T23:59:59.000Z

182

Closed Brayton cycle power conversion systems for nuclear reactors :  

SciTech Connect (OSTI)

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 the manufacturers site (Barber-Nichols Inc.) and installed and operated at Sandia. A sufficiently detailed description of the loop is provided in this report along with the design characteristics of the turbo-alternator-compressor set to allow other researchers to compare their results with those measured in the Sandia test-loop. The third task consisted of a validation effort. In this task the test loop was operated and compared with the modeled results to develop a more complete understanding of this electrically heated closed power generation system and to validate the model. The measured and predicted system temperatures and pressures are in good agreement, indicating that the model is a reasonable representation of the test loop. Typical deviations between the model and the hardware results are less than 10%. Additional tests were performed to assess the capability of the Brayton engine to continue to remove decay heat after the reactor/heater is shutdown, to develop safe and effective control strategies, and to access the effectiveness of gas inventory control as an alternative means to provide load following. In one test the heater power was turned off to simulate a rapid reactor shutdown, and the turbomachinery was driven solely by the sensible heat stored in the heater for over 71 minutes without external power input. This is an important safety feature for CBC systems as it means that the closed Brayton loop will keep cooling the reactor without the need for auxiliary power (other than that needed to circulate the waste heat rejection coolant) provided the heat sink is available.

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

2006-04-01T23:59:59.000Z

183

Large Component Removal/Disposal  

SciTech Connect (OSTI)

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.

Wheeler, D. M.

2002-02-27T23:59:59.000Z

184

Electronuclear ion fusion in an ion cyclotron resonance reactor  

SciTech Connect (OSTI)

A method and apparatus for generating nuclear fusion by ion cyclotron resonance in an ion trap reactor. The reactor includes a cylindrical housing having an axial axis, an internal surface, and first and second ends. First and second end plates that are charged are respectively located at the first and second ends of the cylindrical housing. A gas layer is adsorbed on the internal surface of the cylindrical housing. Ions are desorbed from the gas layer, forming a plasma layer adjacent to the cylindrical housing that includes first ions that have a same charge sign as the first and second end plates. A uniform magnetic field is oriented along the axial axis of the cylindrical housing. Second ions, that are unlike the first ions, but have the same charge sign, are injected into the cylindrical housing along the axial axis of the cylindrical housing. A radio frequency field resonantly accelerates the injected second ions at the cyclotron resonance frequency of the second ions. The second ions circulate in increasing helical orbits and react with the first ions, at the optimum energy for nuclear fusion. The amplitude of the radio frequency field is adjusted to accelerate the second ions at a rate equal to the rate of tangential energy loss of the second ions by nuclear scattering in the first ions, causing the ions to continually interact until fusion occurs.

Cowgill, Donald F.

1996-12-01T23:59:59.000Z

185

The 2005 Solar D House  

E-Print Network [OSTI]

, each of which designed, built, and operated a totally solar-powered home with a home office and their transportation needs using a solar-charged vehicle. Organized by the U.S. Department of Energy and the National Renewable energy Laboratory..., the Solar Decathlon competition challenges university teams to design and build an 800-square foot, totally solar-powered house. The competition took place on the National Mall in Washington D.C., where each house was constructed and operated from...

Garrison, M.

2006-01-01T23:59:59.000Z

186

Nuclear Reactor Safety Design Criteria  

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

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

1993-01-19T23:59:59.000Z

187

Housing & Residential Life Contracts, Assignments & Billing  

E-Print Network [OSTI]

Housing & Residential Life Contracts, Assignments & Billing Comstock Hall-East 210 Delaware St. SE.housing.umn.edu/contractbook. I hereby agree to comply with all University of Minnesota and Housing & Residential Life policies to promptly notify Housing & Residential Life of any felony or misdemeanor charge or conviction prior

Amin, S. Massoud

188

Neutronic reactor  

DOE Patents [OSTI]

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.

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

1983-01-01T23:59:59.000Z

189

TA-2 Water Boiler Reactor Decommissioning Project  

SciTech Connect (OSTI)

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.

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

1991-06-01T23:59:59.000Z

190

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

SciTech Connect (OSTI)

The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the waste-forms generated throughout 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)

Halliwell, Chris [Sellafield Ltd, Sellafield (United Kingdom)

2012-07-01T23:59:59.000Z

191

State space modeling of reactor core in a pressurized water reactor  

SciTech Connect (OSTI)

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.

Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

2014-07-10T23:59:59.000Z

192

Ceramic tile expansion engine housing  

DOE Patents [OSTI]

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.

Myers, B.

1995-04-11T23:59:59.000Z

193

Ceramic tile expansion engine housing  

DOE Patents [OSTI]

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.

Myers, Blake (4650 Almond Cir., Livermore, CA 94550)

1995-01-01T23:59:59.000Z

194

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

SciTech Connect (OSTI)

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.

Brinch, J. [Energetics, Inc., Columbia, MD (United States)

1996-06-01T23:59:59.000Z

195

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

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

Islip Housing Authority Energy Efficiency Turnover Protocols, Islip, New York Building America Whole-House Solutions for Existing Homes: Islip Housing Authority Energy Efficiency...

196

2014 Housing Innovation Awards DOE Challenge Home Application...  

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

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

197

White House Initiative on Historically Black Colleges and Universities...  

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

White House Initiative on Historically Black Colleges and Universities White House Initiative on Historically Black Colleges and Universities How WHI-HBCU are ran White House...

198

Before House Subcommittee on Water and Power - Committee on Natural...  

Energy Savers [EERE]

House Subcommittee on Water and Power - Committee on Natural Resources Before House Subcommittee on Water and Power - Committee on Natural Resources Before House Subcommittee on...

199

Building America Whole-House Solutions for New Homes: Affordable...  

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

New Homes: Affordable Cold Climate Infill Housing with Hybrid Insulation Approach Building America Whole-House Solutions for New Homes: Affordable Cold Climate Infill Housing with...

200

Occupancy Simulation in Three Residential Research Houses  

SciTech Connect (OSTI)

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.

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

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Essays on the household-level effects of house price growth  

E-Print Network [OSTI]

Constructing measures of house price variance . . . . 2.4.4Flip That House? House Price Dynamics and Housing InvestmentHouse Price Data . . . . . . . . . . . . . . . . . . . . .

Sitgraves, Claudia Ayanna

2009-01-01T23:59:59.000Z

202

Kevin Smith Sutherland House 234  

E-Print Network [OSTI]

Kevin Smith Sutherland House 234 PMB 3342 Nashville, TN 37235 January 27, 2010 Mr. Scott at Kevin.m.smith@vanderbilt.edu or by phone at (543)3843909. Thank you for your consideration. Sincerely, Kevin Smith The cover letter needs to be in business letter format...this includes

Bordenstein, Seth

203

The Malay house : rationale and change  

E-Print Network [OSTI]

The Malay house is defined and described in the Malaysian context . Underlying principles or rules that make up the∑ house are derived from the analysis of its physical, spatial and functional elements and the variations ...

Wan Abidin, Wan Burhanuddin B

1981-01-01T23:59:59.000Z

204

Vanderbilt University Office of Housing & Residential Education  

E-Print Network [OSTI]

Vanderbilt University Office of Housing & Residential Education RESIDENTADVISERRECRUITMENT2015 Adviser (RA) is a paraprofessional student staff member for the Office of Housing and Residential Coordinators, Head Residents, and faculty to create a premiere residential experience where students can learn

Bordenstein, Seth

205

Process of designing city housing in Japan  

E-Print Network [OSTI]

pose of this thesis is to show one design approach to providing more preferable housing for users in Japan. Chapter 1 gives an overview of trends in Japanese housing construction, describes user requirements, analyzes ...

Kurokawa, Shoji

1983-01-01T23:59:59.000Z

206

Support arrangements for core modules of nuclear reactors. [PWR  

DOE Patents [OSTI]

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.

Bollinger, L.R.

1983-11-03T23:59:59.000Z

207

Lockout housing and sleeve for safety valve  

SciTech Connect (OSTI)

This patent describes apparatus for use in a subsurface valve. It comprises a lockout housing; and a lockout sleeve.

Dickson, R.L.; Davis, G.R.

1992-07-07T23:59:59.000Z

208

Inside the White House: Solar Panels  

Broader source: Energy.gov [DOE]

Go inside the White House and learn about the installation of solar panels on the roof of the residence.

209

" Million U.S. Housing Units"  

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

Energy Consumption Survey. " " Energy Information Administration 2005 Residential Energy Consumption Survey: Preliminary Housing Characteristics Tables" "Table HC8.7...

210

Hybrid adsorptive membrane reactor  

DOE Patents [OSTI]

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.

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

2011-03-01T23:59:59.000Z

211

RAMA Surveillance Capsule and Component Activation Analyses  

SciTech Connect (OSTI)

This paper presents the calculated-to-measured ratios associated with the application of the RAMA Fluence Methodology software to light water reactor surveillance capsule and reactor component activation evaluations. Comparisons to measurements are performed for pressurized water reactor and boiling water reactor surveillance capsule activity specimens from seventeen operating light water reactors. Comparisons to measurements are also performed for samples removed from the core shroud, top guide, and jet pump brace pads from two reactors. In conclusion: The flexible geometry modeling capabilities provided by RAMA, combined with the detailed representation of operating reactor history and anisotropic scattering detail, produces accurate predictions of the fast neutron fluence and neutron activation for BWR and PWR surveillance capsule geometries. This allows best estimate RPV fluence to be determined without the need for multiplicative bias corrections. The three-dimensional modeling capability in RAMA provides an accurate estimate of the fast neutron fluence for regions far removed from the core mid-plane elevation. The comparisons to activation measurements for various core components indicate that the RAMA predictions are reasonable, and notably conservative (i.e., C/M ratios are consistently greater than unity). It should be noted that in the current evaluations, the top and bottom fuel regions are represented by six inch height nodes. As a result, the leakage-induced decrease in power near the upper and lower edges of the core are not well represented in the current models. More precise predictions of fluence for components that lie above and below the core boundaries could be obtained if the upper and lower fuel nodes were subdivided into multiple axial regions with assigned powers that reflect the neutron leakage at the top and bottom of the core. This use of additional axial sub-meshing at the top and bottom of the core is analogous to the use of pin-wise meshing in peripheral bundles to accurately represent radial leakage effects. The representation of thermal neutron fluence and activations are found to be reasonably accurate and consistently conservative, as demonstrated by comparison to the reactor component thermal neutron reaction activation measurements. Further improvement in the comparisons to measurements could be achieved by exploring the impact of enhanced sub-meshing of the geometry near the components of interest. The mesh densities utilized in the current evaluation are consistent with the mesh requirements for high energy neutron transport. The substantially shorter transport lengths for thermal neutrons relative to high energy neutrons suggests that localized regions of finer meshing are needed in the vicinity of those reactor components requiring thermal neutron fluence evaluations. (authors)

Watkins, Kenneth E.; Jones, Eric N. [TransWare Enterprises Inc., 1565 Mediterranean Dr., Sycamore, IL 60178 (United States); Carter, Robert G. [Electric Power Research Institute, 1300 West W. T. Harris Blvd., Charlotte, NC 28262 (United States)

2011-07-01T23:59:59.000Z

212

Shielded fluid stream injector for particle bed reactor  

DOE Patents [OSTI]

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.

Notestein, John E. (Morgantown, WV)

1993-01-01T23:59:59.000Z

213

White House Forum on Minorites in Energy  

Broader source: Energy.gov [DOE]

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.

214

Chicagoland Single-Family Housing Characterization  

SciTech Connect (OSTI)

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.

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

2012-06-01T23:59:59.000Z

215

Nuclear reactor engineering  

SciTech Connect (OSTI)

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

Glasstone, S.; Sesonske, A.

1982-07-01T23:59:59.000Z

216

RSMASS: A simple model for estimating reactor and shield masses  

SciTech Connect (OSTI)

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.

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

1987-01-01T23:59:59.000Z

217

Reactor safeguards against insider sabotage  

SciTech Connect (OSTI)

A conceptual safeguards system is structured to show how both reactor operations and physical protection resources could be integrated to prevent release of radioactive material caused by insider sabotage. Operational recovery capabilities are addressed from the viewpoint of both detection of and response to disabled components. Physical protection capabilities for preventing insider sabotage through the application of work rules are analyzed. Recommendations for further development of safeguards system structures, operational recovery, and sabotage prevention are suggested.

Bennett, H.A.

1982-03-01T23:59:59.000Z

218

New Developments in Hog Houses and Equipment.  

E-Print Network [OSTI]

for the central house are the half-monitor and the gable-roof. The half-monitor house should be set lengthwise east and west so that the windows face south, while the gable-roof house should be set lengthwise north and south so that the rays of the sun... will shine through the sky-light windows on the east side in the morning, and those on the west side in the afternoon. The central house is better adapted for one who is in the hog business on a larger scale than the average. This house permits a number...

Hale, Fred; Smith, H. P. (Harris Pearson)

1933-01-01T23:59:59.000Z

219

Extending the physical and cultural boundaries of affordable housing : a reconfiguration of the Franklin Field Public Housing Development  

E-Print Network [OSTI]

Public housing is in a state of revision. Changes in attitude and approach to housing low-income people, evident in housing reform, are challenging the standard which public housing has come to represent. After years of ...

Makuku, Owiso A. (Owiso Atsali), 1968-

1999-01-01T23:59:59.000Z

220

ASSOCIATED RESIDENTIAL COMMUNITY HOUSING (ARCH) PROGRAM UC San Diego's Associated Residential Community Housing (ARCH) is committed to supporting the academic  

E-Print Network [OSTI]

ASSOCIATED RESIDENTIAL COMMUNITY HOUSING (ARCH) PROGRAM I. MISSION UC San Diego's Associated Residential Community Housing (ARCH) is committed to supporting the academic mission of the university, Associated Residential Community Housing (ARCH) offers campus housing to graduate and professional students

California at San Diego, University of

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Remotely serviced filter and housing  

DOE Patents [OSTI]

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.

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

1987-07-22T23:59:59.000Z

222

Photoneutron effects on pulse reactor kinetics for the Annular Core Research Reactor (ACRR).  

SciTech Connect (OSTI)

The Annular Core Research Reactor (ACRR) is a swimming-pool type pulsed reactor that maintains an epithermal neutron flux and a nine-inch diameter central dry cavity. One of its uses is neutron and gamma-ray irradiation damage studies on electronic components under transient reactor power conditions. In analyzing the experimental results, careful attention must be paid to the kinetics associated with the reactor to ensure that the transient behavior of the electronic device is understood. Since the ACRR fuel maintains a substantial amount of beryllium, copious quantities of photoneutrons are produced that can significantly alter the expected behavior of the reactor power, especially following a reactor pulse. In order to understand these photoneutron effects on the reactor kinetics, the KIFLE transient reactor-analysis code was modified to include the photoneutron groups associated with the beryllium. The time-dependent behavior of the reactor power was analyzed for small and large pulses, assuming several initial conditions including following several pulses during the day, and following a long steady-state power run. The results indicate that, for these types of initial conditions, the photoneutron contribution to the reactor pulse energy can have a few to tens of percent effect.

Parma, Edward J., Jr.

2009-06-01T23:59:59.000Z

223

The house of the future  

ScienceCinema (OSTI)

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.

None

2010-09-01T23:59:59.000Z

224

Catalytic reactor for low-Btu fuels  

DOE Patents [OSTI]

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.

Smith, Lance (North Haven, CT); Etemad, Shahrokh (Trumbull, CT); Karim, Hasan (Simpsonville, SC); Pfefferle, William C. (Madison, CT)

2009-04-21T23:59:59.000Z

225

Reactor safety method  

DOE Patents [OSTI]

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.

Vachon, Lawrence J. (Clairton, PA)

1980-03-11T23:59:59.000Z

226

SRS Small Modular Reactors  

SciTech Connect (OSTI)

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

None

2012-04-27T23:59:59.000Z

227

SRS Small Modular Reactors  

ScienceCinema (OSTI)

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

None

2014-05-21T23:59:59.000Z

228

Self-actuating and locking control for nuclear reactor  

DOE Patents [OSTI]

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.

Chung, Dong K. (Chatsworth, CA)

1982-01-01T23:59:59.000Z

229

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

230

Nuclear reactor  

DOE Patents [OSTI]

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.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

231

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

SciTech Connect (OSTI)

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.

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

1991-03-01T23:59:59.000Z

232

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

DOE Patents [OSTI]

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.

Blaushild, Ronald M. (Wilkinsburg, PA)

1987-01-01T23:59:59.000Z

233

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

DOE Patents [OSTI]

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.

Blaushild, R.M.

1987-01-30T23:59:59.000Z

234

Spent nuclear fuel discharges from U.S. reactors 1994  

SciTech Connect (OSTI)

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.

NONE

1996-02-01T23:59:59.000Z

235

Small Modular Nuclear Reactors | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomenthe House Committee on Energy andDepartment ofAn Audience ofobjectiveReactor

236

White House honors Los Alamos  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun DengWISP SignIn OctoberWhite House honors Los

237

Open House with Environmental Scientists  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recoveryLaboratorySpeeding access1 TechnicalOilOnline Application ¬ĽOpen House with

238

Containment system for supercritical water oxidation reactor  

DOE Patents [OSTI]

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.

Chastagner, P.

1994-07-05T23:59:59.000Z

239

Savannah River Site production reactor technical specifications. K Production Reactor  

SciTech Connect (OSTI)

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

NONE

1996-02-01T23:59:59.000Z

240

Energy Efficient Affordable Housing Construction Program  

Broader source: Energy.gov [DOE]

The Department of Commerce and Economic Opportunity (DCEO) provides grants through the Energy Efficient Affordable Housing Construction Program. Under this program, grants are provided to Illinois...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Before the House Subcommittee on Investigations & Oversight ...  

Energy Savers [EERE]

and Investigations - Committee on Energy and Commerce Before the House Oversight and Government Reform Subcommittee on Government Management, Organization, and Procurement...

242

Evergreen Sustainable Development Standard for Affordable Housing  

Broader source: Energy.gov [DOE]

The Washington State Department of Commerce created the Evergreen Sustainable Development Standard, a set of green building criteria that is required for any affordable housing project applying for...

243

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

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

244

University of Pittsburgh SUMMER TERM HOUSING APPLICATION  

E-Print Network [OSTI]

SUMMER TERM HOUSING/FOOD SERVICES CONTRACT/Food Services Contract (this "Contract") is made by and between the University of Pittsburgh

Sibille, Etienne

245

International House Collection / William Black (collector)  

E-Print Network [OSTI]

International House Collection / William Black (collector) Revised by Erwin Wodarczak (2010 (collector). ≠ 1950-1953. 45 p. of textual records. Biographical Sketch Born in London, England, William

Handy, Todd C.

246

International House Collection / Stanley Read (collector)  

E-Print Network [OSTI]

International House Collection / Stanley Read (collector) Revised by Erwin Wodarczak (2010 (collector). - 1953-1955. 2 cm of textual records. Biographical Sketch Born in Quebec, Stanley Read earned

Handy, Todd C.

247

Index Revision, House Price Risk, and the Market for House Price Derivatives  

E-Print Network [OSTI]

bias in repeat-sales home price indices. Freddie Mac workingpaper #05Ė03. Index Revision, House Price Risk, and theMarket for House Price Derivatives Calhoun, C. A. (1996).

Deng, Yongheng; Quigley, John M.

2008-01-01T23:59:59.000Z

248

Exploring the enabling approach to housing through the Abuja Mass Housing Scheme  

E-Print Network [OSTI]

The magnitude of the housing problem in Nigeria is immense; the current deficit is around 12 to 16 million units. Government attempts to address housing availability has been a recurring theme throughout Nigeria's history. ...

Umoh, Nse (Nseabasi Effiong)

2012-01-01T23:59:59.000Z

249

A new approach to public housing : redesigning the Mission Hill housing projects  

E-Print Network [OSTI]

In the coming years there will be a need to revisit the question of public housing in general and dealing with existing housing projects in particular. This thesis attempts to provide a new approach to the redesign of ...

Idris, Ahmed Hussein

1994-01-01T23:59:59.000Z

250

Housing&Residential Life booklet 2012-2013  

E-Print Network [OSTI]

Housing&Residential Life booklet 2012-2013 Application Contract www.housing.umn.edu/applying apply of Minnesota Housing & Residential Life AppliCAtion informAtion pAyment informAtion Assignment informAtion move to apply for housing. The date your completed application is received by Housing & Residential Life

Minnesota, University of

251

Undergraduate reactor control experiment  

SciTech Connect (OSTI)

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

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

1992-01-01T23:59:59.000Z

252

Attrition reactor system  

DOE Patents [OSTI]

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.

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

1993-01-01T23:59:59.000Z

253

Attrition reactor system  

DOE Patents [OSTI]

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.

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

1993-09-28T23:59:59.000Z

254

Reactor Sharing Program  

SciTech Connect (OSTI)

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

Vernetson, W.G.

1993-01-01T23:59:59.000Z

255

Control of Reactor and Separator, with Recycle T. Larsson, S. Skogestadand Cheng-Ching Yu  

E-Print Network [OSTI]

Control of Reactor and Separator, with Recycle T. Larsson, S. Skogestad¬£and Cheng-Ching Yu This paper looks at control of a plant that consists of a reactor, separator and recycle of unreacted reactor where component A is converted to a product and the amount converted is given by ¬ī√?¬Ķ√?√? √?√?√ź

Skogestad, Sigurd

256

Reduced Order Based Compensator Control of Thin Film Growth in a CVD Reactor  

E-Print Network [OSTI]

of the reactor so that control and sensing are a basic component of the optimal design e#orts for the reactor. WeReduced Order Based Compensator Control of Thin Film Growth in a CVD Reactor H.T. Banks and H processing approaches with ad­ vanced mathematical modeling, optimization, and control theory to guide

257

Reduced Order Based Compensator Control of Thin Film Growth in a CVD Reactor  

E-Print Network [OSTI]

of the reactor so that control and sensing are a basic component of the optimal design efforts for the reactorReduced Order Based Compensator Control of Thin Film Growth in a CVD Reactor H.T. Banks and H processing approaches with ad- vanced mathematical modeling, optimization, and control theory to guide

258

NGNP Reactor Coolant Chemistry Control Study  

SciTech Connect (OSTI)

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.

Brian Castle

2010-11-01T23:59:59.000Z

259

Optimization of composite tubes for a thermal optical lens housing design  

E-Print Network [OSTI]

and the manufacturing of a carbon fiber reinforced tube in an epoxy resin matrix. This structure intends to serve as the optical lens housing onboard a spacecraft. In addition, some future work needs to be done before this component is certified. The objective...

Garcia Gonzalez, Hector Camerino

2004-09-30T23:59:59.000Z

260

Caribbean House Patrick Brown, Faculty Director  

E-Print Network [OSTI]

1 Caribbean House Patrick Brown, Faculty Director Jerry Aviles, Student Director Sonia Nelson, Student Director OVERVIEW The Caribbean House will be a phenomenal experience for everyone, not just the Caribbean culture and demonstrate the beautiful lifestyle that we try to live everyday. There is already

Hayden, Nancy J.

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Canada House Sarah Watson, Program Director  

E-Print Network [OSTI]

1 Canada House Sarah Watson, Program Director Clifton Beach, Program Director OVERVIEW By becoming part of the Canadian House, students will learn about the culture of Canada and come to appreciate organizational structure will give a new perspective of what living in Canada is like for individuals like us

Hayden, Nancy J.

262

Canada House Jonathon Wilkins, Student Director  

E-Print Network [OSTI]

1 Canada House Jonathon Wilkins, Student Director Emily Phelps, Student Director OVERVIEW In the Canada House program, we will focus on three main focal aspects of Canada: geography, history and proactively all subjects related to Canada. We will view films on a regular basis and hold weekly meetings

Hayden, Nancy J.

263

The BLOOMhouse:Zero Net Energy Housing  

E-Print Network [OSTI]

The 2007 University of Texas Solar Decathlon House is called the BLOOMhouse because it represents the ďseedĒ of new ideas for zero net energy housing. The University of Texas student team developed a prefabricated 7.9 kW stand-alone solar-powered...

Garrison, M.; Krepart, R.; Randall, S.; Novoselac, A.

264

Student Housing South Environmental Impact Report  

E-Print Network [OSTI]

Appendices Student Housing South Environmental Impact Report APPENDIX A. NOTICE OF PREPARATION FOR THE DRAFT ENVIRONMENTAL IMPACT REPORT AND COMMENT LETTERS #12;Appendices Student Housing South Environmental Impact Report #12;NOTICE OF PREPARATION: DRAFT ENVIRONMENTAL IMPACT REPORT DATE: September 25, 2013 TO

Sze, Lawrence

265

Housing & Residential Life Contracts, Assignments & Billing  

E-Print Network [OSTI]

Housing & Residential Life Contracts, Assignments & Billing Comstock Hall-East 210 Delaware St. SE & Residential Life. For the fall semester, I will cancel on or before August 7. For the spring semester, I day until Housing & Residential Life is able to fill my assigned space with a student from the waiting

Minnesota, University of

266

High solids fermentation reactor  

DOE Patents [OSTI]

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.

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

1993-03-02T23:59:59.000Z

267

Improved vortex reactor system  

DOE Patents [OSTI]

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.

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

1995-01-01T23:59:59.000Z

268

Advanced Test Reactor Tour  

SciTech Connect (OSTI)

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.

Miley, Don

2011-01-01T23:59:59.000Z

269

Advanced Test Reactor Tour  

ScienceCinema (OSTI)

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.

Miley, Don

2013-05-28T23:59:59.000Z

270

High solids fermentation reactor  

DOE Patents [OSTI]

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.

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

1993-01-01T23:59:59.000Z

271

Hypothetical Reactor Accident Study  

E-Print Network [OSTI]

- W 4 DfcSkoollo Rise-R-427 CARNSORE: Hypothetical Reactor Accident Study O. Walmod-Larsen, N. O: HYPOTHETICAL REACTOR ACCIDENT STUDY O. Walmod-Larsen, N.O. Jensen, L. Kristensen, A. Heide, K.L. Nedergård, P-basis accident and a series of hypothetical core-melt accidents to a 600 MWe reactor are de- scribed

272

Shutdown heat removal system reliability in thermal reactors  

SciTech Connect (OSTI)

An analysis of the failure probability per year of the shutdown heat removal system (SHRS) at hot standby conditions for two thermal reactor designs is presented. The selected reactor designs are the Pressurized Water Reactor and the Nonproliferation Alternative System Assessment Program Heavy Water Reactor. Failures of the SHRS following the initiating transients of loss of offsite power and loss of main feedwater system are evaluated. Common mode failures between components are incorporated in this anlaysis via the ..beta..-factor method and the sensitivity of the system reliability to common mode failures is investigated parametrically.

Sun, Y.H.; Bari, R.A.

1980-01-01T23:59:59.000Z

273

Integrity of neutron-absorbing components of LWR fuel systems  

SciTech Connect (OSTI)

A study of the integrity and behavior of neutron-absorbing components of light-water (LWR) fuel systems was performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE). The components studies include control blades (cruciforms) for boiling-water reactors (BWRs) and rod cluster control assemblies for pressurized-water reactors (PWRs). The results of this study can be useful for understanding the degradation of neutron-absorbing components and for waste management planning and repository design. The report includes examples of the types of degradation, damage, or failures that have been encountered. Conclusions and recommendations are listed. 84 refs.

Bailey, W.J.; Berting, F.M.

1991-03-01T23:59:59.000Z

274

Greening the U.S. House of Representatives  

E-Print Network [OSTI]

2009. 2. Reduce the carbon footprint of the House by cuttingroadmap to reducing the carbon footprint of the House, whileGoal #2: Reduce the carbon footprint of the House by cutting

Diamond,, Rick

2008-01-01T23:59:59.000Z

275

Annual Performance Evaluation of a Pair of Energy Efficient Houses (WC3 and WC4) in Oak Ridge, TN  

SciTech Connect (OSTI)

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.

Biswas, Kaushik [ORNL; Christian, Jeffrey E [ORNL; Gehl, Anthony C [ORNL; Jackson, Roderick K [ORNL; Boudreaux, Philip R [ORNL

2012-04-01T23:59:59.000Z

276

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

SciTech Connect (OSTI)

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

Not Available

1986-01-01T23:59:59.000Z

277

Passive heat-transfer means for nuclear reactors. [LMFBR  

DOE Patents [OSTI]

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.

Burelbach, J.P.

1982-06-10T23:59:59.000Z

278

Evaluation of aging degradation of structural components  

SciTech Connect (OSTI)

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.

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

1992-03-01T23:59:59.000Z

279

Evaluation of aging degradation of structural components  

SciTech Connect (OSTI)

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.

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

1992-03-01T23:59:59.000Z

280

Reactor vessel support system  

DOE Patents [OSTI]

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.

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

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Inductive coupler for downhole components and method for making same  

DOE Patents [OSTI]

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.

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

2006-05-09T23:59:59.000Z

282

Spinning fluids reactor  

DOE Patents [OSTI]

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.

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

2012-11-20T23:59:59.000Z

283

Determining Reactor Neutrino Flux  

E-Print Network [OSTI]

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

Jun Cao

2012-03-08T23:59:59.000Z

284

Reactor water cleanup system  

DOE Patents [OSTI]

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.

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

1994-12-20T23:59:59.000Z

285

Reactor water cleanup system  

DOE Patents [OSTI]

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.

Gluntz, Douglas M. (San Jose, CA); Taft, William E. (Los Gatos, CA)

1994-01-01T23:59:59.000Z

286

Before the House Science and Technology Subcommittee on Energy...  

Office of Environmental Management (EM)

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...

287

Before the House Science and Technology Subcommittee on Oversight...  

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

on Oversight and Investigations Before the House Science and Technology Subcommittee on Oversight and Investigations Before the House Science and Technology Subcommittee on...

288

Before the House Science and Technology Subcommittee on Energy...  

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

House Science and Technology Subcommittee on Energy and Environment Before the House Science and Technology Subcommittee on Energy and Environment Statement Before the Committee On...

289

Building America Whole-House Solutions for New Homes: Transformations...  

Energy Savers [EERE]

Building America Whole-House Solutions for New Homes: Transformations, Inc. Net Zero Energy Communities (Fact Sheet) Building America Whole-House Solutions for New Homes:...

290

Before the House Subcommittee on Oversight and Investigations...  

Office of Environmental Management (EM)

Job Creation and Regulatory Affairs - House Committee on Oversight and Governmant Reform Before House Subcommittee on Energy and Power and Subcommittee on Oversight and...

291

Before House Subcommittee on Energy and Power and Subcommittee...  

Energy Savers [EERE]

Job Creation and Regulatory Affairs - House Committee on Oversight and Governmant Reform Presentation: DOE Loan Programs Before the House Science, Space, and Technology...

292

Before The Subcommittee on Water and Power - House Committee...  

Energy Savers [EERE]

The Subcommittee on Water and Power - House Committee on Natural Resources Before The Subcommittee on Water and Power - House Committee on Natural Resources Testimony of...

293

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 Natural Resources Committee Testimony of Christopher M. Turner, Administrator SWPA Before the...

294

Testimony Before the House Appropriations Subcommittee on Energy...  

Energy Savers [EERE]

Testimony Before the House Appropriations Subcommittee on Energy and Water Development Testimony Before the House Appropriations Subcommittee on Energy and Water Development...

295

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

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

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

296

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

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

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

297

Before the House Science and Technology, Subcommittee on Energy...  

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

Technology, Subcommittee on Energy and Environment Before the House Science and Technology, Subcommittee on Energy and Environment Before the House Science and Technology,...

298

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...

299

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.

300

White House Office of Science and Technology Policy Summer 2014...  

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

White House Office of Science and Technology Policy Summer 2014 Internship Program Application Period White House Office of Science and Technology Policy Summer 2014 Internship...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

White House Honors Federal Agencies for Saving Taxpayers $133...  

Office of Environmental Management (EM)

White House Honors Federal Agencies for Saving Taxpayers 133 Million in Energy Costs by Increasing Efficiency Measures White House Honors Federal Agencies for Saving Taxpayers...

302

White House Science Fair Recap | Department of Energy  

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

White House Science Fair Recap White House Science Fair Recap Addthis Description Highlights from the inaugural WH science fair on Monday, Ocotober 18th, 2010. Speakers President...

303

Tribal Leaders Provide White House with Input on Bolstering Climate...  

Energy Savers [EERE]

Tribal Leaders Provide White House with Input on Bolstering Climate Resilience Tribal Leaders Provide White House with Input on Bolstering Climate Resilience January 7, 2015 -...

304

White House Council of Economic Advisers and Energy Department...  

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

White House Council of Economic Advisers and Energy Department Release New Report on Resiliency of Electric Grid During Natural Disasters White House Council of Economic Advisers...

305

Secretary Moniz at White House Women's Leadership Summit on Climate...  

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

Secretary Moniz at White House Women's Leadership Summit on Climate and Energy Secretary Moniz at White House Women's Leadership Summit on Climate and Energy Addthis Speakers...

306

White House Meeting Honors New Superior Energy Performance Members...  

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

White House Meeting Honors New Superior Energy Performance Members White House Meeting Honors New Superior Energy Performance Members December 13, 2013 - 11:39am Addthis New...

307

White House Leadership Summit on Women, Climate and Energy |...  

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

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 &...

308

White House Spotlights Solar Innovation as Summit Registration...  

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

White House Spotlights Solar Innovation as Summit Registration Continues White House Spotlights Solar Innovation as Summit Registration Continues April 23, 2014 - 10:38am Addthis...

309

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...

310

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

Office of Environmental Management (EM)

House Natural Resources Committee Before the Subcommittee on Water and Power - House Natural Resources Committee Testimony of Kenneth E. Legg, Administrator SEPA...

311

Los Angeles County's Green Idea House Achieves Efficient Goals...  

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

Los Angeles 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...

312

Before the Subcommittee on Energy -- House Science, Space, and...  

Office of Environmental Management (EM)

on Energy -- House Science, Space, and Technology Committee Testimony of Christopher Smith, Acting Assistant Secretary Before the Subcommittee on Energy -- House Science, Space,...

313

Before The Subcommittee on Water and Power - House Committee...  

Energy Savers [EERE]

The Subcommittee on Water and Power - House Committee on Natural Resources Before The Subcommittee on Water and Power - House Committee on Natural Resources Testimony of Elliot E....

314

Before Subcommittee on Water and Power - House Committee on Natural...  

Energy Savers [EERE]

Subcommittee on Water and Power - House Committee on Natural Resources Before Subcommittee on Water and Power - House Committee on Natural Resources Testimony of Mark Gabriel,...

315

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 William K....

316

Before The Subcommittee on Water and Power - House Committee...  

Energy Savers [EERE]

The Subcommittee on Water and Power - House Committee on Natural Resources Before The Subcommittee on Water and Power - House Committee on Natural Resources Testimony of Mark A....

317

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...

318

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

Office of Environmental Management (EM)

House Subcommittee on Energy and Power - Committee on Energy and Commerce Before the House Subcommittee on Energy and Power - Committee on Energy and Commerce Testimony of Adam...

319

Rural Development Multi-Family Housing Energy Efficiency Initiative...  

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

Development Multi-Family Housing Energy Efficiency Initiative Rural Development Multi-Family Housing Energy Efficiency Initiative In order to help create a more energy independent...

320

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...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

White House Launches the Generation Indigenous Native Youth Challenge...  

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

White House Launches the Generation Indigenous Native Youth Challenge White House Launches the Generation Indigenous Native Youth Challenge February 17, 2015 - 12:06pm Addthis On...

322

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

Energy Savers [EERE]

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...

323

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,...

324

Building America Whole-House Solutions for Existing Homes: Passive...  

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

Whole-House Solutions for Existing Homes: Passive Room-to-Room Air Transfer, Fresno, California (Fact Sheet) Building America Whole-House Solutions for Existing Homes: Passive...

325

Passive Housing for an Aggressive Region | Department of Energy  

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

describes the Capital region and the mission of bringing passive houses to the area. A passive house meets rigorous, voluntary energy efficiency standards and requires little...

326

Building America Whole-House Solutions for New Homes: Hydronic...  

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

Building America Whole-House Solutions for New Homes: Hydronic Heating Coil Versus Propane Furnace (Fact Sheet) Building America Whole-House Solutions for New Homes: Hydronic...

327

Before the Subcommittee on Energy and Environment - House Committee...  

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

Environment - House Committee on Science, Space, and Technology Before the Subcommittee on Energy and Environment - House Committee on Science, Space, and Technology Testimony of...

328

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

SciTech Connect (OSTI)

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‚?Ě 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‚?Ě 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‚?Ě was to stimulate the HTS wire industry with, first 1G, then 2G, HTS wire applications. Over the approximately 5 years of ZP‚??s product development program, the amount of HTS wire employed per FCL and its cost as a percentage of the total FCL product content had not dropped substantially from an unsustainable level of more than 50% of the total cost of the FCL, nor had the availability increased (today the availability of 2G wire for commercial applications outside of specific partnerships with the leading 2G wire manufacturers is extremely limited). ZP had projected a very significant commercial potential for FCLs with higher performance and lower costs compared to the initial models built with 1G wire, which would come about from the widespread availability of low-cost, high-performance 2G HTS wire. The potential for 2G wires at greatly reduced performance-based prices compared to 1G HTS conductor held out the potential for the commercial production of FCLs at price and performance levels attractive to the utility industry. However, the price of HTS wire did not drop as expected and today the available quantities of 2G wire are limited, and the price is higher than the currently available supplies of 1G wire. The commercial option for ZP to provide a reliable and reasonably priced FCL to the utility industry is to employ conventional resistive conductor DC electromagnets to bias the FCL. Since the premise of the original funding was to stimulate the HTS wire industry and ZP concluded that copper-based magnets were more economical for the foreseeable future, DOE and ZP decided to mutually terminate the project.

Frank Darmann; Robert Lombaerde; Franco Moriconi; Albert Nelson

2011-10-31T23:59:59.000Z

329

Materials and Components Technology Division research summary, 1992  

SciTech Connect (OSTI)

The Materials and Components Technology Division (MCT) provides a research and development capability for the design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs related to nuclear energy support the development of the Integral Fast Reactor (IFR): life extension and accident analyses for light water reactors (LWRs); fuels development for research and test reactors; fusion reactor first-wall and blanket technology; and safe shipment of hazardous materials. MCT Conservation and Renewables programs include major efforts in high-temperature superconductivity, tribology, nondestructive evaluation (NDE), and thermal sciences. Fossil Energy Programs in MCT include materials development, NDE technology, and Instrumentation design. The division also has a complementary instrumentation effort in support of Arms Control Technology. Individual abstracts have been prepared for the database.

Not Available

1992-11-01T23:59:59.000Z

330

BDDR, a new CEA technological and operating reactor database  

SciTech Connect (OSTI)

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)

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

2013-07-01T23:59:59.000Z

331

Site Characterization Report ORGDP Diffusion Facilities Permanent Shutdown K-700 Power House and K-27 Switch Yard/Switch House  

SciTech Connect (OSTI)

The K-700 Power House area, initially built to supply power to the K-25 gaseous diffusion plant was shutdown and disassembled in the 1960s. This shutdown was initiated by TVA supplying economical power to the diffusion plant complex. As a result of world wide over production of enriched, reactor grade U{sup 235}, the K-27 switch yard and switch house area was placed in standby in 1985. Subsequently, as the future production requirements decreased, the cost of production increased and the separation technologies for other processes improved, the facility was permanently shutdown in December, 1987. This Site Characterization Report is a part of the FY-88 engineering Feasibility Study for placing ORGDP Gaseous Diffusion Process facilities in 'Permanent Shutdown'. It is sponsored by the Department of Energy through Virgil Lowery of Headquarters--Enrichment and through Don Cox of ORO--Enrichment Operations. The primary purpose of these building or site characterization reports is to document, quantify, and map the following potential problems: Asbestos; PCB containing fluids; Oils, coolants, and chemicals; and External contamination. With the documented quantification of the concerns (problems) the Engineering Feasibility Study will then proceed with examining the potential solutions. For this study, permanent shutdown is defined as the securing and/or conditioning of each facility to provide 20 years of safe service with minimal expenditures and, where feasible, also serving DOE's needs for long-term warehousing or other such low-risk use. The K-700 power house series of buildings were either masonry construction or a mix of masonry and wood. The power generating equipment was removed and sold as salvage in the mid 1960s but the buildings and auxiliary equipment were left intact. The nine ancillary buildings in the power house area use early in the Manhattan Project for special research projects, were left intact minus the original special equipment. During the late 1960s and 1970s, some of the abandoned buildings were used for offices, special projects, and storage. Some of the remaining electrical transformers contain PCBs in concentrations less than 500 ppm. Many of the steam and hot water pipes in the buildings are insulated with asbestos insulation, but none of the equipment or buildings have high counts of surface radioactive contamination. The general conditions of the buildings are from fair to poor. Many should be boarded-up to prevent personnel entry and in some cases demolitions would be the safer alternative.

Thomas R.J., Blanchard R.D.

1988-06-13T23:59:59.000Z

332

Inductive coupler for downhole components and method for making same  

DOE Patents [OSTI]

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.

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

2006-10-03T23:59:59.000Z

333

RSMASS-D models: An improved method for estimating reactor and shield mass for space reactor applications  

SciTech Connect (OSTI)

Three relatively simple mathematical models have been developed to estimate minimum reactor and radiation shield masses for liquid-metal-cooled reactors (LMRs), in-core thermionic fuel element (TFE) reactors, and out-of-core thermionic reactors (OTRs). The approach was based on much of the methodology developed for the Reactor/Shield Mass (RSMASS) model. Like the original RSMASS models, the new RSMASS-derivative (RSMASS-D) models use a combination of simple equations derived from reactor physics and other fundamental considerations, along with tabulations of data from more detailed neutron and gamma transport theory computations. All three models vary basic design parameters within a range specified by the user to achieve a parameter choice that yields a minimum mass for the power level and operational time of interest. The impact of critical mass, fuel damage, and thermal limitations are accounted for to determine the required fuel mass. The effect of thermionic limitations are also taken into account for the thermionic reactor models. All major reactor component masses are estimated, as well as instrumentation and control (I&C), boom, and safety system masses. A new shield model was developed and incorporated into all three reactor concept models. The new shield model is more accurate and simpler to use than the approach used in the original RSMASS model. The estimated reactor and shield masses agree with the mass predictions from separate detailed calculations within 15 percent for all three models.

Marshall, A.C.

1997-10-01T23:59:59.000Z

334

Demonstrating Modernism: Richard Neutra's Early Model Houses  

E-Print Network [OSTI]

Neutra, Design for the General Electric Companyís SmallNeutra, Design for the General Electric Companyís Smallsubmitted to the General Electric Companyís Small House

Peltakian, Danielle

2012-01-01T23:59:59.000Z

335

Achieving Sustainable Construction in Affordable Housing  

SciTech Connect (OSTI)

An energy-efficient design and construction checklist and information sheets on energy-efficient design and construction are two products being developed. These products will help affordable housing providers take the first steps toward a whole-house approach to the design and implementation of energy-efficient construction practices. The checklist presents simple and clear guidance on energy improvements that can be readily addressed now by most affordable housing providers. The information sheets complement the checklist by providing installation instructions and material specifications that are accompanied by detailed graphics. The information sheets also identify benefits of recommended energy-efficiency measures and procedures including cost savings and impacts on health and comfort. This paper presents details on the checklist and information sheets and discusses their use in two affordable housing projects.

Barcik, M.K.; Creech, D.B.; Ternes, M.P.

1998-12-07T23:59:59.000Z

336

Retrofitting the Southeast: The Cool Energy House  

SciTech Connect (OSTI)

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.

Zoeller, W.; Shapiro, C.; Vijayakumar, G.; Puttagunta, S.

2013-02-01T23:59:59.000Z

337

Redefining the edge : housing on Chicago's waterfront  

E-Print Network [OSTI]

This thesis proposes an approach to the design of urban housing which uses the public realm to reconcile the various desires of the city for continuous, accessible fabric, the developer for property value raising enhancements, ...

Montalto, Anthony Olindo

1995-01-01T23:59:59.000Z

338

Ceramic pressure housing with metal endcaps  

DOE Patents [OSTI]

A housing 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.

Downing, Jr., John P. (Port Townsand, WA); DeRoos, Bradley G. (Worthington, OH); Hackman, Donald J. (Columbus, OH)

1995-01-01T23:59:59.000Z

339

Ceramic pressure housing with metal endcaps  

DOE Patents [OSTI]

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.

Downing, J.P. Jr.; DeRoos, B.G.; Hackman, D.J.

1995-06-27T23:59:59.000Z

340

" Million U.S. Housing Units"  

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

7 Air-Conditioning Usage Indicators by Climate Zone, 2005" " Million U.S. Housing Units" ,,"Climate Zone1" ,,"Less than 2,000 CDD and --",,,,"2,000 CDD or More and Less than 4,000...

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

" Million U.S. Housing Units" ,,"2005...  

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

7 Air-Conditioning Usage Indicators by Household Income, 2005" " Million U.S. Housing Units" ,,"2005 Household Income",,,,,"Below Poverty Line","Eligible for Federal Assistance1"...

342

Sustainable construction in Mexican housing markets  

E-Print Network [OSTI]

This thesis examines recent developments in Mexico's housing markets as an example of how sustainable construction is being adapted and applied in developing countries. The recognition that the construction, operation, and ...

Jung, Bomee

2007-01-01T23:59:59.000Z

343

Housing Innovation Awards at the Solar Decathlon  

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

the Energy Efficiency Market Buildings.Energy.gov Housing Innovation Awards at the Solar Decathlon Breakfast Presented by BASF Friday, October 4, 2013 8:30-10:30 a.m. Historic...

344

Housing & Residential Life Living & Learning On Campus  

E-Print Network [OSTI]

& recreational equipment · Recycling program Housing amenities #12;· Residence Directors · Assistant Residence or flammable items · Candles/incense · Pets · Decorative lights · Appliances with open heating elements (space

Netoff, Theoden

345

2013 White House Tribal Nations Conference  

Broader source: Energy.gov [DOE]

On Wednesday, November 13, President Obama will host the White House Tribal Nations Conference at the Department of the Interior. The conference will provide leaders from the 566 federally...

346

Incremental housing at the receding suburban fringe  

E-Print Network [OSTI]

The years from 2005-2010 brought two major events that shook the basic assumptions underlying housing delivery in the United States of America. First, Hurricane Katrina and the catastrophic flooding of New Orleans that ...

Lamb, Zachary B

2010-01-01T23:59:59.000Z

347

Affordable Housing for Artists: A Sustainable Prototype  

E-Print Network [OSTI]

Although many architects and builders feel that designing for both sustainability and affordability is impossible, I believe that the only way we can afford to live is sustainably. Through the design of housing for artists, this thesis...

Ness, M.

1998-01-01T23:59:59.000Z

348

City of Indianapolis- EcoHouse Project  

Broader source: Energy.gov [DOE]

In June 2011, the City of Indianapolis announced the availability of the EcoHouse Project, an energy-efficiency loan program for medium- and low-income homeowners in Indianapolis. The Indianapolis...

349

The California Economy: Singing the Housing Blues  

E-Print Network [OSTI]

THE†CALIFORNIA†ECONOMY:†SINGING†THE†HOUSING† BLUES†Many† parts† of† the† economy† are† doing† better† than†towards†2007†the†entire†economy†is†being†threatened†by†the†

Thornberg, Christopher

2007-01-01T23:59:59.000Z

350

Housing for single-parent families  

E-Print Network [OSTI]

This thesis poses the question of how we are to house the family of the future. The concept of the strictly nuclear family as a backbone of our civilization is disintegrating under the onslaught of careers, of divorce, of ...

Johnson, Katrina Rae

1986-01-01T23:59:59.000Z

351

Housing Policy in the United States  

E-Print Network [OSTI]

How to cite this article Quigley, John M. "housing policy inPolicy Debate 7, 673Ė93. Quigley, J. 2000. A decent home:Affairs 1(1), 53Ė100. Quigley, J. and Raphael, S. 2004. Is

Quigley, John M.

2008-01-01T23:59:59.000Z

352

A Decent Home: Housing Policy in Perspective  

E-Print Network [OSTI]

Hanushek, Eric A. , and John M. Quigley. 1981. ďConsumptionKatherine M. , and John M. Quigley. 1999. ďAccessibility andHousing and Urban Policy. John M. Quigley U.S. Congressional

Quigley, John M.

2002-01-01T23:59:59.000Z

353

Housing Policy in the United States  

E-Print Network [OSTI]

to cite this article Quigley, John M. "housing policy in theHE N EW P ALGRAVE ) By John M. Quigley May 2008 These papersin the United States John M. Quigley From The New Palgrave

Quigley, John M.

2008-01-01T23:59:59.000Z

354

2014 White House Tribal Nations Conference  

Broader source: Energy.gov [DOE]

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 federally recognized tribes the opportunity to interact directly with the President and members of the White House Council on Native American Affairs. Each federally recognized tribe will be invited to send one representative to the conference. Additional details about the conference will be released at a later date.

355

Energy efficient industrialized housing research program  

SciTech Connect (OSTI)

This is the second volume of a two volume report on energy efficient industrialized housing. Volume II contains support documentation for Volume I. The following items are included: individual trip reports; software bibliography; industry contacts in the US, Denmark, and Japan; Cost comparison of industrialized housing in the US and Denmark; draft of the final report on the systems analysis for Fleetwood Mobile Home Manufacturers. (SM)

Berg, R.; Brown, G.Z.; Finrow, J.; Kellett, R.; Mc Donald, M.; McGinn, B.; Ryan, P.; Sekiguchi, T. (Oregon Univ., Eugene, OR (USA). Center for Housing Innovation); Chandra, S.; Elshennawy, A.K.; Fairey, P.; Harrison, J.; Maxwell, L.; Roland, J.; Swart, W. (Florida Solar Energy Center, Cape Canaveral, FL (USA))

1989-01-01T23:59:59.000Z

356

Improved vortex reactor system  

DOE Patents [OSTI]

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.

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

1995-05-09T23:59:59.000Z

357

USER SATISFACTION WITH INNOVATIVE COOLING RETROFITS IN SACRAMENTO PUBLIC HOUSING  

E-Print Network [OSTI]

and a housing authority have been retrofitting their buildings with evaporative coolers, ground-source heatpumps

Diamond, Richard

358

Housing & Residential Services Room and Board Rates 20112012  

E-Print Network [OSTI]

Housing & Residential Services Room and Board Rates 2011­2012 Campus housing offers a variety, please view the Housing & Residential Services website at: housing.iit.edu. McCormick Student Village to participate in the Residential 5 meal plan. Winter Break is included in MSV, Gunsaulus Hall and SSV. DAS room

Heller, Barbara

359

Pressurized fluidized bed reactor  

DOE Patents [OSTI]

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.

Isaksson, J.

1996-03-19T23:59:59.000Z

360

Pressurized fluidized bed reactor  

DOE Patents [OSTI]

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.

Isaksson, Juhani (Karhula, FI)

1996-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Tokamak reactor first wall  

DOE Patents [OSTI]

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.

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

1984-11-20T23:59:59.000Z

362

Next Generation Reactors  

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

Nuclear Advances We are coordinating the Generation IV Nuclear Systems Initiative - an international effort to develop the next generation of nuclear power reactors. Skip...

363

Low power reactor for remote applications  

SciTech Connect (OSTI)

A compact, low power reactor is being designed to provide electric power for remote, unattended applications. Because of the high fuel and maintenance costs for conventional power sources such as diesel generators, a reactor power supply appears especially attractive for remote and inaccessible locations. Operating at a thermal power level of 135 kWt, the power supply achieves a gross electrical output of 25 kWe from an organic Rankine cycle (ORC) engine. By intentional selection of design features stressing inherent safety, operation in an unattended mode is possible with minimal risk to the environment. Reliability is achieved through the use of components representing existing, proven technology. Low enrichment uranium particle fuel, in graphite core blocks, cooled by heat pipes coupled to an ORC converter insures long-term, virtually maintenance free, operation of this reactor for remote applications. 10 refs., 7 figs., 3 tabs.

Meier, K.L.; Palmer, R.G.; Kirchner, W.L.

1985-01-01T23:59:59.000Z

364

Materials Degradation in Light Water Reactors: Life After 60,???  

SciTech Connect (OSTI)

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. Degradation of materials in this environment can lead to reduced performance, and in some cases, sudden failure. A recent EPRI-led study interviewed 47 US nuclear utility executives to gauge perspectives on long-term operation of nuclear reactors. Nearly 90% indicated that extensions of reactor lifetimes to beyond 60 years were likely. When polled on the most challenging issues facing further life extension, two-thirds cited plant reliability as the key issue with materials aging and cable/piping as the top concerns for plant reliability. Materials degradation within a nuclear power plant is very complex. There are many different types of materials within the reactor itself: over 25 different metal alloys can be found with can be found within the primary and secondary systems, not to mention the concrete containment vessel, instrumentation and control, and other support facilities. When this diverse set of materials is placed in the complex and harsh environment coupled with load, degradation over an extended life is indeed quite complicated. To address this issue, the USNRC has developed a Progressive Materials Degradation Approach (NUREG/CR-6923). This approach is intended to develop a foundation for appropriate actions to keep materials degradation from adversely impacting component integrity and safety and identify materials and locations where degradation can reasonably be expected in the future. Clearly, materials degradation will impact reactor reliability, availability, and potentially, safe operation. Routine surveillance and component replacement can mitigate these factors, although failures still occur. With reactor life extensions to 60 years or beyond or power uprates, many components must tolerate the reactor environment for even longer times. This may increase susceptibility for most components and may introduce new degradation modes. While all components (except perhaps the reactor vessel) can be replaced, it may not be economically favorable. Therefore, understanding, controlling, and mitigating materials degradation processes are key priorities for reactor operation, power uprate considerations, and life extensions. This document is written to give an overview of some of the materials degradation issues that may be key for extend reactor service life. A detailed description of all the possible forms of degradation is beyond the scope of this short paper and has already been described in other documents (for example, the NUREG/CR-6923). The intent of this document is to present an overview of current materials issues in the existing reactor fleet and a brief analysis of the potential impact of extending life beyond 60 years. Discussion is presented in six distinct areas: (1) Reactor pressure vessel; (2) Reactor core and primary systems; (3) Reactor secondary systems; (4) Weldments; (5) Concrete; and (6) Modeling and simulations. Following each of these areas, some research thrust directions to help identify and mitigate lifetime extension issues are proposed. Note that while piping and cabling are important for extended service, these components are discussed in more depth in a separate paper. Further, the materials degradation issues associated with fuel cladding and fuel assemblies are not discussed in this section as these components are replaced periodically and will not influence the overall lifetime of the reactor.

Busby, Jeremy T [ORNL; Nanstad, Randy K [ORNL; Stoller, Roger E [ORNL; Feng, Zhili [ORNL; Naus, Dan J [ORNL

2008-04-01T23:59:59.000Z

365

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

Office of Scientific and Technical Information (OSTI)

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor Design and Feasibility Problem Re-direct Destination: Temp Data Fields Rosen, M. A.; Coburn, D. B.; Flynn, T....

366

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...

367

Portfolio for fast reactor collaboration  

SciTech Connect (OSTI)

The development of the LMFBR type reactor in the United Kingdom is reviewed. Design characteristics of a commercial demonstration fast reactor are presented and compared with the Super Phenix reactor.

Rippon, S.

1981-12-01T23:59:59.000Z

368

REACTOR OPERATIONS AND CONTROL  

E-Print Network [OSTI]

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

P√°zsit, Imre

369

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect (OSTI)

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue Universityís Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called Userís Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. Userís week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

370

Control of Reactor and Separator, with Recycle T. Larsson, S. Skogestad and ChengChing Yu y  

E-Print Network [OSTI]

Control of Reactor and Separator, with Recycle T. Larsson, S. Skogestad #3; and Cheng­Ching Yu y This paper looks at control of a plant that consists of a reactor, separator and recycle of unreacted reactor where component A is converted to a product and the amount converted is given by k(T )Mz [mole

Skogestad, Sigurd

371

Two component-three dimensional catalysis  

DOE Patents [OSTI]

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.

Schwartz, Michael (Boulder, CO); White, James H. (Boulder, CO); Sammells, Anthony F. (Boulder, CO)

2002-01-01T23:59:59.000Z

372

Reactor & Nuclear Systems Publications | ORNL  

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

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

373

Reed Reactor Facility. Final report  

SciTech Connect (OSTI)

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

Frantz, S.G.

1994-12-31T23:59:59.000Z

374

Risk Management for Sodium Fast Reactors.  

SciTech Connect (OSTI)

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.

Denman, Matthew R; Groth, Katrina; Cardoni, Jeffrey N; Wheeler, Timothy A.

2015-01-01T23:59:59.000Z

375

On Perturbation Components Correspondence between Diffusion and Transport  

SciTech Connect (OSTI)

We have established a correspondence between perturbation components in diffusion and transport theory. In particular we have established the correspondence between the leakage perturbation component of the diffusion theory to that of the group self scattering in transport theory. This has been confirmed by practical applications on sodium void reactivity calculations of fast reactors. Why this is important for current investigations? Recently, there has been a renewed interest in designing fast reactors where the sodium void reactivity coefficient is minimized. In particular the ASTRID8,9 reactor concept has been optimized with this goal in mind. The correspondence on the leakage term that has been established here has a twofold implication for the design of this kind of reactors. First, this type of reactor has a radial reflector; therefore, as shown before, the sodium void reactivity coefficient calculation requires the use of transport theory. The minimization of the sodium reactivity coefficient is normally done by increasing the leakage component that has a negative sign. The correspondence established in this paper allows to directly look at this component in transport theory. The second implication is related to the uncertainty evaluation on sodium void reactivity. As it has shown before, the total sodium void reactivity effect is the result of a large compensation (opposite sign) between the scattering (called often spectral) component and the leakage one. Consequently, one has to evaluate separately the uncertainty on each separate component and then combine them statistically. If one wants to compute the cross section sensitivity coefficients of the two different components, the formulation established in this paper allows to achieve this goal by playing on the contribution to the sodium void reactivity coming from the group self scattering of the sodium cross section.

G. Palmiotti

2012-11-01T23:59:59.000Z

376

RSMASS: A preliminary reactor/shield mass model for SDI applications  

SciTech Connect (OSTI)

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, specific power limits, or fuel burnup 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 provide good mass estimates for 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.

Marshall, A.C.

1986-08-01T23:59:59.000Z

377

Physics of reactor safety. Quarterly report, October-December 1982. [LMFBR; Argonne National Laboratory  

SciTech Connect (OSTI)

This Quarterly progress report summarizes work done during the months of October-December 1982 in Argonne National Laboratory's Applied Physics and Components Technology Divisions for the Division of Reactor Safety Research of the US Nuclear Regulatory Commission. The work in the Applied Physics Division includes reports on reactor safety modeling and assessment by members of the Reactor Safety Appraisals Section. Work on reactor core thermal-hydraulics is performed in ANL's Components Technology Division, emphasizing 3-dimensional code development for LMFBR accidents under natural convection conditions. An executive summary is provided including a statement of the findings and recommendations of the report.

Not Available

1983-02-01T23:59:59.000Z

378

Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico  

SciTech Connect (OSTI)

The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program.

Salazar, M.; Elder, J.

1992-08-01T23:59:59.000Z

379

105-H Reactor Interim Safe Storage Project Final Report  

SciTech Connect (OSTI)

The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D&D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

E.G. Ison

2008-11-08T23:59:59.000Z

380

Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors  

SciTech Connect (OSTI)

This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activation levels of irradiated reactor vessel internals hardware. The purpose of the analysis is to produce data for the Department of Energy`s Greater-Than-Class C Low-Level Radioactive Waste Program. An MCNP model was developed to analyze the Yankee Rowe reactor facility. The model incorporates reactor geometry, material compositions, and operating history data acquired from Yankee Atomic Electric Company. In addition to the base activation analysis, parametric studies were performed to determine the sensitivity of activation to specific parameters. A component sampling plan was also developed to validate the model results, although the plan was not implemented. The calculations for the Yankee Rowe reactor predict that only the core baffle and the core support plates will be activated to levels above the Class C limits. The parametric calculations show, however, that the large uncertainties in the material compositions could cause errors in the estimates that could also increase the estimated activation level of the core barrel to above the Class C limits. Extrapolation of the results to other reactor facilities indicates that in addition to the baffle and support plates, core barrels may also be activated to above Class C limits; however the classification will depend on the specific operating conditions of the reactor and the specific material compositions of the metal, as well as the use of allowable concentration averaging practices in packaging and classifying the waste.

Love, E.F.; Pauley, K.A.; Reid, B.D.

1995-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR)  

SciTech Connect (OSTI)

This paper is an abstract of the work performed in the frame of the development of the IPSN/GRS approach in view of the EPR conceptual safety features. EPR is a pressurized water reactor which will be based on the experience gained by utilities and designers in France and in Germany. The reactor coolant boundary of a PWR includes the reactor pressure vessel (RPV), those parts of the steam generators (SGs) which contain primary coolant, the pressurizer (PSR), the reactor coolant pumps (RCPs), the main coolant lines (MCLs) with their branches as well as the other connecting pipes and all branching pipes including the second isolation valves. The present work covering the integrity of the reactor coolant boundary is mainly restricted to the integrity of the main coolant lines (MCLs) and reflects the design requirements for the main components of the reactor coolant boundary. In the following the conceptual aspects, i.e. design, manufacture, construction and operation, will be assessed. A main aspect is the definition of break postulates regarding overall safety implications.

Goetsch, D.; Bieniussa, K.; Schulz, H.; Jalouneix, J.

1997-04-01T23:59:59.000Z

382

Critical pulse power components  

SciTech Connect (OSTI)

Critical components for pulsed power conditioning systems will be reviewed. Particular emphasis will be placed on those components requiring significant development efforts. Capacitors, for example, are one of the weakest elements in high-power pulsed systems, especially when operation at high-repetition frequencies for extended periods of time are necessary. Switches are by far the weakest active components of pulse power systems. In particular, opening switches are essentially nonexistent for most applications. Insulaton in all systems and components requires development and improvement. Efforts under way in technology base development of pulse power components will be discussed.

Sarjeant, W.J.; Rohwein, G.J.

1981-01-01T23:59:59.000Z

383

Energy efficient industrialized housing research program  

SciTech Connect (OSTI)

This report summarizes three documents: Multiyear Research Plan, Volume I FY 1989 Task Reports, and Volume II Appendices. These documents describe tasks that were undertaken from November 1988 to December 1989, the first year of the project. Those tasks were: (1) the formation of a steering committee, (2) the development of a multiyear research plan, (3) analysis of the US industrialized housing industry, (4) assessment of foreign technology, (5) assessment of industrial applications, (6) analysis of computerized design and evaluation tools, and (7) assessment of energy performance of baseline and advanced industrialized housing concepts. While this document summarizes information developed in each task area, it doesn't review task by task, as Volume I FY 1989 Task Reports does, but rather treats the subject of energy efficient industrialized housing as a whole to give the reader a more coherent view. 7 figs., 9 refs.

Berg, R.; Brown, G.Z.; Finrow, J.; Kellett, R.; McDonald, M.; McGinn, B.; Ryan, P.; Sekiguchi, Tomoko (Oregon Univ., Eugene, OR (USA). Center for Housing Innovation); Chandra, S.; Elshennawy, A.K.; Fairey, P.; Harrison, J.; Maxwell, L.; Roland, J.; Swart, W. (Florida Solar Energy Center, Cape Canaveral, FL (USA))

1990-02-01T23:59:59.000Z

384

Nuclear reactor control column  

DOE Patents [OSTI]

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.

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

385

Nuclear reactor control column  

SciTech Connect (OSTI)

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

Bachovchin, D.M.

1982-08-10T23:59:59.000Z

386

Reactor Safety Research Programs  

SciTech Connect (OSTI)

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.

Edler, S. K.

1981-07-01T23:59:59.000Z

387

Reactor User Interface Technology Development Roadmaps for a High Temperature Gas-Cooled Reactor Outlet Temperature of 750 degrees C  

SciTech Connect (OSTI)

This report evaluates the technology readiness of the interface components that are required to transfer high-temperature heat from a High Temperature Gas-Cooled Reactor (HTGR) to selected industrial applications. This report assumes that the HTGR operates at a reactor outlet temperature of 750įC and provides electricity and/or process heat at 700įC to conventional process applications, including the production of hydrogen.

Ian Mckirdy

2010-12-01T23:59:59.000Z

388

Building America Industrialized Housing Partnership (BAIHP II)  

SciTech Connect (OSTI)

This report summarizes the work conducted by the Building America Industrialized Housing Partnership (BAIHP - www.baihp.org) during the final budget period (BP5) of our contract, January 1, 2010 to November 30, 2010. Highlights from the four previous budget periods are included for context. BAIHP is led by the Florida Solar Energy Center (FSEC) of the University of Central Florida. With over 50 Industry Partners including factory and site builders, work in BP5 was performed in six tasks areas: Building America System Research Management, Documentation and Technical Support; System Performance Evaluations; Prototype House Evaluations; Initial Community Scale Evaluations; Project Closeout, Final Review of BA Communities; and Other Research Activities.

Abernethy, Bob; Chandra, Subrato; Baden, Steven; Cummings, Jim; Cummings, Jamie; Beal, David; Chasar, David; Colon, Carlos; Dutton, Wanda; Fairey, Philip; Fonorow, Ken; Gil, Camilo; Gordon, Andrew; Hoak, David; Kerr, Ryan; Peeks, Brady; Kosar, Douglas; Hewes, Tom; Kalaghchy, Safvat; Lubliner, Mike; Martin, Eric; McIlvaine, Janet; Moyer, Neil; Liguori, Sabrina; Parker, Danny; Sherwin, John; Stroer, Dennis; Thomas-Rees, Stephanie; Daniel, Danielle; McIlvaine, Janet

2010-11-30T23:59:59.000Z

389

2011 EnergyValue Housing Award Report  

SciTech Connect (OSTI)

This report details the simulation tool(s) and energy modeling methodology followed in making the energy efficiency estimates and documents the estimated performance of the EVHA award winning houses in comparison with the Building America Benchmark and the associated House Simulation Protocols. A summary of each building and its features is included with a brief description of the project and the judges' comments. The purpose of this report is to assess the energy performance of the 2011 EVHA winners as well as align the EVHA Program with the Building America Program.

Sagan, D.; Del Bianco, M.; Wood, A.

2012-10-01T23:59:59.000Z

390

Open House | Photosynthetic Antenna Research Center  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006 The 2002 WholesaleEnergy's 1000Department ofOpen House Open House

391

Open House | Princeton Plasma Physics Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006 The 2002 WholesaleEnergy's 1000Department ofOpen House Open House

392

2014 Building America House Simulation Protocols  

SciTech Connect (OSTI)

As BA has grown to include a large and diverse cross-section of the home building and retrofit industries, it has become more important to develop accurate, consistent analysis techniques to measure progress towards the program's goals. The House Simulation Protocol (HSP) document provides guidance to program partners and managers so they can compare energy savings for new construction and retrofit projects. The HSP provides the program with analysis methods that are proven to be effective and reliable in investigating the energy use of advanced energy systems and of entire houses.

Wilson, E.; Engebrecht-Metzger, C.; Horowitz, S.; Hendron, R.

2014-03-01T23:59:59.000Z

393

Nuclear reactor reflector  

DOE Patents [OSTI]

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

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

1994-01-01T23:59:59.000Z

394

Nuclear reactor reflector  

DOE Patents [OSTI]

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

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

1994-06-07T23:59:59.000Z

395

Fast Breeder Reactor studies  

SciTech Connect (OSTI)

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

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

1980-07-01T23:59:59.000Z

396

Microfluidic electrochemical reactors  

DOE Patents [OSTI]

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

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

2011-03-22T23:59:59.000Z

397

The Development of Improved Energy Efficient Housing for Thailand Utilizing Renewable Energy Technology  

E-Print Network [OSTI]

SimBuild 2004, IBPSA-USA National Conference, Boulder, CO, August 4-6th, 2004, p. 1 THE DEVELOPMENT OF IMPROVED ENERGY EFFICIENT 1 HOUSING FOR THAILAND UTILIZING RENEWABLE ENERGY TECHNOLOGY 2 3... The paper reports on the results of research to reduce energy consumption in residential buildings in a hot and humid climate region (Thailand) using efficient architectural building components, energy efficient building systems, and renewable energy...

Rasisuttha, S.; Haberl, J.

398

Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge  

SciTech Connect (OSTI)

The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O/sub 2/, N/sub 2/, etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized.

Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

1981-05-01T23:59:59.000Z

399

Housing Price Dynamics in Time and Space: Predictability, Liquidity and Investor Returns  

E-Print Network [OSTI]

C. A. (1996). OFHEO house price indexes: HPI technicalsense of elevated housing prices. Federal Reserve Bank ofJ. E. (1991). Measuring prices in retransaction housing

Hwang, Min; Quigley, John M.

2010-01-01T23:59:59.000Z

400

Holistic revitalization in small post-industrial cities : tools for urban housing development  

E-Print Network [OSTI]

For generations, housing programs have sought to utilize redevelopment projects to accomplish broader community revitalization goals. Contemporary affordable housing practice embodies this idea in large housing development ...

Beam, Jeffrey (Jeffrey J.)

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Reactor hot spot analysis  

SciTech Connect (OSTI)

The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

Vilim, R.B.

1985-08-01T23:59:59.000Z

402

P Reactor Grouting  

SciTech Connect (OSTI)

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

None

2010-01-01T23:59:59.000Z

403

RSMASS-D: Reactor and shield mass minimization models  

SciTech Connect (OSTI)

Three relatively simple mathematical models have been developed to estimate minimum reactor and radiation shield masses for liquid metal cooled reactors (LMR's), in-core thermionic reactors (TI's) and out-of-core thermionic reactors (OTR's). The approach was based on much of the methodology developed for the RSMASS model (Marshall 1986). The models use a combination of simple equations derived from reactor physics and other fundamental considerations along with tabulations of data from more detailed neutron and gamma transport theory computations. All three models vary basic design parameters within an allowed range to achieve a parameter choice which yields a minimum mass for the power level and operational time of interest. The impact of critical mass, fuel damage and thermal limitations are accounted for in the computations. Thermionic requirements are also accounted for in the thermionic reactor models. All major reactor component masses are estimated as well as instrumentation and control (I C), boom and safety system mass. A new shield model was developed and incorporated into all three models. The new shield model is more accurate and simpler to use than the approach used in the original RSMASS model. The estimated reactor and shield masses agree with the mass predictions from detailed calculations within 16 percent for all three models.

Marshall, A.C. (Department 0410 Sandia National Laboratories (USA) NE-52 The Department of Energy, Germantown Building, Washington, D.C. 20545 (USA)); Gallup, D.R. (Division 6472 Sandia National Laboratories, P.O. Box 5800, Albuquerque, New Mexico 87185 (USA))

1991-01-01T23:59:59.000Z

404

Nuclear reactor control  

SciTech Connect (OSTI)

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

Ingham, R.V.

1980-01-01T23:59:59.000Z

405

Polymerization reactor control  

SciTech Connect (OSTI)

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

Ray, W.H.

1985-01-01T23:59:59.000Z

406

Molten metal reactors  

DOE Patents [OSTI]

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

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

2013-11-05T23:59:59.000Z

407

White House Forum on Minorities in Energy  

Broader source: Energy.gov [DOE]

At the White House Forum on Minorities in Energy, Secretary Moniz honored the Ambassadors of the Minorities in Energy Initiative -- senior-level leaders dedicated to advancing underrepresented groups in the energy sector. Panel discussions at the event covered a wide range of issues including increasing participation in STEM fields by minorities and engaging communities in energy and climate issues.

408

1 Old Faculty Club 2 Boyd House  

E-Print Network [OSTI]

, Visitor Center 23 Carpenter Hall 24 Carson Engineering Center 25 Devon Energy Hall 26 Felgar Hall 27 Swim Center 76 Cross Center 77 OCCE Cross Center Main 78 Coats Hall, Law 79 Sam Noble Oklahoma MuseumCAMPUS MAP 1 Old Faculty Club 2 Boyd House 3 Whitehand Hall 4 Catlett Music Center 5 Fred Jones Jr

Xue, Ming

409

Bachelor Thesis Future sustainable terraced houses  

E-Print Network [OSTI]

Cardiff University August 4, 2014 #12;Colophon Title: Future sustainable residential buildings in Cardiff a first introduction about sustainability in the building sector. Collecting data about the future climateBachelor Thesis Future sustainable terraced houses in Cardiff Karin Ernst University of Twente

Vellekoop, Michel

410

109 Chase Ave. 215 W. House  

E-Print Network [OSTI]

- Book Store NC Northside Gravely Hospital Campus NC Neuro- Plant #1 Hospital Chiller Hospital Chiller Hill Whitehead Phillips OldWest Polk Place Murphey Grimes Battle Graham Chiller 1307 Craige James Koury Quad Graham Everett Stacy McCaskill Auditorium Chiller Center for Knapp-Sanders Cabin House Quail Hill

McLaughlin, Richard M.

411

SUMMER ARCHITECTURE ACADEMY HOUSING AND MEDICAL  

E-Print Network [OSTI]

SUMMER ARCHITECTURE ACADEMY HOUSING AND MEDICAL INFORMATION AND AUTHORIZATION FOR STUDENTS UNDER 18 YEARS OLD To: Summer Architecture Academy students and parents From: University of Oregon Department of Architecture We are looking forward to another exciting and educational Summer Architecture Academy. Many

412

Life Cycle Cost Housing Need and Sustainability  

E-Print Network [OSTI]

Life Cycle Cost Housing Need and Sustainability Abstract: Jordan is actually facing a rapid urban became difficult to sustain especially concerning the slum areas and the environmental pollution due which could contribute to increase the productivity and sustainability taking into consideration

413

University Housing University of South Carolina  

E-Print Network [OSTI]

at the University of South Carolina. It is designed to be a sustainable living and learning environment and employs a more sustainable campus and society. These programming efforts are a collaboration among University Housing, Sustainable Carolina and other campus partners. Community Features · Attending events

Almor, Amit

414

Illinois Institute of Technology Housing & Residential Services  

E-Print Network [OSTI]

Illinois Institute of Technology Housing & Residential Services Student Guide to 20102011 & assemble beds, etc); · Remove posters, paper, tape, sticky tack, etc from all surfaces; · Wipe clean all walls and furniture; · If living in an apartment, wipe clean the kitchen appliances, cabinets

Heller, Barbara

415

Federal credit and insurance programs: Housing  

E-Print Network [OSTI]

T . LO U I S R E V I E W Quigley Bunce, Harold L. ; Capone,W J U LY / A U G U S T Quigley Working Paper 294, University2005. Kain, John F. and Quigley, John M. Housing Markets and

Quigley, John M.

2006-01-01T23:59:59.000Z

416

Federal Credit and Insurance Programs: Housing  

E-Print Network [OSTI]

T . LO U I S R E V I E W Quigley Bunce, Harold L. ; Capone,W J U LY / A U G U S T Quigley Working Paper 294, University2005. Kain, John F. and Quigley, John M. Housing Markets and

Quigley, John M.

2006-01-01T23:59:59.000Z

417

Campbell Creek Research Houses: A Transformational Impact  

E-Print Network [OSTI]

cathederalized sealed with spray foam and spray fiberglass and sealed Heat pump water heater Compact fluorescent; EPS = expanded polystyrene; HP = heat pump; HPWH = heat pump water heater; HSPF = heating seasonal Meets 2006 IECC Retrofit House (energy savings of 37%) 3 ton heat pump, up to 20 SEER and 13 HSPF Attic

Oak Ridge National Laboratory

418

STARTLINK COMPOSITE HOUSING J. A. Hutchinson1  

E-Print Network [OSTI]

lower embodied energy than a timber frame building, avoids site waste (20-25% of all UK waste friendly and up to 25% cheaper than traditional building. Keywords: Cost, Speed, Energy, Waste, Environment) and reduces shipping and assembly costs because of the light weight. Lightweight houses are easier to build

Mottram, Toby

419

Evaluation of Integrated High Temperature Component Testing Needs  

SciTech Connect (OSTI)

This paper describes the requirements for a large-scale component test capability to support the development of advanced nuclear reactor technology and their adaptation to commercial applications that advance U.S. energy economy, reliability, and security and reduce carbon emissions.

Rafael Soto; David Duncan; Vincent Tonc

2009-05-01T23:59:59.000Z

420

UNSUPERVISED CLUSTERING FOR FAULT DIAGNOSIS IN NUCLEAR POWER PLANT COMPONENTS  

E-Print Network [OSTI]

1 UNSUPERVISED CLUSTERING FOR FAULT DIAGNOSIS IN NUCLEAR POWER PLANT COMPONENTS Piero Baraldi1 of prototypical behaviors. Its performance is tested with respect to an artificial case study and then applied on transients originated by different faults in the pressurizer of a nuclear power reactor. Key Words: Fault

Boyer, Edmond

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

F Reactor Inspection  

SciTech Connect (OSTI)

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

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-10-29T23:59:59.000Z

422

Reactor Safety Research Programs  

SciTech Connect (OSTI)

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

Dotson, CW

1980-08-01T23:59:59.000Z

423

F Reactor Inspection  

ScienceCinema (OSTI)

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

Grindstaff, Keith; Hathaway, Boyd; Wilson, Mike

2014-11-24T23:59:59.000Z

424

Deleveraging domesticity : incremental design forays on middle income housing  

E-Print Network [OSTI]

Housing today has little do with architecture. Design is a currency of services, while housing today is intensively packaged as a consumer good. It is packaged with land as speculative real-estate, and bundled abstractly ...

Miller, Christopher M., M. Arch. (Christopher Michael). Massachusetts Institute of Technology

2013-01-01T23:59:59.000Z

425

Race to Zero Design Competition Webinar: Housing Design Best...  

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

Race to Zero Design Competition Webinar: Housing Design Best Practices Race to Zero Design Competition Webinar: Housing Design Best Practices November 18, 2014 1:00PM to 2:30PM EST...

426

2014-07-08 Issuance: ASRAC Manufactured Housing Working Group...  

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

7-08 Issuance: ASRAC Manufactured Housing Working Group; Notice of Membership 2014-07-08 Issuance: ASRAC Manufactured Housing Working Group; Notice of Membership This document is a...

427

Women at the White House Talk Climate and Energy Solutions |...  

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

Women at the White House Talk Climate and Energy Solutions Women at the White House Talk Climate and Energy Solutions May 31, 2013 - 2:19pm Addthis April Saylor April Saylor Former...

428

Statement from the White House Press Secretary on the Ongoing...  

Energy Savers [EERE]

the White House Press Secretary on the Ongoing U.S. Response to the Earthquakes and Tsunami in Japan Statement from the White House Press Secretary on the Ongoing U.S. Response to...

429

2014 White House Tribal Nations Conference | Department of Energy  

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

White House Tribal Nations Conference 2014 White House Tribal Nations Conference December 3, 2014 9:00AM to 5:00PM EST On Wednesday, December 3, President Obama will host the 2014...

430

White House Blog Post on the President's "Better Buildings Initiative...  

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

White House Blog Post on the President's "Better Buildings Initiative" White House Blog Post on the President's "Better Buildings Initiative" February 4, 2011 - 12:00am Addthis In...

431

White House Highlights Two Energy-Slashing, Open Data Initiatives...  

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

White House Highlights Two Energy-Slashing, Open Data Initiatives White House Highlights Two Energy-Slashing, Open Data Initiatives May 28, 2014 - 10:22am Addthis The Buildings...

432

Keynote Address: Cristin Dorgelo, White House Office of Science...  

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

Cristin Dorgelo, White House Office of Science and Technology Policy Keynote Address: Cristin Dorgelo, White House Office of Science and Technology Policy May 21, 2014 2:20PM to...

433

Keynote Address: Ali Zaidi, the White House Domestic Policy Council...  

Energy Savers [EERE]

Ali Zaidi, the White House Domestic Policy Council Keynote Address: Ali Zaidi, the White House Domestic Policy Council May 21, 2014 2:05PM to 2:30PM PDT Pacific Ballroom Keynote...

434

LIVE from the White House Science Fair | Department of Energy  

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

LIVE from the White House Science Fair LIVE from the White House Science Fair October 18, 2010 - 11:31am Addthis John Schueler John Schueler Former New Media Specialist, Office of...

435

Green luxury student housing : a real estate feasibility study  

E-Print Network [OSTI]

The primary purpose of this thesis is to estimate the demand for student housing that focuses on upperclass undergraduate and graduate students who typically shy away from dormitory housing. The initial chapters provide a ...

Pace, Matthew E. (Matthew Edward)

2007-01-01T23:59:59.000Z

436

Community opposition to affordable housing : jamming the system  

E-Print Network [OSTI]

This thesis explores community opposition to affordable housing in the suburban communities of Massachusetts. In the twenty years since Chapter 774 was enacted, a significant amount of affordable housing has been developed. ...

Dash, Stuart David

1989-01-01T23:59:59.000Z

437

Building America Whole-House Solutions for New Homes: Imagine...  

Office of Environmental Management (EM)

Whole-House Solutions for New Homes: Imagine Homes, San Antonio, Texas Building America Whole-House Solutions for New Homes: Imagine Homes, San Antonio, Texas Case study of Imagine...

438

In search of an affordable housing system for Shanghai, China  

E-Print Network [OSTI]

In 1998, the Chinese government abandoned the danwei ("work-unit") housing allocation system and fully privatized the housing market. Since then, the residential price has never stopped increasing despite the past financial ...

Sun, Linyun

2011-01-01T23:59:59.000Z

439

Upgrading : an alternative approach towards housing reform in China  

E-Print Network [OSTI]

The thesis is a study on urban housing upgrading in China. The main objective is to look at upgrading, which has been widely used in many developing countries, as an alternative approach to solving the existing urban housing ...

He, Fang, 1956-

1989-01-01T23:59:59.000Z

440

Passivhus Norden 2008 1st Nordic passive house conference  

E-Print Network [OSTI]

-Efficiency Heat Pump Water Heater System for Apartment Buildings of Passive House Standard...........57 SESSION 3:00 J√łrn Stene CO2 Heat Pump System for Space Heating and Hot Water Heating in Low-Energy Houses

Hansen, René Rydhof

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Transformation of the courtyard house--low-rise high density urban housing in Korea  

E-Print Network [OSTI]

The idea of low-rise high-density urban housing is based on two fundamental objectives: 1) To provide higher density by intensifying land use as urban growth escalates at an unprecedented rate. 2) To reconsider the essential ...

Park, Gene S. (Gene Sungjin)

1987-01-01T23:59:59.000Z

442

Housing with authority : the role of public and private architects in public housing in Delhi  

E-Print Network [OSTI]

The main concern of this thesis is the role of the architect in the design and production of public housing. The argument presented here is that the method of procurement of architectural skills affects the architectural ...

Gupta, Soni

1991-01-01T23:59:59.000Z

443

New housing in old Chinatown : barriers and incentives to affordable housing development  

E-Print Network [OSTI]

In the 1970s and 80s, the rapid development of San Francisco's Financial District encroached upon Chinatown's intimately-scaled neighborhood. Developers took whole city blocks that housed low-income immigrants to build the ...

Tan, Bryant

2008-01-01T23:59:59.000Z

444

Chinese housing mixology : considerations for the successful development of mixed-income housing  

E-Print Network [OSTI]

In recent years, the Chinese government transformed their national system of housing provision and introduced market mechanisms. The consequent boom in residential real estate development and the emergence of speculative ...

Chan, Janelle (Janelle Jie-Ying)

2007-01-01T23:59:59.000Z

445

University of Central Florida Housing and Residence Life  

E-Print Network [OSTI]

:______________________________________________________________ Phone#:________________________ Cell Phone #:_______________________ Fax #:____________________________E#: _______________________Cell Phone #:_____________________ Fax #:______________________E-mail:_____________________ Housing:____ _________________________ Company Intern Coordinator/Sponsor: ______________________________ Office Phone

Kaup, David J.

446

Pillsbury Court Application Temporary Housing Twin Cities Campus  

E-Print Network [OSTI]

University of Minnesota payroll, explain source of funding: For Office Use Only: Department of Housing: MAIL OR FAX Housing and Residential Life (612) 6246987 University of Minnesota Comstock Hall Telephone Number Date First Appointed to University Earliest Desired Housing Date If not paid through

Amin, S. Massoud

447

THE WHITE HOUSE Office of the Press Secretary  

E-Print Network [OSTI]

THE WHITE HOUSE Office of the Press Secretary FOR IMMEDIATE RELEASE September 30, 2013 President for Scholars Laura Paulson ­ Member, Committee for the Preservation of the White House Quyen D. Chu ­ Member of Minnesota. Laura Paulson, Appointee for Member, Committee for the Preservation of the White House Laura

Wisconsin at Madison, University of

448

USDA Grants to Help Repair Housing in Rural Areas  

Broader source: Energy.gov [DOE]

The U.S. Department of Agriculture (USDA) is accepting applications for the Housing Preservation Grant program, which provides funding to repair low-income housing, rental properties, or co-op owned housing. Eligible sponsors include state agencies, local government, Tribes, and nonprofits.

449

Houston, Texas design/build house. Case study report  

SciTech Connect (OSTI)

The task activities relating to the Houston house, including problems, constructive comments, and successes, are described. Included in appendices are: cost data, methodology for ranking cities, house information sheet, thermal performance analysis, architectural information release, press releases and news clippings, and house pictures. One appendix was abstracted separately. (MHR)

Borden, J. O.; Porter, C. B. [comps.] [comps.

1981-06-01T23:59:59.000Z

450

Natural Ventilation Design for Houses in Thailand Chalermwat Tantasavasdia  

E-Print Network [OSTI]

This paper explores the potential of using natural ventilation as a passive cooling system for new house windows in suburban houses can be opened. Passive cooling design elements are mostly ignored in modern1 Natural Ventilation Design for Houses in Thailand Chalermwat Tantasavasdia , Jelena Srebricb

Chen, Qingyan "Yan"

451

Dual-phase reactor plant with partitioned isolation condenser  

DOE Patents [OSTI]

A nuclear energy plant housing a boiling-water reactor utilizes an isolation condenser in which a single chamber is partitioned into a distributor plenum and a collector plenum. Steam accumulates in the distributor plenum and is conveyed to the collector plenum through an annular manifold that includes tubes extending through a condenser pool. The tubes provide for a transfer of heat from the steam, forming a condensate. The chamber has a disk-shaped base, a cylindrical sidewall, and a semispherical top. This geometry results in a compact design that exhibits significant performance and cost advantages over prior designs.

Hui, Marvin M. (Cupertino, CA)

1992-01-01T23:59:59.000Z

452

Small Modular Reactor Report (SEAB) | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomenthe House Committee on Energy andDepartment ofAn Audience ofobjectiveReactorIn his

453

Mothers' perceptions of housing space : an analysis of 3 married student housing sites: Eastgate, Westgate and Peabody Terrace  

E-Print Network [OSTI]

What is a good housing environment for nurturing, a place where the physical environment reinforces the lives of both parents and child? This thesis looks at three married student housing sites in Cambridge, Massachusetts, ...

Racki, Reena

1974-01-01T23:59:59.000Z

454

Strategizing for housing : an investigation of the production and regulation of low-income housing in the suburgs of Beirut  

E-Print Network [OSTI]

The current consensus in housing policy recognizes the importance of learning from rather than about informal settlements. To serve this end, this dissertation presents a novel methodology for investigating land and housing ...

Fawaz, Mona M., 1972-

2004-01-01T23:59:59.000Z

455

Designing housing in the third world : a prototype for housing the Maquiladora workers in the northern cities of Mexico  

E-Print Network [OSTI]

The difficulty in designing low-income housing is !hat. it will not sit quietly, other problems keep Jostling about it. To design low-income housing one must consider the extreme conditions of poverty and urban problems, ...

Vargas, Rodrigo M. (Rodrigo Manuel)

1993-01-01T23:59:59.000Z

456

REACTOR GROUT THERMAL PROPERTIES  

SciTech Connect (OSTI)

Savannah River Site has five dormant nuclear production reactors. Long term disposition will require filling some reactor buildings with grout up to ground level. Portland cement based grout will be used to fill the buildings with the exception of some reactor tanks. Some reactor tanks contain significant quantities of aluminum which could react with Portland cement based grout to form hydrogen. Hydrogen production is a safety concern and gas generation could also compromise the structural integrity of the grout pour. Therefore, it was necessary to develop a non-Portland cement grout to fill reactors that contain significant quantities of aluminum. Grouts generate heat when they set, so the potential exists for large temperature increases in a large pour, which could compromise the integrity of the pour. The primary purpose of the testing reported here was to measure heat of hydration, specific heat, thermal conductivity and density of various reactor grouts under consideration so that these properties could be used to model transient heat transfer for different pouring strategies. A secondary purpose was to make qualitative judgments of grout pourability and hardened strength. Some reactor grout formulations were unacceptable because they generated too much heat, or started setting too fast, or required too long to harden or were too weak. The formulation called 102H had the best combination of characteristics. It is a Calcium Alumino-Sulfate grout that contains Ciment Fondu (calcium aluminate cement), Plaster of Paris (calcium sulfate hemihydrate), sand, Class F fly ash, boric acid and small quantities of additives. This composition afforded about ten hours of working time. Heat release began at 12 hours and was complete by 24 hours. The adiabatic temperature rise was 54 C which was within specification. The final product was hard and displayed no visible segregation. The density and maximum particle size were within specification.

Steimke, J.; Qureshi, Z.; Restivo, M.; Guerrero, H.

2011-01-28T23:59:59.000Z

457

TREAT (Transient Reactor Test Facility) reactor control rod scram system simulations and testing  

SciTech Connect (OSTI)

Air cylinders moving heavy components (100 to 300 lbs) at high speeds (above 300 in/sec) present a formidable end-cushion-shock problem. With no speed control, the moving components can reach over 600 in/sec if the air cylinder has a 5 ft stroke. This paper presents an overview of a successful upgrade modification to an existing reactor control rod drive design using a computer model to simulate the modified system performance for system design analysis. This design uses a high speed air cylinder to rapidly insert control rods (278 lb moved 5 ft in less than 300 msec) to scram an air-cooled test reactor. Included is information about the computer models developed to simulate high-speed air cylinder operation and a unique new speed control and end cushion design. A patent application is pending with the US Patent Trade Mark Office for this system (DOE case number S-68,622). The evolution of the design, from computer simulations thru operational testing in a test stand (simulating in-reactor operating conditions) to installation and use in the reactor, is also described. 6 figs.

Solbrig, C.W.; Stevens, W.W.

1990-01-01T23:59:59.000Z

458

Current Abstracts Nuclear Reactors and Technology  

SciTech Connect (OSTI)

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 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.

Bales, J.D.; Hicks, S.C. [eds.

1993-01-01T23:59:59.000Z

459

An investigation into the use of REITs to finance affordable housing in Mainland China  

E-Print Network [OSTI]

Mainland China's system of affordable housing provides housing for low and medium income groups. Housing for sale and housing for rent give residents two choices and also give two choices for municipal governments to provide ...

Huang, Yuxuan, M.C.P. Massachusetts Institute of Technology

2010-01-01T23:59:59.000Z

460

Method for reliability analysis of complex reactor systems. [LMFBR  

SciTech Connect (OSTI)

A method and a computer code for efficient and accurate reliability analyses of complex reactor systems are described and illustrated through an example. The method permits realistic analyses through its ability to accurately model and evaluate instantaneous and average unavailabilities for large systems with dependencies. The component models can include continuously monitored, non-repairable, and periodically tested components which are subject to failures resulting from components which are subject to failures resulting from component demands, stand-by conditions, human errors associated with testing and repair, as well as failures during actual operation. The numerical process used is efficient and allows analysis of general system configurations with arbitrary scheduling of maintenance operations.

Elerath, J.G.; Vaurio, J.K.; Wood, A.P.

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

625 SW JACKSON, SUITE 210 PORTLAND, OR 97201 PHONE: 503.725.4375 E-MAIL: HOUSING@PDX.EDU WWW.PDX.EDU/HOUSING Proposed 2011-2012 HOUSING RATES  

E-Print Network [OSTI]

.PDX.EDU/HOUSING Proposed 2011-2012 HOUSING RATES UNIVERSITY HOUSING OFFICE UNFURNISHED HOUSING UPPERCLASSMEN & FRESHMEN, you will be charged the single rate and University Housing will not assign anyone else to that unit. The double rate costs more than half of the single rate as a way to compensate for the additional utilities

Bertini, Robert L.

462

Modelling the Electron Beam Welding of Nuclear Reactor Pressure Vessel Steel  

E-Print Network [OSTI]

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

Cambridge, University of

463

Research gaps and technology needs in development of PHM for passive AdvSMR components  

SciTech Connect (OSTI)

Advanced small modular reactors (AdvSMRs), 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. SMRs are challenged economically because of losses in economy of scale; thus, there is increased motivation to reduce the controllable operations and maintenance costs through automation technologies including prognostics health management (PHM) systems. In this regard, PHM systems have the potential to play a vital role in supporting the deployment of AdvSMRs and face several unique challenges with respect to implementation for passive AdvSMR components. This paper presents a summary of a research gaps and technical needs assessment performed for implementation of PHM for passive AdvSMR components.

Meyer, Ryan M.; Ramuhalli, Pradeep; Hirt, Evelyn H.; Mitchell, Mark R.; Wootan, David W.; Berglin, Eric J.; Henagar, Chuck H. Jr. [Pacific Northwest National Laboratory, 902 Battelle Blvd., Richland, WA 99352 (United States); Coble, Jamie B. [University of Tennessee, Knoxville, Department of Nuclear Engineering, 315 Pasqua Engineering Building, Knoxville, TN 37996 (United States); Bond, Leonard J. [Iowa State University, Center for Nondestructive Evaluation, 1915 Scholl Rd., Ames, IA 50011 (United States)

2014-02-18T23:59:59.000Z

464

Methanation assembly using multiple reactors  

DOE Patents [OSTI]

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

Jahnke, Fred C.; Parab, Sanjay C.

2007-07-24T23:59:59.000Z

465

Power Burst Facility (PBF) Reactor Reactor Decommissioning  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - September 2006PhotovoltaicSeptember 22,Reactor Decommissioning Click here to view

466

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components  

SciTech Connect (OSTI)

Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants.

Ware, A.G.; Morton, D.K.; Nitzel, M.E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1995-03-01T23:59:59.000Z

467

Mass spectrometer vacuum housing and pumping system  

DOE Patents [OSTI]

A vacuum housing and pumping system for a portable gas chromatograph/mass spectrometer (GC/MS). The vacuum housing section of the system has minimum weight for portability while designed and constructed to utilize metal gasket sealed stainless steel to be compatible with high vacuum operation. The vacuum pumping section of the system consists of a sorption (getter) pump to remove atmospheric leakage and outgassing contaminants as well as the gas chromatograph carrier gas (hydrogen) and an ion pump to remove the argon from atmospheric leaks. The overall GC/MS system has broad application to contaminants, hazardous materials, illegal drugs, pollution monitoring, etc., as well as for use by chemical weapon treaty verification teams, due to the light weight and portability thereof.

Coutts, Gerald W. (Livermore, CA); Bushman, John F. (Oakley, CA); Alger, Terry W. (Tracy, CA)

1996-01-01T23:59:59.000Z

468

Foundation House, New York, geothermal heat pump  

SciTech Connect (OSTI)

The Foundation House, planned to house half a dozen nonprofit foundations, will be constructed on 64th Street just east of Central Park in Manhattan, New York. It is in a Landmark District and designed by the architectural firm of Henry George Greene, AIA of Scarsdale, NY (project architect, David Wasserman). The 20,000-square foot building of five floors above ground and two below, will illustrate how energy-savings technology and environmentally sensitive construction methods can be economical. The heating and cooling system, including refrigeration requirements for the freezers and refrigerators in the commercial kitchen, will be provided by geothermal heat pumps using standing column wells. The facility is the first building on the island of Manhattan to feature geothermal heating and cooling. The mechanical system has been the assistance of Carl Orio`s firm of Water & Energy Systems corporation of Atkinson, New Hampshire. The two 1550-foot standing column wells were drilled by John Barnes of Flushing, NY.

Lund, J.W.

1997-08-01T23:59:59.000Z

469

Healthy Housing Opportunities During Weatherization Work  

SciTech Connect (OSTI)

In the summer and early fall of 2010, the National Center for Healthy Housing interviewed people from a selection of state and local agencies that perform weatherizations on low-income housing in order to gauge their approach to improving the health and safety of the homes. The interviews provided a strong cross section of what work agencies can do, and how they go about funding this work when funds from the Weatherization Assistance Program (WAP) do not cover the full extent of the repairs. The report also makes recommendations for WAP in how to assist agencies to streamline and maximize the health and safety repairs they are able to make in the course of a standard weatherization.

Wilson, J.; Tohn, E.

2011-03-01T23:59:59.000Z

470

Mass spectrometer vacuum housing and pumping system  

DOE Patents [OSTI]

A vacuum housing and pumping system is described for a portable gas chromatograph/mass spectrometer (GC/MS). The vacuum housing section of the system has minimum weight for portability while designed and constructed to utilize metal gasket sealed stainless steel to be compatible with high vacuum operation. The vacuum pumping section of the system consists of a sorption (getter) pump to remove atmospheric leakage and outgassing contaminants as well as the gas chromatograph carrier gas (hydrogen) and an ion pump to remove the argon from atmospheric leaks. The overall GC/MS system has broad application to contaminants, hazardous materials, illegal drugs, pollution monitoring, etc., as well as for use by chemical weapon treaty verification teams, due to the light weight and portability thereof. 7 figs.

Coutts, G.W.; Bushman, J.F.; Alger, T.W.

1996-07-23T23:59:59.000Z

471

Performance evaluation of the Balcomb solar house  

SciTech Connect (OSTI)

Additional instrumentation was added to the Balcomb solar house for a six-week period and up to 85 channels were recorded hourly. Some new findings based on an evaluation of these data are presented. (1) The thermal comfort characteristics of four rooms are documented. (2) Relative humidity in the living room varies from 30 to 50%; these data are used to infer an evaporation rate in the house of about 25 kg of water/day. The evaporation rate correlates reasonably well with greenhouse temperature. (3) Heat storage in the greenhouse floor is estimated at about 0.30 kWh/day-m/sup 2/ based on temperatures measured at four depths. (4) Several thermal characteristics of the rock bed are deduced but it is evident that the heat flow is not yet completely understood.

Balcomb, J.D.; Hedstrom, J.C.; Perry, J.E. Jr.

1980-01-01T23:59:59.000Z

472

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

Office of Scientific and Technical Information (OSTI)

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

473

Transverse Component Acknowledgements  

E-Print Network [OSTI]

, 232-237. Raw Data Radial Component Analysis of Treasure Island earthquake data using seismic by Treasure Island Geotechnical Array near San Francisco, California on 06/26/94. It was a magnitude 4

474

Heat dissipating nuclear reactor  

DOE Patents [OSTI]

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

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

1987-01-01T23:59:59.000Z

475

Inexpensive Mini Thermonuclear Reactor  

E-Print Network [OSTI]

This proposed design for a mini thermonuclear reactor uses a method based upon a series of important innovations. A cumulative explosion presses a capsule with nuclear fuel up to 100 thousands of atmospheres, the explosive electric generator heats the capsule/pellet up to 100 million degrees and a special capsule and a special cover which keeps these pressure and temperature in capsule up to 0.001 sec. which is sufficient for Lawson criteria for ignition of thermonuclear fuel. Major advantages of these reactors/bombs is its very low cost, dimension, weight and easy production, which does not require a complex industry. The mini thermonuclear bomb can be delivered as a shell by conventional gun (from 155 mm), small civil aircraft, boat or even by an individual. The same method may be used for thermonuclear engine for electric energy plants, ships, aircrafts, tracks and rockets. Key words: Thermonuclear mini bomb, thermonuclear reactor, nuclear energy, nuclear engine,

Alexander Bolonkin; Alexander Bolonkin

476

Nuclear reactor safety device  

DOE Patents [OSTI]

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

Hutter, Ernest (Wilmette, IL)

1986-01-01T23:59:59.000Z

477

Fusion reactor control  

SciTech Connect (OSTI)

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

Plummer, D.A.

1995-12-31T23:59:59.000Z

478

Thermionic Reactor Design Studies  

SciTech Connect (OSTI)

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

Schock, Alfred

1994-08-01T23:59:59.000Z

479

Reactor for exothermic reactions  

DOE Patents [OSTI]

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

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

1993-01-01T23:59:59.000Z

480

Heat dissipating nuclear reactor  

DOE Patents [OSTI]

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

Hunsbedt, A.; Lazarus, J.D.

1985-11-21T23:59:59.000Z

Note: This page contains sample records for the topic "house reactor components" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

Reactor for exothermic reactions  

DOE Patents [OSTI]

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

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

1993-03-02T23:59:59.000Z

482

Building America House Simulation Protocols (Revised)  

SciTech Connect (OSTI)

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.

Hendron, R.; Engebrecht, C.

2010-10-01T23:59:59.000Z

483

Houses need to breathe--right?  

SciTech Connect (OSTI)

Houses need to breathe, but we can no longer leave the important functions associated with ventilation to be met accidentally. A designed ventilation system must be considered as much a part of a home as its heating system. Windows are a key part of that system because they allow a quick increase in ventilation for unusual events, but neither they nor a leaky building shell can be counted on to provide minimum levels.

Sherman, Max H.

2004-10-01T23:59:59.000Z

484

1/23/07 White House...  

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

2307 White House Office Of Communications T T w w e e n n t t y y I I n n T T e e n n : : S S t t r r e e n n g g t t h h e e n n i i n n g g A A m m e e r r i i c c a a ' ' s s E...

485

2014 Building America House Simulation Protocols  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement3 Beryllium-Associated Worker RegistryDepartment2014 Building America House

486

2014 House Nuclear Cleanup Caucus Oak Ridge  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustionImprovement3 Beryllium-Associated Worker2014 House Nuclear Cleanup Caucus Oak Ridge August 16,

487

LMFBR fuel component costs  

SciTech Connect (OSTI)

A significant portion of the cost of fabricating LMFBR fuels is in the non-fuel components such as fuel pin cladding, fuel assembly ducts and end fittings. The contribution of these to fuel fabrication costs, based on FFTF experience and extrapolated to large LMFBR fuel loadings, is discussed. The extrapolation considers the expected effects of LMFBR development programs in progress on non-fuel component costs.

Epperson, E.M.; Borisch, R.R.; Rice, L.H.

1981-10-29T23:59:59.000Z

488

Steam generator for liquid metal fast breeder reactor  

DOE Patents [OSTI]

Improvements in the design of internal components of J-shaped steam generators for liquid metal fast breeder reactors. Complex design improvements have been made to the internals of J-shaped steam generators which improvements are intended to reduce tube vibration, tube jamming, flow problems in the upper portion of the steam generator, manufacturing complexities in tube spacer attachments, thermal stripping potentials and difficulties in the weld fabrication of certain components.

Gillett, James E. (Greensburg, PA); Garner, Daniel C. (Murrysville, PA); Wineman, Arthur L. (Greensburg, PA); Robey, Robert M. (North Huntingdon, PA)

1985-01-01T23:59:59.000Z

489

Instrumentation to Enhance Advanced Test Reactor Irradiations  

SciTech Connect (OSTI)

The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR will support basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other test reactors has been completed. Based on this review, recommendations are made with respect to what instrumentation is needed at the ATR and a strategy has been developed for obtaining these sensors. Progress toward implementing this strategy is reported in this document. It is anticipated that this report will be updated on an annual basis.

J. L. Rempe; D. L. Knudson; K. G. Condie; J. E. Daw; S. C. Taylor

2009-09-01T23:59:59.000Z

490

Closure head for a nuclear reactor  

DOE Patents [OSTI]

A closure head for a nuclear reactor includes a stationary outer ring integral with the reactor vessel with a first rotatable plug disposed within the stationary outer ring and supported from the stationary outer ring by a bearing assembly. A sealing system is associated with the bearing assembly to seal the annulus defined between the first rotatable plug and the stationary outer ring. The sealing system comprises tubular seal elements disposed in the annulus with load springs contacting the tubular seal elements so as to force the tubular seal elements against the annulus in a manner to seal the annulus. The sealing system also comprises a sealing fluid which is pumped through the annulus and over the tubular seal elements causing the load springs to compress thereby reducing the friction between the tubular seal elements and the rotatable components while maintaining a gas-tight seal therebetween.

Wade, Elman E. (South Huntingdon, PA)

1980-01-01T23:59:59.000Z

491

Housing assembly for electric vehicle transaxle  

DOE Patents [OSTI]

Disclosed is a drive assembly (10) for an electrically powered vehicle (12). The assembly includes a transaxle (16) having a two-speed transmission (40) and a drive axle differential (46) disposed in a unitary housing assembly (38), an oil-cooled prime mover or electric motor (14) for driving the transmission input shaft (42), an adapter assembly (24) for supporting the prime mover on the transaxle housing assembly, and a hydraulic system (172) providing pressurized oil flow for cooling and lubricating the electric motor and transaxle and for operating a clutch (84) and a brake (86) in the transmission to shift between the two-speed ratios of the transmission. The adapter assembly allows the prime mover to be supported in several positions on the transaxle housing. The brake is spring-applied and locks the transmission in its low-speed ratio should the hydraulic system fail. The hydraulic system pump is driven by an electric motor (212) independent of the prime mover and transaxle.

Kalns, Ilmars (Northville, MI)

1981-01-01T23:59:59.000Z

492

Pressurized reactor system and a method of operating the same  

DOE Patents [OSTI]

A method and apparatus are provided for operating a pressurized reactor system in order to precisely control the temperature within a pressure vessel in order to minimize condensation of corrosive materials from gases on the surfaces of the pressure vessel or contained circulating fluidized bed reactor, and to prevent the temperature of the components from reaching a detrimentally high level, while at the same time allowing quick heating of the pressure vessel interior volume during start-up. Superatmospheric pressure gas is introduced from the first conduit into the fluidized bed reactor and heat derived reactions such as combustion and gassification are maintained in the reactor. Gas is exhausted from the reactor and pressure vessel through a second conduit. Gas is circulated from one part of the inside volume to another to control the temperature of the inside volume, such as by passing the gas through an exterior conduit which has a heat exchanger, control valve, blower and compressor associated therewith, or by causing natural convection flow of circulating gas within one or more generally vertically extending gas passages entirely within the pressure vessel (and containing heat exchangers, flow rate control valves, or the like therein). Preferably, inert gas is provided as a circulating gas, and the inert gas may also be used in emergency shut-down situations. In emergency shut-down reaction gas being supplied to the reactor is cut off, while inert gas from the interior gas volume of the pressure vessel is introduced into the reactor.

Isaksson, Juhani M. (Karhula, FI)

1996-01-01T23:59:59.000Z

493

Pressurized reactor system and a method of operating the same  

DOE Patents [OSTI]

A method and apparatus are provided for operating a pressurized reactor system in order to precisely control the temperature within a pressure vessel in order to minimize condensation of corrosive materials from gases on the surfaces of the pressure vessel or contained circulating fluidized bed reactor, and to prevent the temperature of the components from reaching a detrimentally high level, while at the same time allowing quick heating of the pressure vessel interior volume during start-up. Super-atmospheric pressure gas is introduced from the first conduit into the fluidized bed reactor and heat derived reactions such as combustion and gasification are maintained in the reactor. Gas is exhausted from the reactor and pressure vessel through a second conduit. Gas is circulated from one part of the inside volume to another to control the temperature of the inside volume, such as by passing the gas through an exterior conduit which has a heat exchanger, control valve, blower and compressor associated therewith, or by causing natural convection flow of circulating gas within one or more generally vertically extending gas passages entirely within the pressure vessel (and containing heat exchangers, flow rate control valves, or the like therein). Preferably, inert gas is provided as a circulating gas, and the inert gas may also be used in emergency shut-down situations. In emergency shut-down reaction gas being supplied to the reactor is cut off, while inert gas from the interior gas volume of the pressure vessel is introduced into the reactor. 2 figs.

Isaksson, J.M.

1996-06-18T23:59:59.000Z

494

Fast quench reactor method  

DOE Patents [OSTI]

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

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

1999-01-01T23:59:59.000Z

495

Fast quench reactor method  

DOE Patents [OSTI]

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

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

1999-08-10T23:59:59.000Z

496

Diagnostics for hybrid reactors  

SciTech Connect (OSTI)

The Hybrid Reactor(HR) can be considered an attractive actinide-burner or a fusion assisted transmutation for destruction of transuranic(TRU) nuclear waste. The hybrid reactor has two important subsystems: the tokamak neutron source and the blanket which includes a fuel zone where the TRU are placed and a tritium breeding zone. The diagnostic system for a HR must be as simple and robust as possible to monitor and control the plasma scenario, guarantee the protection of the machine and monitor the transmutation.

Orsitto, Francesco Paolo [ENEA Unita' Tecnica Fusione , Associazione ENEA-EURATOM sulla Fusione C R Frascati v E Fermi 45 00044 Frascati (Italy)

2012-06-19T23:59:59.000Z

497

Perspectives on reactor safety  

SciTech Connect (OSTI)

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

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

1994-03-01T23:59:59.000Z

498

Environmentally assisted cracking of light-water reactor materials  

SciTech Connect (OSTI)

Environmentally assisted cracking (EAC) of lightwater reactor (LWR) materials has affected nuclear reactors from the very introduction of the technology. Corrosion problems have afflicted steam generators from the very introduction of pressurized water reactor (PWR) technology. Shippingport, the first commercial PWR operated in the United States, developed leaking cracks in two Type 304 stainless steel (SS) steam generator tubes as early as 1957, after only 150 h of operation. Stress corrosion cracks were observed in the heat-affected zones of welds in austenitic SS piping and associated components in boiling-water reactors (BRWs) as early as 1965. The degradation of steam generator tubing in PWRs and the stress corrosion cracking (SCC) of austenitic SS piping in BWRs have been the most visible and most expensive examples of EAC in LWRs, and the repair and replacement of steam generators and recirculation piping has cost hundreds of millions of dollars. However, other problems associated with the effects of the environment on reactor structures and components am important concerns in operating plants and for extended reactor lifetimes. Cast duplex austenitic-ferritic SSs are used extensively in the nuclear industry to fabricate pump casings and valve bodies for LWRs and primary coolant piping in many PWRs. Embrittlement of the ferrite phase in cast duplex SS may occur after 10 to 20 years at reactor operating temperatures, which could influence the mechanical response and integrity of pressure boundary components during high strain-rate loading (e.g., seismic events). The problem is of most concern in PWRs where slightly higher temperatures are typical and cast SS piping is widely used.

Chopra, O.K.; Chung, H.M.; Kassner, T.F.; Shack, W.J.

1996-02-01T23:59:59.000Z

499

Innovative design of uranium startup fast reactors  

E-Print Network [OSTI]

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

Fei, Tingzhou

2012-01-01T23:59:59.000Z

500

Reactor operation environmental information document  

SciTech Connect (OSTI)

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

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

1989-12-01T23:59:59.000Z