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1

Core Analysis | Open Energy Information  

Open Energy Info (EERE)

Core Analysis Core Analysis Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Core Analysis Details Activities (41) Areas (28) Regions (2) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Rock Lab Analysis Parent Exploration Technique: Rock Lab Analysis Information Provided by Technique Lithology: Core analysis is done to define lithology. Stratigraphic/Structural: Core analysis can locate faults or fracture networks. Oriented core can give additional important information on anisotropy. Hydrological: Thermal: Thermal conductivity can be measured from core samples. Cost Information Low-End Estimate (USD): 2,000.00200,000 centUSD 2 kUSD 0.002 MUSD 2.0e-6 TUSD / 30 foot core Median Estimate (USD): 10,000.001,000,000 centUSD

2

Core Analysis At Fenton Hill HDR Geothermal Area (Laughlin, Et...  

Open Energy Info (EERE)

Activity Details Location Fenton Hill HDR Geothermal Area Exploration Technique Core Analysis Activity Date - 1983 Usefulness useful DOE-funding Unknown Notes A few cores...

3

Core Analysis At International Geothermal Area, Indonesia (Boitnott...  

Open Energy Info (EERE)

Area Indonesia Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown References Greg N. Boitnott (2003) Core Analysis For The Development...

4

Core Analysis At Jemez Mountain Area (Eichelberger & Koch, 1979...  

Open Energy Info (EERE)

1979) Exploration Activity Details Location Jemez Mountain Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown References John C....

5

Core Analysis At Colrado Area (DOE GTP) | Open Energy Information  

Open Energy Info (EERE)

GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Colrado Area (DOE GTP) Exploration Activity Details Location Colado...

6

Core Analysis At Long Valley Caldera Geothermal Area (Pribnow...  

Open Energy Info (EERE)

Activity Details Location Long Valley Caldera Geothermal Area Exploration Technique Core Analysis Activity Date - 2003 Usefulness useful DOE-funding Unknown Notes "Here we...

7

Core Analysis At Alum Area (DOE GTP) | Open Energy Information  

Open Energy Info (EERE)

GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Alum Area (DOE GTP) Exploration Activity Details Location Alum Geothermal...

8

Core Analysis At Fenton Hill HDR Geothermal Area (Brookins &...  

Open Energy Info (EERE)

Activity Details Location Fenton Hill HDR Geothermal Area Exploration Technique Core Analysis Activity Date - 1983 Usefulness useful DOE-funding Unknown Notes See linked...

9

Core Analysis At Long Valley Caldera Geothermal Area (Smith ...  

Open Energy Info (EERE)

Smith & Suemnicht, 1991) Exploration Activity Details Location Long Valley Caldera Geothermal Area Exploration Technique Core Analysis Activity Date 1985 - 1988 Usefulness useful...

10

Processing of Activated Core Components  

SciTech Connect

Used activated components from the core of a NPP like control elements, water channels from a BWR, and others like in-core measurement devices need to be processed into waste forms suitable for interim storage, and for the final waste repository. Processing of the activated materials can be undertaken by underwater cutting and packaging or by cutting and high-pressure compaction in a hot cell. A hot cell is available in Germany as a joint investment between GNS and the Karlsruhe Research Center at the latter's site. Special transport equipment is available to transport the components ''as-is'' to the hot cell. Newly designed underwater processing equipment has been designed, constructed, and operated for the special application of NPP decommissioning. This equipment integrates an underwater cutting device with an 80 ton force underwater in-drum compactor.

Friske, A.; Gestermann, G.; Finkbeiner, R.

2003-02-26T23:59:59.000Z

11

Multi-core Performance Analysis  

NLE Websites -- All DOE Office Websites (Extended Search)

core Performance Analysis core Performance Analysis HPC Computation 1 Performance Analysis * Compiler Feedback * HWPC Data * Load Balance 2 Compiler Feedback * Before optimizing code, it's critical to know what the compiler does to your code - Loop optimizations - Vectorization - Prefetching - ... * Equally important to what the compiler does is what it doesn't do, and why - Data dependencies - Misplaced branches - Unknown loop counts - ... 3 Enabling Compiler Feedback * Portland Group - Minfo=all - Mneginfo - Minfo=ccff (Common Compiler Feedback Format) * Cray - rm (Fortran) - hlist=m (C/C++) * Intel - vec-report1 * Pathscale - LNO:simd_verbose=ON:vintr_verbose=ON:prefetch_v erbose=ON * GNU - ftree-vectorizer-verbose=1

12

E-Print Network 3.0 - analysis identifies core Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

what their analysis of a mock core has revealed... on information obtained from ice core analysis. Higher thinking skills goals for this activity: Standards... for...

13

Core Analysis At Mcgee Mountain Area (DOE GTP) | Open Energy...  

Open Energy Info (EERE)

Mcgee Mountain Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown References (1 January 2011) GTP ARRA Spreadsheet Additional...

14

Core Analysis At Valles Caldera - Sulphur Springs Geothermal...  

Open Energy Info (EERE)

Details Location Valles Caldera - Sulphur Springs Geothermal Area Exploration Technique Core Analysis Activity Date - 1992 Usefulness not indicated DOE-funding Unknown Notes...

15

Core Analysis At Yellowstone Region (Dobson, Et Al., 2003) |...  

Open Energy Info (EERE)

Dobson, Et Al., 2003) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Yellowstone Region (Dobson, Et Al., 2003) Exploration...

16

Core Analysis At Newberry Caldera Area (Carothers, Et Al., 1987...  

Open Energy Info (EERE)

Carothers, Et Al., 1987) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Newberry Caldera Area (Carothers, Et Al., 1987)...

17

Core Analysis At Blue Mountain Geothermal Area (U.S. Geological...  

Open Energy Info (EERE)

Area Exploration Technique Core Analysis Activity Date 2008 - 2008 Usefulness useful DOE-funding Unknown Exploration Basis Core sample from the observation wells Deep Blue No....

18

Core Analysis At Lake City Hot Springs Area (Benoit Et Al., 2005...  

Open Energy Info (EERE)

City Hot Springs Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Rock core analyses and mineral assemblage investigations...

19

Definition: Core Analysis | Open Energy Information  

Open Energy Info (EERE)

Core Analysis Core Analysis Jump to: navigation, search Dictionary.png Core Analysis Core samples are obtained from drilling a well, typically using a synthetic diamond coated bit that has a hollow center so cylindrical rock samples ("core") can be extracted. Core samples successfully recovered are visually inspected to determine rock type, mineralization, and fracture networks, then certain laboratory analyses may ensue to acquire detailed rock properties. View on Wikipedia Wikipedia Definition A core sample is a cylindrical section of (usually) a naturally occurring substance. Most core samples are obtained by drilling with special drills into the substance, for example sediment or rock, with a hollow steel tube called a core drill. The hole made for the core sample is

20

Core Analysis At Dunes Geothermal Area (1976) | Open Energy Information  

Open Energy Info (EERE)

Dunes Geothermal Area (1976) Dunes Geothermal Area (1976) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Dunes Geothermal Area (1976) Exploration Activity Details Location Dunes Geothermal Area Exploration Technique Core Analysis Activity Date 1976 Usefulness not indicated DOE-funding Unknown Exploration Basis Fracture analysis to determine if sealing or open fractures exist Notes Core samples show diagenesis superimposed on episodic fracturing and fracture sealing. The minerals that fill fractures show significant temporal variations. Fracture sealing and low fracture porosity imply that only the most recently formed fractures are open to fluids. References Michael L. Batzle; Gene Simmons (1 January 1976) Microfractures in rocks from two geothermal areas

Note: This page contains sample records for the topic "activity core analysis" 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

Core Analysis At Valles Caldera - Sulphur Springs Area (Woldegabriel &  

Open Energy Info (EERE)

Woldegabriel & Woldegabriel & Goff, 1992) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Valles Caldera - Sulphur Springs Area (Woldegabriel & Goff, 1992) Exploration Activity Details Location Valles Caldera - Sulphur Springs Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Samples for age dating taken from core hole VC-2B in the Suphur Springs area of the Valles Caldera. References Giday WoldeGabriel, Fraser Goff (1992) K-Ar Dates Of Hydrothermal Clays From Core Hole Vc-2B, Valles Caldera, New Mexico And Their Relation To Alteration In A Large Hydrothermal System Retrieved from "http://en.openei.org/w/index.php?title=Core_Analysis_At_Valles_Caldera_-_Sulphur_Springs_Area_(Woldegabriel_%26_Goff,_1992)&oldid=387687"

22

Core Analysis At Raft River Geothermal Area (1976) | Open Energy  

Open Energy Info (EERE)

6) 6) Exploration Activity Details Location Raft River Geothermal Area Exploration Technique Core Analysis Activity Date 1976 Usefulness not indicated DOE-funding Unknown Exploration Basis Fracture analysis to determine if sealing or open fractures exist Notes Core samples show diagenesis superimposed on episodic fracturing and fracture sealing. The minerals that fill fractures show significant temporal variations. Fracture sealing and low fracture porosity imply that only the most recently formed fractures are open to fluids. References Michael L. Batzle; Gene Simmons (1 January 1976) Microfractures in rocks from two geothermal areas Retrieved from "http://en.openei.org/w/index.php?title=Core_Analysis_At_Raft_River_Geothermal_Area_(1976)&oldid=47383

23

Core Analysis At Fort Bliss Area (DOE GTP) | Open Energy Information  

Open Energy Info (EERE)

Fort Bliss Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fort Bliss Area (DOE GTP) Exploration Activity Details...

24

Active Cores in Deep Fields  

E-Print Network (OSTI)

Deep field observations are an essential tool to probe the cosmological evolution of galaxies. In this context, X-ray deep fields provide information about some of the most energetic cosmological objects: active galactic nuclei (AGN). Astronomers are interested in detecting sufficient numbers of AGN to probe the accretion history at high redshift. This talk gives an overview of the knowledge resulting from a highly complete soft X-ray selected sample collected with ROSAT, XMM-Newton and Chandra deep fields. The principal outcome based on X-ray luminosity functions and space density evolution studies is that low-luminosity AGN evolve in a dramatically different way from high-luminosity AGN: The most luminous quasars perform at significantly earlier cosmic times and are most numerous in a unit volume at cosmological redshift z~2. In contrast, low-luminosity AGN evolve later and their space density peaks at z~0.7. This finding is also interpreted as an anti-hierarchical growth of supermassive black holes in the Universe. Comparing this with star formation rate history studies one concludes that supermassive black holes enter the cosmic stage before the bulk of the first stars. Therefore, first solutions of the so-called hen-egg problem are suggested. Finally, status developments and expectations of ongoing and future extended observations such as the XMM-COSMOS project are highlighted.

G. Hasinger; A. Mueller

2005-10-14T23:59:59.000Z

25

Core Analysis At Coso Geothermal Area (1980) | Open Energy Information  

Open Energy Info (EERE)

Core Analysis At Coso Geothermal Area (1980) Core Analysis At Coso Geothermal Area (1980) Exploration Activity Details Location Coso Geothermal Area Exploration Technique Core Analysis Activity Date 1980 Usefulness not indicated DOE-funding Unknown Exploration Basis Determine the heat transfer mechanism Notes In an investigation of the thermal regime of this Basin and Range geothermal area, temperature measurements were made in 25 shallow and 1 intermediate depth borehole. Thermal conductivity measurements were made on 312 samples from cores and drill cuttings. The actual process by which heat is transferred is rather complex; however, the heat flow determinations can be divided into two groups. The first group, less than 4.0 HFU, are indicative of regions with primarily conductive regimes, although

26

Core Analysis At International Geothermal Area, Philippines (Laney, 2005) |  

Open Energy Info (EERE)

Core Analysis At International Geothermal Area Core Analysis At International Geothermal Area Philippines (Laney, 2005) Exploration Activity Details Location International Geothermal Area Philippines Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Improving Exploration Models of Andesite-Hosted Geothermal Systems, Allis, Browne, Bruton, Christensen, Hulen, Lutz, Mindenhall, Nemcok, Norman, Powell and Stimac. The approach we are using is to characterize the petrology, geochemistry and fractures in core and cuttings samples and then integrate these data with measured downhole temperatures and pressures and with the compositions of the reservoir fluids. Our investigations represent cooperative efforts with the Karaha-Bodas Co. LLC (a subsidiary of Caithness Energy) at Karaha-Telaga Bodas, Indonesia and with Philippine

27

Core Analysis At Raft River Geothermal Area (1979) | Open Energy  

Open Energy Info (EERE)

9) 9) Exploration Activity Details Location Raft River Geothermal Area Exploration Technique Core Analysis Activity Date 1979 Usefulness not indicated DOE-funding Unknown Exploration Basis Permitted the lateral and vertical extrapolation of core and test data and bridged the gap between surface geophysical data and core analyses. Notes 1) Microcracks were observed in core samples. A set of observable characteristics of microcracks were discovered in racks from geothermal regions that appears to be unique and to have considerable potential for exploration for geothermal regions. Both permeability and electrical conductivity were measured for a suite of samples with a range of microcracks characteristics. A partial set of samples were collected to study migration of radioactive elements. 2) Laboratory analyses of cores

28

Core Analysis At Raft River Geothermal Area (2011) | Open Energy  

Open Energy Info (EERE)

2011) 2011) Exploration Activity Details Location Raft River Geothermal Area Exploration Technique Core Analysis Activity Date 2011 Usefulness not indicated DOE-funding Unknown Exploration Basis Explore for development of an EGS demonstration project Notes Core was obtained from RRG-3C. The sample is a brecciated and altered siltstone from the base of the Tertiary sequence and is similar to rocks at the base of the Tertiary deposits in RRG-9. The results of thermal and quasi-static mechanical property measurements that were conducted on the core sample are presented. References Jones, C.; Moore, J.; Teplow, W.; Craig, S. (1 January 2011) GEOLOGY AND HYDROTHERMAL ALTERATION OF THE RAFT RIVER GEOTHERMAL SYSTEM, IDAHO Retrieved from "http://en.openei.org/w/index.php?title=Core_Analysis_At_Raft_River_Geothermal_Area_(2011)&oldid=473834

29

Core Analysis At Raft River Geothermal Area (1981) | Open Energy  

Open Energy Info (EERE)

81) 81) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Raft River Geothermal Area (1981) Exploration Activity Details Location Raft River Geothermal Area Exploration Technique Core Analysis Activity Date 1981 Usefulness not indicated DOE-funding Unknown Exploration Basis Determine fault and joint geometry Notes Core taken from less than 200 m above the decollement contains two sets of normal faults. The major set of faults dips between 500 and 70 0. These faults occur as conjugate pairs that are bisected by vertical extension fractures. The second set of faults dips 100 to 200 and may parallel part of the basal decollement or reflect the presence of listric normal faults in the upper plate. References Guth, L. R.; Bruhn, R. L.; Beck, S. L. (1 July 1981) Fault and

30

Neutron activation analysis  

Science Journals Connector (OSTI)

Neutron activation analysis ... Describes the science and techniques of neutron activation analysis. ...

H. R. Lukens

1967-01-01T23:59:59.000Z

31

Core Analysis At Fish Lake Valley Area (DOE GTP) | Open Energy...  

Open Energy Info (EERE)

Fish Lake Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fish Lake Valley Area (DOE GTP) Exploration...

32

Overview on Hydrate Coring, Handling and Analysis  

SciTech Connect

Gas hydrates are crystalline, ice-like compounds of gas and water molecules that are formed under certain thermodynamic conditions. Hydrate deposits occur naturally within ocean sediments just below the sea floor at temperatures and pressures existing below about 500 meters water depth. Gas hydrate is also stable in conjunction with the permafrost in the Arctic. Most marine gas hydrate is formed of microbially generated gas. It binds huge amounts of methane into the sediments. Worldwide, gas hydrate is estimated to hold about 1016 kg of organic carbon in the form of methane (Kvenvolden et al., 1993). Gas hydrate is one of the fossil fuel resources that is yet untapped, but may play a major role in meeting the energy challenge of this century. In June 2002, Westport Technology Center was requested by the Department of Energy (DOE) to prepare a ''Best Practices Manual on Gas Hydrate Coring, Handling and Analysis'' under Award No. DE-FC26-02NT41327. The scope of the task was specifically targeted for coring sediments with hydrates in Alaska, the Gulf of Mexico (GOM) and from the present Ocean Drilling Program (ODP) drillship. The specific subjects under this scope were defined in 3 stages as follows: Stage 1: Collect information on coring sediments with hydrates, core handling, core preservation, sample transportation, analysis of the core, and long term preservation. Stage 2: Provide copies of the first draft to a list of experts and stakeholders designated by DOE. Stage 3: Produce a second draft of the manual with benefit of input from external review for delivery. The manual provides an overview of existing information available in the published literature and reports on coring, analysis, preservation and transport of gas hydrates for laboratory analysis as of June 2003. The manual was delivered as draft version 3 to the DOE Project Manager for distribution in July 2003. This Final Report is provided for records purposes.

Jon Burger; Deepak Gupta; Patrick Jacobs; John Shillinglaw

2003-06-30T23:59:59.000Z

33

Core Analysis At Coso Geothermal Area (1979) | Open Energy Information  

Open Energy Info (EERE)

Coso Geothermal Area (1979) Coso Geothermal Area (1979) Exploration Activity Details Location Coso Geothermal Area Exploration Technique Core Analysis Activity Date 1979 Usefulness useful DOE-funding Unknown Exploration Basis Compare microcracks between Coso and Raft River geothermal areas Notes Microcracks were observed in core samples from Coso. Both permeability and electrical conductivity were measured for a suite of samples with a range of microcracks characteristics. A partial set of samples were collected to study migration of radioactive elements. References Simmons, G.; Batzle, M. L.; Shirey, S. (1 April 1979) Microcrack technology. Progress report, 1 October 1978--31 March 1979 Retrieved from "http://en.openei.org/w/index.php?title=Core_Analysis_At_Coso_Geothermal_Area_(1979)&oldid=473689

34

CFD Analysis of Core Bypass Phenomena  

SciTech Connect

The U.S. Department of Energy is exploring the potential for the VHTR which will be either of a prismatic or a pebble-bed type. One important design consideration for the reactor core of a prismatic VHTR is coolant bypass flow which occurs in the interstitial regions between fuel blocks. Such gaps are an inherent presence in the reactor core because of tolerances in manufacturing the blocks and the inexact nature of their installation. Furthermore, the geometry of the graphite blocks changes over the lifetime of the reactor because of thermal expansion and irradiation damage. The existence of the gaps induces a flow bias in the fuel blocks and results in unexpected increase of maximum fuel temperature. Traditionally, simplified methods such as flow network calculations employing experimental correlations are used to estimate flow and temperature distributions in the core design. However, the distribution of temperature in the fuel pins and graphite blocks as well as coolant outlet temperatures are strongly coupled with the local heat generation rate within fuel blocks which is not uniformly distributed in the core. Hence, it is crucial to establish mechanistic based methods which can be applied to the reactor core thermal hydraulic design and safety analysis. Computational Fluid Dynamics (CFD) codes, which have a capability of local physics based simulation, are widely used in various industrial fields. This study investigates core bypass flow phenomena with the assistance of commercial CFD codes and establishes a baseline for evaluation methods. A one-twelfth sector of the hexagonal block surface is modeled and extruded down to whole core length of 10.704m. The computational domain is divided vertically with an upper reflector, a fuel section and a lower reflector. Each side of the sector grid can be set as a symmetry boundary

Richard W. Johnson; Hiroyuki Sato; Richard R. Schultz

2010-03-01T23:59:59.000Z

35

CFD Analysis of Core Bypass Phenomena  

SciTech Connect

The U.S. Department of Energy is exploring the potential for the VHTR which will be either of a prismatic or a pebble-bed type. One important design consideration for the reactor core of a prismatic VHTR is coolant bypass flow which occurs in the interstitial regions between fuel blocks. Such gaps are an inherent presence in the reactor core because of tolerances in manufacturing the blocks and the inexact nature of their installation. Furthermore, the geometry of the graphite blocks changes over the lifetime of the reactor because of thermal expansion and irradiation damage. The existence of the gaps induces a flow bias in the fuel blocks and results in unexpected increase of maximum fuel temperature. Traditionally, simplified methods such as flow network calculations employing experimental correlations are used to estimate flow and temperature distributions in the core design. However, the distribution of temperature in the fuel pins and graphite blocks as well as coolant outlet temperatures are strongly coupled with the local heat generation rate within fuel blocks which is not uniformly distributed in the core. Hence, it is crucial to establish mechanistic based methods which can be applied to the reactor core thermal hydraulic design and safety analysis. Computational Fluid Dynamics (CFD) codes, which have a capability of local physics based simulation, are widely used in various industrial fields. This study investigates core bypass flow phenomena with the assistance of commercial CFD codes and establishes a baseline for evaluation methods. A one-twelfth sector of the hexagonal block surface is modeled and extruded down to whole core length of 10.704m. The computational domain is divided vertically with an upper reflector, a fuel section and a lower reflector. Each side of the one-twelfth grid can be set as a symmetry boundary

Richard W. Johnson; Hiroyuki Sato; Richard R. Schultz

2009-11-01T23:59:59.000Z

36

Core Analysis At Kilauea Summit Area (Keller, Et Al., 1979) | Open Energy  

Open Energy Info (EERE)

Et Al., 1979) Et Al., 1979) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Kilauea Summit Area (Keller, Et Al., 1979) Exploration Activity Details Location Kilauea Summit Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Core samples were recovered from rather evenly spaced intervals throughout the borehole (Fig. 4) from 29 coring runs. Core recovered with respect to total coring footage was 66.6%. Total recovery of core was 47 m or about 3.7% of the total section penetrated in the drill hole. No cuttings were returned because no mud circulated back to the surface. References George V. Keller, L. Trowbridge Grose, John C. Murray, Catherine K. Skokan (1979) Results Of An Experimental Drill Hole At The Summit Of

37

Geologic analysis of Devonian Shale cores  

SciTech Connect

Cleveland Cliffs Iron Company was awarded a DOE contract in December 1977 for field retrieval and laboratory analysis of cores from the Devonian shales of the following eleven states: Michigan, Illinois, Indiana, Ohio, New York, Pennsylvania, West Virginia, Maryland, Kentucky, Tennessee and Virginia. The purpose of this project is to explore these areas to determine the amount of natural gas being produced from the Devonian shales. The physical properties testing of the rock specimens were performed under subcontract at Michigan Technological University (MTU). The study also included LANDSAT information, geochemical research, structural sedimentary and tectonic data. Following the introduction, and background of the project this report covers the following: field retrieval procedures; laboratory procedures; geologic analysis (by state); references and appendices. (ATT)

none,

1982-02-01T23:59:59.000Z

38

Core Analysis At International Geothermal Area, Indonesia (Laney, 2005) |  

Open Energy Info (EERE)

International Geothermal Area International Geothermal Area Indonesia (Laney, 2005) Exploration Activity Details Location International Geothermal Area Indonesia Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Improving Exploration Models of Andesite-Hosted Geothermal Systems, Allis, Browne, Bruton, Christensen, Hulen, Lutz, Mindenhall, Nemcok, Norman, Powell and Stimac. The approach we are using is to characterize the petrology, geochemistry and fractures in core and cuttings samples and then integrate these data with measured downhole temperatures and pressures and with the compositions of the reservoir fluids. Our investigations represent cooperative efforts with the Karaha-Bodas Co. LLC (a subsidiary of Caithness Energy) at Karaha-Telaga Bodas, Indonesia and with Philippine

39

Core Analysis At Long Valley Caldera Area (Sorey, Et Al., 1991) | Open  

Open Energy Info (EERE)

1991) 1991) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Long Valley Caldera Area (Sorey, Et Al., 1991) Exploration Activity Details Location Long Valley Caldera Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Several newer wells were cored, and the core analyses seemed to prove useful in most cases. At shallow depths in the caldera References Michael L. Sorey, Gene A. Suemnicht, Neil C. Sturchio, Gregg A. Nordquist (1991) New Evidence On The Hydrothermal System In Long Valley Caldera, California, From Wells, Fluid Sampling, Electrical Geophysics, And Age Determinations Of Hot-Spring Deposits Retrieved from "http://en.openei.org/w/index.php?title=Core_Analysis_At_Long_Valley_Caldera_Area_(Sorey,_Et_Al.,_1991)&oldid=386930

40

Core Analysis At Yellowstone Region (Sturchio, Et Al., 1990) | Open Energy  

Open Energy Info (EERE)

Sturchio, Et Al., 1990) Sturchio, Et Al., 1990) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Yellowstone Region (Sturchio, Et Al., 1990) Exploration Activity Details Location Yellowstone Caldera Geothermal Region Exploration Technique Core Analysis Activity Date Usefulness could be useful with more improvements DOE-funding Unknown Notes The samples used for this study were 43 hydrothermal minerals (silica, clay and calcite) from Yellowstone drill cores Y-5, Y-6, Y-7, Y-8, Y-11, Y-12, and Y-13 (Fig. 1). References N. C. Sturchio, T. E. C. Keith, K. Muehlenbachs (1990) Oxygen And Carbon Isotope Ratios Of Hydrothermal Minerals From Yellowstone Drill Cores Retrieved from "http://en.openei.org/w/index.php?title=Core_Analysis_At_Yellowstone_Region_(Sturchio,_Et_Al.,_1990)&oldid=401307"

Note: This page contains sample records for the topic "activity core analysis" 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

Rollover analysis of rotary mode core sampler truck No. 2  

SciTech Connect

This document provides estimate of limiting speed and rollover analysis of rotary mode core sampler truck No. 2 (RMCST No. 2).

Ziada, H.H.

1994-11-08T23:59:59.000Z

42

Core Analysis At Medicine Lake Area (Clausen Et Al, 2006) | Open Energy  

Open Energy Info (EERE)

Clausen Et Al, 2006) Clausen Et Al, 2006) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Medicine Lake Area (Clausen Et Al, 2006) Exploration Activity Details Location Medicine Lake Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes A major challenge to energy production in the region has been locating high-permeability fracture zones in the largely impermeable volcanic host rock. An understanding of the fracture networks will be a key to harnessing geothermal resources in the Cascades. Medicine Lake site was selected for this study because of the extensive collection of core samples, lithologic, structural, geophysical and temperature data that are available. The sample collection totals about 15.8 km of core from 18 wells. Core samples are

43

Core Analysis At Desert Peak Area (Laney, 2005) | Open Energy Information  

Open Energy Info (EERE)

Core Analysis At Desert Peak Area (Laney, 2005) Core Analysis At Desert Peak Area (Laney, 2005) Exploration Activity Details Location Desert Peak Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Remote Sensing for Exploration and Mapping of Geothermal Resources, Wendy Calvin, 2005. Task 1: Detailed analysis of hyperspectral imagery obtained in summer of 2003 over Brady's Hot Springs region was completed and validated (Figure 1). This analysis provided a local map of both sinter and tufa deposits surrounding the Ormat plant, identified fault extensions not previously recognized from field mapping and has helped constrain where to put additional wells that were drilled at the site. Task 2: Initial analysis of Landsat and ASTER data for Buffalo Valley and Pyramid Lake was

44

Core Analysis At Geysers Area (Lambert & Epstein, 1992) | Open Energy  

Open Energy Info (EERE)

Core Analysis At Geysers Area (Lambert & Epstein, Core Analysis At Geysers Area (Lambert & Epstein, 1992) Exploration Activity Details Location Geysers Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Aside from two core fragments from Thermal well No. 7 and one each from Lakoma Fame wells Nos. 8 and 9, all rock and mineral samples were available as cuttings. Cuttings samples were taken during drilling typically at 12-m intervals by the Union Oil Company of California (now UNOCAL), each sample covering a 6-m depth interval. The grains in cuttings fractions were millimeter- to centimetersized. References Steven J. Lambert, Samuel Epstein (1992) Stable-Isotope Studies Of Rocks And Secondary Minerals In A Vapor-Dominated Hydrothermal System At The Geysers, Sonoma County, California

45

Core Analysis At Long Valley Caldera Area (Smith & Suemnicht, 1991) | Open  

Open Energy Info (EERE)

Long Valley Caldera Area (Smith & Long Valley Caldera Area (Smith & Suemnicht, 1991) Exploration Activity Details Location Long Valley Caldera Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Sample for the present investigation consist of drill core and cuttings from all lithologic units identified in LVEW, cuttings from volcanic rocks in LV 13-21, core samples of Early Rhyolite and Bishop Tuff from LV13-26 and core samples of Bishop Tuff from SF38-32, LV48-29 and LV66-28 (Figs. 1 and 2). Surface samples of Early Rhyolite, Bishop Tuff and Paleozoic metasediments (Fig. 1) were also selected for comparative analysis and processed by the same procedures as the well samples. This oxygen isotope and fluid inclusion study has allowed us to determine the pathways of fluid

46

THE COLD SHOULDER: EMISSION MEASURE DISTRIBUTIONS OF ACTIVE REGION CORES  

SciTech Connect

The coronal heating mechanism for active region core loops is difficult to determine because these loops are often not resolved and cannot be studied individually. Rather, we concentrate on the 'inter-moss' areas between loop footpoints. We use observations from the Hinode EUV Imaging Spectrometer and the X-Ray Telescope to calculate the emission measure distributions of eight inter-moss areas in five different active regions. The combined data sets provide both high- and low-temperature constraints and ensure complete coverage in the temperature range appropriate for active regions. For AR 11113, the emission can be modeled with heating events that occur on timescales less than the cooling time. The loops in the core regions appear to be close to equilibrium and are consistent with steady heating. The other regions studied, however, appear to be dominated by nanoflare heating. Our results are consistent with the idea that active region age is an important parameter in determining whether steady or nanoflare heating is primarily responsible for the core emission, that is, older regions are more likely to be dominated by steady heating, while younger regions show more evidence of nanoflares.

Schmelz, J. T.; Pathak, S., E-mail: jschmelz@memphis.edu [Physics Department, University of Memphis, Memphis, TN 38152 (United States)

2012-09-10T23:59:59.000Z

47

Core Analysis At Fort Bliss Area (Combs, Et Al., 1999) | Open Energy  

Open Energy Info (EERE)

9) 9) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Fort Bliss Area (Combs, Et Al., 1999) Exploration Activity Details Location Fort Bliss Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Three principal types of data were obtained from this drilling project: core samples of the lithology penetrated by the holes, records of drilling behavior (such as water level in the hole, changes in rate of penetration etc.), and multiple temperature logs (both during and after drilling) in each well. A suite of geophysical logs (gamma ray, neutron, sonic, and resistivity) was also run tier completion of drilling. References Jim Combs, John T. Finger, Colin Goranson, Charles E. Hockox Jr.,

48

Core Analysis At Valles Caldera - Sulphur Springs Area (Armstrong, Et Al.,  

Open Energy Info (EERE)

Et Al., Et Al., 1995) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Valles Caldera - Sulphur Springs Area (Armstrong, Et Al., 1995) Exploration Activity Details Location Valles Caldera - Sulphur Springs Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes In preparation for this work, 103 core samples were collected at 3-m ( IO ft) intervals from the Madera Limestone and underlying Sandia Formation (both of Pennsylvanian age) intersected in the depth interval 1296.1-1556.9 m (4252.5-5108.2 ft) in CSDP corehole VC-2B, completed in 1988 in the Sulphur Springs area of the Valles caldera (Hulen and Gardner, 1989). These samples were prepared as polished thin sections, and studied by

49

Core Analysis At Long Valley Caldera Area (Pribnow, Et Al., 2003) | Open  

Open Energy Info (EERE)

Pribnow, Et Al., 2003) Pribnow, Et Al., 2003) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Analysis At Long Valley Caldera Area (Pribnow, Et Al., 2003) Exploration Activity Details Location Long Valley Caldera Area Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Here we present a detailed thermal conductivity profile for LVEW (Fig. 5a). Measurements were performed at the geothermal laboratory of the USGS on chips and core samples using divided bar and needle probe instruments. Detailed descriptions of these instruments and measurement procedures are given in Sass et al. (1971a,b). At shallow depths in the caldera References Daniel F. C. Pribnow, Claudia Schutze, Suzanne J. Hurter, Christina

50

The Enzyme-mimic Activity of Ferric Nano-Core Residing in Ferritin...  

NLE Websites -- All DOE Office Websites (Extended Search)

The Enzyme-mimic Activity of Ferric Nano-Core Residing in Ferritin and Its Biosensing Applications. The Enzyme-mimic Activity of Ferric Nano-Core Residing in Ferritin and Its...

51

Neutron activation analysis  

Science Journals Connector (OSTI)

Neutron activation analysis (NAA) is an that relies on the measurement of ?-rays emitted from a sample that was irradiated by neutrons. The rate at which ?-rays are emitted from an element in a sample is dir...

James R. Budahn

1998-01-01T23:59:59.000Z

52

Third (March 2006) Coring and Analysis of Zero-Valent Iron Permeable Reactive Barrier, Monticello, Utah  

Energy.gov (U.S. Department of Energy (DOE))

Third (March 2006) Coring and Analysis of Zero-Valent Iron Permeable Reactive Barrier, Monticello, Utah

53

ACCU Core Sampling/Storage Device for VOC Analysis  

SciTech Connect

The Accu Core sampler system consists of alternating cylindrical clear acrylic sections and one-inch cylindrical stainless steel sections arranged in clear shrink wrap. The set of alternating acrylic and stainless steel sections in the shrink wrap are designed to fit in a Geoprobe dual-tube penetrometer for collection of continuous soil cores. The clear acrylic sections can have 1/2-inch access holes for easy soil headspace screening without violating the integrity of the adjacent stainless steel sections. The Accu Core sampler system can be used to store a soil sample collected in the stainless steel section by capping the ends of the section so it becomes a sample storage container. The sampler system can also be used to collect a subsurface soil sample in one of the sections that can be directly extruded from the section into a container for storage during shipment to the laboratory. In addition, the soil in a sampler section can be quickly sub-sampled using a coring tool and extruded into a storage container so the integrity of the soil is not disrupted and the potential for VOC loss during sub-sampling is greatly reduced. A field validation study was conducted to evaluate the performance of the Accu Core sampler to store VOC soil samples during transportation to the laboratory for analysis and to compare the performance of the Accu Core with current sampling and storage techniques, all of which require sub-sampling when the soil sample is brought to the surface. During some of the validation testing, the acrylic sections having access holes for headspace screening were included in the Accu Core sampler configuration and soil in these sections was screened to show the usefulness of the sample screening capability provided by the Accu Core system. This report presents the results of the field validation study as well as recommendations for the Accu Core sampler system.

Susan S. Sorini; John F. Schabron; Mark M. Sanderson

2007-04-30T23:59:59.000Z

54

Analysis of tru-fueled vhtr prismatic core performance domains  

E-Print Network (OSTI)

Regulatory Commission ORNL Oak Ridge National Laboratory P&T Partitioning and Transmutation PUREX Plutonium Uranium Reduction and Oxidation PWR Pressurized Water Reactor RGPu Reactor Grade Plutonium SCWCR Super-critical Water Cooled Reactor SFR Sodium.... The neutronics analysis using the 3D, whole-core VHTR model was performed using the ORNL SCALE (Standardized Computer Analysis for Licensing Evaluation) code system. The standard SCALE 5.1 TRITON sequence has been upgraded to allow fuel cycle modeling...

Lewis, Tom Goslee

2009-05-15T23:59:59.000Z

55

Neutronic analysis of pebble-bed cores with transuranics  

E-Print Network (OSTI)

(ORNL). This Department of Energy sponsored center is authorized to collect, maintain, analyze, and distribute computer software and data sets in the area of radiation transport and safety. The full-core VHTR pebble-bed model was developed... II.A SCALE 5.0 The 3D full-core pebble-bed VHTR model was initially built using SCALE version 5.0. The modular code system is developed and maintained by ORNL and is readily validated and accepted for use in thermal reactor analysis around...

Pritchard, Megan Leigh

2009-05-15T23:59:59.000Z

56

SAS4A LMFBR whole core accident analysis code  

SciTech Connect

To ensure that public health and safety are protected even under accident conditions in an LMFBR, many accidents are analyzed for their potential consequences. Extremely unlikely accidents that might lead to melting of reactor fuel and release of radioactive fission products are referred to as hypothetical core disruptive accidents (HCDAs). The evaluation of such accidents involves the simultaneous evaluation of thermal, mechanical, hydraulic and neutronic processes and their interactions. The complexity of this analysis requires the use of large, integrated computer codes which address the response of the reactor core and several important systems. The SAS family of codes, developed at Argonne National Laboratory, provides such an analysis capability. The SAS4A code, the latest generation of this series of codes, has recently been completed and released for use to the LMFBR safety community. This paper will summarize the important new capabilitites of this analysis tool and illustrate an application of the integrated capability, while highlighting the importance of specific phenomenological models.

Weber, D.P.; Birgersson, G.; Bordner, G.L.; Briggs, L.L.; Cahalan, J.E.; Dunn, F.E.; Kalimullah; Miles, K.J.; Prohammer, F.G.; Tentner, A.M.

1985-01-01T23:59:59.000Z

57

Development of a multicell methodology to account for heterogeneous core effects in the core-analysis diffusion code  

SciTech Connect

In CANDU R reactor calculations, the lattice-cell cross sections are calculated with WIMS-AECL, and the three-dimensional core neutron-flux and power distributions are calculated with RFSP-IST. The lattice-cell cross sections employed in RFSP-IST and in many other commercial core-analysis diffusion codes are usually based on the use of single-lattice-cell calculations, without considering the effects of the environment. This approximation is not sufficiently accurate for heterogeneous core configurations in the ACR-1000{sup TM}. A multicell correction method is therefore developed in RFSP-IST to account for heterogeneous core effects in the design and analysis of ACR-1000. The calculation results show that the multicell methodology developed in RFSP-IST is effective, generic, and it works well for ACR core analysis. (authors)

Shen, W. [Atomic Energy of Canada Limited, 2251 Speakman Drive, Mississauga, Ont. L5K 1B2 (Canada)

2006-07-01T23:59:59.000Z

58

Criticality Benchmark Analysis of the HTTR Annular Startup Core Configurations  

SciTech Connect

One of the high priority benchmarking activities for corroborating the Next Generation Nuclear Plant (NGNP) Project and Very High Temperature Reactor (VHTR) Program is evaluation of Japan's existing High Temperature Engineering Test Reactor (HTTR). The HTTR is a 30 MWt engineering test reactor utilizing graphite moderation, helium coolant, and prismatic TRISO fuel. A large amount of critical reactor physics data is available for validation efforts of High Temperature Gas-cooled Reactors (HTGRs). Previous international reactor physics benchmarking activities provided a collation of mixed results that inaccurately predicted actual experimental performance.1 Reevaluations were performed by the Japanese to reduce the discrepancy between actual and computationally-determined critical configurations.2-3 Current efforts at the Idaho National Laboratory (INL) involve development of reactor physics benchmark models in conjunction with the International Reactor Physics Experiment Evaluation Project (IRPhEP) for use with verification and validation methods in the VHTR Program. Annular cores demonstrate inherent safety characteristics that are of interest in developing future HTGRs.

John D. Bess

2009-11-01T23:59:59.000Z

59

Core Analysis For The Development And Constraint Of Physical Models Of  

Open Energy Info (EERE)

For The Development And Constraint Of Physical Models Of For The Development And Constraint Of Physical Models Of Geothermal Reservoirs Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Report: Core Analysis For The Development And Constraint Of Physical Models Of Geothermal Reservoirs Details Activities (2) Areas (2) Regions (0) Abstract: Effective reservoir exploration, characterization, and engineering require a fundamental understanding of the geophysical properties of reservoir rocks and fracture systems. Even in the best of circumstances, spatial variability in porosity, fracture density, salinity, saturation, tectonic stress, fluid pressures, and lithology can all potentially produce and/or contribute to geophysical anomalies. As a result, serious uniqueness problems frequently occur when interpreting

60

SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis  

SciTech Connect

Core thermal-hydraulic design and performance analyses for Liquid Metal Fast Breeder Reactors (LMFBRs) require repeated detailed multiassembly calculations to determine radial temperature profiles and subchannel outlet temperatures for various core configurations and subassembly structural analyses. At steady-state, detailed core-wide temperature profiles are required for core restraint calculations and subassembly structural analysis. In addition, sodium outlet temperatures are routinely needed for each reactor operating cycle. The SUPERENERGY-2 thermal-hydraulic code was designed specifically to meet these designer needs. It is applicable only to steady-state, forced-convection flow in LMFBR core geometries.

Basehore, K.L.; Todreas, N.E.

1980-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Core analysis in a low permeability sandstone reservoir: Results from the Multiwell Experiment  

SciTech Connect

Over 4100 ft (1100 ft oriented) of Mesaverde core was taken during the drilling of the three Multiwell Experiment (MWX) wells, for study in a comprehensive core analysis program. This core traversed five separate depositional environments (shoreline/marine, coastal, paludal, fluvial, and paralic), and almost every major sand in the Mesaverde at the site was sampled. This paper summarizes MWX core analysis and describes the petrophysical properties at the MWX site; reservoir parameters, including permeabilities of naturally fractured core; and mechanical rock properties including stress-related measurements. Some correlations are made between reservoir properties and mineralogy/petrology data. Comparisons are made between the properties of lenticular and blanket sandstone morphologies existing at the site. This paper provides an overview of a complete core analysis in a low-permeability sandstone reservoir. 66 refs., 17 figs. , 9 tabs.

Sattler, A.R.

1989-04-01T23:59:59.000Z

62

9,400 years of cosmic radiation and solar activity from ice cores and tree rings  

E-Print Network (OSTI)

9,400 years of cosmic radiation and solar activity from ice cores and tree rings Friedhelm, University of Tokyo, 5-1-5 Kashiwanoha, Kashiwa 277-8582, Japan Edited by Timothy Patterson, Carleton) Understanding the temporal variation of cosmic radiation and solar activity during the Holocene is essential

Wehrli, Bernhard

63

Tank 241-SY-101 push mode core sampling and analysis plan  

SciTech Connect

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for push mode core samples from tank 241-SY-101 (SY-101). It is written in accordance with Data Quality Objective to Support Resolution of the Flammable Gas Safety Issue (Bauer 1998), Low Activity Waste Feed Data Quality Objectives (Wiemers and Miller 1997 and DOE 1998), Data Quality Objectives for TWRS Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for Low-Activity Waste Feed Batch X (Certa 1998), and the Tank Safety Screening Data Quality Objective (Dukelow et al. 1995). The Tank Characterization Technical Sampling Basis document (Brown et al. 1998) indicates that these issues apply to tank SY-101 for this sampling event. Brown et al. also identifies high-level waste, regulatory, pretreatment and disposal issues as applicable issues for this tank. However, these issues will not be addressed via this sampling event.

CONNER, J.M.

1998-10-09T23:59:59.000Z

64

Core Analysis At U.S. West Region (Laney, 2005) | Open Energy Information  

Open Energy Info (EERE)

U.S. West Region (Laney, 2005) U.S. West Region (Laney, 2005) Exploration Activity Details Location U.S. West Region Exploration Technique Core Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Characterization and Conceptual Modeling of Magmatically-Heated and Deep-Circulation, High-Temperature Hydrothermal Systems in the Basin and Range and Cordilleran United States, Moore, Nash, Nemcok, Lutz, Norton, Kaspereit, Berard, van de Putte, Johnson and Deymonaz. Utilizing a wealth of formerly proprietary subsurface samples and datasets for exemplary high-temperature western U.S. geothermal systems, develop and publish detailed and refined new conceptual and numerical hydrothermal-history models of fundamental scientific import but, more importantly, of use to geothermal explorationists and developers as they seek to enhance and

65

Standardizing Activation Analysis: New Software for Photon Activation Analysis  

SciTech Connect

Photon Activation Analysis (PAA) of environmental, archaeological and industrial samples requires extensive data analysis that is susceptible to error. For the purpose of saving time, manpower and minimizing error, a computer program was designed, built and implemented using SQL, Access 2007 and asp.net technology to automate this process. Based on the peak information of the spectrum and assisted by its PAA library, the program automatically identifies elements in the samples and calculates their concentrations and respective uncertainties. The software also could be operated in browser/server mode, which gives the possibility to use it anywhere the internet is accessible. By switching the nuclide library and the related formula behind, the new software can be easily expanded to neutron activation analysis (NAA), charged particle activation analysis (CPAA) or proton-induced X-ray emission (PIXE). Implementation of this would standardize the analysis of nuclear activation data. Results from this software were compared to standard PAA analysis with excellent agreement. With minimum input from the user, the software has proven to be fast, user-friendly and reliable.

Sun, Z. J.; Wells, D.; Green, J. [Idaho Accelerator Center, Idaho State University, 921 S. 8th Ave. Pocatello, ID 83209-8263 (United States); Department of Physics, Idaho State University, 921 S. 8th Ave. Pocatello, ID 83209-8106 (United States); Segebade, C. [Federal Institute for Materials Research and Testing, Unter den Eichen 87, Berlin 12205 (Germany)

2011-06-01T23:59:59.000Z

66

Neutron Activation Analysis of Archaeological Artefacts  

Science Journals Connector (OSTI)

17 December 1970 research-article Neutron Activation Analysis of Archaeological...have been determined by non-destructive neutron activation analysis. Examples are given...1971065519 applications archaeology neutron activation analysis radioactivity 1969...

1970-01-01T23:59:59.000Z

67

Model for LMFBR core transient analysis in real time  

SciTech Connect

Plant safety as well as plant availability can be significantly improved if functions such as data validation, plant state verification, and fault identification are automated. A methodology for automation of these functions was presented in an earlier paper. To implement this methodology, plant models that run significantly faster than real transient time are needed. Such models for the intermediate heat exchanger and a once-through liquid-metal fast breeder reactor (LMFBR) steam generator have been presented. This paper discusses the modeling of LMFBR core transients. It is shown that, with a proper choice of shape functions, a nodal approximation of the coolant, cladding, and fuel temperature distributions leads to adequately accurate power and temperature predictions, as well as adequately short computation times. From the point of view of operational safety, it is desirable to terminate a transient before sodium boiling is initiated in the core. Thus, only the modeling of the preboiling phase of core transients is discussed.

Tzanos, C.P.

1986-01-01T23:59:59.000Z

68

Model for LMFBR core transient analysis in real-time  

SciTech Connect

This paper discusses the modeling of LMFBR core transients. It is shown that with a proper choice of shape functions a nodal approximation of the coolant, cladding, and fuel temperature distributions leads to adequately accurate power and temperature predictions, as well as adequately short computation times.

Tzanos, C.P.

1986-01-01T23:59:59.000Z

69

Supplemental Text Analysis of the ice core samples  

E-Print Network (OSTI)

into a continuous sequence of samples (NIF2, 2197 samples; NIF3, 1980 samples; SIF1, 706 samples; SIF2, 834 samples and the sixth core, NIF1 (drilled one meter from NIF2) has been reserved for other measurements such as AMS 14 C. These comments follow the dating discussion in chronological order. The net down wasting of the NIF (as discussed

Massachusetts at Amherst, University of

70

Thermal hydraulic performance analysis of a small integral pressurized water reactor core  

E-Print Network (OSTI)

A thermal hydraulic analysis of the International Reactor Innovative and Secure (IRIS) core has been performed. Thermal margins for steady state and a selection of Loss Of Flow Accidents have been assessed using three ...

Blair, Stuart R. (Stuart Ryan), 1972-

2003-01-01T23:59:59.000Z

71

PeV neutrinos observed by IceCube from cores of active galactic nuclei  

Science Journals Connector (OSTI)

I show that the high energy neutrino flux predicted to arise from active galactic nuclei cores can explain the PeV neutrinos detected by IceCube without conflicting with the constraints from the observed extragalactic cosmic-ray and ?-ray backgrounds.

Floyd W. Stecker

2013-08-15T23:59:59.000Z

72

Comparative analysis of core drilling and rotary drilling in volcanic terrane  

SciTech Connect

Initially, the goal of this report is to compare and contrast penetration rates of rotary-mud drilling and core drilling in young volcanic terranes. It is widely recognized that areas containing an abundance of recent volcanic rocks are excellent targets for geothermal resources. Exploration programs depend heavily upon reliable subsurface information, because surface geophysical methods may be ineffective, inconclusive, or both. Past exploration drilling programs have mainly relied upon rotary-mud rigs for virtually all drilling activity. Core-drilling became popular several years ago, because it could deal effectively with two major problems encountered in young volcanic terranes: very hard, abrasive rock and extreme difficulty in controlling loss of circulation. In addition to overcoming these difficulties, core-drilling produced subsurface samples (core) that defined lithostratigraphy, structure and fractures far better than drill-chips. It seemed that the only negative aspect of core drilling was cost. The cost-per-foot may be two to three times higher than an ''initial quote'' for rotary drilling. In addition, penetration rates for comparable rock-types are often much lower for coring operations. This report also seeks to identify the extent of wireline core drilling (core-drilling using wireline retrieval) as a geothermal exploration tool. 25 refs., 21 figs., 13 tabs.

Flynn, T.; Trexler, D.T.; Wallace, R.H. Jr. (ed.)

1987-04-01T23:59:59.000Z

73

Assessment of WIMS-AECL/RFSP for CANDU core analysis  

SciTech Connect

The code system used for the design of, currently operating Canada deuterium uranium (CANDU) reactors consists of the cell code POWDERPUFS-V and the finite difference code RFSP. The use of POWDERPUFS-V is limited to natural uranium fuel because of the empirical correlations implemented. For the advanced CANDU fuel cycle using spent pressurized water reactor fuel in CANDU (DUPIC), it is necessary to adopt a lattice code that has a general application in isotopics and geometry modeling. For the DUPIC fuel cycle, it was decided to use WIMS-AECL and RFSP for the lattice parameter generation and core simulation, respectively, with the ENDF/B-V nuclear data processed for WIMS-AECL by Atomic Energy of Canada (AECL).

Choi, Hangbok; Rhee, Bo W.; Park, Hyunsoo [Korea Atomic Energy Research Institute, Daejon (Korea, Democratic People`s Republic of)

1995-12-31T23:59:59.000Z

74

Over Core Stress | Open Energy Information  

Open Energy Info (EERE)

Over Core Stress Over Core Stress Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Over Core Stress Details Activities (1) Areas (1) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Rock Lab Analysis Parent Exploration Technique: Rock Lab Analysis Information Provided by Technique Lithology: Stratigraphic/Structural: Hydrological: Thermal: Dictionary.png Over Core Stress: No definition has been provided for this term. Add a Definition Related Techniques Rock Lab Analysis Core Analysis Cuttings Analysis Isotopic Analysis- Rock Over Core Stress Paleomagnetic Measurements Petrography Analysis Rock Density X-Ray Diffraction (XRD) X-Ray Fluorescence (XRF) References Page Area Activity Start Date Activity End Date Reference Material

75

Analysis Activities at Pacific Northwest National Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on PNNL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

76

Analysis Activities at Oak Ridge National Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on ORNL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

77

Analysis Activities at National Renewable Energy Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on NREL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

78

Analysis Activities at Sandia National Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on SNL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

79

Analysis Activities at Lawrence Livermore National Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on Lawrence Livermore’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

80

Core image analysis of matrix porosity in The Geysers reservoir  

SciTech Connect

Adsorption is potentially an important consideration when calculating reserves at The Geysers. Our investigations of the mineralogical relationships in core samples have shown matrix pore spaces to be largely associated with fractures. Dissolution of calcite from hydrothermal veins increases porosity in the graywacke reservoir. The high relative surface area of secondary alteration phases could promote adsorption. In order to quantify porosity distribution and surface area, Scanning Electron Microscope (SEM) images were analyzed using software developed for the interpretation of satellite imagery, This software classifies the images as either crystal or pore and then accumulates data on pore size, total porosity and surface area of the mineral-pore interface. Review of literature shows that data on thickness of adsorbed water layer does not exist for many of the mineral phases of interest in The Geysers. We have assumed thicknesses of 10, 100, and 5300 Angstroms for the adsorbed layer and calculated the relative proportions of adsorbed water. These calculations show 0.005%, 0.05%, and 2.5% of total water would be adsorbed using the above thicknesses.

Nielson, Dennis L.; Nash, Greg; Hulen, Jeffrey B.; Tripp, Alan C.

1993-01-28T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling  

SciTech Connect

Collecting and preserving undamaged core samples containing gas hydrates from depth is difficult because of the pressure and temperature changes encountered upon retrieval. Hydrate-bearing core samples were collected at the BPXA-DOE-USGS Mount Elbert Gas Hydrate Stratigraphic Test Well in February 2007. Coring was performed while using a custom oil-based drilling mud, and the cores were retrieved by a wireline. The samples were characterized and subsampled at the surface under ambient winter arctic conditions. Samples thought to be hydrate bearing were preserved either by immersion in liquid nitrogen (LN), or by storage under methane pressure at ambient arctic conditions, and later depressurized and immersed in LN. Eleven core samples from hydrate-bearing zones were scanned using x-ray computed tomography to examine core structure and homogeneity. Features observed include radial fractures, spalling-type fractures, and reduced density near the periphery. These features were induced during sample collection, handling, and preservation. Isotopic analysis of the methane from hydrate in an initially LN-preserved core and a pressure-preserved core indicate that secondary hydrate formation occurred throughout the pressurized core, whereas none occurred in the LN-preserved core, however no hydrate was found near the periphery of the LN-preserved core. To replicate some aspects of the preservation methods, natural and laboratory-made saturated porous media samples were frozen in a variety of ways, with radial fractures observed in some LN-frozen sands, and needle-like ice crystals forming in slowly frozen clay-rich sediments. Suggestions for hydrate-bearing core preservation are presented.

Kneafsey, Timothy J.; Lu, Hailong; Winters, William; Boswell, Ray; Hunter, Robert; Collett, Timothy S.

2009-09-01T23:59:59.000Z

82

Lattice-Strain Control of the Activity in Dealloyed Core-Shell Fuel Cell Catalysts  

SciTech Connect

Electrocatalysis will play a key role in future energy conversion and storage technologies, such as water electrolysers, fuel cells and metal–air batteries. Molecular interactions between chemical reactants and the catalytic surface control the activity and efficiency, and hence need to be optimized; however, generalized experimental strategies to do so are scarce. Here we show how lattice strain can be used experimentally to tune the catalytic activity of dealloyed bimetallic nanoparticles for the oxygen-reduction reaction, a key barrier to the application of fuel cells and metal–air batteries. We demonstrate the core–shell structure of the catalyst and clarify the mechanistic origin of its activity. The platinum-rich shell exhibits compressive strain, which results in a shift of the electronic band structure of platinum and weakening chemisorption of oxygenated species. We combine synthesis, measurements and an understanding of strain from theory to generate a reactivity–strain relationship that provides guidelines for tuning electrocatalytic activity.

Strasser, Peter; Shirlaine, Koh; Anniyev, Toyli; Greeley, Jeffrey P.; More, Karren L.; Yu, Chengfei; Liu, Zengcai; Kaya, Sarp; Nordlund, Dennis; Ogasawara, Hirohito; Toney, Michael F.; Nilsson, Anders R.

2010-04-30T23:59:59.000Z

83

Lattice-Strain Control of the Activity in Dealloyed Core-Shell Fuel Cell Catalysts  

SciTech Connect

Electrocatalysis will play a key role in future energy conversion and storage technologies, such as water electrolysers, fuel cells and metal-air batteries. Molecular interactions between chemical reactants and the catalytic surface control the activity and efficiency, and hence need to be optimized; however, generalized experimental strategies to do so are scarce. Here we show how lattice strain can be used experimentally to tune the catalytic activity of dealloyed bimetallic nanoparticles for the oxygen-reduction reaction, a key barrier to the application of fuel cells and metal-air batteries. We demonstrate the core-shell structure of the catalyst and clarify the mechanistic origin of its activity. The platinum-rich shell exhibits compressive strain, which results in a shift of the electronic band structure of platinum and weakening chemisorption of oxygenated species. We combine synthesis, measurements and an understanding of strain from theory to generate a reactivity-strain relationship that provides guidelines for tuning electrocatalytic activity.

Strasser, P. [Berlin Institute of Technology (Technische Universitat Berlin); Koh, Shirlaine [University of Houston, Houston; Anniyev, Toyli [SLAC National Accelerator Laboratory; Greeley, Jeff [Argonne National Laboratory (ANL); More, Karren Leslie [ORNL; Yu, Chengfei [University of Houston, Houston; Liu, Zengcai [University of Houston, Houston; Kaya, Sarpa [SLAC National Accelerator Laboratory; Nordlund, Dennis [SLAC National Accelerator Laboratory; Ogasawara, Hirohito [SLAC National Accelerator Laboratory; Toney, Michael F. [SLAC National Accelerator Laboratory; Anders, Nilsson [SLAC National Accelerator Laboratory

2010-01-01T23:59:59.000Z

84

Thermal hydraulic aspects in the analysis of LMFBR disrupted-core situations  

SciTech Connect

This paper presents the thermal-hydraulic aspects of current interest in the modeling of LMFBR hypothetical core-disruptive accidents, with special emphasis on the Loss of Flow situations. The models presented have been incorporated in LEVITATE, a code for the analysis of fuel and cladding dynamics under LOF conditions, which has recently become part of the SAS4A code system. The influence of different thermal-hydraulic models on fuel motion is illustrated by a comparison between the results calculated by LEVITATE, the data from the L7-TREAT experiment and the results calculated by SLUMPY. The results calculated by LEVITATE are in fair agreement with the experimentally observed early fuel dispersal. The marginally acceptable energetic events obtained in the analysis of high void-worth LMFBR cores during Loss-of-Flow transients coupled with uncertainties about some of the thermal-hydraulic parameters motivate, among other factors, the need for the design low void-worth LMFBR cores.

Tentner, A.M.; Wider, H.U.

1981-01-01T23:59:59.000Z

85

Ex-Core CFD Analysis Results for the Prometheus Gas Reactor  

SciTech Connect

This paper presents the initial nozzle-to-nozzle (N2N) reactor vessel model scoping studies using computational fluid dynamics (CFD) analysis methods. The N2N model has been solved under a variety of different boundary conditions. This paper presents some of the basic hydraulic results from the N2N CFD analysis effort. It also demonstrates how designers were going to apply the analysis results to modify a number of the design features. The initial goals for developing a preliminary CFD N2N model were to establish baseline expectations for pressure drops and flow fields around the reactor core. Analysis results indicated that the averaged reactor vessel pressure drop for all analyzed cases was 46.9 kPa ({approx}6.8 psid). In addition, mass flow distributions to the three core fuel channel regions exhibited a nearly inverted profile to those specified for the in-core thermal/hydraulic design. During subsequent design iterations, the goal would have been to modify or add design features that would have minimized reactor vessel pressure drop and improved flow distribution to the inlet of the core.

Lorentz, Donald G. [Space Engineering, Bechtel Bettis, Inc. West Mifflin, PA 15122 (United States)

2007-01-30T23:59:59.000Z

86

Development of integrated core disruptive accident analysis code for FBR - ASTERIA-FBR  

SciTech Connect

The evaluation of consequence at the severe accident is the most important as a safety licensing issue for the reactor core of liquid metal cooled fast breeder reactor (LMFBR), since the LMFBR core is not in an optimum condition from the viewpoint of reactivity. This characteristics might induce a super-prompt criticality due to the core geometry change during the core disruptive accident (CDA). The previous CDA analysis codes have been modeled in plural phases dependent on the mechanism driving a super-prompt criticality. Then, the following event is calculated by connecting different codes. This scheme, however, should introduce uncertainty and/or arbitrary to calculation results. To resolve the issues and obtain the consistent calculation results without arbitrary, JNES is developing the ASTERIA-FBR code for the purpose of providing the cross-check analysis code, which is another required scheme to confirm the validity of the evaluation results prepared by applicants, in the safety licensing procedure of the planned high performance core of Monju. ASTERIA-FBR consists of the three major calculation modules, CONCORD, dynamic-GMVP, and FEMAXI-FBR. CONCORD is a three-dimensional thermal-hydraulics calculation module with multi-phase, multi-component, and multi-velocity field model. Dynamic-GMVP is a space-time neutronics calculation module. FEMAXI-FBR calculates the fuel pellet deformation behavior and fuel pin failure behavior. This paper describes the needs of ASTERIA-FBR development, major module outlines, and the model validation status. (authors)

Ishizu, T.; Endo, H.; Tatewaki, I.; Yamamoto, T. [Japan Nuclear Energy Safety Organization JNES, Toranomon Towers Office, 4-1-28, Toranomon, Minato-ku, Tokyo (Japan); Shirakawa, N. [Inst. of Applied Energy IAE, Shimbashi SY Bldg., 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo (Japan)

2012-07-01T23:59:59.000Z

87

DIAGNOSING THE TIME DEPENDENCE OF ACTIVE REGION CORE HEATING FROM THE EMISSION MEASURE. II. NANOFLARE TRAINS  

SciTech Connect

The time dependence of heating in solar active regions can be studied by analyzing the slope of the emission measure distribution coolward of the peak. In a previous study we showed that low-frequency heating can account for 0% to 77% of active region core emission measures. We now turn our attention to heating by a finite succession of impulsive events for which the timescale between events on a single magnetic strand is shorter than the cooling timescale. We refer to this scenario as a 'nanoflare train' and explore a parameter space of heating and coronal loop properties with a hydrodynamic model. Our conclusions are (1) nanoflare trains are consistent with 86% to 100% of observed active region cores when uncertainties in the atomic data are properly accounted for; (2) steeper slopes are found for larger values of the ratio of the train duration {Delta} {sub H} to the post-train cooling and draining timescale {Delta} {sub C}, where {Delta} {sub H} depends on the number of heating events, the event duration and the time interval between successive events ({tau} {sub C}); (3) {tau} {sub C} may be diagnosed from the width of the hot component of the emission measure provided that the temperature bins are much smaller than 0.1 dex; (4) the slope of the emission measure alone is not sufficient to provide information about any timescale associated with heating-the length and density of the heated structure must be measured for {Delta} {sub H} to be uniquely extracted from the ratio {Delta} {sub H}/{Delta} {sub C}.

Reep, J. W.; Bradshaw, S. J. [Department of Physics and Astronomy, Rice University, Houston, TX 77005 (United States)] [Department of Physics and Astronomy, Rice University, Houston, TX 77005 (United States); Klimchuk, J. A., E-mail: jeffrey.reep@rice.edu, E-mail: stephen.bradshaw@rice.edu, E-mail: james.a.klimchuk@nasa.gov [NASA Goddard Space Flight Center, Solar Physics Lab., Code 671, 8800 Greenbelt Road, Greenbelt, MD 20771 (United States)

2013-02-20T23:59:59.000Z

88

OUTFLOWS AND DARK BANDS AT ARCADE-LIKE ACTIVE REGION CORE BOUNDARIES  

SciTech Connect

Observations from the EUV Imaging Spectrometer (EIS) on board Hinode have revealed outflows and non-thermal line broadening in low intensity regions at the edges of active regions (ARs). We use data from Hinode's EIS, Solar Dynamic Observatory's Atmospheric Imaging Assembly and Helioseismic and Magnetic Imager, and the Transition Region and Coronal Explorer instrument to investigate the boundaries of arcade-like AR cores for NOAA ARs 11112, 10978, and 9077. A narrow, low intensity region that is observed at the core's periphery as a dark band shows outflows and increased spectral line broadening. This dark band is found to exist for days and appears between the bright coronal loop structures of different coronal topologies. We find a case where the dark band region is formed between the magnetic field from emerging flux and the field of the pre-existing flux. A magnetic field extrapolation indicates that this dark band is coincident with the spine lines or magnetic separatrices in the extrapolated field. This occurs over unipolar regions where the brightened coronal field is separated in connectivity and topology. This separation does not appear to be infinitesimal and an initial estimate of the minimum distance of separation is found to be Almost-Equal-To 1.5-3.5 Mm.

Scott, J. T.; Martens, P. C. H.; Tarr, L. [Department of Physics, Montana State University, Bozeman, MT 59717 (United States)

2013-03-10T23:59:59.000Z

89

E-Print Network 3.0 - active region core Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

the core is controlled... by the rate at which the mantle can remove heat. Rapid core cooling favours the operation of a geodynamo Source: Nimmo, Francis - Department of Earth...

90

Neutronic analysis of the conversion of HEU to LEU fuel for a 5-MW MTR core  

SciTech Connect

In recent years, due to cessation of highly enriched uranium (HEU) fuel supply, practical steps have been taken to substitute HEU fuel in almost all research reactors by medium-enriched uranium or low-enriched uranium (LEU) fuels. In this study, a neutronic calculation of a 5-MW research reactor core fueled with HEU (93% /sup 235/U) is presented. In order to assess the performance of the core with the LEU (< 20%) fuel replacement, while keeping fuel element geometry nearly unchanged, several different /sup 235/U loadings were examined. The core consists of 22 standard fuel elements (SFEs) and 6 control fuel elements (CFEs). Each fuel elements has 18 curved plates of which two end plates are dummies. Initial /sup 235/U content is 195 g /sup 235/U/SFE and 9.7 g /sup 235/U/CFE or /PFE. In all calculations the permitted changes to the fuel elements are (a) 18 active plates per SFE, (b) fuel plates assumed to be flat, and (c) 8 or 9 active plates per CFE.

Pazirandeh, A.; Bartsch, G.

1987-01-01T23:59:59.000Z

91

Transportation activity analysis using smartphones  

E-Print Network (OSTI)

Transportation activity surveys investigate when, where and how people travel in urban areas to provide information necessary for urban transportation planning. In Singapore, the Land Transport Authority (LTA) carries out ...

Xiao, Yu

92

Analysis of core damage frequency from internal events: Peach Bottom, Unit 2  

SciTech Connect

This document contains the internal event initiated accident sequence analyses for Peach Bottom, Unit 2; one of the reference plants being examined as part of the NUREG-1150 effort by the Nuclear Regulatory Commission. NUREG-1150 will document the risk of a selected group of nuclear power plants. As part of that work, this report contains the overall core damage frequency estimate for Peach Bottom, Unit 2, and the accompanying plant damage state frequencies. Sensitivity and uncertainty analyses provided additional insights regarding the dominant contributors to the Peach Bottom core damage frequency estimate. The mean core damage frequency at Peach Bottom was calculated to be 8.2E-6. Station blackout type accidents (loss of all ac power) were found to dominate the overall results. Anticipated Transient Without Scram accidents were also found to be non-negligible contributors. The numerical results are largely driven by common mode failure probability estimates and to some extent, human error. Because of significant data and analysis uncertainties in these two areas (important, for instance, to the most dominant scenario in this study), it is recommended that the results of the uncertainty and sensitivity analyses be considered before any actions are taken based on this analysis.

Kolaczkowski, A.M.; Lambright, J.A.; Ferrell, W.L.; Cathey, N.G.; Najafi, B.; Harper, F.T.

1986-10-01T23:59:59.000Z

93

Tank 241-AZ-102 Privatization Push Mode Core Sampling and Analysis Plan  

SciTech Connect

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for samples obtained from tank 241-AZ-102. The purpose of this sampling event is to obtain information about the characteristics of the contents of 241-AZ-102. Push mode core samples will be obtained from risers 15C and 24A to provide sufficient material for the chemical analyses and tests required to satisfy these data quality objectives. The 222-S Laboratory will extrude core samples, composite the liquids and solids, perform chemical analyses, and provide subsamples to the Process Chemistry Laboratory. The Process Chemistry Laboratory will prepare test plans and perform process tests to evaluate the behavior of the 241-AZ-102 waste undergoing the retrieval and treatment scenarios defined in the applicable DQOs. Requirements for analyses of samples originating in the process tests will be documented in the corresponding test plan.

TEMPLETON, A.M.

1999-07-08T23:59:59.000Z

94

Low time resolution analysis of polar ice cores cannot detect impulsive nitrate events  

E-Print Network (OSTI)

Ice cores are archives of climate change and possibly large solar proton events (SPEs). Wolff et al. (2012) used a single event, a nitrate peak in the GISP2-H core, which McCracken et al. (2001a) time associated with the poorly quantified 1859 Carrington event, to discredit SPE-produced, impulsive nitrate deposition in polar ice. This is not the ideal test case. We critique the Wolff et al. analysis and demonstrate that the data they used cannot detect impulsive nitrate events because of resolution limitations. We suggest re-examination of the top of the Greenland ice sheet at key intervals over the last two millennia with attention to fine resolution and replicate sampling of multiple species. This will allow further insight into polar depositional processes on a sub-seasonal scale, including atmospheric sources, transport mechanisms to the ice sheet, post-depositional interactions, and a potential SPE association.

Smart, D F; Melott, A L; Laird, C M

2015-01-01T23:59:59.000Z

95

Classification of Hepatitis C Virus Type 2 Isolates by Phylogenetic Analysis of Core and NS5 Regions  

Science Journals Connector (OSTI)

...Virus Type 2 Isolates by Phylogenetic Analysis of Core and NS5 Regions Mauro Pistello Fabrizio Maggi Claudia Fornai Alessandro Leonildi Antonietta Morrica Maria Linda Vatteroni Mauro Bendinelli Retrovirus Center and Virology Section Department of Biomedicine...

Mauro Pistello; Fabrizio Maggi; Claudia Fornai; Alessandro Leonildi; Antonietta Morrica; Maria Linda Vatteroni; Mauro Bendinelli

1999-06-01T23:59:59.000Z

96

Delayed neutron activation analysis for safeguards  

Science Journals Connector (OSTI)

Delayed neutron activation analysis (DNAA) presents a fast, accurate, and reliable method for quantification of fissile material. The method has relatively few sources of error and may be accomplished nondestruct...

D. C. Glasgow

2008-04-01T23:59:59.000Z

97

Thermal hydraulic method for whole core design analysis of an HTGR  

SciTech Connect

A new thermal hydraulic method and initial results are presented for core-wide steady state analysis of prismatic High Temperature Gas-Cooled Reactors (HTGR). The method allows for the complete solution of temperature and coolant mass flow distribution by solving quasi-steady energy balances for the discretized core. Assembly blocks are discretized into unit cells for which the average temperature of each unit cell is determined. Convective heat removal is coupled to the unit cell energy balances by a 1-D axial flow model. The flow model uses established correlations for friction factor and Nusselt number. Bypass flow is explicitly calculated by using an initial guess for mass flow distribution and determining the exit pressure of each flow channel. The mass flow distribution is updated until a uniform core exit pressure condition is reached. Results are obtained for the MHTGR-350 with emphasis on the change in thermal hydraulic parameters due to various steady state power profiles and bypass gap widths. Steady state temperature distribution and its variations are discussed. (authors)

Huning, A. J.; Garimella, S. [George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA (United States)

2013-07-01T23:59:59.000Z

98

TRACE/PARCS Core Modeling of a BWR/5 for Accident Analysis of ATWS Events  

SciTech Connect

The TRACE/PARCS computational package [1, 2] isdesigned to be applicable to the analysis of light water reactor operational transients and accidents where the coupling between the neutron kinetics (PARCS) and the thermal-hydraulics and thermal-mechanics (TRACE) is important. TRACE/PARCS has been assessed for itsapplicability to anticipated transients without scram(ATWS) [3]. The challenge, addressed in this study, is to develop a sufficiently rigorous input model that would be acceptable for use in ATWS analysis. Two types of ATWS events were of interest, a turbine trip and a closure of main steam isolation valves (MSIVs). In the first type, initiated by turbine trip, the concern is that the core will become unstable and large power oscillations will occur. In the second type,initiated by MSIV closure,, the concern is the amount of energy being placed into containment and the resulting emergency depressurization. Two separate TRACE/PARCS models of a BWR/5 were developed to analyze these ATWS events at MELLLA+ (maximum extended load line limit plus)operating conditions. One model [4] was used for analysis of ATWS events leading to instability (ATWS-I);the other [5] for ATWS events leading to emergency depressurization (ATWS-ED). Both models included a large portion of the nuclear steam supply system and controls, and a detailed core model, presented henceforth.

Cuadra A.; Baek J.; Cheng, L.; Aronson, A.; Diamond, D.; Yarsky, P.

2013-11-10T23:59:59.000Z

99

Analysis of core damage frequency: Peach Bottom, Unit 2 internal events appendices  

SciTech Connect

This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. The mean core damage frequency is 4.5E-6 with 5% and 95% uncertainty bounds of 3.5E-7 and 1.3E-5, respectively. Station blackout type accidents (loss of all ac power) contributed about 46% of the core damage frequency with Anticipated Transient Without Scram (ATWS) accidents contributing another 42%. The numerical results are driven by loss of offsite power, transients with the power conversion system initially available operator errors, and mechanical failure to scram. 13 refs., 345 figs., 171 tabs.

Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L. (Science Applications International Corp., Albuquerque, NM (USA); Sandia National Labs., Albuquerque, NM (USA))

1989-08-01T23:59:59.000Z

100

Analysis of the nuclear measurement program for an optimized BR2 core configuration  

SciTech Connect

This paper presents the analysis of the results of the Nuclear Measurement Program (NMP) executed during the shut-down of cycle 05/2012 of the BR2 reactor. The aim of the NMP was to determine the properties of a reactor core load with a new configuration of the control rods and to evaluate/verify the predicted numerical results by MCNPX. The methods used for the interpretation of the measurement results include combinations of an analytical method for determination of the axial relative control rod efficiency and least square techniques. (authors)

Van Den Branden, G.; Kalcheva, S.; Sikik, E.; Koonen, E. [SCK-CEN, BR2 Reactor, Boeretang 200, Mol, 2400 (Belgium)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Coupling the core analysis program DeCART to the fuel performance application BISON  

SciTech Connect

The 3D neutron transport and core analysis program DeCART was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the method of characteristics) to a high fidelity fuel performance program, both of which can simulate 3D problems. DeCART provides sub-pin level resolution of the multigroup neutron flux, with resonance treatment, during burnup or a fast transient. BISON implicitly solves coupled thermomechanical equations for the fuel on a sub-millimeter level finite element mesh. A method was developed for mapping the fission rate density and fast neutron flux from DeCART to BISON. Multiple depletion cases were run with one-way data transfer from DeCART to BISON. The one-way data transfer of fission rate density is shown to agree with the fission rate density obtained from an internal Lassman-style model in BISON. One-way data transfer was also demonstrated in a 3D case in which azimuthal asymmetry was induced in the fission rate density profile of a fuel rod modeled in DeCART. Two-way data transfer was established by mapping the temperature distribution from BISON to DeCART. A Picard iterative algorithm was developed for the loose coupling with two-way data transfer. (authors)

Gleicher, F. N.; Spencer, B.; Novascone, S.; Williamson, R.; Martineau, R. C. [Idaho National Laboratory, 2525 N. Fremont Avenue, Idaho Falls, ID 83415 (United States); Rose, M.; Downar, T. J.; Collins, B. [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, MI 48105 (United States)

2013-07-01T23:59:59.000Z

102

Neutron Activation Analysis of Manganese and Sodium in Bacterial Cells  

Science Journals Connector (OSTI)

...research-article Metabolism and Products Neutron Activation Analysis of Manganese and Sodium...Columbus, Ohio 43210. The application of neutron activation analysis for mineral determinations...two elements. The results indicate that neutron activation analysis is readily applicable...

Woodrow B. Krueger; Walter E. Carey; Bruno J. Kolodzeij

1970-12-01T23:59:59.000Z

103

Analysis Activities at Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Laboratory Laboratory Operated by The University of Chicago Center for Transportation Research Argonne National Laboratory Argonne National Laboratory Marianne M. Mintz Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. 2 ANL's Charter ANL's Charter ANL's Charter Systems analysis in Energy Systems (CTR), Decision and Information Sciences History of working in partnership with industry Analytical work has spanned the range of: Energy Supply - globally and by region Demand for transportation fuels - globally and region Assessment of vehicle technologies and fuels Economic analysis and interaction between energy prices and macro activity Life-cycle analyses of energy use and environmental impacts associated with

104

Building waste management core indicators through Spatial Material Flow Analysis: Net recovery and transport intensity indexes  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Sustainability and proximity principles have a key role in waste management. Black-Right-Pointing-Pointer Core indicators are needed in order to quantify and evaluate them. Black-Right-Pointing-Pointer A systematic, step-by-step approach is developed in this study for their development. Black-Right-Pointing-Pointer Transport may play a significant role in terms of environmental and economic costs. Black-Right-Pointing-Pointer Policy action is required in order to advance in the consecution of these principles. - Abstract: In this paper, the material and spatial characterization of the flows within a municipal solid waste (MSW) management system are combined through a Network-Based Spatial Material Flow Analysis. Using this information, two core indicators are developed for the bio-waste fraction, the Net Recovery Index (NRI) and the Transport Intensity Index (TII), which are aimed at assessing progress towards policy-related sustainable MSW management strategies and objectives. The NRI approaches the capacity of a MSW management system for converting waste into resources through a systematic metabolic approach, whereas the TII addresses efficiency in terms of the transport requirements to manage a specific waste flow throughout the entire MSW management life cycle. Therefore, both indicators could be useful in assessing key MSW management policy strategies, such as the consecution of higher recycling levels (sustainability principle) or the minimization of transport by locating treatment facilities closer to generation sources (proximity principle). To apply this methodological approach, the bio-waste management system of the region of Catalonia (Spain) has been chosen as a case study. Results show the adequacy of both indicators for identifying those points within the system with higher capacity to compromise its environmental, economic and social performance and therefore establishing clear targets for policy prioritization. Moreover, this methodological approach permits scenario building, which could be useful in assessing the outcomes of hypothetical scenarios, thus proving its adequacy for strategic planning.

Font Vivanco, David, E-mail: font@cml.leidenuniv.nl [Institut de Ciencia i Tecnologia Ambientals (ICTA), Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona (UAB), 08193 Bellaterra, Barcelona (Spain); Institute of Environmental Sciences (CML), Leiden University, P.O. Box 9518, 2300 RA Leiden (Netherlands); Puig Ventosa, Ignasi [ENT Environment and Management, Carrer Sant Joan 39, First Floor, 08800 Vilanova i la Geltru, Barcelona (Spain); Gabarrell Durany, Xavier [Institut de Ciencia i Tecnologia Ambientals (ICTA), Departament d'Enginyeria Quimica, Universitat Autonoma de Barcelona (UAB), 08193 Bellaterra, Barcelona (Spain)

2012-12-15T23:59:59.000Z

105

Processing and geologic analysis of conventional cores from well ER-20-6 No. 1, Nevada Test Site  

SciTech Connect

In 1996, Well Cluster ER-20-6 was drilled on Pahute Mesa in Area 20, in the northwestern corner of the Nevada Test Site (NTS). The three wells of the cluster are located from 166 to 296 meters (m) (544 to 971 feet [ft]) southwest of the site of the underground nuclear test code-named BULLION, conducted in 1990 in Emplacement Hole U-20bd. The well cluster was planned to be the site of a forced-gradient experiment designed to investigate radionuclide transport in groundwater. To obtain additional information on the occurrence of radionuclides, nature of fractures, and lithology, a portion of Well ER-20-6 No. 1, the hole closest to the explosion cavity, was cored for later analysis. Bechtel Nevada (BN) geologists originally prepared the geologic interpretation of the Well Cluster ER-20-6 site and documented the geology of each well in the cluster. However, the cores from Well ER-20-6 No. 1 were not accessible at the time of that work. As the forced-gradient experiment and other radio nuclide migration studies associated with the well cluster progressed, it was deemed appropriate to open the cores, describe the geology, and re-package the core for long-term air-tight storage. This report documents and describes the processing, geologic analysis, and preservation of the conventional cores from Well ER20-6 No. 1.

Prothro, L.B., Townsend, M.J.; Drellack, S.L. Jr. [and others

1997-09-01T23:59:59.000Z

106

Measurements and analysis of control rod worths in large heterogeneous LMFBR cores  

SciTech Connect

The ZPPR-13 program provides basic physics data for heterogeneous LMFBR cores of 700 MW(e) size. A number of internal blanket variations were studied and measurements of control rod worths were made in each configuration. The cores are sensitive to asymmetric perturbations and have strong interaction effects between control rods. Calculations with ENDF/B-IV data are within about 5% of experimental values but show systematic variations in accuracy of prediction with location in the core.

Collins, P.J.; Brumbach, S.B.; Carpenter, S.G.

1984-01-01T23:59:59.000Z

107

Neutron Activation Analysis for the Demonstration of Amphibolite Rock-Weathering Activity of a Yeast  

Science Journals Connector (OSTI)

...research-article General Microbial Ecology Neutron Activation Analysis for the Demonstration...University of Kiel, Kiel, Germany Neutron activation analysis was employed in a...demonstrated by comparing a spectrum of neutron-activated amphibolite powder (particle...

E. Rades-Rohkohl; P. Hirsch; O. Fränzle

1979-12-01T23:59:59.000Z

108

AN ANALYSIS OF THE DEUTERIUM FRACTIONATION OF STAR-FORMING CORES IN THE PERSEUS MOLECULAR CLOUD  

SciTech Connect

We have performed a pointed survey of N{sub 2}D{sup +} 2-1 and N{sub 2}D{sup +} 3-2 emission toward 64 N{sub 2}H{sup +}-bright starless and protostellar cores in the Perseus molecular cloud using the Arizona Radio Observatory Submillimeter Telescope and Kitt Peak 12 m telescope. We find a mean deuterium fractionation in N{sub 2}H{sup +}, R{sub D} = N(N{sub 2}D{sup +})/N(N{sub 2}H{sup +}), of 0.08, with a maximum R{sub D} = 0.2. In detected sources, we find no significant difference in the deuterium fractionation between starless and protostellar cores, nor between cores in clustered or isolated environments. We compare the deuterium fraction in N{sub 2}H{sup +} with parameters linked to advanced core evolution. We only find significant correlations between the deuterium fraction and increased H{sub 2} column density, as well as with increased central core density, for all cores. Toward protostellar sources, we additionally find a significant anticorrelation between R{sub D} and bolometric temperature. We show that the Perseus cores are characterized by low CO depletion values relative to previous studies of star-forming cores, similar to recent results in the Ophiuchus molecular cloud. We suggest that the low average CO depletion is the dominant mechanism that constrains the average deuterium fractionation in the Perseus cores to small values. While current equilibrium and dynamic chemical models are able to reproduce the range of deuterium fractionation values we find in Perseus, reproducing the scatter across the cores requires variation in parameters such as the ionization fraction or the ortho-to-para-H{sub 2} ratio across the cloud, or a range in core evolution timescales.

Friesen, R. K. [National Radio Astronomy Observatory, 520 Edgemont Rd., Charlottesville, VA 22903 (United States)] [National Radio Astronomy Observatory, 520 Edgemont Rd., Charlottesville, VA 22903 (United States); Kirk, H. M. [Origins Institute, McMaster University, 1280 Main Street West, Hamilton, ON L8S 4M1 (Canada)] [Origins Institute, McMaster University, 1280 Main Street West, Hamilton, ON L8S 4M1 (Canada); Shirley, Y. L., E-mail: friesen@di.utoronto.ca [Steward Observatory, University of Arizona, 933 N. Cherry Ave., Tucson, AZ 85721 (United States)

2013-03-01T23:59:59.000Z

109

Analysis of fractures in volcanic cores from Pahute Mesa, Nevada Test Site  

SciTech Connect

The Nevada Test Site (NTS), located in Nye County, southern Nevada, was the location of 828 announced underground nuclear tests, conducted between 1951 and 1992. Approximately one-third of these tests were detonated near or below the water table. An unavoidable consequence of these testing activities was introducing radionuclides into the subsurface environment, impacting groundwater. Groundwater flows beneath the NTS almost exclusively through interconnected natural fractures in carbonate and volcanic rocks. Information about these fractures is necessary to determine hydrologic parameters for future Corrective Action Unit (CAU)-specific flow and transport models which will be used to support risk assessment calculations for the U.S. Department of Energy, Nevada Operations Office (DOE/NV) Underground Test Area (UGTA) remedial investigation. Fracture data are critical in reducing the uncertainty of the predictive capabilities of CAU-specific models because of their usefulness in generating hydraulic conductivity values and dispersion characteristics used in transport modeling. Specifically, fracture aperture and density (spacing) are needed to calculate the permeability anisotropy of the formations. Fracture mineralogy information is used qualitatively to evaluate diffusion and radionuclide retardation potential in transport modeling. All these data can best be collected through examination of core samples.

Drellack, S.L. Jr.; Prothro, L.B.; Roberson, K.E. [and others

1997-09-01T23:59:59.000Z

110

High-resolution crosswell imaging of a west Texas carbonate reservoir. Part 5: Core analysis  

SciTech Connect

The authors conducted a core analysis program to provide supporting data to a series of crosswell field experiments being carried out in McElroy Field by Stanford University`s Seismic Tomography Project. The objective of these experiments is to demonstrate the use of crosswell seismic profiling for reservoir characterization and for monitoring CO{sub 2} flooding. For these west Texas carbonates, they estimate that CO{sub 2} saturation causes P-wave velocity to change by {minus}1.9% (pooled average, range = {minus}6.3 to +0.1%), S-wave velocity by +0.6% (range = 0 to 2.7%), and the P-to-S velocity ratio by {minus}2.4% (range = {minus}6.4 to {minus}0.3%). When one compares these results to the precisions they can expect from traveltime tomography (about {+-} 1% for P- and S-wave velocity and about {+-} 2% for the P-to-S velocity ratio), they conclude that time-lapse traveltime tomography is sensitive enough to resolve changes in the P-wave velocity, S-wave velocity, and P-to-S velocity ratio that result from CO{sub 2} saturation. They concentrated here don the potential for CO{sub 2} saturation to affect seismic velocities. The potential for CO{sub 2} saturation to affect other seismic properties, not discussed here, may prove to be more significant (e.g., P-wave and S-wave impedance).

Nolen-Hoeksema, R.C.; Harris, J.M. [Stanford Univ., CA (United States)] [Stanford Univ., CA (United States); Wang, Z. [Chevron Petroleum Technology Co., La Habra, CA (United States)] [Chevron Petroleum Technology Co., La Habra, CA (United States); Langan, R.T. [Chevron Petroleum Technology Co., La Habra, CA (United States)] [Chevron Petroleum Technology Co., La Habra, CA (United States); [Stanford Univ., CA (United States). Geophysics Dept.

1995-05-01T23:59:59.000Z

111

New aspects in the analysis of loss-of-flow transients for homogeneous and heterogeneous LMFBR cores  

SciTech Connect

This paper presents the results of analyses of unprotected loss-of-flow (LOF) transients which have been performed to date using the new SAS4A code system. Accident histories for homogeneous and heterogeneous demo-sized cores (300 MWe) are compared and emphasis is placed on phenomena occurring after the initiation of fuel motion as described by LEVITATE. LEVITATE is the SAS4A model for the analysis of fuel and cladding dynamics under loss-of-flow (LOF) conditions and is believed to be the most-sophisticated computational tool currently available for fuel-motion analysis. The results of this analysis indicate that the initiation phase of an unprotected loss-of-flow accident has a considerably lower energetics potential in a heterogeneous core than in a homogeneous core. The difference is larger than previously indicated by SAS3D. Better phenomenological models implemented in SAS4A provide increased confidence in this aspect of safety evaluation of LMFBR cores.

Tentner, A.M.; Wider, H.U.

1982-01-01T23:59:59.000Z

112

WWER Expert System for Fuel Failure Analysis Using Data on Primary Coolant Activity  

SciTech Connect

The computer expert system for fuel failure analysis of WWER during operation is presented. The diagnostics is based on the measurement of specific activity of reference nuclides in reactor primary coolant and application of a computer code for the data interpretation. The data analysis includes an evaluation of tramp uranium mass in reactor core, detection of failures by iodine and caesium spikes, evaluation of burnup of defective fuel. Evaluation of defective fuel burnup was carried out by applying the relation of caesium nuclides activity in spikes and relations of activities of gaseous fission products for steady state operational conditions. The method of burnup evaluation of defective fuel by use of fission gas activity is presented in detail. The neural-network analysis is performed for determination of failed fuel rod number and defect size. Results of the expert system application are illustrated for several fuel campaigns on operating WWER NPPs. (authors)

Likhanskii, V.V.; Evdokimov, I.A.; Sorokin, A.A.; Khromov, A.G.; Kanukova, V.D.; Apollonova, O.V. [SRC RF TRINITI, 142190, Troitsk, Moscow Reg. (Russian Federation); Ugryumov, A.V. [JSC TVEL, 119017, 24/26 Bolshaya Ordynka st., Moscow (Russian Federation)

2007-07-01T23:59:59.000Z

113

Radio Sources in Low-Luminosity Active Galactic Nuclei. I. VLA Detections of Compact, Flat-Spectrum Cores  

E-Print Network (OSTI)

We report a 0.2" resolution, 15 GHz survey of a sample of 48 low-luminosity active galactic nuclei with the Very Large Array. Compact radio emission has been detected in 57% (17 of 30) of LINERs and low-luminosity Seyferts, at least 15 of which have a flat to inverted radio spectrum (alpha > -0.3). The compact radio cores are found in both type 1 (i.e. with broad Halpha) and type 2 (without broad Halpha) nuclei. The 2 cm radio power is significantly correlated with the emission-line ([OI] lambda6300) luminosity. While the present observations are consistent with the radio emission originating in star-forming regions, higher resolution radio observations of 10 of the detected sources, reported in a companion paper (Falcke et al. 2000), show that the cores are very compact (= 10^8K) and probably synchrotron self-absorbed, ruling out a starburst origin. Thus, our results suggest that at least 50% of low-luminosity Seyferts and LINERs in the sample are accretion powered, with the radio emission presumably coming from jets or advection-dominated accretion flows. We have detected only 1 of 18 `transition' (i.e. LINER + HII) nuclei observed, indicating their radio cores are significantly weaker than those of `pure' LINERs.

Neil M. Nagar; Heino Falcke; Andrew S. Wilson; Luis C. Ho

2000-05-18T23:59:59.000Z

114

Analysis of fuel options for the breakeven core configuration of the Advanced Recycling Reactor  

SciTech Connect

A trade-off study is performed to determine the impacts of various fuel forms on the core design and core physics characteristics of the sodium-cooled Toshiba- Westinghouse Advanced Recycling Reactor (ARR). The fuel forms include oxide, nitride, and metallic forms of U and Th. The ARR core configuration is redesigned with driver and blanket regions in order to achieve breakeven fissile breeding performance with the various fuel types. State-of-the-art core physics tools are used for the analyses. In addition, a quasi-static reactivity balance approach is used for a preliminary comparison of the inherent safety performances of the various fuel options. Thorium-fueled cores exhibit lower breeding ratios and require larger blankets compared to the U-fueled cores, which is detrimental to core compactness and increases reprocessing and manufacturing requirements. The Th cores also exhibit higher reactivity swings through each cycle, which penalizes reactivity control and increases the number of control rods required. On the other hand, using Th leads to drastic reductions in void and coolant expansion coefficients of reactivity, with the potential for enhancing inherent core safety. Among the U-fueled ARR cores, metallic and nitride fuels result in higher breeding ratios due to their higher heavy metal densities. On the other hand, oxide fuels provide a softer spectrum, which increases the Doppler effect and reduces the positive sodium void worth. A lower fuel temperature is obtained with the metallic and nitride fuels due to their higher thermal conductivities and compatibility with sodium bonds. This is especially beneficial from an inherent safety point of view since it facilitates the reactor cool-down during loss of power removal transients. The advantages in terms of inherent safety of nitride and metallic fuels are maintained when using Th fuel. However, there is a lower relative increase in heavy metal density and in breeding ratio going from oxide to metallic or nitride Th fuels relative to the U counterpart fuels. (authors)

Stauff, N.E.; Klim, T.K.; Taiwo, T.A. [Argonne National Laboratory, Argonne, IL (United States); Fiorina, C. [Politecnico di Milano, Milan (Italy); Franceschini, F. [Westinghouse Electric Company LLC., Cranberry Township, Pennsylvania (United States)

2013-07-01T23:59:59.000Z

115

Analysis Activities at Idaho National Engineering & Environmental Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on INEENL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

116

Analysis Activities at Fossil Energy/ National Energy Technology Laboratory  

Energy.gov (U.S. Department of Energy (DOE))

Presentation on NETL’s analysis activities to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

117

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor  

SciTech Connect

The Deep Burn (DB) Project is a U.S. Department of Energy sponsored feasibility study of Transuranic Management using high burnup fuel in the high temperature helium cooled reactor (HTR). The DB Project consists of seven tasks: project management, core and fuel analysis, spent fuel management, fuel cycle integration, TRU fuel modeling, TRU fuel qualification, and HTR fuel recycle. In the Phase II of the Project, we conducted nuclear analysis of TRU destruction/utilization in the HTR prismatic block design (Task 2.1), deep burn fuel/TRISO microanalysis (Task 2.3), and synergy with fast reactors (Task 4.2). The Task 2.1 covers the core physics design, thermo-hydraulic CFD analysis, and the thermofluid and safety analysis (low pressure conduction cooling, LPCC) of the HTR prismatic block design. The Task 2.3 covers the analysis of the structural behavior of TRISO fuel containing TRU at very high burnup level, i.e. exceeding 50% of FIMA. The Task 4.2 includes the self-cleaning HTR based on recycle of HTR-generated TRU in the same HTR. Chapter IV contains the design and analysis results of the 600MWth DB-HTR core physics with the cycle length, the average discharged burnup, heavy metal and plutonium consumptions, radial and axial power distributions, temperature reactivity coefficients. Also, it contains the analysis results of the 450MWth DB-HTR core physics and the analysis of the decay heat of a TRU loaded DB-HTR core. The evaluation of the hot spot fuel temperature of the fuel block in the DB-HTR (Deep-Burn High Temperature Reactor) core under full operating power conditions are described in Chapter V. The investigated designs are the 600MWth and 460MWth DB-HTRs. In Chapter VI, the thermo-fluid and safety of the 600MWth DB-HTRs has been analyzed to investigate a thermal-fluid design performance at the steady state and a passive safety performance during an LPCC event. Chapter VII describes the analysis results of the TRISO fuel microanalysis of the 600MWth and 450MWth DB-HTRs. The TRISO fuel microanalysis covers the gas pressure buildup in a coated fuel particle including helium production, the thermo-mechanical behavior of a CFP, the failure probabilities of CFPs, the temperature distribution in a CPF, and the fission product (FP) transport in a CFP and a graphite. In Chapter VIII, it contains the core design and analysis of sodium cooled fast reactor (SFR) with deep burn HTR reactor. It considers a synergistic combination of the DB-MHR and an SFR burner for a safe and efficient transmutation of the TRUs from LWRs. Chapter IX describes the design and analysis results of the self-cleaning (or self-recycling) HTR core. The analysis is considered zero and 5-year cooling time of the spent LWR fuels.

Francesco Venneri; Chang-Keun Jo; Jae-Man Noh; Yonghee Kim; Claudio Filippone; Jonghwa Chang; Chris Hamilton; Young-Min Kim; Ji-Su Jun; Moon-Sung Cho; Hong-Sik Lim; MIchael A. Pope; Abderrafi M. Ougouag; Vincent Descotes; Brian Boer

2010-09-01T23:59:59.000Z

118

Developing Fully Coupled Dynamical Reactor Core Isolation System Models in RELAP-7 for Extended Station Black-Out Analysis  

SciTech Connect

The reactor core isolation cooling (RCIC) system in a boiling water reactor (BWR) provides makeup water to the reactor vessel for core cooling when the main steam lines are isolated and the normal supply of water to the reactor vessel is lost. It was one of the very few safety systems still available during the Fukushima Daiichi accidents after the tsunamis hit the plants and the system successfully delayed the core meltdown for a few days for unit 2 & 3. Therefore, detailed models for RCIC system components are indispensable to understand extended station black-out accidents (SBO) for BWRs. As part of the effort to develop the new generation reactor system safety analysis code RELAP-7, major components to simulate the RCIC system have been developed. This paper describes the models for those components such as turbine, pump, and wet well. Selected individual component test simulations and a simplified SBO simulation up to but before core damage is presented. The successful implementation of the simplified RCIC and wet well models paves the way to further improve the models for safety analysis by including more detailed physical processes in the near future.

Haihua Zhao; Ling Zou; Hongbin Zhang; David Andrs; Richard Martineau

2014-04-01T23:59:59.000Z

119

Active Automobile Engine Vibration Analysis Technical Report Number 1  

E-Print Network (OSTI)

Active Automobile Engine Vibration Analysis Technical Report Number 1 Page 1 of 26 DISTRIBUTION STATEMENT: Distribution authorized to all. Active Automobile Engine Vibration Analysis Technical Report at the University of Southern California #12;Active Automobile Engine Vibration Analysis Technical Report Number 1

Levi, Anthony F. J.

120

Phase Coherence Analysis of Solar Magnetic Activity  

E-Print Network (OSTI)

Over 24 years of synoptic data from the NSO Kitt Peak Vacuum Telescope is used to investigate the coherency and source of the 27-day (synodic) periodicity that is observed over multiple solar cycles in various solar-related time series. A strong 27.03-day period signal, recently reported by Neugebauer et al. (2000), is clearly detected in power spectra of time series from integrated full-disk measurements of the magnetic flux in the 868.8 nm Fe I line and the line equivalent width in the 1083.0 nm He I line. Using spectral analysis of synoptic maps of photospheric magnetic fields, in addition to constructing maps of the surface distribution of activity, we find that the origin of the 27.03-day signal is long-lived complexes of active regions in the northern hemisphere at a latitude of approximately 18 degrees. In addition, using a new time series analysis technique which utilizes the phase variance of a signal, the coherency of the 27.03-day period signal is found to be significant for the past two decades. However, using the past 120 years of the sunspot number time series, the 27.03-day period signal is found to be a short-lived, no longer than two 11-year solar cycles, quasi-stationary signal.

Carl J. Henney; John W. Harvey

2006-12-20T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Validation of a model for faster than real time LMFBR core transient analysis  

SciTech Connect

This report briefly describes experimental validation of a computer model used to analyze LMFBR type core transients. This model is used to predict coolant, cladding, and fuel temperature distributions during transient overpower accidents. (JDH)

Tzanos, C.P.

1987-01-01T23:59:59.000Z

122

Intrinsic reactivity feedback characteristics for safety analysis of heterogeneous and homogeneous LMFBR core designs  

SciTech Connect

This paper presents a comparison of the intrinsic reactivity feedback characteristics of homogeneous and heterogeneous LMFBR designs. The comparisons are shown for a 1000 MWth LMFBR core design. However, the applicability of the conclusions drawn from these comparisons are generic to larger LMFBRs. Consistent sodium void worth distributions have been calculated for heterogeneous and homogeneous 1000 MWth LMFBR core designs. The basic calculations were performed with three dimensional models using ENDF/B-III cross section data and first order perturbation theory.

Doncals, R.A.; Lake, J.A.

1982-01-01T23:59:59.000Z

123

Analysis of BWR core nuclear thermal hydraulic oscillation with three dimensional transient program  

Science Journals Connector (OSTI)

A three-dimensional BWR core dynamics program STANDY has been developed. STANDY takes into account parallel channel effect and evaluates fuel thermal margin. Peach Bottom 2 and Vermont Yankee stability test data have been analyzed by STANDY. Calculated decay ratios and resonance frequencies agreed well with measured data. Limit cycle oscillation at Vermont Yankee test has been also simulated. Oscillation amplitude agreed well with experiment. A hypothetical core condition has been made up to examine unstable oscillations in BWR core. Analyses of the core revealed that oscillation at conditions close to instability initiation reaches small amplitude limit cycle, and change in fuel thermal margin is very small during the limit cycle. Although increase in core power or decrease in flow causes rapid increase in power oscillation amplitude, the ratio of thermal margin change to power amplitude stays almost constant. It has also been found that increase in hot channel power level does not necessarily cause larger thermal margin change because higher power may widen frequency difference between core average and hot channel.

O. Yokomizo; M. Sakurai; Y. Yoshimoto; K. Kitayama; T. Enomoto; N. Fukuda; K. Chuman

1987-01-01T23:59:59.000Z

124

Core-based integrated sedimentologic, stratigraphic, and geochemical analysis of the oil shale bearing Green River Formation, Uinta Basin, Utah  

NLE Websites -- All DOE Office Websites (Extended Search)

DOE Award No.: DE-FE0001243 DOE Award No.: DE-FE0001243 Topical Report CORE-BASED INTEGRATED SEDIMENTOLOGIC, STRATIGRAPHIC, AND GEOCHEMICAL ANALYSIS OF THE OIL SHALE BEARING GREEN RIVER FORMATION, UINTA BASIN, UTAH Submitted by: University of Utah Institute for Clean and Secure Energy 155 South 1452 East, Room 380 Salt Lake City, UT 84112 Prepared for: United States Department of Energy National Energy Technology Laboratory April 2011 Oil & Natural Gas Technology Office of Fossil Energy Core-based integrated sedimentologic, stratigraphic, and geochemical analysis of the oil shale bearing Green River Formation, Uinta Basin, Utah Topical Report Reporting Period: October 31, 2009 through March 31, 2011 Authors: Lauren P. Birgenheier, Energy and Geoscience Insitute, University of Utah

125

EVALUATION OF CORE PHYSICS ANALYSIS METHODS FOR CONVERSION OF THE INL ADVANCED TEST REACTOR TO LOW-ENRICHMENT FUEL  

SciTech Connect

Computational neutronics studies to support the possible conversion of the ATR to LEU are underway. Simultaneously, INL is engaged in a physics methods upgrade project to put into place modern computational neutronics tools for future support of ATR fuel cycle and experiment analysis. A number of experimental measurements have been performed in the ATRC in support of the methods upgrade project, and are being used to validate the new core physics methods. The current computational neutronics work is focused on performance of scoping calculations for the ATR core loaded with a candidate LEU fuel design. This will serve as independent confirmation of analyses that have been performed previously, and will evaluate some of the new computational methods for analysis of a candidate LEU fuel for ATR.

Mark DeHart; Gray S. Chang

2012-04-01T23:59:59.000Z

126

Evaluation of core physics analysis methods for conversion of the INL advanced test reactor to low-enrichment fuel  

SciTech Connect

Computational neutronics studies to support the possible conversion of the ATR to LEU are underway. Simultaneously, INL is engaged in a physics methods upgrade project to put into place modern computational neutronics tools for future support of ATR fuel cycle and experiment analysis. A number of experimental measurements have been performed in the ATRC in support of the methods upgrade project, and are being used to validate the new core physics methods. The current computational neutronics work is focused on performance of scoping calculations for the ATR core loaded with a candidate LEU fuel design. This will serve as independent confirmation of analyses that have been performed previously, and will evaluate some of the new computational methods for analysis of a candidate LEU fuel for ATR. (authors)

DeHart, M. D.; Chang, G. S. [Idaho National Laboratory, 2525 Fremont Street, Idaho Falls, ID 83415-3870 (United States)

2012-07-01T23:59:59.000Z

127

Advanced BWR core component designs and the implications for SFD analysis  

SciTech Connect

Prior to the DF-4 boiling water reactor (BWR) severe fuel damage (SFD) experiment conducted at the Sandia National Laboratories in 1986, no experimental data base existed for guidance in modeling core component behavior under postulated severe accident conditions in commercial BWRs. This paper will present the lessons learned from the DF-4 experiment (and subsequent German CORA BWR SFD tests) and the impact on core models in the current generation of SFD codes. The DF-4 and CORA BWR test assemblies were modeled on the core component designs circa 1985; that is, the 8 x 8 fuel assembly with two water rods and a cruciform control blade constructed of B{sub 4}C-filled tubelets. Within the past ten years, the state-of-the-art with respect to BWR core component development has out-distanced the current SFD experimental data base and SFD code capabilities. For example, modern BWR control blade design includes hafnium at the tips and top of each control blade wing for longer blade operating lifetimes; also water rods have been replaced by larger water channels for better neutronics economy; and fuel assemblies now contain partial-length fuel rods, again for better neutronics economy. This paper will also discuss the implications of these advanced fuel assembly and core component designs on severe accident progression and on the current SFD code capabilities.

Ott, L.J.

1997-02-01T23:59:59.000Z

128

Stress analysis of jacks, frame and bearing connections, and drill rod for core sampler truck No. 2  

SciTech Connect

This analysis evaluates the structural design adequacy of several components and connections for the rotary mode core sampler truck (RMCST) No. 2. This analysis was requested by the Characterization Equipment Group (WHC 1994a). The components addressed in this report are listed below: front jack assembly and connection to the truck chassis; rear jack assembly and connection to the truck chassis; center outrigger jacks and connection to the truck chassis; lower frame assembly and connection to the truck chassis; bolt connections for bearing plate assembly (for path of maximum load); traverse slide brackets and mounting of the traverse jack cylinders; and drill rod (failure loads).

Ziada, H.H.

1995-02-28T23:59:59.000Z

129

Evaluation of storing Shippingport Core II spent blanket fuel assemblies in the T Plant PWR Core II fuel pool without active cooling  

SciTech Connect

PWR Core II fuel pool chiller-off test was conducted because it appeared possible that acceptable pool-water temperatures could be maintained without operating the chillers, thus saving hundreds of thousands of dollars in maintenance and replacement costs. Test results showed that the water-cooling capability is no longer needed to maintain pool temperature below 38{degrees}C (100{degrees}F).

Gilbert, E.R.; Lanning, D.D. [Pacific Northwest Lab., Richland, WA (United States); Dana, C.M.; Hedengren, D.C. [Westinghouse Hanford Co., Richland, WA (United States)

1994-10-01T23:59:59.000Z

130

Automated Audio-visual Activity Analysis  

E-Print Network (OSTI)

Current computer vision techniques can effectively monitor gross activities in sparse environments. Unfortunately, visual stimulus is often not sufficient for reliably discriminating between many types of activity. In ...

Stauffer, Chris

2005-09-20T23:59:59.000Z

131

DIAGNOSING THE TIME-DEPENDENCE OF ACTIVE REGION CORE HEATING FROM THE EMISSION MEASURE. I. LOW-FREQUENCY NANOFLARES  

SciTech Connect

Observational measurements of active region emission measures contain clues to the time dependence of the underlying heating mechanism. A strongly nonlinear scaling of the emission measure with temperature indicates a large amount of hot plasma relative to warm plasma. A weakly nonlinear (or linear) scaling of the emission measure indicates a relatively large amount of warm plasma, suggesting that the hot active region plasma is allowed to cool and so the heating is impulsive with a long repeat time. This case is called low-frequency nanoflare heating, and we investigate its feasibility as an active region heating scenario here. We explore a parameter space of heating and coronal loop properties with a hydrodynamic model. For each model run, we calculate the slope {alpha} of the emission measure distribution EM(T){proportional_to}T {sup {alpha}}. Our conclusions are: (1) low-frequency nanoflare heating is consistent with about 36% of observed active region cores when uncertainties in the atomic data are not accounted for; (2) proper consideration of uncertainties yields a range in which as many as 77% of observed active regions are consistent with low-frequency nanoflare heating and as few as zero; (3) low-frequency nanoflare heating cannot explain observed slopes greater than 3; (4) the upper limit to the volumetric energy release is in the region of 50 erg cm{sup -3} to avoid unphysical magnetic field strengths; (5) the heating timescale may be short for loops of total length less than 40 Mm to be consistent with the observed range of slopes; (6) predicted slopes are consistently steeper for longer loops.

Bradshaw, S. J.; Reep, J. W. [Department of Physics and Astronomy, Rice University, Houston, TX 77005 (United States); Klimchuk, J. A., E-mail: stephen.bradshaw@rice.edu, E-mail: jeffrey.reep@rice.edu, E-mail: james.a.klimchuk@nasa.gov [NASA Goddard Space Flight Center, Solar Physics Lab., Code 671, 8800 Greenbelt Road, Greenbelt, MD 20771 (United States)

2012-10-10T23:59:59.000Z

132

Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling  

E-Print Network (OSTI)

while using a custom oil-based drilling mud, and the coresIn addition, the oil-based drilling fluid used during coringto remove the rind of oil-based drilling fluids. Zones that

Kneafsey, Timothy J.

2010-01-01T23:59:59.000Z

133

Analysis of Sandwich Shells with Metallic Foam Cores based on the Uniaxial Tensile Test  

SciTech Connect

On this work, the authors present the development and evaluation of an innovative system able to perform reliable panels of sandwich sheets with metallic foam cores for industrial applications, especially in automotive and aeronautical industries. This work is divided into two parts; in the first part the mathematical model used to describe the behavior of sandwich shells with metal cores form is presented and some numerical examples are presented. In the second part of this work, the numerical results are validated using the experimental results obtained from the mechanical experiments. Using the isotropic hardening crushable foam constitutive model, available on ABAQUS, a set of different mechanical tests were simulated. The isotropic hardening model available uses a yield surface that is an ellipse centered at the origin in the p-q stress plane. Using this constitutive model, the uniaxial tensile test for this material was simulated, and a comparison with the experimental results was made.

Mata, H.; Fernandes, A. A.; Parente, M. P. L.; Jorge, R. Natal [IDMEC-FEUP, Rua Dr. Roberto Frias, 4200-465, Porto (Portugal); Santos, A. [INEGI, Rua Dr. Roberto Frias, 4200-465, Porto (Portugal); Valente, R. A. F. [Universidade de Aveiro, Campus Universitario de Santiago, 3810-193, Aveiro (Portugal)

2011-05-04T23:59:59.000Z

134

ALARA Analysis for Shippingport Pressurized Water Reactor Core 2 Fuel Storage in the Canister Storage Building (CSB)  

E-Print Network (OSTI)

The addition of Shippingport Pressurized Water Reactor (PWR) Core 2 Blanket Fuel Assembly storage in the Canister Storage Building (CSB) will increase the total cumulative CSB personnel exposure from receipt and handling activities. The loaded Shippingport Spent Fuel Canisters (SSFCs) used for the Shippingport fuel have a higher external dose rate. Assuming an MCO handling rate of 170 per year (K East and K West concurrent operation), 24-hr CSB operation, and nominal SSFC loading, all work crew personnel will have a cumulative annual exposure of less than the 1,000 mrem limit.

Lewis, M E

2000-01-01T23:59:59.000Z

135

Conceptual design analysis of an MHD power conversion system for droplet-vapor core reactors. Final report  

SciTech Connect

A nuclear driven magnetohydrodynamic (MHD) generator system is proposed for the space nuclear applications of few hundreds of megawatts. The MHD generator is coupled to a vapor-droplet core reactor that delivers partially ionized fissioning plasma at temperatures in range of 3,000 to 4,000 K. A detailed MHD model is developed to analyze the basic electrodynamics phenomena and to perform the design analysis of the nuclear driven MHD generator. An incompressible quasi one dimensional model is also developed to perform parametric analyses.

Anghaie, S.; Saraph, G.

1995-12-31T23:59:59.000Z

136

Thermal hydraulics analysis of the MIT research reactor in support of a low enrichment uranium (LEU) core conversion .  

E-Print Network (OSTI)

??The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density… (more)

Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

137

Analysis Activities at National Renewable Energy Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Laboratory Laboratory DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. Margaret K. Mann Hydrogen Analysis Task Leader Charter * NREL's mission: NREL develops renewable energy and energy efficiency technologies and practices, advances related science and engineering, and transfers knowledge and innovations to address the nation's energy and environmental goals. * The NREL Hydrogen Analysis Group provides leadership in hydrogen production, delivery, transition, and market analysis, to increase the efficiency of hydrogen research and implementation. * The NREL Hydrogen Analysis Group has received the majority of its funding from the DOE Hydrogen Program (now HFCIT), with some funding coming from PBA and OFCVT

138

ANALYSIS OF GENE EXPRESSION PROFILES AND DRUG ACTIVITY PATTERNS BY  

E-Print Network (OSTI)

are more related to the kind of cancer than to drug activity patterns. Dependency analysis using Bayesian1 11 ANALYSIS OF GENE EXPRESSION PROFILES AND DRUG ACTIVITY PATTERNS BY CLUSTERING AND BAYESIAN of data produced from up- to-date biological experimental processes needs appropriate data mining

139

Core Analysis At Snake River Plain Region (DOE GTP) | Open Energy...  

Open Energy Info (EERE)

Activity Date Usefulness not indicated DOE-funding Unknown References (1 January 2011) GTP ARRA Spreadsheet Additional References Retrieved from "http:en.openei.orgw...

140

Analysis of core samples from the BPXA-DOE-USGS Mount Elbert gas hydrate stratigraphic test well: Insights into core disturbance and handling  

E-Print Network (OSTI)

future gas hydrate core handling and preservation in sand-gas-hydrate-bearing zones, in which the sediments (particularly the sands)sand deposits are primarily being investigated in the Mount Elbert well, much of the world’s natural gas hydrate

Kneafsey, Timothy J.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Tank 241-AZ-102 Privatization Push Mode Core Sampling and Analysis Plan  

SciTech Connect

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for samples obtained from tank 241-AZ-102.

RASMUSSEN, J.H.

2000-05-23T23:59:59.000Z

142

Analysis Activities at Pacific Northwest National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Pacific Northwest National Laboratory Pacific Northwest National Laboratory Pacific Northwest National Laboratory's Hydrogen Analysis Capabilities Marylynn Placet Manager, Energy Policy and Planning Group m.placet@pnl.gov (202) 646-5249 DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. U.S. Department of Energy Pacific Northwest National Laboratory 2 Charter PNNL Energy Science and Technology Directorate's Energy Mission: Secure, clean, and affordable energy systems in a carbon constrained world. PNNL Analysis Objectives/Principles: * Development of state-of-the-art analysis tools for critical policy issues (e.g., climate change, electricity grid issues) * Use of tools appropriate to the need * Objectivity; analysis based on best available,

143

Analysis of Advanced Fuel Assemblies and Core Designs for the Current and Next Generations of LWRs  

SciTech Connect

The objective of the project is to design and analyze advanced fuel assemblies for use in current and future light water reactors and to assess their ability to reduce the inventory of transuranic elements, while preserving operational safety. The reprocessing of spent nuclear fuel can delay or avoid the need for a second geological repository in the US. Current light water reactor fuel assembly designs under investigation could reduce the plutonium inventory of reprocessed fuel. Nevertheless, these designs are not effective in stabilizing or reducing the inventory of minor actinides. In the course of this project, we developed and analyzed advanced fuel assembly designs with improved thermal transmutation capability regarding transuranic elements and especially minor actinides. These designs will be intended for use in thermal spectrum (e.g., current and future fleet of light water reactors in the US). We investigated various fuel types, namely high burn-up advanced mixed oxides and inert matrix fuels, in various geometrical designs that are compliant with the core internals of current and future light water reactors. Neutronic/thermal hydraulic effects were included. Transmutation efficiency and safety parameters were used to rank and down-select the various designs.

Jean Ragusa; Karen Vierow

2011-09-01T23:59:59.000Z

144

Analysis Activities at Lawrence Livermore National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Laboratory / Energy Security and Technology Program Jeffrey Stewart Group Leader: Applied Statistics and Economics DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. 2 Charter * LLNL's mission is to provide research in the areas of national and homeland security and other important areas to DOE such as Energy,Climate and Water * To conduct systems and economic modeling and analysis to determine the technical and economic characteristics of individual technologies within systems to achieve policy objectives * DOE NETL, NE,Policy,HEU; Japanese Govt, CEC, Internal 3 History * LLNL has had a systems analysis group for over 25 years supporting national security, defense, energy and environment programs

145

Analysis of core damage frequency: Peach Bottom, Unit 2 internal events  

SciTech Connect

This document contains the appendices for the accident sequence analysis of internally initiated events for the Peach Bottom, Unit 2 Nuclear Power Plant. This is one of the five plant analyses conducted as part of the NUREG-1150 effort for the Nuclear Regulatory Commission. The work performed and described here is an extensive reanalysis of that published in October 1986 as NUREG/CR-4550, Volume 4. It addresses comments from numerous reviewers and significant changes to the plant systems and procedures made since the first report. The uncertainty analysis and presentation of results are also much improved, and considerable effort was expended on an improved analysis of loss of offsite power. The content and detail of this report is directed toward PRA practitioners who need to know how the work was done and the details for use in further studies. 58 refs., 58 figs., 52 tabs.

Kolaczkowski, A.M.; Cramond, W.R.; Sype, T.T.; Maloney, K.J.; Wheeler, T.A.; Daniel, S.L. (Science Applications International Corp., Albuquerque, NM (USA); Sandia National Labs., Albuquerque, NM (USA))

1989-08-01T23:59:59.000Z

146

Immune activation suppresses plasma testosterone level: a meta-analysis  

Science Journals Connector (OSTI)

...sizes of immune challenge on plasma T levels. (Immune challenges...M Sexual selection. In Princeton University Press 1994Princeton, NJ:Princeton University Press Barthelemy...Immune activation suppresses plasma testosterone level: a meta-analysis...

2008-01-01T23:59:59.000Z

147

Analysis Activities at Oak Ridge National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Oak Ridge National Laboratory Oak Ridge National Laboratory David L. Greene Engineering Science and Technology Division Paul N. Leiby Environmental Sciences Division Juan Ferrada Nuclear Science and Technology Division DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. 2 OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY Charter * The Engineering Science and Technology Division, National Transportation Research Center conducts engineering and analytical R&D for DOE, other federal sponsors and the private sector. * The Environmental Sciences Division conducts interdisciplinary research, develops technology, and performs analyses to understand and assess responses to global and regional change, environmental stress, and resource use.

148

HYDRATE CORE DRILLING TESTS  

SciTech Connect

The ''Methane Hydrate Production from Alaskan Permafrost'' project is a three-year endeavor being conducted by Maurer Technology Inc. (MTI), Noble, and Anadarko Petroleum, in partnership with the U.S. DOE National Energy Technology Laboratory (NETL). The project's goal is to build on previous and ongoing R&D in the area of onshore hydrate deposition. The project team plans to design and implement a program to safely and economically drill, core and produce gas from arctic hydrates. The current work scope includes drilling and coring one well on Anadarko leases in FY 2003 during the winter drilling season. A specially built on-site core analysis laboratory will be used to determine some of the physical characteristics of the hydrates and surrounding rock. Prior to going to the field, the project team designed and conducted a controlled series of coring tests for simulating coring of hydrate formations. A variety of equipment and procedures were tested and modified to develop a practical solution for this special application. This Topical Report summarizes these coring tests. A special facility was designed and installed at MTI's Drilling Research Center (DRC) in Houston and used to conduct coring tests. Equipment and procedures were tested by cutting cores from frozen mixtures of sand and water supported by casing and designed to simulate hydrate formations. Tests were conducted with chilled drilling fluids. Tests showed that frozen core can be washed out and reduced in size by the action of the drilling fluid. Washing of the core by the drilling fluid caused a reduction in core diameter, making core recovery very difficult (if not impossible). One successful solution was to drill the last 6 inches of core dry (without fluid circulation). These tests demonstrated that it will be difficult to capture core when drilling in permafrost or hydrates without implementing certain safeguards. Among the coring tests was a simulated hydrate formation comprised of coarse, large-grain sand in ice. Results with this core showed that the viscosity of the drilling fluid must also be carefully controlled. When coarse sand was being cored, the core barrel became stuck because the drilling fluid was not viscous enough to completely remove the large grains of sand. These tests were very valuable to the project by showing the difficulties in coring permafrost or hydrates in a laboratory environment (as opposed to a field environment where drilling costs are much higher and the potential loss of equipment greater). Among the conclusions reached from these simulated hydrate coring tests are the following: Frozen hydrate core samples can be recovered successfully; A spring-finger core catcher works best for catching hydrate cores; Drilling fluid can erode the core and reduces its diameter, making it more difficult to capture the core; Mud must be designed with proper viscosity to lift larger cuttings; and The bottom 6 inches of core may need to be drilled dry to capture the core successfully.

John H. Cohen; Thomas E. Williams; Ali G. Kadaster; Bill V. Liddell

2002-11-01T23:59:59.000Z

149

A statistical analysis of avalanching heat transport in stationary enhanced core confinement regimes  

SciTech Connect

We present a statistical analysis of heat transport in stationary enhanced confinement regimes obtained from flux-driven gyrofluid simulations. The probability density functions of heat flux in improved confinement regimes, characterized by the Nusselt number, show significant deviation from Gaussian, with a markedly fat tail, implying the existence of heat avalanches. Two types of avalanching transport are found to be relevant to stationary states, depending on the degree of turbulence suppression. In the weakly suppressed regime, heat avalanches occur in the form of quasi-periodic (QP) heat pulses. Collisional relaxation of zonal flow is likely to be the origin of these QP heat pulses. This phenomenon is similar to transient limit cycle oscillations observed prior to edge pedestal formation in recent experiments. On the other hand, a spectral analysis of heat flux in the strongly suppressed regime shows the emergence of a 1/f (f is the frequency) band, suggesting the presence of self-organized criticality (SOC)-like episodic heat avalanches. This episodic 1/f heat avalanches have a long temporal correlation and constitute the dominant transport process in this regime.

Tokunaga, S.; Jhang, Hogun; Kim, S. S. [WCI Center for Fusion Theory, National Fusion Research Institute, 52, Yeoeun-dong, Yusung-Gu, Daejon (Korea, Republic of); Diamond, P. H. [WCI Center for Fusion Theory, National Fusion Research Institute, 52, Yeoeun-dong, Yusung-Gu, Daejon (Korea, Republic of); Center for Astrophysics and Space Sciences and Department of Physics, University of California San Diego, La Jolla, California 92093-0429 (United States)

2012-09-15T23:59:59.000Z

150

Core Specialization  

NLE Websites -- All DOE Office Websites (Extended Search)

Core Specialization Core Specialization Core Specialization Core Specialization (CS) is a feature of the Cray operating system that allows the user to reserve one or more cores per node for handling system services, and thus reduce the effects of timing jitter due to interruptions from the operating system at the expense of (possibly) requiring more nodes to run an application. The specialized cores may also be used in conjunction with Cray's MPI asynchronous progress engine [1] to improve the overlap of communication and computation for applications that use non-blocking MPI functions. In the absence of CS, the compute cores must service their own non-blocking calls. Hyper-Threading complicates questions abouty the most effective use of processor resources. HT doubles the number of compute stream (i.e.

151

Core Specialization  

NLE Websites -- All DOE Office Websites (Extended Search)

Core Core Specialization Core Specialization Core Specialization (CS) is a feature of the Cray operating system that allows the user to reserve one or more cores per node for handling system services, and thus reduce the effects of timing jitter due to interruptions from the operating system at the expense of (possibly) requiring more nodes to run an application. The specialized cores may also be used in conjunction with Cray's MPI asynchronous progress engine [1] to improve the overlap of communication and computation for applications that use non-blocking MPI functions. In the absence of CS, the compute cores must service their own non-blocking calls. Hyper-Threading complicates questions abouty the most effective use of processor resources. HT doubles the number of compute stream (i.e.

152

Prognostic Importance of Gleason 7 Disease Among Patients Treated With External Beam Radiation Therapy for Prostate Cancer: Results of a Detailed Biopsy Core Analysis  

SciTech Connect

Purpose: To analyze the effect of primary Gleason (pG) grade among a large cohort of Gleason 7 prostate cancer patients treated with external beam radiation therapy (EBRT). Methods and Materials: From May 1989 to January 2011, 1190 Gleason 7 patients with localized prostate cancer were treated with EBRT at a single institution. Of these patients, 613 had a Gleason 7 with a minimum of a sextant biopsy with nonfragmented cores and full biopsy core details available, including number of cores of cancer involved, percentage individual core involvement, location of disease, bilaterality, and presence of perineural invasion. Median follow-up was 6 years (range, 1-16 years). The prognostic implication for the following outcomes was analyzed: biochemical recurrence-free survival (bRFS), distant metastasis-free survival (DMFS), and prostate cancer-specific mortality (PCSM). Results: The 8-year bRFS rate for pG3 versus pG4 was 77.6% versus 61.3% (P<.0001), DMFS was 96.8% versus 84.3% (P<.0001), and PCSM was 3.7% versus 8.1% (P=.002). On multivariate analysis, pG4 predicted for significantly worse outcome in all parameters. Location of disease (apex, base, mid-gland), perineural involvement, maximum individual core involvement, and the number of Gleason 3+3, 3+4, or 4+3 cores did not predict for distant metastases. Conclusions: Primary Gleason grade 4 independently predicts for worse bRFS, DMFS, and PCSM among Gleason 7 patients. Using complete core information can allow clinicians to utilize pG grade as a prognostic factor, despite not having the full pathologic details from a prostatectomy specimen. Future staging and risk grouping should investigate the incorporation of primary Gleason grade when complete biopsy core information is used.

Spratt, Daniel E.; Zumsteg, Zach; Ghadjar, Pirus; Pangasa, Misha; Pei, Xin [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)] [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Fine, Samson W. [Department of Pathology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)] [Department of Pathology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Yamada, Yoshiya; Kollmeier, Marisa [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)] [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States); Zelefsky, Michael J., E-mail: zelefskm@mskcc.org [Department of Radiation Oncology, Memorial Sloan-Kettering Cancer Center, New York, New York (United States)

2013-04-01T23:59:59.000Z

153

Core Holes | Open Energy Information  

Open Energy Info (EERE)

Core Holes Core Holes Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Core Holes Details Activities (8) Areas (7) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Drilling Techniques Exploration Sub Group: Exploration Drilling Parent Exploration Technique: Exploration Drilling Information Provided by Technique Lithology: Core holes are drilled to identify lithology and mineralization Stratigraphic/Structural: Retrieved samples can be used to identify fracture networks or faults Hydrological: Thermal: Thermal conductivity measurements can be done on retrieved samples. Dictionary.png Core Holes: A core hole is a well that is drilled using a hallow drill bit coated with synthetic diamonds for the purposes of extracting whole rock samples from

154

Behavior of an heterogeneous annular FBR core during an unprotected loss of flow accident: Analysis of the primary phase with SAS-SFR  

SciTech Connect

In the framework of a substantial improvement on FBR core safety connected to the development of a new Gen IV reactor type, heterogeneous core with innovative features are being carefully analyzed in France since 2009. At EDF R and D, the main goal is to understand whether a strong reduction of the Na-void worth - possibly attempting a negative value - allows a significant improvement of the core behavior during an unprotected loss of flow accident. Also, the physical behavior of such a core is of interest, before and beyond the (possible) onset of Na boiling. Hence, a cutting-edge heterogeneous design, featuring an annular shape, a Na-plena with a B{sub 4}C plate and a stepwise modulation of fissile core heights, was developed at EDF by means of the SDDS methodology, with a total Na-void worth of -1 $. The behavior of such a core during the primary phase of a severe accident, initiated by an unprotected loss of flow, is analyzed by means of the SAS-SFR code. This study is carried-out at KIT and EDF, in the framework of a scientific collaboration on innovative FBR severe accident analyses. The results show that the reduction of the Na-void worth is very effective, but is not sufficient alone to avoid Na-boiling and, hence, to prevent the core from entering into the primary phase of a severe accident. Nevertheless, the grace time up to boiling onset is greatly enhanced in comparison to a more traditional homogeneous core design, and only an extremely low fraction of the fuel (<0.1%) enters into melting at the end of this phase. A sensitivity analysis shows that, due to the inherent neutronic characteristics of such a core, the gagging scheme plays a major role on the core behavior: indeed, an improved 4-zones gagging scheme, associated with an enhanced control rod drive line expansion feed-back effect, finally prevents the core from entering into sodium boiling. This major conclusion highlights both the progress already accomplished and the need for more detailed future analyses, particularly concerning: the neutronic burn-up scheme, the modeling of the diagrid effect and the control rod drive line expansion feed-backs, as well as the primary/secondary systems thermal-hydraulics behavior. (authors)

Massara, S.; Schmitt, D.; Bretault, A.; Lemasson, D.; Darmet, G.; Verwaerde, D. [EDF R and D, 1, Avenue du General de Gaulle, 92141 Clamart (France); Struwe, D.; Pfrang, W.; Ponomarev, A. [Karlsruher Institut fuer Technologie KIT, Institut fuer Neutronenphysik und Reaktortechnik INR, Hermann-von-Helmholtz-Platz 1, Gebaude 521, 76344 Eggenstein-Leopoldshafen (Germany)

2012-07-01T23:59:59.000Z

155

E-Print Network 3.0 - activation analysis pgaa Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

for: activation analysis pgaa Page: << < 1 2 3 4 5 > >> 1 Combinatorial approaches for hydrogen storage materials Summary: Gamma Activation Analysis (PGAA) Quantitative H...

156

INDUSTRIAL/MILITARY ACTIVITY-INITIATED ACCIDENT SCREENING ANALYSIS  

SciTech Connect

Impacts due to nearby installations and operations were determined in the Preliminary MGDS Hazards Analysis (CRWMS M&O 1996) to be potentially applicable to the proposed repository at Yucca Mountain. This determination was conservatively based on limited knowledge of the potential activities ongoing on or off the Nevada Test Site (NTS). It is intended that the Industrial/Military Activity-Initiated Accident Screening Analysis provided herein will meet the requirements of the ''Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (NRC 1987) in establishing whether this external event can be screened from further consideration or must be included as a design basis event (DBE) in the development of accident scenarios for the Monitored Geologic Repository (MGR). This analysis only considers issues related to preclosure radiological safety. Issues important to waste isolation as related to impact from nearby installations will be covered in the MGR performance assessment.

D.A. Kalinich

1999-09-27T23:59:59.000Z

157

On the determination of phosphorous via charged particle activation analysis  

E-Print Network (OSTI)

of Cyclotron Terminal . "or Activation Analysis Ql ? WATER INLET Q2 ? BNC CONNECTOR Q3 ? LUCITE Q4 ? CA RBON Figure 3. Four-leaved Carl. on Pea, -. Monitor 1. Ta COLLIMATOR 2. Cu HEAT SINK K MONITOR 4. SAMPLE 5. Cu BASE PLATE 6. WATER COOLING I 2... of Cyclotron Terminal . "or Activation Analysis Ql ? WATER INLET Q2 ? BNC CONNECTOR Q3 ? LUCITE Q4 ? CA RBON Figure 3. Four-leaved Carl. on Pea, -. Monitor 1. Ta COLLIMATOR 2. Cu HEAT SINK K MONITOR 4. SAMPLE 5. Cu BASE PLATE 6. WATER COOLING I 2...

Poland, John Edward

2012-06-07T23:59:59.000Z

158

Recovery Efficiency Test Project: Phase 1, Activity report. Volume 1: Site selection, drill plan preparation, drilling, logging, and coring operations  

SciTech Connect

The recovery Efficiency Test well project addressed a number of technical issues. The primary objective was to determine the increased efficiency gas recovery of a long horizontal wellbore over that of a vertical wellbore and, more specifically, what improvements can be expected from inducing multiple hydraulic fractures from such a wellbore. BDM corporation located, planned, and drilled a long radius turn horizontal well in the Devonian shale Lower Huron section in Wayne County, West Virginia, demonstrating that state-of-the-art technology is capable of drilling such wells. BDM successfully tested drilling, coring, and logging in a horizontal well using air as the circulating medium; conducted reservoir modeling studies to protect flow rates and reserves in advance of drilling operations; observed two phase flow conditions in the wellbore not observed previously; cored a fracture zone which produced gas; observed that fractures in the core and the wellbore were not systematically spaced (varied from 5 to 68 feet in different parts of the wellbore); observed that highest gas show rates reported by the mud logger corresponded to zone with lowest fracture spacing (five feet) or high fracture frequency. Four and one-half inch casting was successfully installed in the borehole and was equipped to isolate the horizontal section into eight (8) zones for future testing and stimulation operations. 6 refs., 48 figs., 10 tabs.

Overbey, W.K. Jr.; Carden, R.S.; Kirr, J.N.

1987-04-01T23:59:59.000Z

159

Thermal metastabilities in the solar core  

E-Print Network (OSTI)

Linear stability analysis indicates that solar core is thermally stable for infinitesimal internal perturbations. For the first time, thermal metastabilities are found in the solar core when outer perturbations with significant amplitude are present. The obtained results show that hot bubbles generated by outer perturbations may travel a significant distance in the body of the Sun. These deep-origin hot bubbles have mass, energy, and chemical composition that may be related to solar flares. The results obtained may have remarkable relations to activity cycles in planets like Jupiter and also in extrasolar planetary systems.

Attila Grandpierre; Gabor Agoston

2002-01-18T23:59:59.000Z

160

CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor  

E-Print Network (OSTI)

Very High Temperature Rector (VHTR) had been designated as one of those promising reactors for the Next Generation (IV) Nuclear Plant (NGNP). For a prismatic core VHTR, one of the most crucial design considerations is the bypass flow and crossflow...

Wang, Huhu 1985-

2012-12-13T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Summary of micrographic analysis of fracture coating phases on drill cores from Pahute Mesa, Nevada Test Site. Revision 1  

SciTech Connect

The flow path between Pahute Mesa and the groundwater discharge area in Oasis Valley (approximately 18 miles to the southwest) is of concern due to the relatively short travel distance between a recharge area where underground nuclear testing has been conducted and the off-site water users. Groundwater flow and transport modeling by IT Corporation (IT) has shown rapid tritium transport in the volcanic rock aquifers along this flow path. The resultant estimates of rapid transport were based on water level data, limited hydraulic conductivity data, estimates of groundwater discharge rates in Oasis Valley, assumed porosities, and estimated retardation rates. Many of these parameters are poorly constrained and may vary considerably. Sampling and analytical techniques are being applied as an independent means to determine transport rates by providing an understanding of the geochemical processes that control solute movement along the flow path. As part of these geochemical investigations, this report summarizes the analysis of fracture coating mineral phases from drill core samples from the Pahute mesa area of the Nevada Test Site (NTS). Archived samples were collected based on the presence of natural fractures and on the types and abundance of secondary mineral phases present on those fracture surfaces. Mineral phases present along fracture surfaces are significant because, through the process of water-rock interaction, they can either contribute (as a result of dissolution) or remove (as a result of precipitation or adsorption) constituents from solution. Particular attention was paid to secondary calcite occurrences because they represent a potential source of exchangeable carbon and can interact with groundwater resulting in a modified isotopic signature and apparent water age.

NONE

1998-12-01T23:59:59.000Z

162

Analysis of alternatives for immobilized low activity waste disposal  

SciTech Connect

This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

Burbank, D.A.

1997-10-28T23:59:59.000Z

163

Analyses of Oxyanion Materials by Prompt Gamma Activation Analysis  

SciTech Connect

Prompt gamma activation analysis (PGAA) has been used to analyze metal ion oxyanion materials that have multiple applications, including medicine, materials, catalysts, and electronics. The significance for the need for accurate, highly sensitive analyses for the materials is discussed in the context of quality control of end products containing the parent element in each material. Applications of the analytical data for input to models and theoretical calculations related to the electronic and other properties of the materials are discussed.

Firestone, Richard B; Perry, D.L.; English, G.A.; Firestone, R.B.; Leung, K.-N.; Garabedian, G.; Molnar, G.L.; Revay, Zs.

2008-03-24T23:59:59.000Z

164

Fusion Activation through Attachment Protein Stalk Domains Indicates a Conserved Core Mechanism of Paramyxovirus Entry into Cells  

Science Journals Connector (OSTI)

...research-article Structure and Assembly Fusion Activation through Attachment Protein...viral integral membrane glycoproteins (fusion [F] and attachment [HN, H, or G...receptor recognition, followed by the fusion of viral and cellular membranes, resulting...

Sayantan Bose; Albert S. Song; Theodore S. Jardetzky; Robert A. Lamb

2014-01-22T23:59:59.000Z

165

Viscoelastic Analysis of Sandwich Beams Having Aluminum and Fiber-reinforced Polymer Skins with a Polystyrene Foam Core  

E-Print Network (OSTI)

Sandwich beams are composite systems having high stiffness-to-weight and strength-to-weight ratios and are used as light weight load bearing components. The use of thin, strong skin sheets adhered to thicker, lightweight core materials has allowed...

Roberts-Tompkins, Altramese L.

2010-07-14T23:59:59.000Z

166

Nanostructured Polyaniline-Decorated Pt/C@PANI Core–Shell Catalyst with Enhanced Durability and Activity  

Science Journals Connector (OSTI)

(1) However, the insufficient electrocatalytic activity and durability of Pt cathode catalysts still remains a major obstacle for PEMFC applications. ... Figure 4. Polarization curves of single PEM fuel cells with cathodes fabricated from (a) PANI@Pt/C (30%) and (b) Pt/C catalysts after the indicated numbers of CV cycles. ... Time-effective and reliable methods for studying catalyst durability are indispensable for developing PEMFC catalysts. ...

Siguo Chen; Zidong Wei; XueQiang Qi; Lichun Dong; Yu-Guo Guo; Lijun Wan; Zhigang Shao; Li Li

2012-08-01T23:59:59.000Z

167

Visible-Light Photochemical Activity of Heterostructured Core-Shell Materials Composed of Selected Ternary Titanates and Ferrites  

E-Print Network (OSTI)

-24 For example, CdS,25 Cu2O,26 BiOI,22 ZnFe2O4,27 and CuInS2,28 were combined with TiO2 for visible °C shows the highest reaction rate. Fe-doped TiO2, which absorbs visible light, did not show enhanced active under visible light, such as metal and nonmetal doping,3,8-12 dye sensitization,13

Rohrer, Gregory S.

168

Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source Reactor at Oak Ridge National Laboratory  

SciTech Connect

This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at the Oak Ridge National Laboratory (ORNL). Damage propagation is postulated to occur from thermal conduction between damaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur because of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A scoping study was conducted to learn what parameters are important for core damage propagation, and to obtain initial estimates of core melt mass for addressing recriticality and steam explosion events. The study included investigating the effects of the plate contact area, the convective heat transfer coefficient, thermal conductivity upon fuel swelling, and the initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects on damage propagation. The results provide useful insights into how various uncertain parameters affect damage propagation.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-09-01T23:59:59.000Z

169

Reactivity Effects of Differences Between JEFF-3.1 and ENDF/B-VI.8 in Analysis of Six MASURCA Cores of the R-Z Program  

SciTech Connect

Six early cores of the MASURCA R-Z program were modeled using ERANOS 2.1. These cores were designed such that their neutron spectra would be similar to that of an oxide-fueled sodium-cooled fast reactor, some containing enriched uranium and others containing depleted uranium and plutonium. Effects of modeling assumptions and solution methods both in ECCO lattice calculations and in BISTRO Sn flux solutions were evaluated using JEFF-3.1 cross-section libraries. Reactivity effects of differences between JEFF-3.1 and ENDF/B-VI.8 were also quantified using perturbation theory analysis. The most important nuclide with respect to reactivity differences between cross-section libraries was 23Na, primarily a result of differences in the angular dependence of elastic scattering which is more forward-peaked in ENDF/B-VI.8 than in JEFF-3.1. Differences in 23Na inelastic scattering cross-sections between libraries also generated significant differences in reactivity, more due to the differences in magnitude of the cross-sections than the angular dependence. The nuclide 238U was also found to be important with regard to reactivity differences between the two libraries mostly due to a large effect of inelastic scattering differences and two smaller effects of elastic scattering and fission cross-sections. In the cores which contained plutonium, 239Pu fission cross-section differences contributed significantly to the reactivity differences between libraries.

MIchael A. Pope

2010-02-01T23:59:59.000Z

170

Very High Temperature Reactor (VHTR) Deep Burn Core and Fuel Analysis -- Complete Design Selection for the Pebble Bed Reactor  

SciTech Connect

The Deep-Burn (DB) concept focuses on the destruction of transuranic nuclides from used light water reactor fuel. These transuranic nuclides are incorporated into TRISO coated fuel particles and used in gas-cooled reactors with the aim of a fractional fuel burnup of 60 to 70% in fissions per initial metal atom (FIMA). This high performance is expected through the use of multiple recirculation passes of the fuel in pebble form without any physical or chemical changes between passes. In particular, the concept does not call for reprocessing of the fuel between passes. In principle, the DB pebble bed concept employs the same reactor designs as the presently envisioned low-enriched uranium core designs, such as the 400 MWth Pebble Bed Modular Reactor (PBMR-400). Although it has been shown in the previous Fiscal Year (2009) that a PuO2 fueled pebble bed reactor concept is viable, achieving a high fuel burnup, while remaining within safety-imposed prescribed operational limits for fuel temperature, power peaking and temperature reactivity feedback coefficients for the entire temperature range, is challenging. The presence of the isotopes 239-Pu, 240-Pu and 241-Pu that have resonances in the thermal energy range significantly modifies the neutron thermal energy spectrum as compared to a ”standard,” UO2-fueled core. Therefore, the DB pebble bed core exhibits a relatively hard neutron energy spectrum. However, regions within the pebble bed that are near the graphite reflectors experience a locally softer spectrum. This can lead to power and temperature peaking in these regions. Furthermore, a shift of the thermal energy spectrum with increasing temperature can lead to increased absorption in the resonances of the fissile Pu isotopes. This can lead to a positive temperature reactivity coefficient for the graphite moderator under certain operating conditions. The effort of this task in FY 2010 has focused on the optimization of the core to maximize the pebble discharge burnup level, while retaining its inherent safety characteristics. Using generic pebble bed reactor cores, this task will perform physics calculations to evaluate the capabilities of the pebble bed reactor to perform utilization and destruction of LWR used-fuel transuranics. The task will use established benchmarked models, and will introduce modeling advancements appropriate to the nature of the fuel considered (high TRU content and high burn-up).

B. Boer; A. M. Ougouag

2010-09-01T23:59:59.000Z

171

Rock Lab Analysis | Open Energy Information  

Open Energy Info (EERE)

Rock Lab Analysis Rock Lab Analysis Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Rock Lab Analysis Details Activities (0) Areas (0) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: Rock Lab Analysis Parent Exploration Technique: Lab Analysis Techniques Information Provided by Technique Lithology: Core and cuttings analysis is done to define lithology. Water rock interaction. Can determine detailed information about rock composition and morphology. Density of different lithologic units. Rapid and unambiguous identification of unknown minerals.[1] Stratigraphic/Structural: Core analysis can locate faults or fracture networks. Oriented core can give additional important information on anisotropy. Historic structure and deformation of land.

172

Photon Activation Analysis at the Idaho Accelerator Center  

SciTech Connect

Activation methods require minimal sample preparation and provide sufficiently high sensitivity for detecting the vast majority of the elements throughout the periodic table. In this paper we shall discuss photon activation analysis (PAA) at the Idaho Accelerator Center. The process of PAA begins with exposing a sample with photons in the energy range of 10 to 30 MeV. Many nuclides in the sample will become activated and, in turn, these radionuclides will decay by emitting characteristic radiation. These characteristic radiation decays are the telltale signatures for identifying elements which can then be measured with spectrometers such as a high-purity Germanium detector. PAA is not an 'absolute' method, as the samples under investigation must be irradiated along with a reference or calibrating material having a well-known elemental composition. The quantitative evaluation is performed through comparing the two resulting element spectra from the unknown sample and reference material. Besides the obvious advantage of being non-destructive, PAA has minimal contamination issues. Moreover, materials that are difficult to treat chemically, such as certain refractory metals, dusts, ashes, etc., offer no hindrance to the technique of PAA. A further advantage is that PAA is very well suited for investigated minute samples (sub-milligram dust particles) to very large ones (in the multi-kg range). PAA is a robust technique as there are no real limitations concerning the nature of material to be studied.

Wells, Douglas P.; Cole, Philip L. [Idaho Accelerator Center, 1500 Alvin Ricken Drive, Pocatello, ID 83201 (United States); Department of Physics, Idaho State University, Pocatello, Idaho 83209 (United States); Segebade, Christian R. [Idaho Accelerator Center, 1500 Alvin Ricken Drive, Pocatello, ID 83201 (United States)

2010-08-04T23:59:59.000Z

173

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

NLE Websites -- All DOE Office Websites (Extended Search)

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

174

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

175

Core - Corona Model analysis of the Low Energy Beam Scan at RHIC (Relativistic Heavy Ion Collider) in Brookhaven (USA)  

E-Print Network (OSTI)

The centrality dependence of spectra of identified particles in collisions between ultrarelativistic heavy ions with a center of mass energy ($\\sqrt{s}$) of 39 and 11.5 $AGeV$ is analyzed in the core - corona model. We show that at these energies the spectra can be well understood assuming that they are composed of two components whose relative fraction depends on the centrality of the interaction: The core component which describes an equilibrated quark gluon plasma and the corona component which is caused by nucleons close to the surface of the interaction zone which scatter only once and which is identical to that observed in proton-proton collisions. The success of this approach at 39 and 11.5 $AGeV$ shows that the physics does not change between this energy and $\\sqrt{s}=200~ AGeV$ for which this model has been developed (Aichelin 2008). This presents circumstantial evidence that a quark gluon plasma is also created at center of mass energies as low as 11.5 $AGeV$.

M. Gemard; J. Aichelin

2014-02-02T23:59:59.000Z

176

Active charge/passive discharge solar heating systems: thermal analysis  

SciTech Connect

The performance of active charge/passive discharge solar space-heating systems is analyzed. This type of system combines liquid-cooled solar collector panels with a massive integral storage component that passively heats the building interior by radiation and free convection. The TRNSYS simulation program is used to evaluate system performance and to provide input for the development of a simplified analysis method. This method, which provides monthly calculations of delivered solar energy, is based on Klein's Phi-bar procedure and data from hourly TRNSYS simulations. The method can be applied to systems using a floor slab, a structural wall, or a water tank as the storage component. Important design parameters include collector area and orientation, building heat loss, collector and heat-exchanger efficiencies, storage capacity, and storage to room coupling.

Swisher, J.

1981-01-01T23:59:59.000Z

177

Testing the quasi-absolute method in photon activation analysis  

SciTech Connect

In photon activation analysis (PAA), relative methods are widely used because of their accuracy and precision. Absolute methods, which are conducted without any assistance from calibration materials, are seldom applied for the difficulty in obtaining photon flux in measurements. This research is an attempt to perform a new absolute approach in PAA - quasi-absolute method - by retrieving photon flux in the sample through Monte Carlo simulation. With simulated photon flux and database of experimental cross sections, it is possible to calculate the concentration of target elements in the sample directly. The QA/QC procedures to solidify the research are discussed in detail. Our results show that the accuracy of the method for certain elements is close to a useful level in practice. Furthermore, the future results from the quasi-absolute method can also serve as a validation technique for experimental data on cross sections. The quasi-absolute method looks promising.

Sun, Z. J. [Chemical Sciences and Engineering Division, Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439 (United States); Wells, D. [Physics Department, South Dakota School of Mines and Technology, 501 E. Saint Joseph St. Rapid City, SD 57701 (United States); Starovoitova, V.; Segebade, C. [Idaho Accelerator Center, Idaho State University, 921 S. 8th Ave. Pocatello, ID 83209 (United States)

2013-04-19T23:59:59.000Z

178

Improved mesh based photon sampling techniques for neutron activation analysis  

SciTech Connect

The design of fusion power systems requires analysis of neutron activation of large, complex volumes, and the resulting particles emitted from these volumes. Structured mesh-based discretization of these problems allows for improved modeling in these activation analysis problems. Finer discretization of these problems results in large computational costs, which drives the investigation of more efficient methods. Within an ad hoc subroutine of the Monte Carlo transport code MCNP, we implement sampling of voxels and photon energies for volumetric sources using the alias method. The alias method enables efficient sampling of a discrete probability distribution, and operates in 0(1) time, whereas the simpler direct discrete method requires 0(log(n)) time. By using the alias method, voxel sampling becomes a viable alternative to sampling space with the 0(1) approach of uniformly sampling the problem volume. Additionally, with voxel sampling it is straightforward to introduce biasing of volumetric sources, and we implement this biasing of voxels as an additional variance reduction technique that can be applied. We verify our implementation and compare the alias method, with and without biasing, to direct discrete sampling of voxels, and to uniform sampling. We study the behavior of source biasing in a second set of tests and find trends between improvements and source shape, material, and material density. Overall, however, the magnitude of improvements from source biasing appears to be limited. Future work will benefit from the implementation of efficient voxel sampling - particularly with conformal unstructured meshes where the uniform sampling approach cannot be applied. (authors)

Relson, E.; Wilson, P. P. H.; Biondo, E. D. [University of Wisconsin-Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)

2013-07-01T23:59:59.000Z

179

Carbon Dioxide Information Analysis Center: FY 1992 activities  

SciTech Connect

During the course of a fiscal year, Oak Ridge National Laboratory`s Carbon Dioxide Information Analysis Center (CDIAC) distributes thousands of specialty publications-numeric data packages (NDPs), computer model packages (CMPs), technical reports, public communication publications, newsletters, article reprints, and reference books-in response to requests for information related to global environmental issues, primarily those pertaining to climate change. CDIACs staff also provides technical responses to specific inquiries related to carbon dioxide (CO{sub 2}), other trace gases, and climate. Hundreds of referrals to other researchers, policy analysts, information specialists, or organizations are also facilitated by CDIAC`s staff. This report provides an account of the activities accomplished by CDIAC during the period October 1, 1991 to September 30, 1992. An organizational overview of CDIAC and its staff is supplemented by a detailed description of inquiries received and CDIAC`s response to those inquiries. As analysis and description of the preparation and distribution of numeric data packages, computer model packages, technical reports, newsletters, fact sheets, specialty publications, and reprints is provided. Comments and descriptions of CDIAC`s information management systems, professional networking, and special bilateral agreements are also described.

Cushman, R.M. [Oak Ridge National Lab., TN (United States). Carbon Dioxide Information Analysis Center; Stoss, F.W. [Tennessee Univ., Knoxville, TN (United States). Energy, Environment and Resources Center

1993-03-01T23:59:59.000Z

180

CANDU core analysis with spent PWR fuel of fixed {sup 235}U and {sup 239}Pu content  

SciTech Connect

The direct use of spent pressurized water reactor (PWR) fuel in a CANDU (DUPIC) fuel cycle requires that the spent PWR fuel be refabricated as a DUPIC fuel to be used in a CANDU reactor that was originally designed for the natural uranium fuel. Because there is no separation of isotopes from the spent PWR fuel, the DUPIC fuel contains all the actinides and fission products as fuel constituents and, therefore, the isotopic composition changes depending on the initial and discharge conditions of PWR fuels. Such heterogeneity in fuel composition is not desirable, especially for a CANDU reactor that adopts an on-power refueling scheme, because the operational flexibility is reduced appreciably if the fuel bundles of different composition are loaded throughout the core.

Choi, Hangbok; Roh, Gyu H.; Park, J.W. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Logging-while-coring method and apparatus  

DOE Patents (OSTI)

A method and apparatus for downhole coring while receiving logging-while-drilling tool data. The apparatus includes core collar and a retrievable core barrel. The retrievable core barrel receives core from a borehole which is sent to the surface for analysis via wireline and latching tool The core collar includes logging-while-drilling tools for the simultaneous measurement of formation properties during the core excavation process. Examples of logging-while-drilling tools include nuclear sensors, resistivity sensors, gamma ray sensors, and bit resistivity sensors. The disclosed method allows for precise core-log depth calibration and core orientation within a single borehole, and without at pipe trip, providing both time saving and unique scientific advantages.

Goldberg, David S. (New York, NY); Myers, Gregory J. (Cornwall, NY)

2007-11-13T23:59:59.000Z

182

Spectroscopical Analysis of Mechano-chemically Activated Surfaces  

E-Print Network (OSTI)

Mechano-chemical activation is fundamentally different than chemical activation in that energy is added to alter the state of bond energy instead of exciting electrons to produce a chemical reaction. Mechano-chemical activation has demonstrated...

Cooper, Rodrigo

2012-10-19T23:59:59.000Z

183

Modeling and analysis framework for core damage propagation during flow-blockage-initiated accidents in the Advanced Neutron Source reactor at Oak Ridge National Laboratory  

SciTech Connect

This paper describes modeling and analysis to evaluate the extent of core damage during flow blockage events in the Advanced Neutron Source (ANS) reactor planned to be built at ORNL. Damage propagation is postulated to occur from thermal conduction between dmaged and undamaged plates due to direct thermal contact. Such direct thermal contact may occur beause of fuel plate swelling during fission product vapor release or plate buckling. Complex phenomena of damage propagation were modeled using a one-dimensional heat transfer model. A parametric study was done for several uncertain variables. The study included investigating effects of plate contact area, convective heat transfer coefficient, thermal conductivity on fuel swelling, and initial temperature of the plate being contacted by the damaged plate. Also, the side support plates were modeled to account for their effects of damage propagation. Results provide useful insights into how variouss uncertain parameters affect damage propagation.

Kim, S.H.; Taleyarkhan, R.P.; Navarro-Valenti, S.; Georgevich, V.

1995-12-31T23:59:59.000Z

184

Analysis of Fuel Ethanol Transportation Activity and Potential Distribution Constraints  

SciTech Connect

This paper provides an analysis of fuel ethanol transportation activity and potential distribution constraints if the total 36 billion gallons of renewable fuel use by 2022 is mandated by EPA under the Energy Independence and Security Act (EISA) of 2007. Ethanol transport by domestic truck, marine, and rail distribution systems from ethanol refineries to blending terminals is estimated using Oak Ridge National Laboratory s (ORNL s) North American Infrastructure Network Model. Most supply and demand data provided by EPA were geo-coded and using available commercial sources the transportation infrastructure network was updated. The percentage increases in ton-mile movements by rail, waterways, and highways in 2022 are estimated to be 2.8%, 0.6%, and 0.13%, respectively, compared to the corresponding 2005 total domestic flows by various modes. Overall, a significantly higher level of future ethanol demand would have minimal impacts on transportation infrastructure. However, there will be spatial impacts and a significant level of investment required because of a considerable increase in rail traffic from refineries to ethanol distribution terminals.

Das, Sujit [ORNL; Peterson, Bruce E [ORNL; Chin, Shih-Miao [ORNL

2010-01-01T23:59:59.000Z

185

The investigation of spices by use of instrumental neutron activation analysis  

E-Print Network (OSTI)

contaminants. For this research, instrumental neutron-activation analysis (INAA) was used to determine the activities of U-235 fission products in common spices. Using this information, the concentrations of natural uranium in these spices and the doses...

Wise, Jatara Rob

2008-10-10T23:59:59.000Z

186

E-Print Network 3.0 - activity based analysis Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

Sciences 4 Reasoning about Repairability of Workflows at Design Time Summary: activities can be provided by the workflow designer based on the analysis of different aspects...

187

Both core and F proteins of hepatitis C virus could enhance cell proliferation in transgenic mice  

SciTech Connect

Highlights: •HCV core and F proteins could induce hepatocyte proliferation in the transgenic mice. •?-Catenin signaling pathway was activated by core protein in the transgenic mice. •?-Catenin signaling pathway was activated by myc-F protein in the transgenic mice. •Expression of SMA protein was enhanced by core but not myc-F protein. -- Abstract: The role of the protein encoded by the alternative open reading frame (ARF/F/core+1) of the Hepatitis C virus (HCV) genome in viral pathogenesis remains unknown. The different forms of ARF/F/core+1 protein were labile in cultured cells, a myc-tag fused at the N-terminus of the F protein made it more stable. To determine the role of core and F proteins in HCV pathogenesis, transgenic mice with either protein expression under the control of Albumin promoter were generated. Expression of core protein and F protein with myc tag (myc-F) could be detected by Western blotting analysis in the livers of these mice. The ratio of liver to body weight is increased for both core and myc-F transgenic mice compared to that of wild type mice. Indeed, the proliferating cell nuclear antigen protein, a proliferation marker, was up-regulated in the transgenic mice with core or myc-F protein. Further analyses by microarray and Western blotting suggested that ?-catenin signaling pathway was activated by either core or myc-F protein in the transgenic mice. These transgenic mice were further treated with either Diethynitrosamine (a tumor initiator) or Phenobarbital (a tumor promoter). Phenobarbital but not Diethynitrosamine treatment could increase the liver/body weight ratio of these mice. However, no tumor formation was observed in these mice. In conclusion, HCV core and myc-F proteins could induce hepatocyte proliferation in the transgenic mice possibly through ?-catenin signaling pathway.

Hu, Wen-Ta [Graduate Institute of Medical Biotechnology, Tzu Chi University, Hualien, Taiwan (China)] [Graduate Institute of Medical Biotechnology, Tzu Chi University, Hualien, Taiwan (China); Li, Hui-Chun [Department of Biochemistry, Tzu Chi University, Hualien, Taiwan (China)] [Department of Biochemistry, Tzu Chi University, Hualien, Taiwan (China); Lee, Shen-Kao; Ma, Hsin-Chieh; Yang, Chee-Hing; Chen, Hung-Ling [Graduate Institute of Medical Biotechnology, Tzu Chi University, Hualien, Taiwan (China)] [Graduate Institute of Medical Biotechnology, Tzu Chi University, Hualien, Taiwan (China); Lo, Shih-Yen, E-mail: losylo@mail.tcu.edu.tw [Graduate Institute of Medical Biotechnology, Tzu Chi University, Hualien, Taiwan (China) [Graduate Institute of Medical Biotechnology, Tzu Chi University, Hualien, Taiwan (China); Department of Laboratory Medicine, Buddhist Tzu Chi General Hospital, Hualien, Taiwan (China)

2013-05-24T23:59:59.000Z

188

Tank 241-AP-105, cores 208, 209 and 210, analytical results for the final report  

SciTech Connect

This document is the final laboratory report for Tank 241-AP-105. Push mode core segments were removed from Risers 24 and 28 between July 2, 1997, and July 14, 1997. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-AP-105 Push Mode Core Sampling and Analysis Plan (TSAP) (Hu, 1997) and Tank Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT), differential scanning calorimetry (DSC) analysis, or total organic carbon (TOC) analysis exceeded the notification limits as stated in TSAP and DQO. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group, and are not considered in this report. Appearance and Sample Handling Two cores, each consisting of four segments, were expected from Tank 241-AP-105. Three cores were sampled, and complete cores were not obtained. TSAP states core samples should be transported to the laboratory within three calendar days from the time each segment is removed from the tank. This requirement was not met for all cores. Attachment 1 illustrates subsamples generated in the laboratory for analysis and identifies their sources. This reference also relates tank farm identification numbers to their corresponding 222-S Laboratory sample numbers.

Nuzum, J.L.

1997-10-24T23:59:59.000Z

189

Core Values | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Core Values Core Values Core Values People - People are our most important resource. We respect and use our experience and skills and appreciate our diversity. Business Excellence - We are fiscally responsible and actively pursue best business practices. Safety - We protect our human and material resources and promote safe work practices within the office and at our sites. Communication - We take full advantage of our virtual organization's strengths and share information freely across all levels of the organization. Leadership and Teamwork - We encourage leadership and teamwork at all levels of the organization. We value active participation and demonstrate respect for each other. Customer Service - We openly communicate with all our customers in a timely manner and actively seek opportunities to improve our services.

190

UNL Core for Applied Genomics and Ecology  

E-Print Network (OSTI)

UNL Core for Applied Genomics and Ecology Bioinformatics training Roche 454 GS-FLX Registration, Microbiomes, Variant Analysis, Whole Genomes, Transcriptomes Data Analysis and Statistics CAGE database and employer. University of Nebraska-Lincoln*Core for Applied Genomics and Ecology* 323 Filley Hall *Lincoln

Farritor, Shane

191

Composition and On Demand Deployment of Distributed Brain Activity Analysis Application on Global Grids  

E-Print Network (OSTI)

1 Composition and On Demand Deployment of Distributed Brain Activity Analysis Application on Global are brain science and high-energy physics. The analysis of brain activity data gathered from the MEG and analyze brain functions and requires access to large-scale computational resources. The potential platform

Abramson, David

192

Activation analysis of concrete and graphite in the experimental reactor RUS  

Science Journals Connector (OSTI)

......in the whole reactor, as a function...consistency and the reliability of the nuclear...for activation analysis. We believe...industrial nuclear reactors. INTRODUCTION...consistency and the reliability of the nuclear...for activation analysis. We believe...industrial nuclear reactors. | CEA Saclay......

M. Cometto; D. Ridikas; M. C. Aubert; F. Damoy; D. Ancius

2005-12-20T23:59:59.000Z

193

Specification and Analysis of the AER/NCA Active Network Protocol Suite in  

E-Print Network (OSTI)

Specification and Analysis of the AER/NCA Active Network Protocol Suite to the specification and analy- sis of the AER/NCA suite of active network multicast protocol compo- nents, AER/NCA poses challenging new problems for its formal specification and analysis. Real-Time Maude

Ã?lveczky, Peter Csaba

194

Audio visual information fusion for human activity analysis  

E-Print Network (OSTI)

xviii Chapter 1 Audio visual human activity4.2 Person tracking using audio-visual cues . . . . .Probabilistic framework for audio-visual information fusion

Thagadur Shivappa, Shankar

2010-01-01T23:59:59.000Z

195

FY 2006 Annual Progress Report for Advanced Vehicle Technology Analysis and Evaluation Activities  

NLE Websites -- All DOE Office Websites (Extended Search)

AdvAnced vehicle Technology AdvAnced vehicle Technology AnAlysis And evAluATion AcTiviTies U.S. Department of Energy FreedomCAR and Vehicle Technologies Program 1000 Independence Avenue, S.W. Washington, DC 20585-0121 FY 2006 Annual Progress Report for Advanced Vehicle Technology Analysis and Evaluation Activities Submitted to: U.S. Department of Energy Energy Efficiency and Renewable Energy FreedomCAR and Vehicle Technologies Program Advanced Vehicle Technology Analysis and Evaluation Lee Slezak, Technology Manager Advanced Vehicle Technology Analysis and Evaluation Activities FY 2006 Annual Report CONTENTS I. INTRODUCTION............................................................................................................................ 1 II. MODELING AND SIMULATION ................................................................................................ 9

196

Core Holes At Blue Mountain Geothermal Area (Fairbank & Niggemann...  

Open Energy Info (EERE)

Exploration Activity Details Location Blue Mountain Geothermal Area Exploration Technique Core Holes Activity Date 2002 - 2004 Usefulness useful DOE-funding Unknown Exploration...

197

Hanford 100-N Area In Situ Apatite and Phosphate Emplacement by Groundwater and Jet Injection: Geochemical and Physical Core Analysis  

SciTech Connect

The purpose of this study is to evaluate emplacement of phosphate into subsurface sediments in the Hanford Site 100-N Area by two different technologies: groundwater injection of a Ca-citrate-PO4 solution and water-jet injection of sodium phosphate and/or fish-bone apatite. In situ emplacement of phosphate and apatite adsorbs, then incorporates Sr-90 into the apatite structure by substitution for calcium. Overall, both technologies (groundwater injection of Ca-citrate-PO4) and water-jet injection of sodium phosphate/fish-bone apatite) delivered sufficient phosphate to subsur¬face sediments in the 100-N Area. Over years to decades, additional Sr-90 will incorporate into the apatite precipitate. Therefore, high pressure water jetting is a viable technology to emplace phosphate or apatite in shallow subsurface sediments difficult to emplace by Ca-citrate-PO4 groundwater injections, but further analysis is needed to quantify the relevant areal extent of phosphate deposition (in the 5- to 15-ft distance from injection points) and cause of the high deposition in finer grained sediments.

Szecsody, James E.; Vermeul, Vincent R.; Fruchter, Jonathan S.; Williams, Mark D.; Rockhold, Mark L.; Qafoku, Nikolla; Phillips, Jerry L.

2010-07-01T23:59:59.000Z

198

On the determination of trace elements in cocoa and coffee by instrumental neutron activation analysis  

E-Print Network (OSTI)

. Charlene Helton for her helpful and productive suggestions, and, of course, for undertaking the laborious task or. typing the final manuscript. DEDICATION To mv parents. TABLE OF CONTENTS Chapter ~Pa e INTRODUCTION THEORY Neutron Activation..., commercial cocoa. CHAPTER II THEORY Neutron Activation Analysis Neutron Activation Analysis was proposed by Von Hevesy and Levi in 1936 (32). hey irradiated a yttrium sample with neutrons from a radium-beryllium source and determined the im urity...

Adanuvor, Prosper Kwasi

2012-06-07T23:59:59.000Z

199

Candu 6 severe core damage accident consequence analysis for steam generator tube rupture scenario using MAAP4-CANDU V4.0.5A: preliminary results  

SciTech Connect

This paper describes the preliminary results of the consequence analysis for a generic AECL CANDU 6 station, when it undergoes a postulated, low probability Steam Generator multiple Tube Rupture (SGTR) severe accident with assumed unavailability of several critical plant safety systems. The Modular Accident Analysis Program for CANDU (MAAP4-CANDU) code was used for this analysis. The SGTR accident is assumed to begin with the guillotine rupture of 10 steam generator tubes in one steam generator in Primary Heat Transport System (PHTS) loop 1. For the reference case, the following systems were assumed unavailable: moderator and shield cooling, emergency core cooling, crash cool-down, and main and auxiliary feed water. Two additional cases were analyzed, one with the crash cool-down system available, and another with the crash cool-down and the auxiliary feed water systems available. The three scenarios considered in this study show that most of the initial fission product inventory would be retained within the containment by various fission product retention mechanisms. For the case where the crash cool-down system was credited but the auxiliary feed water systems were not credited, the total mass of volatile fission products released to the environment including stable and radioactive isotopes was about four times more than in the reference case, because fission products could be released directly from the PHTS to the environment through the Main Steam Safety Valves (MSSVs), bypassing the containment. For the case where the crash cool-down and auxiliary feed water systems were credited, the volatile fission product release to the environment was insignificant, because the fission product release was substantially mitigated by scrubbing in the water pool in the secondary side of the steam generator (SG). (authors)

Petoukhov, S.M.; Awadh, B.; Mathew, P.M. [Chalk River Laboratories, Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2006-07-01T23:59:59.000Z

200

Tank 241-BY-111, cores 168 and 171 analytical results for the final report  

SciTech Connect

This document is the final laboratory report for Tank 241-BY-111. Push mode core segments were removed from risers 15 and 12A between August 13, 1996, and September 3, 1996. Segments were received and extruded at 222-S Laboratory. Analyses were performed in accordance with Tank 241-BY-111 Rotary Mode Core Sampling and Analysis Plan (TSAP) (Kruger, 1996) and Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). None of the subsamples submitted for total alpha activity (AT) or differential scanning calorimetry (DSC) analyses exceeded the notification limits stated in DQO. Two cores of nine segments were expected from this tank. Sampling problems prevented the acquisition of complete cores. Attachment 1 illustrates subsamples generated in the laboratory for analysis and identifies their sources. This reference also relates tank farm identification numbers to their corresponding 222-S Laboratory Information Management System (LIMS) sample numbers.

Nuzum, J.L.

1997-05-02T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Cold neutron facility for prompt gamma-neutron activation analysis  

Science Journals Connector (OSTI)

The restart of the recently upgraded research reactor in Budapest is foreseen at the end of this year. A number of fast, thermal and cold neutron beams will serve for research, industrial and educational activiti...

G. Molnár; ZS. Révay; Á. Veres; A. Simonits…

1993-01-01T23:59:59.000Z

202

Every BCG with a Strong Radio Agn has an X-Ray Cool Core: Is the Cool Core-Noncool Core Dichotomy Too Simple?  

Science Journals Connector (OSTI)

The radio active galactic nucleus (AGN) feedback in X-ray cool cores has been proposed as a crucial ingredient in the evolution of baryonic structures. However, it has long been known that strong radio AGNs also exist in "noncool core" clusters, which brings up the question whether an X-ray cool core is always required for the radio feedback. In this work, we present a systematic analysis of brightest cluster galaxies (BCGs) and strong radio AGNs in 152 groups and clusters from the Chandra archive. All 69 BCGs with radio AGN more luminous than 2 ? 1023 W Hz–1 at 1.4 GHz are found to have X-ray cool cores. BCG cool cores can be divided into two classes: the large cool core (LCC) class and the corona class. Small coronae, easily overlooked at z > 0.1, can trigger strong heating episodes in groups and clusters, long before LCCs are formed. Strong radio outbursts triggered by coronae may destroy embryonic LCCs and thus provide another mechanism to prevent the formation of LCCs. However, it is unclear whether coronae are decoupled from the radio feedback cycles as they have to be largely immune to strong radio outbursts. Our sample study also shows the absence of groups with a luminous cool core while hosting a strong radio AGN, which is not observed in clusters. This points to a greater impact of radio heating on low-mass systems than clusters. Few L 1.4 GHz > 1024 W Hz–1 radio AGNs (~16%) host an L 0.5-10 keV > 1042 erg s–1 X-ray AGN, while above these thresholds, all X-ray AGNs in BCGs are also radio AGNs. As examples of the corona class, we also present detailed analyses of a BCG corona associated with a strong radio AGN (ESO 137-006 in A3627) and one of the faintest coronae known (NGC 4709 in the Centaurus cluster). Our results suggest that the traditional cool core/noncool core dichotomy is too simple. A better alternative is the cool core distribution function, with the enclosed X-ray luminosity or gas mass.

M. Sun

2009-01-01T23:59:59.000Z

203

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal floods during mid-loop operations. Volume 4  

SciTech Connect

The major objective of the Surry internal flood analysis was to provide an improved understanding of the core damage scenarios arising from internal flood-related events. The mean core damage frequency of the Surry plant due to internal flood events during mid-loop operations is 4.8E-06 per year, and the 5th and 95th percentiles are 2.2E-07 and 1.8E-05 per year, respectively. Some limited sensitivity calculations were performed on three plant improvement options. The most significant result involves modifications of intake-level structure on the canal, which reduced core damage frequency contribution from floods in mid-loop by about 75%.

Kohut, P. [Brookhaven National Lab., Upton, NY (United States)

1994-07-01T23:59:59.000Z

204

Analysis Activities at Idaho National Engineering & Environmental Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Engineering and Environmental Laboratory Engineering and Environmental Laboratory Systems Analysis Finis Southworth, PhD Department Manager Systems & Decision Science DOE Hydrogen, Fuel Cells, and Infrastructure Technologies Program Systems Analysis Workshop July 28-29, 2004 Washington, D.C. Idaho National Engineering and Environmental Laboratory Charter Systems & Decision Science Mission: Develop and apply science-based systems, systems engineering, and decision science capabilities that result in successful projects and effective, defensible decisions Systems & Decision Science Funding: 0 2 4 6 8 10 12 $M National & Homeland Security Systems Integration and Analysis Other (YMP, Cleanup, etc.) Energy Current S&DS Funding = $18M FY04 FY03 Idaho National Engineering and Environmental Laboratory

205

Stability of Molten Core Materials  

SciTech Connect

The purpose of this report is to document a literature and data search for data and information pertaining to the stability of nuclear reactor molten core materials. This includes data and analysis from TMI-2 fuel and INL’s LOFT (Loss of Fluid Test) reactor project and other sources.

Layne Pincock; Wendell Hintze

2013-01-01T23:59:59.000Z

206

Peptidomimetics in the Discovery of New Insect Growth Regulators: Studies on the Structure?Activity Relationships of the Core Pentapeptide Region of Allatostatins  

Science Journals Connector (OSTI)

The CA were selected as the target, and the core pentapeptide region (YDFGL) was chosen as the lead sequence in the search for new IGRs based on the allatostatins. ... Substitution of Leu with Ile, Val, Met, and Nle demonstrated little inhibition of JH biosynthesis by III5 (<200-fold) and III6 (<100-fold) relative to the penptapeptide, and III7 and III8 showed no effect on JH biosynthesis. ...

Zhen-peng Kai; Yong Xie; Juan Huang; Stephen S. Tobe; Jin-rui Zhang; Yun Ling; Li Zhang; Yi-chen Zhao; Xin-ling Yang

2011-02-18T23:59:59.000Z

207

Multi-core Performance Analysis  

NLE Websites -- All DOE Office Websites (Extended Search)

Extreme Scaling on Extreme Scaling on Petascale-class Systems Cray XE/XT Porting, Scaling, and Optimization 46 VECTORIZATION: LOOP ORDER MATTERS 47 55. 1 ii = 0 56. 1 2-----------< do b = abmin, abmax 57. 1 2 3---------< do j=ijmin, ijmax 58. 1 2 3 ii = ii+1 59. 1 2 3 jj = 0 60. 1 2 3 4-------< do a = abmin, abmax 61. 1 2 3 4 r8----< do i = ijmin, ijmax 62. 1 2 3 4 r8 jj = jj+1 63. 1 2 3 4 r8 f5d(a,b,i,j) = f5d(a,b,i,j) + tmat7(ii,jj) 64. 1 2 3 4 r8 f5d(b,a,i,j) = f5d(b,a,i,j) - tmat7(ii,jj) 65. 1 2 3 4 r8 f5d(a,b,j,i) = f5d(a,b,j,i)

208

Multi-core Performance Analysis  

NLE Websites -- All DOE Office Websites (Extended Search)

Scaling on Petascale- class Systems Cray XEXT Architecture, System Software, and Scientific Libraries 34 CRAY XEXT SYSTEM ARCHITECTURE 35 DDR3 Channel DDR3 Channel DDR3 Channel...

209

Neutron Activation Analysis of Milligram Quantifies of Lunar Rocks and Soils  

Science Journals Connector (OSTI)

...Tl) detector, depending on efficiency and purity requirements. Approximately...performed at the Union Car-bide "swimming pool" reactor at Ster-ling Forest...RNAA; radiochemical, high-energy gamma, activation analysis, RGAA...

Karl K. Turekian; D. P. Kharkar

1970-01-30T23:59:59.000Z

210

The determination of phosphorus by fast neutron activation analysis  

E-Print Network (OSTI)

THE DETERMXNATIQN OF PHOSPHORUS BY FAST NEUTRON ACTIVATION ANAXYSIS Thesis MAEN TO ON Submitted to the Graduate College of Texas ASM University in partial fulfillment of the reguirekents for the degree of MASTER OF SC XENCE May 1964 Major... subject, : chemistr'y THE DETERMXNATXON OF PHOSPHORUS BY FAST NEUTRON ACTXVATXON ANAXYSXS Thesis By MAEN TO ON Approved as to style and content by: (Chairman of Committee) (Memb of Committee) (Head of Department) (Member of Committee) May 1964 AC...

To-On, Maen

2012-06-07T23:59:59.000Z

211

Idealized Test Cases for Dynamical Core Experiments  

E-Print Network (OSTI)

Idealized Test Cases for Dynamical Core Experiments Christiane Jablonowski (University of Michigan-13/2006 #12;Motivation · Test cases for 3D dynamical cores on the sphere ­ are hard to find in the literature groups ­ lack standardized & easy-to-use analysis techniques · Idea: Establish a collection of test cases

Jablonowski, Christiane

212

Flow instabilities in the core and the coolant circuit of advances low-boiling light water reacto: classification of causes and development of simulator for the future analysis  

E-Print Network (OSTI)

parameters due to closed loop system feedback. In turn, these cause over-circuit instability in the reactor. Core power generation changes are carried out by means of influencing the nuclear fission process through changing the multiplication factor...

Rezvyi, Aleksey

2012-06-07T23:59:59.000Z

213

Analysis of chemical competition for binding sites on activated charcoal  

E-Print Network (OSTI)

. This interaction of adsorbates (6) is known as co-adsorption. The function of a co-adsorbate is not entirely clear, holm, it may be seen as a modification or The citations follow the style of the American Industrial ene Association Journal. deactivation... of the adsorbent. Since activated charcoal is a non-polar sorbent, the adsorbed oznpaund with the highest toiling point or largest nal~ volunN will be most strongly held, and wi11 displace other adsorbed carpounds in decreasing order down the length...

Gallerani, Susan Jane

2012-06-07T23:59:59.000Z

214

Utilization of neutron activation analysis in groundwater analyses  

SciTech Connect

Although work at the Massachusetts Institute of Technology's Nuclear Reactor Laboratory is basically research oriented, over the past number of years, numerous neutron activation analyses (NAAs) have been performed for commercial purposes. This has been true particularly in cases where other analytical techniques have been found to be insufficient or in cases where special sample considerations are involved. The requests for these analyses came from a wide range of institutions, including government laboratories, medical centers, utilities, and commercial companies. In most cases, instrumental NAA (INAA) was the method of choice because of the method's extremely low detection limits, multielement characteristics, nondestructive nature, and ability to work with different sample sizes.

Beal, J.W. (Fairfield Univ., CT (United States)); Olmez, I. (Massachusetts Institute of Technology, Cambridge, MA (United States))

1993-01-01T23:59:59.000Z

215

CONTROL SYSTEM FOR ACTIVE ANKLE-FOOT ORTHOSIS AND GAIT ANALYSIS  

E-Print Network (OSTI)

CONTROL SYSTEM FOR ACTIVE ANKLE-FOOT ORTHOSIS AND GAIT ANALYSIS CONTROL SYSTEM FOR ACTIVE ANKLE system has mounted into two basic components: insole for the healthy leg and ankle-foot orthoses. Proposed ankle-foot orthosis is with one degree of freedom which foot segment is connected to the shank

Mustakerov, Ivan

216

Analysis of Seismic Activity near Theodore Roosevelt Dam, Arizona, during the Occupation  

E-Print Network (OSTI)

E Analysis of Seismic Activity near Theodore Roosevelt Dam, Arizona, during the Occupation, and Lepolt Linkimer Online Material: Plot of viable focal mechanisms and table of regional seismic velocity model. INTRODUCTION Rate and distribution of seismic activity are important indica- tors of the overall

Fouch, Matthew J.

217

Water Research 36 (2002) 11811192 Accuracy analysis of a respirometer for activated sludge  

E-Print Network (OSTI)

Water Research 36 (2002) 1181­1192 Accuracy analysis of a respirometer for activated sludge dynamic transfer, pH, and the influence of sludge condition on ``start-up'' behaviour. It is shown to what extent Elsevier Science Ltd. All rights reserved. Keywords: Respirometry; Oxygen uptake rate; Activated sludge

218

Sensitivity Analysis of Optimal Operation of an Activated Sludge Process Model for Economic Controlled Variable Selection  

E-Print Network (OSTI)

Sensitivity Analysis of Optimal Operation of an Activated Sludge Process Model for Economic operation conducted on an activated sludge process model based on the test-bed benchmark simulation model no structure that leads to optimal economic operation, while promptly rejecting disturbances at lower layers

Skogestad, Sigurd

219

Specification and Analysis of the AER/NCA Active Network Protocol Suite in  

E-Print Network (OSTI)

Specification and Analysis of the AER/NCA Active Network Protocol Suite in Real­Time Maude Peter and the Maude formal methodology to the specification and analy­ sis of the AER/NCA suite of active network and the composability of its components, AER/NCA poses challenging new problems for its formal specification

Ã?lveczky, Peter Csaba

220

A method for activation analysis of ruthenium in sea water  

E-Print Network (OSTI)

of these isotopes in the marine environment, it is essential that a method for the analysis of trace amounts of stable ruthenium be developed, and applied to the study of the chemical and physical dis- tribution of ruthenium in sea water, marine biota... 100 27. 2 82 34. 8 100 30. 2 91 30. 6 92 26. 9 81 8 (Tracer Only) 34. 5 100 Standard 33. 3 Average Counting time ? Eorty minutes 103 Tracer ? Ru 93 Stable ruthenium added ? 0. Z6 ug 14 TABLE 4 Nuclear Data for Ruthenium Isotope Per Cent...

Dixon, Bryan William

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Bayesian modelling of the cool core galaxy group NGC 4325  

E-Print Network (OSTI)

We present an X-ray analysis of the radio-quiet cool-core galaxy group NGC 4325 (z=0.026) based on Chandra and ROSAT observations. The Chandra data were analysed using XSPEC deprojection, 2D spectral mapping and forward-fitting with parametric models. Additionally, a Markov chain Monte Carlo method was used to perform a joint Bayesian analysis of the Chandra and ROSAT data. The results of the various analysis methods are compared, particularly those obtained by forward-fitting and deprojection. The spectral mapping reveals the presence of cool gas displaced up to 10 kpc from the group centre. The Chandra X-ray surface brightness shows the group core to be highly disturbed, and indicates the presence of two small X-ray cavities within 15 kpc of the group core. The XSPEC deprojection analysis shows that the group has a particularly steep entropy profile, suggesting that an AGN outburst may be about to occur. With the evidence of prior AGN activity, but with no radio emission currently observed, we suggest that the group in in a pre-outburst state, with the cavities and displaced gas providing evidence of a previous, weak AGN outburst.

Paul A. Russell; Trevor J. Ponman; Alastair J. R. Sanderson

2007-03-01T23:59:59.000Z

222

Core Drilling Demonstration  

Energy.gov (U.S. Department of Energy (DOE))

Tank Farms workers demonstrate core drilling capabilities for Hanford single-shell tanks. Core drilling is used to determine the current condition of each tank to assist in the overall assessment...

223

FY2003 Annual Progress Report for Advanced Vehicle Technology Analysis and Evaluation Activities  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Advanced Vehicle Technology Analysis and Evaluation Activities Bringing you a prosperous future where energy is clean, abundant, reliable and affordable 2003 Annual Progress Report freedomCAR & vehicle technologies program Less dependence on foreign oil, and eventual transition to an emissions-free, petroleum-free vehicle U.S. Department of Energy FreedomCAR & Vehicle Technologies Program 1000 Independence Avenue, S.W. Washington, DC 20585-0121 FY 2003 Annual Progress Report for Advanced Vehicle Technology Analysis and Evaluation Activities Submitted to: U.S. Department of Energy Energy Efficiency and Renewable Energy FreedomCAR and Vehicle Technologies Program Advanced Vehicle Technology Analysis and Evaluation Lee Slezak, Technology Manager Advanced Vehicle Technology Analysis and Evaluation Activities

224

Core Hole Drilling And Testing At The Lake City, California Geothermal  

Open Energy Info (EERE)

Hole Drilling And Testing At The Lake City, California Geothermal Hole Drilling And Testing At The Lake City, California Geothermal Field Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Conference Paper: Core Hole Drilling And Testing At The Lake City, California Geothermal Field Details Activities (4) Areas (1) Regions (0) Abstract: Unavailable Author(s): Dick Benoit, Joe Moore, Colin Goranson, David Blackwell Published: GRC, 2005 Document Number: Unavailable DOI: Unavailable Core Analysis At Lake City Hot Springs Area (Benoit Et Al., 2005) Core Holes At Lake City Hot Springs Area (Benoit Et Al., 2005) Flow Test At Lake City Hot Springs Area (Benoit Et Al., 2005) Static Temperature Survey At Lake City Hot Springs Area (Benoit Et Al., 2005) Lake City Hot Springs Geothermal Area Retrieved from "http://en.openei.org/w/index.php?title=Core_Hole_Drilling_And_Testing_At_The_Lake_City,_California_Geothermal_Field&oldid=389996

225

Summary of micrographic analysis of selected core samples from Well ER-20-6{number_sign}1 in support of matrix diffusion testing  

SciTech Connect

ER-20-6{number_sign}1 was cored to determine fracture and lithologic properties proximal to the BULLION test cavity. Selected samples from ER-20-6{number_sign}1 were subjected to matrix and/or fracture diffusion experiments to assess solute movement in this environment. Micrographic analysis of these samples suggests that the similarity in bulk chemical composition results in very similar mineral assemblages forming along natural fractures. These samples are all part of the mafic-poor Calico Hills Formation and exhibit fracture-coating mineral assemblages dominated by mixed illite/smectite clay and illite, with local opaline silica (2,236 and 2, 812 feet), and zeolite (at 2,236 feet). Based on this small sample population, the magnitude to which secondary phases have formed on fracture surfaces bears an apparently inverse relationship to the competency of the host lithology, reflected by variations in the degree of fracturing and the development of secondary phases on fracture surfaces. In the flow breccia at 2,851 feet, thinly developed, localized coatings are developed along persistent open fracture apertures in this competent rock type. Fractures in the devitrified lava from 2,812 feet are irregular, and locally blocked by secondary mineral phases. Natural fractures on the zeolitized tuff from 2,236 feet are discontinuous and irregular and typically obstructed with secondary mineral phases. There are also a second set of clean fractures in the 2,236 foot sample which lack secondary mineral phases and are interpreted to have been induced by the BULLION test. Based on these results, it is expected that matrix diffusion will be enhanced in samples where potentially transmissive fractures exhibit the greatest degree of obstruction (2,236>2,812=2,835>2,851). It is unclear what influence the induced fractures observed at 2,236 feet may have on diffusion given the lack of knowledge on their extent. It is assumed that the bulk matrix diffusion characteristics of the sample at 2,835 feet will be equivalent to the unfractured characteristics of the sample at 2,812 feet.

IT Corporation, Las Vegas

1998-09-25T23:59:59.000Z

226

TMI-2 core shipping preparations  

SciTech Connect

Shipping the damaged core from the Unit 2 reactor of Three Mile Island Nuclear Power Station near Harrisburg, PA, to the Idaho National Engineering Laboratory near Idaho Falls, ID, required development and implementation of a completely new spent fuel transportation system. This paper describes the equipment developed, the planning and activities used to implement the hardware systems into the facilities, and the planning involved in making the rail shipments. It also includes a summary of recommendations resulting from this experience.

Ball, L.J.; (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Barkanic, R.J. (Bechtel North American Power Corporation (United States)); Conaway, W.T. II (GPU Nuclear Corporation, Three Mile Island, Middletown, PA (United States)); Schmoker, D.S. (Nuclear Packaging, Inc., Federal Way, WA (United States))

1988-01-01T23:59:59.000Z

227

Core Holes At Long Valley Caldera Geothermal Area (Eichelberger...  

Open Energy Info (EERE)

Eichelberger, Et Al., 1988) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Holes At Long Valley Caldera Geothermal Area (Eichelberger, Et...

228

Core Holes At Steamboat Springs Area (Warpinski, Et Al., 2004...  

Open Energy Info (EERE)

Steamboat Springs Area (Warpinski, Et Al., 2004) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Holes At Steamboat Springs Area (Warpinski,...

229

Core Holes At Long Valley Caldera Geothermal Area (Urban, Et...  

Open Energy Info (EERE)

Urban, Et Al., 1987) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Holes At Long Valley Caldera Geothermal Area (Urban, Et Al., 1987)...

230

TOBUREN, MARK CHRISTOPHER. Power Analysis and Instruction Schedul-ing for Reduced di/dt in the Execution Core of High-Performance Microprocessors.  

E-Print Network (OSTI)

to a processor's average peak power dissipation is the pres- ence of high di=dt in its execution core. High-energy-cycle energy constraints. This thesis proposes a novel approach to instruction scheduling based on the con- cept of schedule slack, which builds energy e cient schedules by limiting the energy dissipated

Conte, Thomas M.

231

Determination of thorium in seawater by neutron activation analysis and mass spectrometry  

SciTech Connect

The recent development of neutron activation analysis and mass spectrometric methods for the determination of /sup 232/Th in seawater has made possible rapid sampling and analysis of this long-lived, non-radiogenic thorium isotope on small-volume samples. The marine geochemical utility of /sup 232/Th, whose concentration in seawater is extremely low, warrants the development of these sensitive techniques. The analytical methods and some results are presented and discussed in this article. 24 refs., 3 figs.

Huh, Chih-An

1987-01-01T23:59:59.000Z

232

Photon activation analysis as a new technique for body composition studies  

SciTech Connect

A study was undertaken to demonstrate the usefulness of the recently developed photon activation analysis (PAA) technique for in vivo body composition studies. PAA can be used for direct measurement of total-body oxygen, nitrogen, and carbon. Sequential measurements were made on rats fed diets of 0%, 4.2%, or 20% protein for 6 1/2 wk, and significant changes in body composition were noted. In addition, rats of different ages, strains, nutritional states, and degrees of obesity were included in a comparison of PAA results in vivo with results from chemical analysis after sacrifice of the animals. High positive correlations were found between PAA measurements of carbon and chemical analysis measurements of fat and between PAA measurements of oxygen and chemical analysis measurements of total-body water. A low positive correlation was found between PAA measurements of nitrogen and chemical analysis measurements of protein.

Ulin, K.; Meydani, M.; Zamenhof, R.G.; Blumberg, J.B.

1986-12-01T23:59:59.000Z

233

Ten channel background alpha radiometer for nondestructive analysis of low activity samples  

SciTech Connect

The description of a ten-channel alpha-radiometer based on large-area semiconductor detectors is presented in this paper. The radiometer is intended for determination of soil pollution by alpha-active radionuclides using thick samples. The analysis of isotopes is also provided. The concentrations of Pu and Am isotopes in soil samples are determined.

Pugatch, V.M.; Pavlenko, Y.N.; Vasiliev, Y.O.; Nenakhov, A.N.; Tkatch, N.M.; Barabash, L.I.; Berdnichenko, S.V.; Litovchenko, P.G.; Rosenfeld, A.B.; Zinets, O.S. (Inst. for Nuclear Research, Kiev (USSR))

1992-10-01T23:59:59.000Z

234

European Wind Energy Conference 2007 Milan Measurement based analysis of active and reactive power  

E-Print Network (OSTI)

European Wind Energy Conference 2007 ­ Milan 1 Measurement based analysis of active and reactive to the network through distribution systems. Because the production units, the distribution systems units will cover consumption in the vicinity. This can contribute to the reduction of the system losses

235

Performance Analysis of a Hybrid Asymmetric Multilevel Inverter for High Voltage Active Power Filter Applications  

E-Print Network (OSTI)

Performance Analysis of a Hybrid Asymmetric Multilevel Inverter for High Voltage Active Power voltage-source inverters connected in series (known as cascaded hybrid asymmetric multilevel inverter voltage application due to semiconductor constraint. In order to achieve higher power level, hybrid

Catholic University of Chile (Universidad Católica de Chile)

236

Efficiency of static core turn-off in a system-on-a-chip with variation  

DOE Patents (OSTI)

A processor-implemented method for improving efficiency of a static core turn-off in a multi-core processor with variation, the method comprising: conducting via a simulation a turn-off analysis of the multi-core processor at the multi-core processor's design stage, wherein the turn-off analysis of the multi-core processor at the multi-core processor's design stage includes a first output corresponding to a first multi-core processor core to turn off; conducting a turn-off analysis of the multi-core processor at the multi-core processor's testing stage, wherein the turn-off analysis of the multi-core processor at the multi-core processor's testing stage includes a second output corresponding to a second multi-core processor core to turn off; comparing the first output and the second output to determine if the first output is referring to the same core to turn off as the second output; outputting a third output corresponding to the first multi-core processor core if the first output and the second output are both referring to the same core to turn off.

Cher, Chen-Yong; Coteus, Paul W; Gara, Alan; Kursun, Eren; Paulsen, David P; Schuelke, Brian A; Sheets, II, John E; Tian, Shurong

2013-10-29T23:59:59.000Z

237

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1. Volume 5: Analysis of core damage frequency from seismic events during mid-loop operations  

SciTech Connect

In 1989 the US Nuclear Regulatory Commission (NRC) initiated an extensive program to examine carefully the potential risks during low-power and shutdown operations. The program included two parallel projects, one at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1) and the other at Sandia National Laboratories studying a boiling water reactor (Grand Gulf). Both the Brookhaven and Sandia projects have examined only accidents initiated by internal plant faults--so-called ``internal initiators.`` This project, which has explored the likelihood of seismic-initiated core damage accidents during refueling shutdown conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Surry Unit 1. All of the many systems modeling assumptions, component non-seismic failure rates, and human error rates that were used in the internal-initiator study at Surry have been adopted here, so that the results of the two studies can be as comparable as possible. Both the Brookhaven study and this study examine only two shutdown plant operating states (POSs) during refueling outages at Surry, called POS 6 and POS 10, which represent mid-loop operation before and after refueling, respectively. This analysis has been limited to work analogous to a level-1 seismic PRA, in which estimates have been developed for the core-damage frequency from seismic events during POSs 6 and 10. The results of the analysis are that the core-damage frequency of earthquake-initiated accidents during refueling outages in POS 6 and POS 10 is found to be low in absolute terms, less than 10{sup {minus}6}/year.

Budnitz, R.J. [Future Resources Associates, Inc., Berkeley, CA (United States); Davis, P.R. [PRD Consulting (United States); Ravindra, M.K.; Tong, W.H. [EQE International, Inc., Irvine, CA (United States)

1994-08-01T23:59:59.000Z

238

Cognitive tasks in information analysis: Use of event dwell time to characterize component activities  

SciTech Connect

Technology-based enhancement of information analysis requires a detailed understanding of the cognitive tasks involved in the process. The information search and report production tasks of the information analysis process were investigated through evaluation of time-stamped workstation data gathered with custom software. Model tasks simulated the search and production activities, and a sample of actual analyst data were also evaluated. Task event durations were calculated on the basis of millisecond-level time stamps, and distributions were plotted for analysis. The data indicate that task event time shows a cyclic pattern of variation, with shorter event durations (< 2 sec) reflecting information search and filtering, and longer event durations (> 10 sec) reflecting information evaluation. Application of cognitive principles to the interpretation of task event time data provides a basis for developing “cognitive signatures” of complex activities, and can facilitate the development of technology aids for information intensive tasks.

Sanquist, Thomas F.; Greitzer, Frank L.; Slavich, Antoinette L.; Littlefield, Rik J.; Littlefield, Janis S.; Cowley, Paula J.

2004-09-28T23:59:59.000Z

239

Photon Activation Analysis--An Analytical Application Of High-Energy Electron Accelerators  

SciTech Connect

Photon activation analysis (PAA) was introduced about contemporarily with the other activation analysis methods (neutron, NAA, and charged particle activation, CPAA). Nonetheless, for different reasons, PAA has been applied less frequently than the other techniques mentioned. The incident photon energy should exceed about 12 MeV (except in some special rare applications) so as to obtain appreciably high activity yields of the product nuclides. Thus, cyclic electron accelerators (LINACs or microtrons) are used for activation preferably. The predominant photonuclear reaction is of the ({gamma},n)-type. Thus, normally neutron-deficient nuclides are produced. These usually emit gamma rays, annihilation quanta and characteristic X-ray fluorescence, all of whom can be used for analytical evaluation. The spectrometry equipment is the same as used for the other activation techniques (semiconductor detectors, sodium iodide crystals in coincidence geometry). Being uncharged high energy photons have a large penetration power, thus do not suffer from strong matrix absorption. Although not having a detection power as large as in NAA (in the most cases), PAA offers several further convincing advantages, e.g. several elements not or hardly detectable by NAA can be analysed: Titanium, nickel, thallium, lead, bismuth and, in particular, the light elements carbon, nitrogen, oxygen, fluorine, phosphorus. Several typical applications will be described.

Segebade, Christian R.; Goerner, Wolf [Federal Institute of Materials Research and Testing Unter den Eichen 87, 12205 Berlin (Germany)

2009-03-10T23:59:59.000Z

240

An Innovative Three-Dimensional Heterogeneous Coarse-Mesh Transport Method for Advanced and Generation IV Reactor Core Analysis and Design  

SciTech Connect

This project has resulted in a highly efficient method that has been shown to provide accurate solutions to a variety of 2D and 3D reactor problems. The goal of this project was to develop (1) an accurate and efficient three-dimensional whole-core neutronics method with the following features: based sollely on transport theory, does not require the use of cross-section homogenization, contains a highly accurate and self-consistent global flux reconstruction procedure, and is applicable to large, heterogeneous reactor models, and to (2) create new numerical benchmark problems for code cross-comparison.

Farzad Rahnema

2009-11-12T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

-The Core of CS -Curricula  

E-Print Network (OSTI)

- Advanced Courses #12;The Core of CS Curricula #12;CS Body of Knowledge Area > Unit > Topic Core vs elective#12;ACM vs U S I #12;- The Core of CS - Curricula - Introductory Courses - Intermediate Courses Introductory Intermediate Advanced Core Elective Units #12;Courses Introductory Intermediate Advanced Core

Hauswirth, Matthias

242

Core shroud corner joints  

DOE Patents (OSTI)

A core shroud is provided, which includes a number of planar members, a number of unitary corners, and a number of subassemblies each comprising a combination of the planar members and the unitary corners. Each unitary corner comprises a unitary extrusion including a first planar portion and a second planar portion disposed perpendicularly with respect to the first planar portion. At least one of the subassemblies comprises a plurality of the unitary corners disposed side-by-side in an alternating opposing relationship. A plurality of the subassemblies can be combined to form a quarter perimeter segment of the core shroud. Four quarter perimeter segments join together to form the core shroud.

Gilmore, Charles B.; Forsyth, David R.

2013-09-10T23:59:59.000Z

243

Neuroscience Instrumentation and Distributed Analysis of Brain Activity Data: A Case for eScience on Global Grids  

E-Print Network (OSTI)

1 Neuroscience Instrumentation and Distributed Analysis of Brain Activity Data: A Case for e commonly observed in scientific disciplines. Two popular scientific disciplines of this nature are brain science and high-energy physics. The analysis of brain activity data gathered from the MEG

Buyya, Rajkumar

244

Oxygen to the core  

NLE Websites -- All DOE Office Websites (Extended Search)

1-01 1-01 For immediate release: 01/10/2013 | NR-13-01-01 Oxygen to the core Anne M Stark, LLNL, (925) 422-9799, stark8@llnl.gov Printer-friendly An artist's conception of Earth's inner and outer core. LIVERMORE, Calif. -- An international collaboration including researchers from Lawrence Livermore National Laboratory has discovered that the Earth's core formed under more oxidizing conditions than previously proposed. Through a series of laser-heated diamond anvil cell experiments at high pressure (350,000 to 700,000 atmospheres of pressure) and temperatures (5,120 to 7,460 degrees Fahrenheit), the team demonstrated that the depletion of siderophile (also known as "iron loving") elements can be produced by core formation under more oxidizing conditions than earlier

245

Core assembly storage structure  

DOE Patents (OSTI)

A structure for the storage of core assemblies from a liquid metal-cooled nuclear reactor. The structure comprises an enclosed housing having a substantially flat horizontal top plate, a bottom plate and substantially vertical wall members extending therebetween. A plurality of thimble members extend downwardly through the top plate. Each thimble member is closed at its bottom end and has an open end adjacent said top plate. Each thimble member has a length and diameter greater than that of the core assembly to be stored therein. The housing is provided with an inlet duct for the admission of cooling air and an exhaust duct for the discharge of air therefrom, such that when hot core assemblies are placed in the thimbles, the heat generated will by convection cause air to flow from the inlet duct around the thimbles and out the exhaust duct maintaining the core assemblies at a safe temperature without the necessity of auxiliary powered cooling equipment.

Jones, Jr., Charles E. (Northridge, CA); Brunings, Jay E. (Chatsworth, CA)

1988-01-01T23:59:59.000Z

246

The computerized identification of reactor-produced isotopes in an activation analysis environment  

E-Print Network (OSTI)

- ability of a complete, positive identification appears small. How- ever, with the addition of a least squares method of resolving interferences and the application of a figure indicating the value (figure-of-merit) placed on each elimination test...THE COMPUTERIZED IDENTIFICATION OF REACTOR-PRODUCED ISOTOP ' S IN AN ACTIVATION ANALYSIS ENVIRON&vIENT A Thesi. s by DANIEI. aOIIN SCHLUETER Submitted to the Grec'u&ate College of Texas ARM University in pa. tial fulfillment o...

Schlueter, Daniel John

1971-01-01T23:59:59.000Z

247

Bayesian statistics applied to neutron activation data for reactor flux spectrum analysis  

Science Journals Connector (OSTI)

Abstract In this paper, we present a statistical method, based on Bayesian statistics, to analyze the neutron flux spectrum from the activation data of different isotopes. The experimental data were acquired during a neutron activation experiment performed at the TRIGA Mark II reactor of Pavia University (Italy) in four irradiation positions characterized by different neutron spectra. In order to evaluate the neutron flux spectrum, subdivided in energy groups, a system of linear equations, containing the group effective cross sections and the activation rate data, has to be solved. However, since the system’s coefficients are experimental data affected by uncertainties, a rigorous statistical approach is fundamental for an accurate evaluation of the neutron flux groups. For this purpose, we applied the Bayesian statistical analysis, that allows to include the uncertainties of the coefficients and the a priori information about the neutron flux. A program for the analysis of Bayesian hierarchical models, based on Markov Chain Monte Carlo (MCMC) simulations, was used to define the problem statistical model and solve it. The first analysis involved the determination of the thermal, resonance-intermediate and fast flux components and the dependence of the results on the Prior distribution choice was investigated to confirm the reliability of the Bayesian analysis. After that, the main resonances of the activation cross sections were analyzed to implement multi-group models with finer energy subdivisions that would allow to determine the neutron flux groups, their uncertainties and correlations with good accuracy. The results were then compared with the ones obtained from the Monte Carlo simulations of the reactor fluxes performed with the MCNP code, finding in general a good agreement.

Davide Chiesa; Ezio Previtali; Monica Sisti

2014-01-01T23:59:59.000Z

248

Core Holes At Kilauea East Rift Geothermal Area (Bargar, Et Al...  

Open Energy Info (EERE)

Activity Details Location Kilauea East Rift Geothermal Area Exploration Technique Core Holes Activity Date 1989 - 1991 Usefulness useful DOE-funding Unknown Exploration...

249

ANALYSIS OF CDTE ACTIVATION TREATMENT WITH A NOVEL APPROACH Andrei Salavei^, Ivan Rimmaudo^, Fabio Piccinelli*, Daniele Menossi+  

E-Print Network (OSTI)

ANALYSIS OF CDTE ACTIVATION TREATMENT WITH A NOVEL APPROACH Andrei Salavei^, Ivan Rimmaudo^, Fabio approach for CdTe activation treatment. Starting from a baseline of CdTe devices made with CdCl2 activation­voltage characteristics) of finished devices. Keywords: CdTe, CdCl2, High-Efficiency. 1 INTRODUCTION CdTe thin film solar

Romeo, Alessandro

250

Analysis of influence of fuel price on individual activity-travel time expenditure  

Science Journals Connector (OSTI)

Abstract Fluctuation in fuel prices may lead to adaptations in people?s activity-travel behavior. Compared to other triggers of behavioral change, the impact of fuel prices has received only scant attention in the literature, especially with respect to short-run change in activity-travel behavior. To gain insight into this issue, travel diaries of a representative sample of individuals in the Netherlands who use the car for daily travel were analyzed. Seemingly unrelated regression analysis was used to examine the effects of fuel price on people?s travel time expenditures for different kinds of activities, differentiating between weekdays and weekends. The results indicate that fuel price is negatively correlated with travel time expenditures by car, and that this relationship differs between weekdays and weekends. When faced with increasing fuel prices, people seem to prefer reducing travel time expenditure by car for compulsory trips more than for leisure trips.

Dujuan Yang; Harry Timmermans

2013-01-01T23:59:59.000Z

251

AO Core Competency Worksheet  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

AO Core Competency Worksheet AO Core Competency Worksheet 1 DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS Key Cyber Security Role: Authorizing Official (AO) Role Definition: The AO is the Senior DOE Management Federal official with the authority to formally assume responsibility and be held fully accountable for operating an information system at an acceptable level of risk. Competency Area: Incident Management Functional Requirement: Manage Competency Definition: Refers to the knowledge and understanding of the processes and procedures required to prevent, detect, investigate, contain, eradicate, and recover from incidents that impact the organizational mission as directed by the DOE Cyber Incident Response Capability (CIRC). Behavioral Outcome: Individuals fulfilling the role of AO will have a working knowledge of policies

252

Earth's Core Hottest Layer  

NLE Websites -- All DOE Office Websites (Extended Search)

Earth's Core Hottest Layer Earth's Core Hottest Layer Name: Alfred Status: Grade: 6-8 Location: FL Country: USA Date: Spring 2011 Question: Why is the inner core the hottest layer? How is that possible? Replies: There are two factors causing the center of the Earth hotter than various layers of the Earth's. First, the more dense is the layer. The denser layer, the hotter it will be. In addition, the source of the heating is due to heat produced by nuclear decay. These substances tend to be more dense than lower dense substances. So the source of heat (temperature) is higher, the greater will be the temperature. Having said all that, the reasons are rather more complicated in the "real" Earth. If the inner layers were less dense they would rise (bubble) to the "surface" leaving the inner layers more dense and thus hotter layers.

253

2000 BTS Core Databook  

Buildings Energy Data Book (EERE)

0 BTS CORE DATABOOK 0 BTS CORE DATABOOK 2000 BTS CORE DATABOOK OFFICE OF ENERGY EFFICIENCY AND RENEWABLE ENERGY * U.S. DEPARTMENT OF ENERGY This version is dated: August 7, 2000 DISCLAIMER This document was designed for the internal use of the United States Department of Energy. This document was also designed to be occasionally updated and, therefore, this copy may not reflect the most current version. This document was prepared as account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that

254

SWEPP PAN assay system uncertainty analysis: Active mode measurements of solidified aqueous sludge waste  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory is being used as a temporary storage facility for transuranic waste generated by the US Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Active Neutron (PAN) radioassay system. This paper is one of a series of reports quantifying the results of the uncertainty analysis of the PAN system measurements for specific waste types and measurement modes. In particular this report covers active mode measurements of weapons grade plutonium-contaminated aqueous sludge waste contained in 208 liter drums (item description codes 1, 2, 7, 800, 803, and 807). Results of the uncertainty analysis for PAN active mode measurements of aqueous sludge indicate that a bias correction multiplier of 1.55 should be applied to the PAN aqueous sludge measurements. With the bias correction, the uncertainty bounds on the expected bias are 0 {+-} 27%. These bounds meet the Quality Assurance Program Plan requirements for radioassay systems.

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.

1997-12-01T23:59:59.000Z

255

Using Photon Activation Analysis To Determine Concentrations Of Unknown Components In Reference Materials  

SciTech Connect

Using certified multi-element reference materials for instrumental analyses one frequently is confronted with the embarrassing fact that the concentration of some desired elements are not given in the respective certificate, nonetheless are detectable, e.g. by photon activation analysis (PAA). However, these elements might be determinable with sufficient quality of the results using scaling parameters and the well-known quantities of a reference element within the reference material itself. Scaling parameters include: activation threshold energy, Giant Dipole Resonance (GDR) peak and endpoint energy of the bremsstrahlung continuum; integrated photo-nuclear cross sections for the isotopes of the reference element; bremsstrahlung continuum integral; target thickness; photon flux density. Photo-nuclear cross sections from the unreferenced elements must be known, too. With these quantities, the integral was obtained for both the known and unknown elements resulting in an inference of the concentration of the unreported element based upon the reported value, thus also the concentration of the unreferenced element in the reference material. A similar method to determine elements using the basic nuclear and experimental data has been developed for thermal neutron activation analysis some time ago (k{sub 0} Method).

Green, Jaromy; Sun, Zaijing [Idaho State University, Physics Department, 921 S. 8th Avenue, Stop 8106, Pocatello, ID 83209 (United States); Wells, Doug [Idaho State University, Physics Department, 921 S. 8th Avenue, Stop 8106, Pocatello, ID 83209 (United States); Idaho Accelerator Center, 1500 Ricken Drive, Pocatello, ID 83201 (United States); Maschner, Herb [Idaho State University, Anthropology Department, 921 S. 8th Avenue, Stop 8005, Pocatello, ID 83209 (United States)

2011-06-01T23:59:59.000Z

256

Energy-dispersive X-ray microanalysis of the bone mineral content in human trabecular bone: A comparison with ICPES and neutron activation analysis  

Science Journals Connector (OSTI)

To evaluate the accuracy of bone mineral composition determination by electron microprobe analysis (EDX) the measurements have been compared to instrumental neutron activation analysis (INAA) and chemical anal...

K. Åkesson; M. D. Grynpas; R. G. V. Hancock; R. Odselius…

1994-09-01T23:59:59.000Z

257

Hopper Multi-Core FAQ  

NLE Websites -- All DOE Office Websites (Extended Search)

Hopper Multi-Core FAQ Hopper Multi-Core FAQ Hopper Multi-Core FAQ Q. How is Hopper Different than Franklin? A. The new Hopper Phase-II system will have 24 cores per node. Franklin had only four. Q. What else is different? A. There is less memory per core. Hopper has 1.3 GB / core rather than 2.0 GB / core on Franklin. A code using MPI on Hopper may be more likely to exhaust available memory, causing an error. Additionally, Hopper's memory hierarchy is "deeper" and more non-uniform than Franklin's and this can have a big impact on performance in certain cases. Hopper's 24 cores per node are implemented on two sockets, each containing two six-core dies (see the image below). Each of the six-core dies has direct access to one-quarter of the node's total memory. Thus,

258

Geographically-Based Infrastructure Analysis  

NLE Websites -- All DOE Office Websites (Extended Search)

Infrastructure Infrastructure Analysis Margo Melendez & Keith Parks January 26, 2006 Geographically-Based Infrastructure Analysis (GIA) Utilizes GIS, geographically segregated data, and transition expertise to add the spatial component to infrastructure analysis NREL Core Competencies * Geographic data, tools, and expertise * Flexibility to address a wide array of transition issues NREL Capability Diagram Geographically-based Infrastructure Analysis GIS Transportation Technologies & Systems Electric & Hydrogen Technologies Energy Analysis Office GIA Activities Previous and Ongoing * HYDS ME - Evaluates best infrastructure options * Interstate Infrastructure Analysis - Minimal infrastructure to facilitate interstate travel during transition New Analyses * Quantifying transitional hydrogen demand

259

TMI-2 core examination  

SciTech Connect

The examination of the damaged core at the Three Mile Island Unit 2 (TMI-2) reactor is structured to address the following safety issues: fission product release, transport, and deposition; core coolability; containment integrity; and recriticality during severe accidents; as well as zircaloy cladding ballooning and oxidation during so-called design basis accidents. The numbers of TMI-2 components or samples to be examined, the priority of each examination, the safety issue addressed by each examination, the principal examination techniques to be employed, and the data to be obtained and the principal uses of the data are discussed in this paper.

Hobbins, R.R.; MacDonald, P.E.; Owen, D.E.

1983-01-01T23:59:59.000Z

260

Tank 241-TX-104, cores 230 and 231 analytical results for the final report  

SciTech Connect

This document is the analytical laboratory report for tank 241-TX-104 push mode core segments collected between February 18, 1998 and February 23, 1998. The segments were subsampled and analyzed in accordance with the Tank 241-TX-104 Push Mode Core Sampling and Analysis Plan (TSAP) (McCain, 1997), the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO) (Turner, et al., 1995) and the Safety Screening Data Quality Objective (DQO) (Dukelow, et.al., 1995). The analytical results are included in the data summary table. None of the samples submitted for Differential Scanning Calorimetry (DSC) and Total Alpha Activity (AT) exceeded notification limits as stated in the TSAP. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997) and are not considered in this report. Appearance and Sample Handling Attachment 1 is a cross reference to relate the tank farm identification numbers to the 222-S Laboratory LabCore/LIMS sample numbers. The subsamples generated in the laboratory for analyses are identified in these diagrams with their sources shown. Core 230: Three push mode core segments were removed from tank 241-TX-104 riser 9A on February 18, 1998. Segments were received by the 222-S Laboratory on February 19, 1998. Two segments were expected for this core. However, due to poor sample recovery, an additional segment was taken and identified as 2A. Core 231: Four push mode core segments were removed from tank 241-TX-104 riser 13A between February 19, 1998 and February 23, 1998. Segments were received by the 222-S Laboratory on February 24, 1998. Two segments were expected for this core. However, due to poor sample recovery, additional segments were taken and identified as 2A and 2B. The TSAP states the core samples should be transported to the laboratory within three calendar days from the time each segment is removed from the tank; this requirement was not met for the segments from Core 231.

Diaz, L.A.

1998-07-07T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix I, Volume 2, Part 5  

SciTech Connect

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Lab. (BNL) and Sandia National Labs. (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this volume of the report is to document the approach utilized in the level-1 internal events PRA for the Surry plant, and discuss the results obtained. A phased approach was used in the level-1 program. In phase 1, which was completed in Fall 1991, a coarse screening analysis examining accidents initiated by internal events (including internal fire and flood) was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis.

Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J. [Brookhaven National Lab., Upton, NY (United States); Bley, D.; Johnson, D. [PLG Inc., Newport Beach, CA (United States); Holmes, B. [AEA Technology, Dorset (United Kingdom)] [and others

1994-06-01T23:59:59.000Z

262

TMI-2 core damage: a summary of present knowledge  

SciTech Connect

Extensive fuel damage (oxidation and fragmentation) has occurred and the top approx. 1.5 m of the center portion of the TMI-2 core has relocated. The fuel fragmentation extends outward to slightly beyond one-half the core radius in the direction examined by the CCTV camera. While the radial extent of core fragmentation in other directions was not directly observed, control and spider drop data and in-core instrument data suggest that the core void is roughly symmetrical, although there are a few indications of severe fuel damage extending to the core periphery. The core material fragmented into a broad range of particle sizes, extending down to a few microns. APSR movement data, the observation of damaged fuel assemblies hanging unsupported from the bottom of the reactor upper plenum structure, and the observation of once-molten stainless steel immediately above the active core indicate high temperatures (up to at least 1720 K) extended to the very top of the core. The relative lack of damage to the underside of the plenum structure implies a sharp temperature demarcation at the core/plenum interface. Filter debris and leadscrew deposit analyses indicate extensive high temperature core materials interaction, melting of the Ag-In-Cd control material, and transport of particulate control material to the plenum and out of the vessel.

Owen, D.E.; Mason, R.E.; Meininger, R.D.; Franz, W.A.

1983-01-01T23:59:59.000Z

263

X-RAY FLUORESCENCE ANALYSIS OF HANFORD LOW ACTIVITY WASTE SIMULANTS  

SciTech Connect

Savannah River National Laboratory (SRNL) was requested to develop an x-ray fluorescence (XRF) spectrometry method for elemental characterization of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) pretreated low activity waste (LAW) stream to the LAW Vitrification Plant. The WTP is evaluating the potential for using XRF as a rapid turnaround technique to support LAW product compliance and glass former batching. The overall objective of this task was to develop XRF analytical methods that provide the rapid turnaround time (<8 hours) requested by the WTP, while providing sufficient accuracy and precision to determine waste composition variations. For Phase 1a, SRNL (1) evaluated, selected, and procured an XRF instrument for WTP installation, (2) investigated three XRF sample methods for preparing the LAW sub-sample for XRF analysis, and (3) initiated scoping studies on AN-105 (Envelope A) simulant to determine the instrument's capability, limitations, and optimum operating parameters. After preliminary method development on simulants and the completion of Phase 1a activities, SRNL received approval from WTP to begin Phase 1b activities with the objective of optimizing the XRF methodology. Three XRF sample methods used for preparing the LAW sub-sample for XRF analysis were studied: direct liquid analysis, dried spot, and fused glass. The direct liquid method was selected because its major advantage is that the LAW can be analyzed directly without any sample alteration that could bias the method accuracy. It also is the fastest preparation technique--a typical XRF measurement could be completed in < 1hr after sample delivery. Except for sodium, the method detection limits (MDLs) for the most important analytes in solution, the hold point elements, were achieved by this method. The XRF detection limits are generally adequate for glass former batching and product composition reporting, but may be inadequate for some species (Hg, Cd, and Ba) important to land disposal restrictions. The long term precision (24-hr) also was good with percent relative standard deviations (%RSDs) < 10 % for most elements in filtered solution. There were some issues with a few elements precipitating out of solution over time affecting the long term precision of the method. Additional research will need to be performed to resolve this sample stability problem. Activities related to methodology optimization in the Phase 1b portion of the study were eliminated as a result of WTP request to discontinue remaining activities due to funding reduction. These preliminary studies demonstrate that developing an XRF method to support the LAW vitrification plant is feasible. When funding is restored for the WTP, it is recommended that optimization of this technology should be pursued.

Jurgensen, A; David Missimer, D; Ronny Rutherford, R

2006-05-08T23:59:59.000Z

264

Activities  

Energy.gov (U.S. Department of Energy (DOE))

Activities and events provide Residential Network members the opportunity to discuss similar needs and challenges, and to collectively identify effective strategies and useful resources.

265

SECA Core Technology Program  

NLE Websites -- All DOE Office Websites (Extended Search)

January 27 - January 27 - 28, 2005 Workshop Peer Review Rating Results Summary Donald Collins SECA Core January 2005 Workshop Peer Review Summary - DWC,PM-30,3-10-05 2 of 21 Review Process Summary * Core Technology Project Presentations - Project Objectives & Results - Non-proprietary Information - Industry, National Lab & University Participation * Verbal & Written Constructive Comments - Written Comments on Peer Review Forms - Industry Verbal Feedback at Workshop * Core Participant Review & Reply to Comments - Reply to Comment Issues * DOE NETL Redirect Projects as Needed M a t e r i a l s C o n t r o l s & D i a g n o s t i c s P o w e r E le c t r o n ic s F u e l P r o c e s s i n g Manufacturing M o d e li n g & S im u la ti o n SECA Core January 2005 Workshop Peer Review Summary - DWC,PM-30,3-10-05 3 of 21 Peer Review Questions

266

SECA Core Technology Program  

NLE Websites -- All DOE Office Websites (Extended Search)

May 12 - May 12 - 13, 2004 Workshop Peer Review Rating Results Summary Donald Collins SECA Core May 2004 Workshop Peer Review Summary - DWC,PM-30,5-21-04 2 of 16 Review Process Summary * Core Technology Project Presentations - Project Objectives & Results - Non-proprietary Information - Industry, National Lab & University Participation * Verbal & Written Constructive Comments - Written Comments on Peer Review Forms - Industry Verbal Feedback at Workshop * Core Participant Review & Reply to Comments - Reply to Comment Issues * DOE NETL Redirect Projects as Needed M a t e r i a l s C o n t r o l s & D i a g n o s t i c s P o w e r E le c t r o n ic s F u e l P r o c e s s i n g Manufacturing M o d e li n g & S im u la ti o n SECA Core May 2004 Workshop Peer Review Summary - DWC,PM-30,5-21-04 3 of 16 Peer Review Questions

267

Plan ?: core or cusp?  

Science Journals Connector (OSTI)

......research-article Article Plan beta: core or cusp? Thomas...Breddels (2013) for a detailed review of the more sophisticated numerical...is available for each star (standard technique). Large data sets...velocity space, we use the standard definition, for the velocity......

Thomas D. Richardson; Douglas Spolyar; Matthew D. Lehnert

2014-01-01T23:59:59.000Z

268

Core competence (knowledge) (skill)  

E-Print Network (OSTI)

Core competence 8 5~8 2 3 4 5 6 7 8 PPS003 Ver. 1.1 2011/03/07 #12; 2 (knowledge) (skill) (attitude) Set of skill, knowledge or attitude which should be learned or acquired by each, 2000) (knowledge) (skill) (attitude) Set of skill, knowledge or attitude which should be learned

Wu, Yih-Min

269

Dynamics of core accretion  

Science Journals Connector (OSTI)

......formation, the accretor is of course a rocky planetary core, on to which gas accretion...both cases, the distributions are nearly flat at large distances (i.e.-R H...the evolution of the simulation, using a safety factor of J- 4. Nevertheless, at time......

Andrew F. Nelson; Maximilian Ruffert

2013-01-01T23:59:59.000Z

270

Dynamics of core accretion  

Science Journals Connector (OSTI)

......the accretor is of course a rocky planetary core, on to which...the distributions are nearly flat at large distances (i.e...numerically induced collapse through violation of the Jeans criterion (Truelove...of the simulation, using a safety factor of J- 4. Nevertheless......

Andrew F. Nelson; Maximilian Ruffert

2013-01-01T23:59:59.000Z

271

Prompt gamma-ray neutron activation analysis methodology for determination of boron from trace to major contents  

Science Journals Connector (OSTI)

Prompt gamma ray neutron activation analysis (PGNAA) is an isotope specific online nuclear analytical technique for non-destructive determination of elements in diverse matrices [1–5...]. Though in principle all ...

R. Acharya

2009-08-01T23:59:59.000Z

272

Vehicle Technologies Office Merit Review 2014: Overview and Progress of the Battery Testing, Design and Analysis Activity  

Energy.gov (U.S. Department of Energy (DOE))

Presentation given by the Department of Energy's Energy Storage area at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about the battery testing, design, and analysis activity.

273

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

274

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

275

Using Dublin Core application profiles to manage diverse metadata developments  

Science Journals Connector (OSTI)

This paper discusses the use of Dublin Core application profiles at the British Library as part of a resource discovery strategy. It shows how they can be used to control the proliferation of metadata formats in digitisation activity and provide interoperability ... Keywords: British library, Dublin Core application profiles, SRU, Z39.50, gateway, interoperability, metadata formats, resource discovery strategy

Robina Clayphan; Bill Oldroyd

2005-09-01T23:59:59.000Z

276

Tank 241-A-101, cores 154 and 156 analytical results for the 45 day report  

SciTech Connect

This document is the 45-day laboratory report for tank 241 -A-101 push mode core segments collected between July II, 1996 and July 25, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-A-101 Push Mode Core Sampling and Analysis Plan (TSAP) (Field, 1996) and the Safety Screening Data Quality Objective (DQO)(Dukelow, et al., 1995). The analytical results are included in the data summary table (Table 1). None of the samples submitted for Total Alpha Activity (AT) or Differential Scanning Calorimetry (DSC) analyses exceeded notification limits as stated in the Safety Screening DQO (Dukelow, et al., 1995). Statistical evaluation on results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. Primary safety screening results and the raw data from thermogravimetric analysis (TGA) and DSC analyses are included in this report.

Steen, F.H.

1996-10-18T23:59:59.000Z

277

Specification and Analysis of the AER/NCA Active Network Protocol Suite in Real-Time Maude  

E-Print Network (OSTI)

Specification and Analysis of the AER/NCA Active Network Protocol Suite in Real-Time Maude Peter-Time Maude tool and the Maude formal methodology to the specification and analysis of the AER/NCA suite-sensitive behavior, the presence of probabilistic algorithms, and the composability of its components, AER/NCA poses

Ã?lveczky, Peter Csaba

278

Analysis of control strategies for thermally activated building systems under demand side management mechanisms  

Science Journals Connector (OSTI)

Abstract Thermally activated buildings systems (TABS) are systems that integrate heating/cooling devices in the building structure, so that the building elements act as thermal storage and have an active role in the energy supply and demand management. Although TABS are well known systems, there are still open questions in their realization, mainly concerning appropriate control strategies which are influenced by the large thermal inertia. The purpose of this paper is to analyze the influence of demand side management control strategies on the performance of a thermally activated building system applied in a commercial building. The goal is to estimate the potential of TABS for load shifting requested by the electricity grid. The analysis is performed by means of a sample case: first the existing TABS control strategy and then the possible implementation of DSM mechanisms are analyzed. In particular three different demand side management mechanisms are evaluated: (i) a peak shaving strategy, (ii) a random request of switching on/off the system and (iii) a night load shifting strategy. The simulation results show high potential of TABS within the DSM framework, since TABS allow load control while scarcely affect thermal comfort.

A. Arteconi; D. Costola; P. Hoes; J.L.M. Hensen

2014-01-01T23:59:59.000Z

279

Core Measure Results  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Core Measure Core Measure Results FY 07 Results FY 08 Results FY 09 Results FY 10 Target FY 10 Customer Perspective: Customer Satisfaction: -Timeliness NM 81 NM NM NM -Quality NM 90 NM NM NM Effective Service Partnership: -Extent of Customer Satisfaction with the responsiveness, etc. NM 87 NM NM NM Internal Business Perspective: Acquisition Excellence: -Extent to which internal quality control systems are effective 86 87 84 87 88 Most Effective Use of Contracting Approaches to Maximize Efficiency and Cost Effectiveness: Use of Electronic Commerce: - % of delivery & purchase orders issued electronically as a % of total simplified actions 70 72 89 99 100 - % of new competitive transactions > $100K conducted through EC 70 72 91 100 95 Performance Based Service Contracts: - PBSCs awarded as a % of eligible new

280

Banded electromagnetic stator core  

DOE Patents (OSTI)

A stator core for an electromagnetic pump includes a plurality of circumferentially adjoining groups of flat laminations disposed about a common centerline axis and collectively defining a central bore and a discontinuous outer perimeter, with adjacent groups diverging radially outwardly to form V-shaped gaps. An annular band surrounds the groups and is predeterminedly tensioned to clamp together the laminations, and has a predetermined flexibility in a radial direction to form substantially straight bridge sections between the adjacent groups.

Fanning, Alan W. (San Jose, CA); Gonzales, Aaron A. (San Jose, CA); Patel, Mahadeo R. (San Jose, CA); Olich, Eugene E. (Aptos, CA)

1996-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Banded electromagnetic stator core  

DOE Patents (OSTI)

A stator core for an electromagnetic pump includes a plurality of circumferentially adjoining groups of flat laminations disposed about a common centerline axis and collectively defining a central bore and a discontinuous outer perimeter, with adjacent groups diverging radially outwardly to form V-shaped gaps. An annular band surrounds the groups and is predeterminedly tensioned to clamp together the laminations, and has a predetermined flexibility in a radial direction to form substantially straight bridge sections between the adjacent groups.

Fanning, Alan W. (San Jose, CA); Gonzales, Aaron A. (San Jose, CA); Patel, Mahadeo R. (San Jose, CA); Olich, Eugene E. (Aptos, CA)

1994-01-01T23:59:59.000Z

282

Variable depth core sampler  

DOE Patents (OSTI)

A variable depth core sampler apparatus comprising a first circular hole saw member, having longitudinal sections that collapses to form a point and capture a sample, and a second circular hole saw member residing inside said first hole saw member to support the longitudinal sections of said first hole saw member and prevent them from collapsing to form a point. The second hole saw member may be raised and lowered inside said first hole saw member.

Bourgeois, Peter M. (Hamburg, NY); Reger, Robert J. (Grand Island, NY)

1996-01-01T23:59:59.000Z

283

Electromagnetic pump stator core  

DOE Patents (OSTI)

A stator core for supporting an electrical coil includes a plurality of groups of circumferentially abutting flat laminations which collectively form a bore and perimeter. A plurality of wedges are interposed between the groups, with each wedge having an inner edge and a thicker outer edge. The wedge outer edges abut adjacent ones of the groups to provide a continuous path around the perimeter. 21 figures.

Fanning, A.W.; Olich, E.E.; Dahl, L.R.

1995-01-17T23:59:59.000Z

284

Banded electromagnetic stator core  

DOE Patents (OSTI)

A stator core for an electromagnetic pump includes a plurality of circumferentially adjoining groups of flat laminations disposed about a common centerline axis and collectively defining a central bore and a discontinuous outer perimeter, with adjacent groups diverging radially outwardly to form V-shaped gaps. An annular band surrounds the groups and is predeterminedly tensioned to clamp together the laminations, and has a predetermined flexibility in a radial direction to form substantially straight bridge sections between the adjacent groups. 5 figs.

Fanning, A.W.; Gonzales, A.A.; Patel, M.R.; Olich, E.E.

1996-06-11T23:59:59.000Z

285

Banded electromagnetic stator core  

DOE Patents (OSTI)

A stator core for an electromagnetic pump includes a plurality of circumferentially adjoining groups of flat laminations disposed about a common centerline axis and collectively defining a central bore and a discontinuous outer perimeter, with adjacent groups diverging radially outwardly to form V-shaped gaps. An annular band surrounds the groups and is predeterminedly tensioned to clamp together the laminations, and has a predetermined flexibility in a radial direction to form substantially straight bridge sections between the adjacent groups. 5 figures.

Fanning, A.W.; Gonzales, A.A.; Patel, M.R.; Olich, E.E.

1994-04-05T23:59:59.000Z

286

Variable depth core sampler  

DOE Patents (OSTI)

A variable depth core sampler apparatus is described comprising a first circular hole saw member, having longitudinal sections that collapses to form a point and capture a sample, and a second circular hole saw member residing inside said first hole saw member to support the longitudinal sections of said first hole saw member and prevent them from collapsing to form a point. The second hole saw member may be raised and lowered inside said first hole saw member. 7 figs.

Bourgeois, P.M.; Reger, R.J.

1996-02-20T23:59:59.000Z

287

Tank 241-TX-118, core 236 analytical results for the final report  

SciTech Connect

This document is the analytical laboratory report for tank 241-TX-118 push mode core segments collected between April 1, 1998 and April 13, 1998. The segments were subsampled and analyzed in accordance with the Tank 241-TX-118 Push Mode Core sampling and Analysis Plan (TSAP) (Benar, 1997), the Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995), the Data Quality Objective to Support Resolution of the Organic Complexant Safety Issue (Organic DQO) (Turner, et al, 1995) and the Historical Model Evaluation Data Requirements (Historical DQO) (Sipson, et al., 1995). The analytical results are included in the data summary table (Table 1). None of the samples submitted for Differential Scanning Calorimetry (DSC) and Total Organic Carbon (TOC) exceeded notification limits as stated in the TSAP (Benar, 1997). One sample exceeded the Total Alpha Activity (AT) analysis notification limit of 38.4{micro}Ci/g (based on a bulk density of 1.6), core 236 segment 1 lower half solids (S98T001524). Appropriate notifications were made. Plutonium 239/240 analysis was requested as a secondary analysis. The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997) and are not considered in this report.

ESCH, R.A.

1998-11-19T23:59:59.000Z

288

E-Print Network 3.0 - active network analysis Sample Search Results  

NLE Websites -- All DOE Office Websites (Extended Search)

activity of coupled networks. The neurons... and activity propagation in coupled neural networks from rat cortical cells grown on a micro-electrode array... for parallel activity...

289

Core–Shell Catalysts in PEMFC Cathode Environments  

Science Journals Connector (OSTI)

A wide variety of core–shell electrocatalysts have been investigated in recent years, showing benefits for the oxygen reduction reaction (ORR) in acid electrolytes. Particularly high values of activity per gram o...

Sarah Ball

2013-01-01T23:59:59.000Z

290

CHARACTERIZATION OF CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY  

SciTech Connect

During the month of September 2008, grout core samples were collected from the Saltstone Disposal Facility, Vault 4, cell E. This grout was placed during processing campaigns in December 2007 from Deliquification, Dissolution and Adjustment Batch 2 salt solution. The 4QCY07 Waste Acceptance Criteria sample collected on 11/16/07 represents the salt solution in the core samples. Core samples were retrieved to initiate the historical database of properties of emplaced Saltstone and to demonstrate the correlation between field collected and laboratory prepared samples. Three samples were collected from three different locations. Samples were collected using a two-inch diameter concrete coring bit. In April 2009, the core samples were removed from the evacuated sample container, inspected, transferred to PVC containers, and backfilled with nitrogen. Samples furthest from the wall were the most intact cylindrically shaped cored samples. The shade of the core samples darkened as the depth of coring increased. Based on the visual inspection, sample 3-3 was selected for all subsequent analysis. The density and porosity of the Vault 4 core sample, 1.90 g/cm{sup 3} and 59.90% respectively, were comparable to values achieved for laboratory prepared samples. X-ray diffraction analysis identified phases consistent with the expectations for hydrated Saltstone. Microscopic analysis revealed morphology features characteristic of cementitious materials with fly ash and calcium silicate hydrate gel. When taken together, the results of the density, porosity, x-ray diffraction analysis and microscopic analysis support the conclusion that the Vault 4, Cell E core sample is representative of the expected waste form.

Cozzi, A.; Duncan, A.

2010-01-28T23:59:59.000Z

291

Photon Activation Analysis Of Light Elements Using 'Non-Gamma' Radiation Spectroscopy - The Instrumental Determination Of Phosphorus  

SciTech Connect

Unlike metal determinations the analysis of light elements (e.g., carbon, oxygen, phosphorus) is frequently problematic, in particular if analysed instrumentally. In photon activation analysis (PAA) the respective activation products do not emit gamma radiation in the most cases. Usually, annihilation quanta counting and subsequent decay curve analysis have been used for determinations of C, N, O, and F. However, radiochemical separation of the respective radioisotopes mostly is indispensable. For several reasons, some of the light elements cannot be analysed following this procedure, e.g. phosphorus. In this contribution the instrumental PAA of phosphorus in organic matrix by activation with bremsstrahlung of an electron linear accelerator and subsequent beta spectroscopy is described. The accuracy of the results was excellent as obtained by analysis of a BCR Reference Material.

Segebade, Christian [Idaho Accelerator Centre (IAC), Idaho State University, 1500 Alvin Ricken Drive, Pocatello, ID 83201 (United States); Goerner, Wolf [Bundesanstalt fuer Materialforschung und -pruefung, unter den Eichen 86, 12205 Berlin (Germany)

2011-06-01T23:59:59.000Z

292

Tank 241-AN-103, cores 166 and 167 analytical results for the final report  

SciTech Connect

This document is the analytical laboratory report for tank 241-AN-103 [Hydrogen Watch Listed] push mode core segments collected between September 13, 1996 and September 23, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-AN-103 Push Mode Core Sampling and Analysis Plan (TSAP), the Safety Screening Data Quality Objective (DQO) and the Flammable Gas Data Quality Objective (DQO). The analytical results are included in the data summary table. The raw data are included in this document. None of the samples submitted for Total Alpha Activity (AT), Total Organic Carbon (TOC) and Plutonium analyses exceeded notification limits as stated in the TSAP. One sample submitted for Differential Scanning Calorimetry (DSC) analysis exceeded the notification limit of 480 Joules/g (dry weight basis) as stated in the Safety Screening DQO. Appropriate notifications were made. Statistical evaluation of results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. Appearance and Sample Handling Attachment 1 is a cross reference to relate the tank farm identification numbers to the 222-S Laboratory LabCore/LIMS sample numbers. The subsamples generated in the laboratory for analyses are identified in these diagrams with their sources shown. The diagrams identifying the core composites are also included. Core 166 Nineteen push mode core segments were removed from tank 241-AN-103 riser 12A between September 13, 1996 and September 17, 1996. Segments were received by the 222-S Laboratory between September 20, 1996 and September 30, 1996. Table 2 summarizes the extrusion information. Selected segments (2, 5 and 14) were sampled using the Retained Gas Sampler (RGS) and extruded by the Process Chemistry and Statistical Analysis Group. Core 167 Eighteen push mode core segments were removed from tank 241-AN-103 riser 21A between September 18, 1996 and September 23, 1996. Tank Farm Operations were unsuccessful in obtaining segment 19 due to the high downforce encountered during sampling. Segments were received by the 222-S Laboratory between September 23, 1996 and September 30, 1996. Table 3 summarizes the extrusion information.

Steen, F.H.

1997-05-15T23:59:59.000Z

293

DOE-HDBK-1163-2003; Integration of Multiple Hazard Analysis Requirements and Activities  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE-HDBK-1163-2003 October 2003 DOE HANDBOOK INTEGRATION OF MULTIPLE HAZARD ANALYSIS REQUIREMENTS AND ACTIVITIES U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS DOE-HDBK-1163-2003 ii This document has been reproduced directly from the best available copy. It is available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-HDBK-1163-2003 iii FOREWORD 1. This Department of Energy (DOE) standard is approved for use by all DOE Components and

294

Multi-Group Transport Methods for High-Resolution Neutron Activation Analysis  

SciTech Connect

The accurate and efficient simulation of coupled neutron-photon problems is necessary for several important radiation detection applications. Examples include the detection of nuclear threats concealed in cargo containers and prompt gamma neutron activation analysis for nondestructive determination of elemental composition of unknown samples. In these applications, high-resolution gamma-ray spectrometers are used to measure the spectrum of the emitted photon flux, which consists of both continuum and characteristic gamma rays with discrete energies. Monte Carlo transport is the most commonly used simulation tool for this type of problem, but computational times for many problems can be prohibitively long. This work explores the use of multi-group deterministic methods for the simulation of coupled neutron-photon problems.

Burns, Kimberly A.; Smith, Leon E.; Gesh, Christopher J.; Shaver, Mark W.

2009-09-24T23:59:59.000Z

295

Core Competency Worksheets for Significant Cybersecurity Roles...  

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

Core Competency Worksheets for Significant Cybersecurity Roles Core Competency Worksheets for Significant Cybersecurity Roles The OCIO has developed core competency worksheets for...

296

Determination of boron in aluminum and aluminum-magnesium alloy by charged particle activation analysis  

SciTech Connect

Charge particle activation analysis is applied to the determination of boron in aluminum and aluminum-magnesium alloy. The /sup 10/B(p,..cap alpha..)/sup 7/Be, the /sup 10/B(d,..cap alpha..n)/sup 7/Be, and the /sup 10/B(d,n)/sup 11/C reactions are used. Proton activation allows an instrumental determination. When the /sup 10/B(d,..cap alpha..n)/sup 7/Be reaction is used, beryllium-7 is separated from the matrix by liquid-liquid extraction; beryllium acetylacetonate is extracted with carbon tetrachloride after complexation of other metal ions with ethylenediaminetetraacetic acid. After back extraction beryllium is precipitated as beryllium hydroxide and heated to beryllium oxide. When the /sup 10/B(d,n)/sup 11/C reaction is used, carbon-11 is separated as carbon dioxide by dissolution of the sample in a mixture of sulfuric acid, phosphoric acid, water, and potassium dichromate. The chemical yield of both separation methods was determined. The results obtained have a relative standard deviation of 5-9% at the 1-33 ..mu..g/g concentration. The different nuclear reactions yield results that are in good mutual agreement and also agree satisfactorily with those of nonnuclear analytical methods.

Mortier, R.; Vandecasteele, C.; Strijckmans, K.; Hoste, J.

1984-10-01T23:59:59.000Z

297

Active charge/passive discharge solar heating systems: thermal analysis and performance comparisons  

SciTech Connect

This study analyzes the performance of active charge/passive discharge solar space heating systems. This type of system combines liquid-cooled solar collector panels with a massive integral storage component that passively heats the building interior by radiation and free convection. The TRNSYS simulation program is used to evaluate system performance and to provide input for the development of a simplified analysis method. This method, which provides monthly calculations of delivered solar energy, is based on Klein's Phi-bar procedure and data from hourly TRNSYS simulations. The method can be applied to systems using a floor slab, a structural wall, or a water tank as the storage component. Important design parameters include collector area and orientation, building heat loss, collector and heat-exchanger efficiencies, storage capacity, and storage-to-room coupling. Performance simulation results are used for comparisons with active and passive solar designs. Economic comparisons are based on these data and additional system features, such as cooling augmentation and integration of heating components with structural members.

Swisher, J.

1981-06-01T23:59:59.000Z

298

Development of a core design optimization tool and analysis in support of the planned LEU conversion of the MIT Research Reactor (MITR-II) ; Development of a core design optimization tool and analysis in support of the planned low enriched uranium conversion of the MIT Research Reactor (MITR-II) .  

E-Print Network (OSTI)

??The MIT Research Reactor (MITR-II) is currently undergoing analysis for the planned conversion from high enriched uranium (HEU) to low enriched uranium (LEU), as part… (more)

Connaway, Heather M. (Heather Moira)

2012-01-01T23:59:59.000Z

299

2001 BTS Core Databook  

Buildings Energy Data Book (EERE)

1 BTS CORE 1 BTS CORE DATABOOK OFFICE OF ENERGY EFFICIENCY AND RENEWABLE ENERGY U.S. DEPARTMENT OF ENERGY This version is dated: November 30, 2001 REVISED data tables on the web site that have been changed since November 30, 2001 include tables: 5.6.7 5.6.8 5.6.9 5.10.8 5.10.9 5.10.10 5.10.11 5.10.12 5.10.13 5.10.14 5.10.15 5.10.16 5.10.17 5.10.18 NEW data tables on the web site that have been added since July 13, 2001 include tables: 5.6.14 5.9.7 5.9.8 5.9.9 REVISED data tables on the web site that have been changed since July 13, 2001 include tables: 4.1.1 4.1.2 4.1.4 4.1.5 4.2.1 4.2.2 4.2.3 4.2.4 4.2.5 4.2.9 4.3.1 4.3.2 4.3.3 4.3.4 4.5.1 4.5.2 4.5.3 5.1.2 5.3.1 5.8.1 5.10.1 6.2.4 7.1.8 7.3.3 These tables are not included in this version of the 2001 BTS Core Databook. DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER

300

Core-tube data logger  

SciTech Connect

Wireline core drilling, increasingly used for geothermal exploration, employs a core-tube to capture a rock core sample during drilling. Three types of core-tube data loggers (CTDL) have been built and tested to date by Sandia national Laboratories. They are: (1) temperature-only logger, (2) temperature/inclinometer logger and (3) heat-shielded temperature/inclinometer logger. All were tested during core drilling operations using standard wireline diamond core drilling equipment. While these tools are designed for core-tube deployment, the tool lends itself to be adapted to other drilling modes and equipment. Topics covered in this paper include: (1) description on how the CTDLs are implemented, (2) the components of the system, (3) the type of data one can expect from this type of tool, (4) lessons learned, (5) comparison to its counterpart and (6) future work.

Henfling, J.A.; Normann, R.A.; Knudsen, S.; Drumheller, D.

1997-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

A Visual Analytics Approach to Structured Data Analysis to Enhance Nonproliferation and Arms Control Verification Activities  

SciTech Connect

Analysis activities for Nonproliferation and Arms Control verification require the use of many types of data. Tabular structured data, such as Excel spreadsheets and relational databases, have traditionally been used for data mining activities, where specific queries are issued against data to look for matching results. The application of visual analytics tools to structured data enables further exploration of datasets to promote discovery of previously unknown results. This paper discusses the application of a specific visual analytics tool to datasets related to the field of Arms Control and Nonproliferation to promote the use of visual analytics more broadly in this domain. Visual analytics focuses on analytical reasoning facilitated by interactive visual interfaces (Wong and Thomas 2004). It promotes exploratory analysis of data, and complements data mining technologies where known patterns can be mined for. Also with a human in the loop, they can bring in domain knowledge and subject matter expertise. Visual analytics has not widely been applied to this domain. In this paper, we will focus on one type of data: structured data, and show the results of applying a specific visual analytics tool to answer questions in the Arms Control and Nonproliferation domain. We chose to use the T.Rex tool, a visual analytics tool developed at PNNL, which uses a variety of visual exploration patterns to discover relationships in structured datasets, including a facet view, graph view, matrix view, and timeline view. The facet view enables discovery of relationships between categorical information, such as countries and locations. The graph tool visualizes node-link relationship patterns, such as the flow of materials being shipped between parties. The matrix visualization shows highly correlated categories of information. The timeline view shows temporal patterns in data. In this paper, we will use T.Rex with two different datasets to demonstrate how interactive exploration of the data can aid an analyst with arms control and nonproliferation verification activities. Using a dataset from PIERS (PIERS 2014), we will show how container shipment imports and exports can aid an analyst in understanding the shipping patterns between two countries. We will also use T.Rex to examine a collection of research publications from the IAEA International Nuclear Information System (IAEA 2014) to discover collaborations of concern. We hope this paper will encourage the use of visual analytics structured data analytics in the field of nonproliferation and arms control verification. Our paper outlines some of the challenges that exist before broad adoption of these kinds of tools can occur and offers next steps to overcome these challenges.

Gillen, David S.

2014-08-07T23:59:59.000Z

302

Measurement of chromium VI and chromium III in stainless steel welding fumes with electron spectroscopy for chemical analysis and neutron activation analysis  

E-Print Network (OSTI)

Measurement of Chromium YI and Chromium III in Stainless Steel Welding Fumes with Electron Spectroscopy for Chemical Analysis and Neutron Activation Analysis (December 1977) Gerald Myron Lautner; B. S. , Louisiana State University; Co-Chairmen of Advisory... steel plates sized 15. 2 by 26. 7 by 0. 64 centimeters (6. 0 by 10. 5 by 0. 25 inches). The manufacturer lists the following typical analysis for Type 304 stainless plate; C ? 0. 08 percent; Mn - 2. 00 percent; Si - 1 00 percent; Cr = 18. 00 - 20. 00...

Lautner, Gerald Myron

1977-01-01T23:59:59.000Z

303

Soft-core Processor Customization using the Design of Experiments David Sheldon, Frank Vahid*, Stefano Lonardi  

E-Print Network (OSTI)

by the analysis in turn drives a soft-core tuning heuristic. We show that using DoE to sort the parameters by 40-45% by using predictive tuning methods already built into a DoE tool. 1. Introduction Soft-coreSoft-core Processor Customization using the Design of Experiments Paradigm David Sheldon, Frank

Lonardi, Stefano

304

Analysis of the interaction between air transportation and economic activity : a worldwide perspective  

E-Print Network (OSTI)

Air transportation usage and economic activity are interdependent. Air transportation provides employment and enables certain economic activities which are dependent on the availability of air transportation services. The ...

Ishutkina, Mariya A. (Mariya Aleksandrovna)

2009-01-01T23:59:59.000Z

305

Dynamic core length in saturated core fault current limiters  

Science Journals Connector (OSTI)

A saturated core fault current limiter (SCFCL) is a non-linear core-reactor where the core is saturated by an external superconducting DC bias source to achieve a low core permeability at nominal AC currents. Fault current levels in the AC coils de-saturate the core and transform it to a higher permeability state, hence limiting the fault current. In this work we describe the transition between saturated and de-saturated states in three SCFCL configurations. The 'effective core length', Leff, of the SCFCL, defined as the length of the de-saturated AC core limb, is introduced for exploring this transition as a function of the current, I, in the AC coil. Practically, Leff allows one to see the SCFCL as an inductor with a variable core length, allowing calculations of the impedance of the SCFCL over the whole range of operating currents. The Leff(I) curve is further used to calculate the dynamics of the demagnetization factor in a SCFCL. We show that the strong change in the magnetic induction of a SCFCL at high current is the result of both increasing the effective core length and decreasing the demagnetization factor. The method and results presented here serve as an important tool for comparing between various SCFCL concepts not only by comparing their impedance values at the extreme fault and nominal current conditions but also by providing an insight into the full de-saturation process.

Y Nikulshin; Y Wolfus; A Friedman; Y Yeshurun

2013-01-01T23:59:59.000Z

306

3D Continuum radiative transfer in complex dust configurations around young stellar objects and active nuclei II. 3D Structure of the dense molecular cloud core Rho Oph D  

E-Print Network (OSTI)

Constraints on the density and thermal 3D structure of the dense molecular cloud core Rho Oph D are derived from a detailed 3D radiative transfer modeling. Two ISOCAM images at 7 and 15 micron are fitted simultaneously by representing the dust distribution in the core with a series of 3D Gaussian density profiles. Size, total density, and position of the Gaussians are optimized by simulated annealing to obtain a 2D column density map. The projected core density has a complex elongated pattern with two peaks. We propose a new method to calculate an approximate temperature in an externally illuminated complex 3D structure from a mean optical depth. This T(tau)-method is applied to a 1.3 mm map obtained with the IRAM 30m telescope to find the approximate 3D density and temperature distribution of the core Rho Oph D. The spatial 3D distribution deviates strongly from spherical symmetry. The elongated structure is in general agreement with recent gravo-turbulent collapse calculations for molecular clouds. We discuss possible ambiguities of the background determination procedure, errors of the maps, the accuracy of the T(tau)-method, and the influence of the assumed dust particle sizes and properties.

J. Steinacker; A. Bacmann; Th. Henning; R. Klessen; M. Stickel

2004-10-26T23:59:59.000Z

307

activities  

NLE Websites -- All DOE Office Websites (Extended Search)

Detecting Things We Cannot See: Learning the Concepts of Control and Detecting Things We Cannot See: Learning the Concepts of Control and Variable in an Experiment Submitted by Anita Brook-Dupree, 1996 TRAC teacher at Fermilab, Teacher, Alternative Middle Years School, Philadelphia, PA. Particle physicists at Fermilab in Batavia, Illinois are faced with the problem of detecting the presence of sub-atomic particles they cannot see. During my summer as a TRAC teacher at Fermilab, I tried to think of ways to teach middle school students about things we cannot see. I want to thank my nine-year-old daughter Gia for the idea for the following activity. I was lamenting that I could not come up with ideas of how to relate the work of Fermilab scientists to anything that my students would understand. Then I was reminded by my daughter, that when I brought her to school on the

308

Analysis of the Interaction Between Air Transportation and Economic Activity: A Worldwide Perspective  

E-Print Network (OSTI)

Air transportation usage and economic activity are interdependent. Air transportation provides employment

Hansman, R. John

2009-03-30T23:59:59.000Z

309

Analysis of the Interaction Between Air Transportation and Economic Activity: A Worldwide Perspective  

E-Print Network (OSTI)

Air transportation usage and economic activity are interdependent. Air transportation provides employment

Ishutkina, Mariya A.

2011-10-14T23:59:59.000Z

310

FY2005 - Annual Progress Report for Advanced Vehicle Technology Analysis and Evaluation Activities  

NLE Websites -- All DOE Office Websites (Extended Search)

AdvAnced vehicle AdvAnced vehicle Technology AnAlysis And evAluATion AcTiviTies Less dependence on foreign oil, and eventual transition to an emissions-free, petroleum-free vehicle F r e e d o m C A r A n d V e h i C l e T e C h n o l o g i e s P r o g r A m Acknowledgement We would like to express our sincere appreciation to QSS Group, Inc., Oak Ridge National Laboratory, and Argonne National Laboratory for their technical and artistic contributions in preparing and publishing this report. In addition, we would like to thank all the participants for their contributions to the pro- grams and all the authors who prepared the project abstracts that comprise this report. This document highlights work sponsored by agencies of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any

311

Research trends in neutron activation analysis in nuclear science and technology: a global perspective  

Science Journals Connector (OSTI)

This paper quantitatively analyses the growth and development of research in Neutron Activation Analysis (NAA) in terms of publications. As per the International Nuclear Information System (INIS) database during 1993-2007, a total of 6491 publications were published. The highest number of papers in a year (615) was published in 2004. The average number of publications published per year was 432.73. Japan topped the list with 605 publications followed by the USA with 468, Brazil with 449, China with 442, the Russian Federation with 324 and India with 316. The authorship and collaboration trend is towards multi-authored papers. Researchers in Japan, Brazil and China are more inclined to work in larger groups. The highly productive institutions were Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, Brazil with 281 publications; Bhabha Atomic Research Centre, Mumbai, India with 257; Institute of High Energy Physics, Academia Sinica, Beijing, China with 162; and Japan Atomic Energy Agency, Tokai, Ibaraki, Japan with 140. The journals most preferred by the scientists for the publication of papers are the Journal of Radioanalytical and Nuclear Chemistry with 1204 papers, followed by Applied Radiation and Isotopes with 116 papers, and Nuclear Instruments and Methods in Physics Research-A with 84 papers.

Anil Sagar; B.S. Kademani; Vijai Kumar

2009-01-01T23:59:59.000Z

312

Cold neutron prompt gamma activation analysis, a non-destructive technique for hydrogen level assessment in zirconium alloys  

E-Print Network (OSTI)

embrittlement by decreasing overall corrosion and/or by decreasing the amount of hydrogen ingress for a givenCold neutron prompt gamma activation analysis, a non-destructive technique for hydrogen level to quantitatively assess hydrogen concentration in zirconium alloys. The technique, called Cold Neutron Prompt Gamma

Motta, Arthur T.

313

Generating Unstructured Nuclear Reactor Core Meshes in Parallel  

Science Journals Connector (OSTI)

Abstract Recent advances in supercomputers and parallel solver techniques have enabled users to run large simulations problems using millions of processors. Techniques for multiphysics nuclear reactor core simulations are under active development in several countries. Most of these techniques require large unstructured meshes that can be hard to generate in a standalone desktop computers because of high memory requirements, limited processing power, and other complexities. We have previously reported on a hierarchical lattice-based approach for generating reactor core meshes. Here, we describe efforts to exploit coarse-grained parallelism during reactor assembly and reactor core mesh generation processes. We highlight several reactor core examples including a very high temperature reactor, a full-core model of the Korean MONJU reactor, a ¼ pressurized water reactor core, the fast reactor Experimental Breeder Reactor-II core with a XX09 assembly, and an advanced breeder test reactor core. The times required to generate large mesh models, along with speedups obtained from running these problems in parallel, are reported. A graphical user interface to the tools described here has also been developed.

Rajeev Jain; Timothy J. Tautges

2014-01-01T23:59:59.000Z

314

Preliminary engineering design of sodium-cooled CANDLE core  

Science Journals Connector (OSTI)

The CANDLE burning process is characterized by the autonomous shifting of burning region with constant reactivity and constant spacial power distribution. Evaluations of such critical burning process by using widely used neutron diffusion and burning codes under some realistic engineering constraints are valuable to confirm the technical feasibility of the CANDLE concept and to put the idea into concrete core design. In the first part of this paper it is discussed that whether the sustainable and stable CANDLE burning process can be reproduced even by using conventional core analysis tools such as SLAROM and CITATION-FBR. As a result it is certainly possible to demonstrate it if the proper core configuration and initial fuel composition required as CANDLE core are applied to the analysis. In the latter part an example of a concrete image of sodium cooled metal fuel 2000MWt rating CANDLE core has been presented by assuming an emerging inevitable technology of recladding. The core satisfies engineering design criteria including cladding temperature pressure drop linear heat rate and cumulative damage fraction (CDF) of cladding fast neutron fluence and sodium void reactivity which are defined in the Japanese FBR design project. It can be concluded that it is feasible to design CADLE core by using conventional codes while satisfying some realistic engineering design constraints assuming that recladding at certain time interval is technically feasible.

2012-01-01T23:59:59.000Z

315

Experimental studies of 6000-litre LMFBR cores at ZPPR  

SciTech Connect

The ZPPR-10 program has provided basic physics data for large two-zone conventional LMFBR cores. The early assemblies, 10A and 10B, had core volumes of 4600 litres. The assemblies reported here have core volumes of 6000 litres and represent 900 MW(e) reactors. The measurements emphasized the spatial variation of reaction rate distribution and control rod worths for configurations having 19 and 31 control rod positions. Two configurations with rods inserted were made critical by fuel additions in the later phases. A number of sodium void reactivities were measured. Analysis was made with ENDF/B-IV data.

Carpenter, S.G.; Collins, P.J.; Beck, C.L.; Gasidlo, J.M.; Goin, R.W.; Kaiser, R.E.; Maddison, D.W.; Olsen, D.N.

1980-01-01T23:59:59.000Z

316

Microsoft Word - IronCore  

NLE Websites -- All DOE Office Websites (Extended Search)

November/December 2013 November/December 2013 Percolation Explains How Earth's Iron Core Formed The formation of Earth's metallic core, which makes up a third of our planet's mass, represents the most significant differentiation event in Earth's history. Earth's present layered structure with a metallic core and an overlying silicate mantle would have required mechanisms to separate iron alloy from a silicate phase. Percolation of liquid iron alloy moving through a solid silicate matrix (much as water percolates through porous rock, or even coffee grinds) has been proposed as a possible model for core formation (Figure 1). Many previous experimental results have ruled out percolation as a major core formation mechanism for Earth at the relatively lower pressure conditions in the upper mantle, but

317

Neutron Scattering Studies and Modeling of the HMG 14 Core Nucleosome Complex  

Science Journals Connector (OSTI)

There is considerable evidence relating the nonhistone proteins HMG 14 and HMG 17 with the structure of active or protentially active chromatin. In this study, bulk nucleosome core particles prepared from chicken...

E. C. Uberbacher; D. E. Olins; G. J. Bunick; W. C. Koehler

1984-01-01T23:59:59.000Z

318

Screening potato genotypes for antioxidant activity, identification of the responsible compounds, and differentiating Russet Norkotah strains using AFLP and microsatellite marker analysis  

E-Print Network (OSTI)

SCREENING POTATO GENOTYPES FOR ANTIOXIDANT ACTIVITY, IDENTIFICATION OF THE RESPONSIBLE COMPOUNDS, AND DIFFERENTIATING RUSSET NORKOTAH STRAINS USING AFLP AND MICROSATELLITE MARKER ANALYSIS A Dissertation by ANNA LOUISE HALE... FOR ANTIOXIDANT ACTIVITY, IDENTIFICATION OF THE RESPONSIBLE COMPOUNDS, AND DIFFERENTIATING RUSSET NORKOTAH STRAINS USING AFLP AND MICROSATELLITE MARKER ANALYSIS A Dissertation by ANNA LOUISE HALE Submitted to Texas A&M University in partial fulfillment...

Hale, Anna Louise

2005-02-17T23:59:59.000Z

319

India-NREL Energy Activities | Open Energy Information  

Open Energy Info (EERE)

NREL Cooperation NREL Cooperation Name India-NREL Cooperation Agency/Company /Organization National Renewable Energy Laboratory Sector Energy Focus Area Energy Efficiency, Buildings, Solar, Wind Topics Market analysis, Policies/deployment programs, Background analysis Country India Southern Asia References National Renewable Energy Laboratory, EERE Supported International Activities FY 2009 Annual Operating Plan (August 25, 2009) Abstract The NREL tasks for buildings in India began in FY08 under the Building and Efficiency Task Force of the Asia Pacific Partnership (APP). NREL's efforts under the APP build on core DOE/NREL capabilities in building energy simulation and focus on key collaborative activities in the commercial building sector in India. India Buildings Activities

320

E-Print Network 3.0 - activation analysis determinacao Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

Modelos Hierarquicos Generalizados sob Planos Amostrais Summary: :www.visgraf.impa.brProjectsvirtualsetpage04.html 2.17 - http:www-cui.darmstadt.gmd.devisitActivities...

Note: This page contains sample records for the topic "activity core analysis" 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

E-Print Network 3.0 - activation analysis body Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

. Such findings provide support for an active role of body representations in the processes underlying the RHI... 1 Body mereology F. de Vignemont, M. Tsakiris and P....

322

E-Print Network 3.0 - activation analysis estudo Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

Dinmica Espacial SER-410-3 Processamento... , A Microwave remote sensing: active and passive. Boston, MA: Artech House, 1981. v.13. Warner, T.A.; Nellis, M... .; Collins,...

323

E-Print Network 3.0 - activation pixe analysis Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

Aged Rubber Material : On The Additives Behaviour Versus Aging Time Summary: PIXE, Micro-PIXE and RBS Analysis of Thermal Aged Rubber Material : On The Additives...

324

Vehicle Technologies Office Merit Review 2014: Impact Analysis: VTO Baseline and Scenario (BaSce) Activities  

Energy.gov (U.S. Department of Energy (DOE))

Presentation given by Argonne National Laboratory at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about impact analysis...

325

Vehicle Technologies Office Merit Review 2014: Cell Analysis, Modeling, and Prototyping (CAMP) Facility Research Activities  

Energy.gov (U.S. Department of Energy (DOE))

Presentation given by Argonne National Laboratory at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about cell analysis,...

326

E-Print Network 3.0 - activation analysis caracterizacion Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

Sciences 4 ENVIRONMENTAL INFORMATION SYSTEM FOR ANALYSIS AND FORECAST OF AIR POLLUTION (APPLICATION TO SANTIAGO DE CHILE) Summary: ENVIRONMENTAL INFORMATION SYSTEM FOR...

327

GMAD: Graph-based Malware Activity Detection by DNS traffic analysis  

Science Journals Connector (OSTI)

Malicious activities on the Internet are one of the most dangerous threats to Internet users and organizations. Malicious software controlled remotely is addressed as one of the most critical methods for executing the malicious activities. Since blocking ... Keywords: Botnet, DNS, Graph clustering, Malware domain name, Sequential correlation

Jehyun Lee, Heejo Lee

2014-08-01T23:59:59.000Z

328

Possible AGN Shock Heating in the Cool Core Galaxy Cluster Abell 478  

E-Print Network (OSTI)

We present a detailed X-ray study of the intracluster medium (ICM) of the nearby, cool-core galaxy cluster Abell 478, with Chandra and XMM observations. Using a wavelet smoothing hardness analysis, we derive detailed temperature maps of A478, revealing a surprising amount of temperature structure. The broad band Chandra spectral fits yield temperatures which are significantly hotter than those from XMM, but the Fe ionization temperature shows good agreement. We show that the temperature discrepancy is slightly reduced when comparing spectra from regions selected to enclose nearly isothermal gas. However, by simulating multi-temperature spectra and fitting them with a single temperature model, we find no significant difference between Chandra and XMM, indicating that non-isothermality cannot fully explain the discrepancy. We have discovered 4 hot spots located between 30--50 kpc from the cluster center, where the gas temperature is roughly a factor of 2 higher than in the surrounding material. We estimate the combined excess thermal energy present in these hot spots to be (3+/-1)x10^59 erg. The location of and amount of excess energy present in the hot spots are suggestive of a common origin within the cluster core, which hosts an active galactic nucleus. This cluster also possesses a pair of X-ray cavities coincident with weak radio lobes, as reported in a previous analysis, with an associated energy <10% of the thermal excess in the hot spots. The presence of these hot spots could indicate strong-shock heating of the ICM from the central radio source -- one of the first such detections in a cool core cluster. We also probe the mass distribution in the core and find it to be characterized by a logarithmic slope of -0.35+/-0.22, which is significantly flatter than an NFW cusp of -1. (abridged)

Alastair J. R. Sanderson; Alexis Finoguenov; Joseph J. Mohr

2004-12-14T23:59:59.000Z

329

A SYSTEMATIC SURVEY OF HIGH-TEMPERATURE EMISSION IN SOLAR ACTIVE REGIONS  

SciTech Connect

The recent analysis of observations taken with the EUV Imaging Spectrometer and X-Ray Telescope instruments on Hinode suggests that well-constrained measurements of the temperature distribution in solar active regions can finally be made. Such measurements are critical for constraining theories of coronal heating. Past analysis, however, has suffered from limited sample sizes and large uncertainties at temperatures between 5 and 10 MK. Here we present a systematic study of the differential emission measure distribution in 15 active region cores. We focus on measurements in the 'inter-moss' region, that is, the region between the loop footpoints, where the observations are easier to interpret. To reduce the uncertainties at the highest temperatures we present a new method for isolating the Fe XVIII emission in the AIA/SDO 94 A channel. The resulting differential emission measure distributions confirm our previous analysis showing that the temperature distribution in an active region core is often strongly peaked near 4 MK. We characterize the properties of the emission distribution as a function of the total unsigned magnetic flux. We find that the amount of high-temperature emission in the active region core is correlated with the total unsigned magnetic flux, while the emission at lower temperatures, in contrast, is inversely related. These results provide compelling evidence that high-temperature active region emission is often close to equilibrium, although weaker active regions may be dominated by evolving million degree loops in the core.

Warren, Harry P. [Space Science Division, Naval Research Laboratory, Washington, DC 20375 (United States); Winebarger, Amy R. [NASA Marshall Space Flight Center, VP 62, Huntsville, AL 35812 (United States); Brooks, David H. [College of Science, George Mason University, 4400 University Drive, Fairfax, VA 22030 (United States)

2012-11-10T23:59:59.000Z

330

Alkali solution treatment on sandstone cores  

E-Print Network (OSTI)

was used for filtering the solution before the injection into the core. Hassler-t e Core Holder A stainless steel core holder was used to hold the core for treatment with the solutions. The core sample was positioned in the center of the core holder... and heat the water in the flask. Electric Heatin Ta e A silicone rubber embedded flexible heating tape was used to wrap the core holder to heat the core sample to the desired temperature. The maximum 0 continuous operating temperature of the tape...

Lee, Suk Jin

2012-06-07T23:59:59.000Z

331

Predicting the unpredictable: critical analysis and practical implications of predictive anticipatory activity  

E-Print Network (OSTI)

OF THE EVIDENCE FOR PAA p-Hacking One QRP that appears to beThis activity, dubbed“p-hacking”because it involves cuttingques- tion is whether p-hacking can explain the signi?cant

Mossbridge, Julia A; Tressoldi, Patrizio; Utts, Jessica; Ives, John A; Radin, Dean; Jonas, Wayne B

2014-01-01T23:59:59.000Z

332

Design and analysis of active fluid-and-cellular solid composites for controllable stiffness robotic elements  

E-Print Network (OSTI)

The purpose of this thesis is to investigate the use of a new class of materials for realizing soft robots. Specifically, meso-scale composites--composed of cellular solids impregnated with active fluids-were be designed ...

Cheng, Nadia G. (Nadia Gen San)

2009-01-01T23:59:59.000Z

333

E-Print Network 3.0 - activation analysis principles Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

4 5 1 emerging Principles: The U of R Campus will 12;Actively lead... May 11, 2010 Open House Presentation 12;where we re at consolidated outcomes: vision ... Source: Argerami,...

334

E-Print Network 3.0 - activation dose analysis Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

65 AJR:176, February 2001 289 Estimated Risks of Radiation- Summary: dose at CT in pediatric patients. Radiology 1997;203:417-422 22. Olerud HM. Analysis of factors... ....

335

E-Print Network 3.0 - activation analysis avaliacao Sample Search...  

NLE Websites -- All DOE Office Websites (Extended Search)

1979. L... .J. Newman. Complex Analysis, 2nd ed., Springer-Verlag, 1996 L.T. Magalhaes. Analise Complexa em Uma Vari... avel e Aplicacoes, IST, Fevereiro de 2004. ...

336

Tank 241-T-203, core 190 analytical results for the final report  

SciTech Connect

This document is the analytical laboratory report for tank 241-T-203 push mode core segments collected on April 17, 1997 and April 18, 1997. The segments were subsainpled and analyzed in accordance with the Tank 241-T-203 Push Mode Core Sampling andanalysis Plan (TSAP) (Schreiber, 1997a), the Safety Screening Data Quality Objective (DQO)(Dukelow, et al., 1995) and Leffer oflnstructionfor Core Sample Analysis of Tanks 241-T-201, 241-T-202, 241-T-203, and 241-T-204 (LOI)(Hall, 1997). The analytical results are included in the data summary report (Table 1). None of the samples submitted for Differential Scanning Calorimetry (DSC), Total Alpha Activity (AT) and Total Organic Carbon (TOC) exceeded notification limits as stated in the TSAP (Schreiber, 1997a). The statistical results of the 95% confidence interval on the mean calculations are provided by the Tank Waste Remediation Systems (TWRS) Technical Basis Group in accordance with the Memorandum of Understanding (Schreiber, 1997b) and not considered in this report.

Steen, F.H.

1997-08-05T23:59:59.000Z

337

Generation of spatial weighting functions for ex-core detectors by adjoint transport calculation  

SciTech Connect

The response rate of ex-core detectors depends on the power level, power distribution, and reactor configuration. For the analysis of the detector response rate for various core power distributions, it is important to generate spatial weighting functions that are insensitive to small changes in the core power distribution and determined by the reactor configuration. Two-dimensional discrete ordinates adjoint transport calculations are used to calculate the core axial weighting functions. The effects of the reactors operating conditions on the core axial weighting functions are analyzed, and it is found that the soluble boron concentration in the reactor coolant has little effect while the core power level affects the core axial weighting functions significantly. A comparison between the results of the adjoint and forward transport calculations shows an excellent agreement. However, the adjoint transport method provides more detailed data and requires less computing time than forward transport method.

Ahn, Joon Gi; Cho, Nam Zin (Korea Advanced Inst. of Science and Tech., Taejon (Korea, Republic of). Dept. of Nuclear Engineering); Kuh, Jung Eui (Korea Atomic Energy Research Inst., Taejon (Korea, Republic of). Safety Analysis Division)

1993-07-01T23:59:59.000Z

338

A MODEL FOR TIME-AND BUDGET-CONSTRAINED ACTIVITY DEMAND ANALYSIS  

E-Print Network (OSTI)

the derivation of a system of demands for activity participation by applying microeconomic theory in a time-price to be of discrete choices (e.g., Train et al. 1987); many models of jointly estimated demand responses lack-time demand elasticities, values of time, and other behavioral properties. METHODOLOGY Microeconomic

Kockelman, Kara M.

339

Activation analysis of concrete and graphite in the experimental reactor RUS  

Science Journals Connector (OSTI)

......nature of the radiological waste generated during decommissioning...flow going to different waste repositories may substantially...of decommissioning and storage. The present work has...developed for determining the long-term induced activity in the...mass flows going to the waste repositories and hence......

M. Cometto; D. Ridikas; M. C. Aubert; F. Damoy; D. Ancius

2005-12-20T23:59:59.000Z

340

Fusion-neutron-yield, activation measurements at the Z accelerator: Design, analysis, and sensitivity  

SciTech Connect

We present a general methodology to determine the diagnostic sensitivity that is directly applicable to neutron-activation diagnostics fielded on a wide variety of neutron-producing experiments, which include inertial-confinement fusion (ICF), dense plasma focus, and ion beam-driven concepts. This approach includes a combination of several effects: (1) non-isotropic neutron emission; (2) the 1/r{sup 2} decrease in neutron fluence in the activation material; (3) the spatially distributed neutron scattering, attenuation, and energy losses due to the fielding environment and activation material itself; and (4) temporally varying neutron emission. As an example, we describe the copper-activation diagnostic used to measure secondary deuterium-tritium fusion-neutron yields on ICF experiments conducted on the pulsed-power Z Accelerator at Sandia National Laboratories. Using this methodology along with results from absolute calibrations and Monte Carlo simulations, we find that for the diagnostic configuration on Z, the diagnostic sensitivity is 0.037% ± 17% counts/neutron per cm{sup 2} and is ? 40% less sensitive than it would be in an ideal geometry due to neutron attenuation, scattering, and energy-loss effects.

Hahn, K. D., E-mail: kdhahn@sandia.gov; Ruiz, C. L.; Fehl, D. L.; Chandler, G. A.; Knapp, P. F.; Smelser, R. M.; Torres, J. A. [Sandia National Laboratories, Diagnostics and Target Physics, Albuquerque, New Mexico 87123 (United States)] [Sandia National Laboratories, Diagnostics and Target Physics, Albuquerque, New Mexico 87123 (United States); Cooper, G. W.; Nelson, A. J. [Department of Chemical and Nuclear Engineering, University of New Mexico, Albuquerque, New Mexico 87131 (United States)] [Department of Chemical and Nuclear Engineering, University of New Mexico, Albuquerque, New Mexico 87131 (United States); Leeper, R. J. [Los Alamos National Laboratories, Plasma Physics Group, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratories, Plasma Physics Group, Los Alamos, New Mexico 87545 (United States)

2014-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Coupling High-Energy Radiography And Photon Activation Analysis (PAA) To Optimize The Characterization Of Nuclear Waste Packages  

SciTech Connect

Radiological characterization of nuclear waste packages is an industrial issue in order to select the best mode of storage. The alpha-activity, mainly due to the presence of actinides ({sup 235}U, {sup 238}U, {sup 239}Pu,...) inside the package, is one of the most important parameter to assess during the characterization. Photon Activation Analysis (PAA) is a non-destructive active method (NDA method) based on the photofission process and on the detection of delayed particles (neutrons and gammas). This technique is well-adapted to the characterization of large concrete waste packages. However, PAA methods often require a simulation step which is necessary to analyze experimental results and to quantify the global mass of actinides. The weak point of this approach is that characteristics of the package are often not well-known, these latter having a huge impact on the final simulation result. High-energy radiography, based on the use of a linear electron accelerator (LINAC), allows to visualize the content of the package and is also a performing way to tune simulation models and to optimize the characterization process by PAA. In this article, we present high-energy radiography results obtained for two different large concrete waste packages in the SAPHIR facility (Active Photon and Irradiation System). This facility is dedicated to PAA study and development and setup for a decade in CEA Saclay. We also discuss possibilities offered by the coupling between high-energy radiography and PAA techniques.

Carrel, F.; Agelou, M.; Gmar, M.; Laine, F.; Lamotte, T.; Lazaro, D.; Poumarede, B.; Rattoni, B. [CEA, LIST, F-91191, Gif-sur-Yvette (France)

2009-12-02T23:59:59.000Z

342

Donaldson Active Regeneration PM System  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Modeling - FEA * Failure Mode Analysis & Life Prediction - Reliability Analysis * FMEA, Fault Tree Analysis, Risk Assessment, etc. Active System Durability & Reliability...

343

Numerical implementation of shape memory alloy (SMA) constitutive response and structural analysis of active composites  

E-Print Network (OSTI)

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . B. 3. Stresses B. 4. Incremental Constitutive Relationship . B. 5. Principle of Virtual Work B. 6. Finite Element Formulation of Equilibrium Equations . . . . B. 7. Final Equations . 116 116 117 117 118 120 122 VITA 126 LIST OF TABLES... of Active Composites. (December 1995) Muhammad Abu Bakar Siddiq Qidwai, B. S. , Middle East Technical University Chair of Advisory Committee: Dr. Dimittis C. Lagoudas Numerical implementation of the thermomechanical constitutive response of shape memory...

Qidwai, Muhammad Abu Bakar Siddiq

2012-06-07T23:59:59.000Z

344

Large core fiber optic cleaver  

DOE Patents (OSTI)

The present invention relates to a device and method for cleaving optical fibers which yields cleaved optical fiber ends possessing high damage threshold surfaces. The device can be used to cleave optical fibers with core diameters greater than 400 {micro}m. 30 figs.

Halpin, J.M.

1996-03-26T23:59:59.000Z

345

Stellar core collapse and supernova  

SciTech Connect

Massive stars that end their stable evolution as their iron cores collapse to a neutron star or black hole long been considered good candidates for producing Type II supernovae. For many years the outward propagation of the shock wave produced by the bounce of these iron cores has been studied as a possible mechanism for the explosion. For the most part, the results of these studies have not been particularly encouraging, except, perhaps, in the case of very low mass iron cores or very soft nuclear equations of state. The shock stalls, overwhelmed by photodisintegration and neutrino losses, and the star does not explode. More recently, slow late time heating of the envelope of the incipient neutron star has been found to be capable of rejuvenating the stalled shock and producing an explosion after all. The present paper discusses this late time heating and presents results from numerical calculations of the evolution, core collapse, and subsequent explosion of a number of recent stellar models. For the first time they all, except perhaps the most massive, explode with reasonable choices of input physics. 39 refs., 17 figs., 1 tab.

Wilson, J.R.; Mayle, R.; Woosley, S.E.; Weaver, T.

1985-04-01T23:59:59.000Z

346

Wright State University CORE Scholar  

E-Print Network (OSTI)

Wright State University CORE Scholar Psychology Faculty Publications Psychology 10-1-2010 The Statistical Properties of the Survivor Interaction Contrast Joseph W. Houpt Wright State University - Main Campus, joseph.houpt@wright.edu James T. Townsend Follow this and additional works at: http://corescholar.libraries.wright

Townsend, James T.

347

Development of a new deuterium–deuterium (D–D) neutron generator for prompt gamma-ray neutron activation analysis  

Science Journals Connector (OSTI)

Abstract A new deuterium–deuterium (D–D) neutron generator has been developed by Adelphi Technology for prompt gamma neutron activation analysis (PGNAA), neutron activation analysis (NAA), and fast neutron radiography. The generator makes an excellent fast, intermediate, and thermal neutron source for laboratories and industrial applications that require the safe production of neutrons, a small footprint, low cost, and small regulatory burden. The generator has three major components: a Radio Frequency Induction Ion Source, a Secondary Electron Shroud, and a Diode Accelerator Structure and Target. Monoenergetic neutrons (2.5 MeV) are produced with a yield of 1010 n/s using 25–50 mA of deuterium ion beam current and 125 kV of acceleration voltage. The present study characterizes the performance of the neutron generator with respect to neutron yield, neutron production efficiency, and the ionic current as a function of the acceleration voltage at various RF powers. In addition the Monte Carlo N-Particle Transport (MCNP) simulation code was used to optimize the setup with respect to thermal flux and radiation protection.

K. Bergaoui; N. Reguigui; C.K. Gary; C. Brown; J.T. Cremer; J.H. Vainionpaa; M.A. Piestrup

2014-01-01T23:59:59.000Z

348

The determination of titanium, germanium and gallium by charged particle activation analysis  

E-Print Network (OSTI)

V FWHM for the 1. 332 MeV y-ray of Co; Peak-to-Compton ratio: 20. 1; 60 Efficiency relative to a 3 x 3 inch NaI (Tl) detector for the 1. 332 MeV y-ray measured at 25 cm distance: 3 05%%d Data Ac uisition and Processin Data was acquired via a 4096... of the reaction had to be sufficiently high to make measurements of ppm level concentrations feasible. The thick target yields were calculated by correlating the activities of the particular Y-rays 16 back to the time at the end of the irradiation...

Novak, Leo Robert

1975-01-01T23:59:59.000Z

349

X-RAY FLUORESCENCE ANALYSIS OF HANFORD LOW ACTIVITY WASTE SIMULANTS METHOD DEVELOPMENT  

SciTech Connect

The x-ray fluorescence laboratory (XRF) in the Analytical Development Directorate (ADD) of the Savannah River National Laboratory (SRNL) was requested to develop an x-ray fluorescence spectrometry method for elemental characterization of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) pretreated low activity waste (LAW) stream to the LAW Vitrification Plant. The WTP is evaluating the potential for using XRF as a rapid turnaround technique to support LAW product compliance and glass former batching. The overall objective of this task was to develop an XRF analytical method that provides rapid turnaround time (<8 hours), while providing sufficient accuracy and precision to determine variations in waste.

Jurgensen, A; David Missimer, D; Ronny Rutherford, R

2007-08-08T23:59:59.000Z

350

Determination of selected trace elements in human head hair by neutron activation analysis  

E-Print Network (OSTI)

the scope of this discussion. The final category of data contains barium and strontium. There was no data in the literature to use as a comparison, therefore the values of 49 ppm for barium and 87 ppm for strontium must stand on their own merit...) in Japan and of course, the current work in Texas. The results of the correlation analysis were that there were no significant correlations between any of the elements except in the case of strontium and barium which yielded a Pearson correlation coef...

Courson, Leonard Austin

2012-06-07T23:59:59.000Z

351

Resolving piping analysis issues to minimize impact on installation activities during refueling outage at nuclear power plants  

SciTech Connect

While it is required to maintain piping code compliance for all phases of installation activities during outages at a nuclear plant, it is equally essential to reduce challenges to the installation personnel on how plant modification work should be performed. Plant betterment activities that incorporate proposed design changes are continually implemented during the outages. Supporting analysis are performed to back these activities for operable systems. The goal is to reduce engineering and craft man-hours and minimize outage time. This paper outlines how plant modification process can be streamlined to facilitate construction teams to do their tasks that involve safety related piping. In this manner, installation can proceed by minimizing on the spot analytical effort and reduce downtime to support the proposed modifications. Examples are provided that permit performance of installation work in any sequence. Piping and hangers including the branch lines are prequalified and determined operable. The system is up front analyzed for all possible scenarios. The modification instructions in the work packages is flexible enough to permit any possible installation sequence. The benefit to this approach is large enough in the sense that valuable outage time is not extended and on site analytical work is not required.

Bhavnani, D. [Public Service Electric and Gas Co., Hancocks Bridge, NJ (United States)

1996-12-01T23:59:59.000Z

352

Tank 241-BY-109, cores 201 and 203, analytical results for the final report  

SciTech Connect

This document is the final laboratory report for tank 241-BY-109 push mode core segments collected between June 6, 1997 and June 17, 1997. The segments were subsampled and analyzed in accordance with the Tank Push Mode Core Sampling and Analysis Plan (Bell, 1997), the Tank Safety Screening Data Quality Objective (Dukelow, et al, 1995). The analytical results are included.

Esch, R.A.

1997-11-20T23:59:59.000Z

353

Modeling the Arm II core in MicroCap IV  

SciTech Connect

This paper reports on how an electrical model for the core of the Arm II machine was created and how to use this model. We wanted to get a model for the electrical characteristics of the ARM II core, in order to simulate this machine and to assist in the design of a future machine. We wanted this model to be able to simulate saturation, variable loss, and reset. Using the Hodgdon model and the circuit analysis program MicroCap IV, this was accomplished. This paper is written in such a way as to allow someone not familiar with the project to understand it.

Dalton, A.C.

1996-11-01T23:59:59.000Z

354

Compound and Elemental Analysis At International Geothermal Area, Indonesia  

Open Energy Info (EERE)

Indonesia Indonesia (Laney, 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Compound and Elemental Analysis At International Geothermal Area Indonesia (Laney, 2005) Exploration Activity Details Location International Geothermal Area Indonesia Exploration Technique Compound and Elemental Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Improving Exploration Models of Andesite-Hosted Geothermal Systems, Allis, Browne, Bruton, Christensen, Hulen, Lutz, Mindenhall, Nemcok, Norman, Powell and Stimac. The approach we are using is to characterize the petrology, geochemistry and fractures in core and cuttings samples and then integrate these data with measured downhole temperatures and pressures and with the compositions of the reservoir fluids. Our investigations represent

355

Cuttings Analysis At International Geothermal Area, Philippines (Laney,  

Open Energy Info (EERE)

Cuttings Analysis At International Geothermal Area Cuttings Analysis At International Geothermal Area Philippines (Laney, 2005) Exploration Activity Details Location International Geothermal Area Philippines Exploration Technique Cuttings Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Improving Exploration Models of Andesite-Hosted Geothermal Systems, Allis, Browne, Bruton, Christensen, Hulen, Lutz, Mindenhall, Nemcok, Norman, Powell and Stimac. The approach we are using is to characterize the petrology, geochemistry and fractures in core and cuttings samples and then integrate these data with measured downhole temperatures and pressures and with the compositions of the reservoir fluids. Our investigations represent cooperative efforts with the Karaha-Bodas Co. LLC (a subsidiary of

356

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations, Appendices A--D. Volume 2, Part 2  

SciTech Connect

During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the Potential risks during low Power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the Plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this report is to document the approach utilized in the Surry plant and discuss the results obtained. A parallel report for the Grand Gulf plant is prepared by SNL. This study shows that the core-damage frequency during mid-loop operation at the Surry plant is comparable to that of power operation. We recognize that there is very large uncertainty in the human error probabilities in this study. This study identified that only a few procedures are available for mitigating accidents that may occur during shutdown. Procedures written specifically for shutdown accidents would be useful. This document, Volume 2, Pt. 2 provides appendices A through D of this report.

Chu, T.L.; Musicki, Z.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)] [and others

1994-06-01T23:59:59.000Z

357

Laminated electromagnetic pump stator core  

DOE Patents (OSTI)

A stator core for an electromagnetic pump includes a plurality of circumferentially abutting tapered laminations extending radially outwardly from a centerline axis to collectively define a radially inner bore and a radially outer circumference. Each of the laminations includes radially inner and outer edges and has a thickness increasing from the inner edge toward the outer edge to provide a substantially continuous path adjacent the circumference. This pump is used in nuclear fission reactors. 19 figs.

Fanning, A.W.

1995-08-08T23:59:59.000Z

358

Radial illite On the cores of the Soultz well EPS1,  

E-Print Network (OSTI)

are quarries, abandoned or with activities. Six samples have been also collected among the granite cores and alteration halo (Ottenhöffen quarry, Germany) On these outcrops, we have measured planes of fracture

Paris-Sud XI, Université de

359

A MULTI-WAVELENGTH ANALYSIS OF NGC 4178: A BULGELESS GALAXY WITH AN ACTIVE GALACTIC NUCLEUS  

SciTech Connect

We present Gemini longslit optical spectroscopy and Very Large Array radio observations of the nuclear region of NGC 4178, a late-type bulgeless disk galaxy recently confirmed to host an active galactic nucleus (AGN) through infrared and X-ray observations. Our observations reveal that the dynamical center of the galaxy is coincident with the location of the Chandra X-ray point source discovered in a previous work, providing further support for the presence of an AGN. While the X-ray and IR observations provide robust evidence for an AGN, the optical spectrum shows no evidence for the AGN, underscoring the need for the penetrative power of mid-IR and X-ray observations in finding buried or weak AGNs in this class of galaxy. Finally, the upper limit to the radio flux, together with our previous X-ray and IR results, is consistent with the scenario in which NGC 4178 harbors a deeply buried AGN accreting at a high rate.

Secrest, N. J.; Satyapal, S.; Gliozzi, M. [Department of Physics and Astronomy, George Mason University, MS 3F3, 4400 University Drive, Fairfax, VA 22030 (United States); Moran, S. M. [Department of Physics and Astronomy, Johns Hopkins University, 366 Bloomberg Center, 3400 N. Charles Street, Baltimore, MD 21218 (United States); Cheung, C. C. [Space Science Division, Naval Research Laboratory, Washington, DC 20375-5352 (United States); Giroletti, M. [INAF Istituto di Radioastronomia, I-40129 Bologna (Italy); Bergmann, M. P. [NOAO Gemini Science Center, P.O. Box 26732, Tucson, AZ 85726 (United States); Seth, A. C. [Department of Physics and Astronomy, University of Utah, Salt Lake City, UT 84112 (United States)

2013-11-10T23:59:59.000Z

360

HyCore | Open Energy Information  

Open Energy Info (EERE)

HyCore Jump to: navigation, search Name: HyCore Place: Norway Sector: Hydro, Solar Product: JV between Umicore and Norsk Hydro to manufacture solar-grade silicon. References:...

Note: This page contains sample records for the topic "activity core analysis" 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

Matrix Acidizing Parallel Core Flooding Apparatus  

E-Print Network (OSTI)

and provide this information to the field. To conduct various experiments, core flooding setups are created. The setup consists of a core holder, accumulator, overburden pump, injection pump, accumulator, pressure sensors, and a back pressure regulator...

Ghosh, Vivek

2013-07-23T23:59:59.000Z

362

The SimCore/Alpha Functional Simulator  

Science Journals Connector (OSTI)

We have developed a function-level processor simulator, SimCore/Alpha Functional Simulator Version 2.0 (SimCore Version 2.0), for processor architecture research and processor education. This paper describes the design and implementation of SimCore Version ...

Kenji Kise; Takahiro Katagiri; Hiroki Honda; Toshitsugu Yuba

2004-06-01T23:59:59.000Z

363

Core Competency Worksheets for Significant Cybersecurity Roles  

Energy.gov (U.S. Department of Energy (DOE))

OCIO has developed core competency worksheets for significant cyber roles to assist training personnel, curricula developers, supervisors, etc. with identifying core skills needed to perform their functional roles. Core competencies can be used to develop training objectives for site or organization-specific role-based training.

364

GCFR core thermal-hydralic design  

SciTech Connect

The approach for developing the thermal-hydraulic core assembly designs for the gas-cooled fast reactor (GCFR) is reviewed, and key considerations for improving the core performance at all power and flow conditions are discussed. It is shown how the thermal-hydraulic core assembly designs evolve from evaluations of plant size, material limitations, safety criteria, and structural performance considerations.

Schleuter, G.; Baxi, C.B.; Bennett, F.O.

1980-05-01T23:59:59.000Z

365

Russian techniques for more productive core drilling  

SciTech Connect

This is a short discussion of the trends and technology being used in Russia to increase the production of core drilling. The currently used rigs are given with the plans for improvement in drive methods and to reduce trip time in the recovery of cores. The recommendations by the Russians to improve the core recovery quality and quantity are also given.

Not Available

1984-09-01T23:59:59.000Z

366

Policy and Analysis Team | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Policy and Analysis Team Policy and Analysis Team Policy and Analysis Team The mission of Policy and Analysis is to provide a consistent, objective, and credible analysis for the Office of Energy Efficiency and Renewable Energy's (EERE's) activities and an understanding of the effect of various policies on EERE's core mission. This includes guiding investment decisions through credible data and scenario analyses in order to maximize their effectiveness and return on investment for the taxpayer. To browse our collection of energy analysis publications and resources, visit our resource library here. Why it Matters We inform EERE's corporate decisions and program implementation through data-driven, portfolio-based analysis of technology and policy to help drive cost-effective decisions.

367

Quasi-Anharmonic Analysis Reveals Intermediate States In The Nuclear Co-Activator Receptor Binding Domain Ensemble  

SciTech Connect

The molten globule nuclear receptor co-activator binding domain (NCBD) of CREB binding protein (CBP) selectively recruits transcription co-activators (TCAs) during the formation of the transcription preinitiation complex. NCBD:TCA interactions have been implicated in several cancers, however, the mechanisms of NCBD:TCA recognition remain uncharacterized. NCBD:TCA intermolecular recognition has challenged traditional investigation as both NCBD and several of its corresponding TCAs are intrinsically disordered. Using 40 {micro}s of explicit solvent molecular dynamics simulations, we relate the conformational diversity of ligand-free NCBD to its bound configurations. We introduce two novel techniques to quantify the conformational heterogeneity of ligand-free NCBD, dihedral quasi-anharmonic analysis (dQAA) and hierarchical graph-based diffusive clustering. With this integrated approach we find that three of four ligand-bound states are natively accessible to the ligand-free NCBD simulations with root-mean squared deviation (RMSD) less than 2 {angstrom}. These conformations are accessible via diverse pathways while a rate-limiting barrier must be crossed in order to access the fourth bound state.

Agarwal, Pratul K [ORNL] [ORNL; Ramanathan, Arvind [ORNL] [ORNL

2012-01-01T23:59:59.000Z

368

Structured design, consistency analysis and failure reasoning of business workflows with activity-control templates and causal ordering  

Science Journals Connector (OSTI)

The design, analysis, control and diagnosis of business workflows have been major challenges for enterprise information system designers. We propose a structured framework for workflow design, formal semantics, consistency analysis, execution automation and failure reasoning targeting E-commerce applications. A business workflow is modeled by using a visual tool named activity-control (AC) diagram. Frequently occurring business procedures are captured by the adoptions of reusable AC templates. With formally defined semantics by a combination of first-order logic and happen-before causal ordering in distributed system theory, workflow consistency can be mechanically analyzed at design time while failure reasoning can be applied at execution time for problem diagnosis. A completely specified model is automatically converted to a workflow by an iterative traversal algorithm that maps an AC diagram to an XML workflow specification which can then be executed automatically by an XML workflow engine. A failure reasoning and diagnosis algorithm is devised to find all possible causes of a failed execution when problems occur. Preliminary proof-of-concept implementation and evaluation results demonstrate the feasibility and effectiveness of our framework and techniques.

Shiow-yang Wu; Kuo-Chang Lin

2011-01-01T23:59:59.000Z

369

DOE CYBER SECURITY EBK: MINIMUM CORE COMPETENCY TRAINING REQUIREMENTS...  

Office of Environmental Management (EM)

DOE CYBER SECURITY EBK: MINIMUM CORE COMPETENCY TRAINING REQUIREMENTS DOE CYBER SECURITY EBK: MINIMUM CORE COMPETENCY TRAINING REQUIREMENTS DOE CYBER SECURITY EBK: CORE COMPETENCY...

370

DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CORE COMPETENCY TRAINING REQUIREMENTS: CA DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS: CA DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS. Key Cyber...

371

Core Coupling in Nb-99  

E-Print Network (OSTI)

to be good. NUCLEAR REACTIONS, NUCLEAR STRUCTURE '"Mop, 'He), E =40.7 Mev, measured o(8) 99Nb levels deduced S. Calculated levels, 4, n', 8 NNb, particle- core-coupling model. The proton configurations of nuclei in the Zr-Mo region have been the subject... of much experimental interest. ' ' The only information available on ~Nb, however, was obtained by measurement of y decay following 99Zr P decay, ~ and is rather lim- ited. We have studied the levels of "Nb with the Mo(d, 'He) reaction at 40.7-Me...

Bindal, P. K.; Youngblood, David H.

1974-01-01T23:59:59.000Z

372

Cuttings Analysis At Long Valley Caldera Area (Smith & Suemnicht, 1991) |  

Open Energy Info (EERE)

Long Valley Caldera Area (Smith Long Valley Caldera Area (Smith & Suemnicht, 1991) Exploration Activity Details Location Long Valley Caldera Area Exploration Technique Cuttings Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Sample for the present investigation consist of drill core and cuttings from all lithologic units identified in LVEW, cuttings from volcanic rocks in LV 13-21, core samples of Early Rhyolite and Bishop Tuff from LV13-26 and core samples of Bishop Tuff from SF38-32, LV48-29 and LV66-28 (Figs. 1 and 2). Surface samples of Early Rhyolite, Bishop Tuff and Paleozoic metasediments (Fig. 1) were also selected for comparative analysis and processed by the same procedures as the well samples. This oxygen isotope and fluid inclusion study has allowed us to determine the pathways of fluid

373

SoCore Energy | Open Energy Information  

Open Energy Info (EERE)

SoCore Energy SoCore Energy Jump to: navigation, search Name SoCore Energy Place Chicago, Illinois Zip 60601 Sector Solar Product Chicago-based solar installer and mounting solution company that also arranges for solar loans and PPAs. References SoCore Energy[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. SoCore Energy is a company located in Chicago, Illinois . References ↑ "SoCore Energy" Retrieved from "http://en.openei.org/w/index.php?title=SoCore_Energy&oldid=351218" Categories: Clean Energy Organizations Companies Organizations Stubs What links here Related changes Special pages Printable version Permanent link Browse properties About us Disclaimers Energy blogs

374

Analysis of closed-pool boilup using the TRANSIT-HYDRO code. [LMFBR  

SciTech Connect

The benign termination of the transition phase of a hypothetical LMFBR accident rests on the avoidance of highly energetic recriticalities prior to escape of bottled molten core materials from the active core region. In scenarios where molten fuel is trapped due to axial blockages, the maintenance of subcritical configurations until radial flow paths develop requires stable boil-up of the molten fuel/steel mixture. This paper describes the analysis of an experiment investigating the behavior of closed boiling pools using the two-fluid hydrodynamics module of TRANSIT-HYDRO, a deterministic transition-phase analysis code.

Graff, D.L.

1983-01-04T23:59:59.000Z

375

Core Holes At Fort Bliss Area (Combs, Et Al., 1999) | Open Energy  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » Core Holes At Fort Bliss Area (Combs, Et Al., 1999) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Holes At Fort Bliss Area (Combs, Et Al., 1999) Exploration Activity Details Location Fort Bliss Area Exploration Technique Core Holes Activity Date Usefulness not indicated DOE-funding Unknown Notes Drilling for the four holes followed the same general pattern: 1) set a conductor casing to a depth of 30-50', 2) drill - 6" hole through mostly sand/clay sedentary formations to 500-600', 3) set 4-1/2" surface casing at that depth 4) core HQ (3.89" dia.) mostly through limestone/dolornite or

376

ON THE EVOLUTION OF THE CORES OF RADIO SOURCES AND THEIR EXTENDED RADIO EMISSION  

SciTech Connect

The work in this paper aims at determining the evolution and possible co-evolution of radio-loud active galactic nuclei (AGNs) and their cores via their radio luminosity functions (i.e., total and core RLFs, respectively). Using a large combined sample of 1063 radio-loud AGNs selected at low radio frequency, we investigate the RLF at 408 MHz of steep-spectrum radio sources. Our results support a luminosity-dependent evolution. Using core flux density data of the complete sample 3CRR, we investigate the core RLF at 5.0 GHz. Based on the combined sample with incomplete core flux data, we also estimate the core RLF using a modified factor of completeness. Both results are consistent and show that the comoving number density of radio cores displays a persistent decline with redshift, implying a negative density evolution. We find that the core RLF is obviously different from the total RLF at the 408 MHz band which is mainly contributed by extended lobes, implying that the cores and extended lobes could not be co-evolving at radio emission.

Yuan Zunli; Wang Jiancheng, E-mail: yuanzunli@ynao.ac.cn [National Astronomical Observatories, Yunnan Observatory, Chinese Academy of Sciences, Kunming 650011 (China)

2012-01-10T23:59:59.000Z

377

Cracking behavior of cored structures  

SciTech Connect

The effects of compositional gradients, are considered based on a thermodynamic analysis, referred to as the Cahn-Hillard analysis, which describes the degree to which a local surface energy is modified by the presence of a composition gradient. The analysis predicts that both ductile and brittle fracture mechanisms are enhanced by the presence of a composition gradient. Data on stress corrosion cracking and fatigue crack growth in selected FCC alloys are used to illustrate the significance of microsegregation on mechanical properties.

Wahid, A.; Olson, D.L.; Matlock, D.K. (Colorado School of Mines, Golden, CO (United States). Center for Welding and Joining Research); Kelly, T.J. (General Electric Aircraft Engines, Evendale, OH (United States))

1991-01-01T23:59:59.000Z

378

Solar Activity Index: Validity Supported by Oxygen Isotope Dating  

Science Journals Connector (OSTI)

...CENTURIES OF CLIMATIC RECORD FROM CAMP CENTURY ON GREENLAND ICE SHEET, SCIENCE...sup> concentration in Greenland Camp Century ice core, correlation with solar...activity absolute age Arctic region Camp Century ice core dates general listing...

J. R. Bray

1970-05-01T23:59:59.000Z

379

Core Capabilities | Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

The Advanced Photon Source is one of the brightest sources of X-rays in the The Advanced Photon Source is one of the brightest sources of X-rays in the Western Hemisphere. Photons are accelerated to over 99% of the speed of light around its ring, which is the size of a baseball stadium. To view a larger version of the image, click on it. The Center for Nanoscale Materials at Argonne is a premier user facility, providing expertise, instruments, and infrastructure for interdisciplinary nanoscience and nanotechnology research. To view a larger version of the image, click on it. Core Capabilities Argonne's vision is to lead the world in discovery science and engineering that provides technical solutions to the grand challenges of our time. Argonne's vision is to lead the world in discovery science and engineering that provides technical solutions to the grand challenges of our time:

380

Test report -- Prototype core sampler  

SciTech Connect

The purpose of this test is to determine the adequacy of the prototype sampler, provided to Westinghouse Hanford Company (WHC) by DOE-RL. The sampler was fabricated for DOE-RL by the Concord Company by request of DOE-RL. This prototype sampler was introduced as a technology that can be easily deployed (similar to the current auger system) and will reliably collect representative samples. The sampler is similar to the Universal Sampler i.e., smooth core barrel and piston with an O-ring seal, but lacks a rotary valve near the throat of the sampler. This makes the sampler inappropriate for liquid sampling, but reduces the outside diameter of the sampler considerably, which should improve sample recovery. Recovery testing was performed with the supplied sampler in three different consistencies of Kaolin sludge simulants.

Linschooten, C.G.

1995-01-17T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Nuclear core and fuel assemblies  

DOE Patents (OSTI)

A fast flux nuclear core of a plurality of rodded, open-lattice assemblies having a rod pattern rotated relative to a rod support structure pattern. Elongated fuel rods are oriented on a triangular array and laterally supported by grid structures positioned along the length of the assembly. Initial inter-assembly contact is through strongbacks at the corners of the support pattern and peripheral fuel rods between adjacent assemblies are nested so as to maintain a triangular pitch across a clearance gap between the other portions of adjacent assemblies. The rod pattern is rotated relative to the strongback support pattern by an angle .alpha. equal to sin .sup.-1 (p/2c), where p is the intra-assembly rod pitch and c is the center-to-center spacing among adjacent assemblies.

Downs, Robert E. (Monroeville, PA)

1981-01-01T23:59:59.000Z

382

A benchmark for investigating the radial dependence of C/E for control rod worths in large decoupled cores  

SciTech Connect

The first physics measurements of a heterogeneous core on the critical assembly ZPPR-7 at ANL showed that the C/E ratios with ENDF/B data for the worths of the control rods in the outer bank were several percent higher than those at the inner bank positions. This radial variation in the C/E for the rod worths was further confirmed in the analysis of the large conventional core ZPPR-10, and again in the analysis of the large heterogeneous core series ZPPR-13. In the design of a power reactor, the number of control rods, and their disposition, are determined by calculations. Misprediction of the worth of the control rods can lead to serious economic penalties by restricting the operation of the core. Retrofitting a core to accommodate more worth will be costly and is likely to lead to a non-optimized core. This document provides a discussion of these calculations. 7 refs., 7 figs., 12 tabs.

Salvatores, M. (CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)); Orechwa, Y. (Argonne National Lab., IL (USA)); Collins, P.J. (Argonne National Lab., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

383

Modern Records of Atmospheric Carbon Dioxide (CO2) and a 2000-year Ice-core  

NLE Websites -- All DOE Office Websites (Extended Search)

Carbon Dioxide (CO2) » Ice Cores Carbon Dioxide (CO2) » Ice Cores Modern Records of Atmospheric Carbon Dioxide (CO2) and a 2000-year Ice-core Record from Law Dome, Antarctica Introduction This page provides an introduction and links to records of atmospheric carbon dioxide (CO2) concentrations over the last 2000 years, emphasizing large data bases each representing many currently active stations. Records since about 1960 (depending on location) have been obtained from samples of ambient-air at remote stations, which represent changing global atmospheric concentrations rather than influences of local sources. The longer (2000-year) record is from the Law Dome ice core in Antarctica. The ice-core record has been merged with modern annual data from Cape Grim, Tasmania to provide a 2000-year record ending with the most recent data. A

384

Modern Records of Atmospheric Methane (CH4) and a 2000-year Ice-core Record  

NLE Websites -- All DOE Office Websites (Extended Search)

(CH4) » Ice Cores (CH4) » Ice Cores Modern Records of Atmospheric Methane (CH4) and a 2000-year Ice-core Record from Law Dome, Antarctica Introduction This page provides an introduction and links to records of atmospheric methane (CH4) over the last 2000 years, emphasizing large data bases each representing currently active stations. Records in recent decades (time period depending on location) have been obtained from samples of ambient-air at remote locations, which represent global atmospheric conditions rather than influences of local sources. The longer (2000-year) record is from the Law Dome ice core in Antarctica. The ice-core record has been merged with modern annual data from Cape Grim, Tasmania to provide a 2000-year record ending with the most recent data. A spline function has

385

Application of neutron activation analysis and high resolution x-ray spectrometry for the determination of trace quantities of elements with short-lived activation products  

E-Print Network (OSTI)

Conversion Interferences and Errors 3, PROCEDURES AND EXPERIMENTAL SETUP Sample Preparation Pneumatic Sample Transfer System Sample Irradiation X-ray Spectrometry Data Reduction 4. DISCUSSION AND RESULTS System Analysis Analysis Problems.... C. Roentgen made the classic observation that a highly penatrative radiation, unknown at that time, was produced when fast electrons impinged on matter. This radiation, which h called x-rays, was being studied in all parts of the world less than...

Marshall, John Richard

1974-01-01T23:59:59.000Z

386

Large Pitch Hollow Core Honeycomb Fiber  

Science Journals Connector (OSTI)

A new kind of hollow core photonic crystal fiber (HC-PCF) for broadband guidance is introduced. Structural and optical properties of a fabricated example are detailed.

Beaudou, Benoît; Couny, François; Benabid, Fetah; Roberts, Peter John

387

The nascent Coso metamorphic core complex, east-central California, brittle  

Open Energy Info (EERE)

nascent Coso metamorphic core complex, east-central California, brittle nascent Coso metamorphic core complex, east-central California, brittle upper plate structure revealed by reflection seismic data Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: The nascent Coso metamorphic core complex, east-central California, brittle upper plate structure revealed by reflection seismic data Details Activities (1) Areas (1) Regions (0) Abstract: The relationships between upper crustal faults, the brittle-ductile transition zone, and underlying magmatic features imaged by multifold seismic reflection data are consistent with the hypothesis that the Coso geothermal field, which lies within an extensional step-over between dextral faults, is a young, actively developing metamorphic core complex. The reflection images were processed using a non-linear simulated

388

Core Holes At Lake City Hot Springs Area (Benoit Et Al., 2005) | Open  

Open Energy Info (EERE)

Holes At Lake City Hot Springs Area (Benoit Et Holes At Lake City Hot Springs Area (Benoit Et Al., 2005) Exploration Activity Details Location Lake City Hot Springs Area Exploration Technique Core Holes Activity Date Usefulness useful DOE-funding Unknown Notes Three core holes drilled between 2002 and 2005. Depths: 1,728; 3,435; 4,727 ft. Two deeper wells encountered temps of 327 and 329 oF and permable fractures in sedimentary and volcanic rocks; enabled injection and flow testing up to 70 gpm. Quartz fluid inclusions give temps of 264 and 316 oF. Core drillling allowed an understanding of geology and geothermal system that could never have been obtained from cuttings in this particular geologic setting. References Dick Benoit, Joe Moore, Colin Goranson, David Blackwell (2005) Core Hole Drilling And Testing At The Lake City, California Geothermal Field

389

Searches for sterile neutrinos with IceCube DeepCore  

Science Journals Connector (OSTI)

We show that study of the atmospheric neutrinos in the 10–100 GeV energy range by DeepCore subarray of the IceCube Neutrino Observatory can substantially constrain the mixing of sterile neutrinos of mass ?1??eV with active neutrinos. In the scheme with one sterile neutrino we calculate ?? and ?¯? oscillation probabilities as well as zenith angle distributions of ??CC (charge current) events in different energy intervals in DeepCore. The distributions depend on the mass hierarchy of active neutrinos. Therefore, in principle, the hierarchy can be identified, if ?s exists. After a few years of exposure the DeepCore data will allow us to exclude the mixing of |U?4|2?0.02 indicated by the LSND/MiniBooNE results. Combination of the DeepCore and high-energy IceCube data will further improve sensitivity to ?s mixing parameters.

Soebur Razzaque and A. Yu. Smirnov

2012-05-18T23:59:59.000Z

390

Natural thorium isotopes in marine sediment core off Labuan port  

SciTech Connect

Sediment core was collected from Labuan port and analyzed to determine the radioactivity of thorium (Th) isotopes. The objectives of this study are to determine the possible sources of Th isotopes at Labuan port and estimates the sedimentation rate based on {sup 228}Th/{sup 232}Th model. The results suggest the {sup 230}Th and {sup 232}Th might be originated from terrestrial sedimentary rock while {sup 228}Th originated by authigenic origin. High ratio value of {sup 230}Th/{sup 232}Th detected at the top surface sediment indicates the increasing of {sup 230}Th at the recent years which might be contributed from the anthropogenic sources. The sedimentation rate of core sediment from Labuan Port was successfully estimated by using {sup 228}Th/{sup 232}Th model. The result show high sedimentation rate with 4.67 cm/year indicates rapid deposition occurred at this study area due to the high physical activity at the Labuan port. By assume the constant sedimentation rate at this area; we estimated the age of 142 cm core sediment obtained from Labuan port is 32 years started from 1981 to 2012. This chronology will be used in forthcoming research to investigate the historical profile of anthropogenic activities affecting the Labuan port.

Hafidz, B. Y.; Asnor, A. S.; Terence, R. C.; Mohamed, C. A. R. [School of Environmental and Natural Resource Sciences, Faculty of Science and Technology, Universiti Kebangsaan Malaysia 43600, Bangi, Selangor (Malaysia)

2014-02-12T23:59:59.000Z

391

New insights on the solar core  

E-Print Network (OSTI)

Since the detection of the asymptotic properties of the dipole gravity modes in the Sun, the quest to find individual gravity modes has continued. An extensive and deeper analysis of 14 years of continuous GOLF/SoHO observational data, unveils the presence of a pattern of peaks that could be interpreted as individual dipole gravity modes in the frequency range between 60 and 140 microHz, with amplitudes compatible with the latest theoretical predictions. By collapsing the power spectrum we have obtained a quite constant splitting for these patterns in comparison to regions where no g modes were expected. Moreover, the same technique applied to simultaneous VIRGO/SoHO data unveils some common signals between the power spectra of both instruments. Thus, we are able to identify and characterize individual g modes with their central frequencies, amplitudes and splittings allowing to do seismic inversions of the rotation profile inside the solar core. These results open a new light on the physics and dynamics of t...

Garcia, R A; Ballot, J; Eff-Darwich, A; Garrido, R; Jimenez, A; Mathis, S; Mathur, S; Moya, A; Palle, P L; Regulo, C; Sato, K; Suarez, J C; Turck-Chieze, S

2010-01-01T23:59:59.000Z

392

Origin of the Core Francis Nimmo  

E-Print Network (OSTI)

Origin of the Core Francis Nimmo Dept. Earth Sciences, University of California, Santa Cruz F. Nimmo, Dept. Earth Sciences, University of California, Santa Cruz, CA 95064, USA (fnimmo@es.ucsc.edu), tel. 831-459-1783, fax. 831-459-3074 1 #12;Origin of the Core All major bodies of the inner solar

Nimmo, Francis

393

Experto Universitario Java Sesin 1: Spring core  

E-Print Network (OSTI)

Enterprise Spring © 2012-2013 Depto. Ciencia de la Computación e IA Spring core Puntos a tratar 2 #12;Experto Universitario Java Enterprise Spring © 2012-2013 Depto. Ciencia de la Computación e IA;Experto Universitario Java Enterprise Spring © 2012-2013 Depto. Ciencia de la Computación e IA Spring core

Escolano, Francisco

394

Module Handbook Core Univ. of Oldenburg  

E-Print Network (OSTI)

· Mechanical and Electrical Systems of the WEC Content: Energy conversion process in Wind Turbines · Wind/EUREC Course 2008/2009 #12;EUREC Core Courses at University of Oldenburg, 1st Semester Wind Energy Module Module Description: Wind Energy Field: Core Oldenburg Courses: Wind Energy Wind Energy

Habel, Annegret

395

Shape evolution of a core-shell spherical particle under hydrostatic pressure  

Science Journals Connector (OSTI)

The morphological evolution by surface diffusion of a core-shell spherical particle has been investigated theoretically under hydrostatic pressure when the shear modulii of the core and shell are different. A linear stability analysis has demonstrated that depending on the pressure, shear modulii, and radii of both phases, the free surface of the composite particle may be unstable with respect to a shape perturbation. A stability diagram finally emphasizes that the roughness development is favored in the case of a hard shell with a soft core.

Jérôme Colin

2012-03-30T23:59:59.000Z

396

Assessment of energetic costs of AhR activation by ?-naphthoflavone in rainbow trout (Oncorhynchus mykiss) hepatocytes using metabolic flux analysis  

SciTech Connect

Exposure to environmental contaminants such as activators of the aryl hydrocarbon receptor (AhR) leads to the induction of defense and detoxification mechanisms. While these mechanisms allow organisms to metabolize and excrete at least some of these environmental contaminants, it has been proposed that these mechanisms lead to significant energetic challenges. This study tests the hypothesis that activation of the AhR by the model agonist ?-naphthoflavone (?NF) results in increased energetic costs in rainbow trout (Oncorhynchus mykiss) hepatocytes. To address this hypothesis, we employed traditional biochemical approaches to examine energy allocation and metabolism including the adenylate energy charge (AEC), protein synthesis rates, Na{sup +}/K{sup +}-ATPase activity, and enzyme activities. Moreover, we have used for the first time in a fish cell preparation, metabolic flux analysis (MFA) an in silico approach for the estimation of intracellular metabolic fluxes. Exposure of trout hepatocytes to 1 ?M ?NF for 48 h did not alter hepatocyte AEC, protein synthesis, or Na{sup +}/K{sup +}-ATPase activity but did lead to sparing of glycogen reserves and changes in activities of alanine aminotransferase and citrate synthase suggesting altered metabolism. Conversely, MFA did not identify altered metabolic fluxes, although we do show that the dynamic metabolism of isolated trout hepatocytes poses a significant challenge for this type of approach which should be considered in future studies. - Highlights: • Energetic costs of AhR activation by ?NF was examined in rainbow trout hepatocytes. • Metabolic flux analysis was performed on a fish cell preparation for the first time. • Exposure to ?NF led to sparing of glycogen reserves and altered enzyme activities. • Adenylate energy charge was maintained despite temporal changes in metabolism.

Nault, Rance, E-mail: naultran@msu.edu [Ottawa-Carleton Institute of Biology, Department of Biology and Centre for Advanced Research in Environmental Genomics, University of Ottawa, Ottawa, Ontario, K1N 6N5 (Canada); Abdul-Fattah, Hiba [Ottawa-Carleton Institute of Biology, Department of Biology and Centre for Advanced Research in Environmental Genomics, University of Ottawa, Ottawa, Ontario, K1N 6N5 (Canada); Mironov, Gleb G.; Berezovski, Maxim V. [Ottawa-Carleton Institute of Biology, Department of Biology and Centre for Advanced Research in Environmental Genomics, University of Ottawa, Ottawa, Ontario, K1N 6N5 (Canada); Department of Chemistry, University of Ottawa, Ottawa, Ontario, K1N 6N5 (Canada); Moon, Thomas W. [Ottawa-Carleton Institute of Biology, Department of Biology and Centre for Advanced Research in Environmental Genomics, University of Ottawa, Ottawa, Ontario, K1N 6N5 (Canada)

2013-08-15T23:59:59.000Z

397

Core File Settings | Argonne Leadership Computing Facility  

NLE Websites -- All DOE Office Websites (Extended Search)

Core File Settings Core File Settings The following environment variables control core file creation and contents. Specify regular (non-script) jobs using the qsub argument --env (Note: two dashes). Specify script jobs (--mode script) using the --envs (Note: two dashes) or --exp_env (Note: two dashes) options of runjob. For additional information about setting environment variables in your job, visit http://www.alcf.anl.gov/user-guides/running-jobs#environment-variables. Generation The following environment variables control conditions of core file generation and naming: BG_COREDUMPONEXIT=1 Creates a core file when the application exits. This is useful when the application performed an exit() operation and the cause and location of the exit() is not known. BG_COREDUMPONERROR=1

398

Lab Analysis Techniques | Open Energy Information  

Open Energy Info (EERE)

form form View source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit with form History Facebook icon Twitter icon » Lab Analysis Techniques Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Lab Analysis Techniques Details Activities (0) Areas (0) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Lab Analysis Techniques Exploration Sub Group: None Parent Exploration Technique: Exploration Techniques Information Provided by Technique Lithology: Water rock interaction; Rapid and unambiguous identification of unknown minerals; Bulk and trace element analysis of rocks, minerals, and sediments; Obtain detailed information about rock composition and morphology; Determine detailed information about rock composition and morphology; Cuttings are used to define lithology; Core analysis is done to define lithology

399

Experimental studies of a large heterogeneous LMFBR benchmark core, ZPPR-13A  

SciTech Connect

The ZPPR-13 program provides basic physics information for testing calculations of radially heterogeneous cores of about 700 MWe size. ZPPR-13 is part of the JUPITER cooperative program between Japan and the US. The results are presented of measurements and analysis for the first assembly, ZPPR-13A. These are the first data for heterogeneous cores of this size available in the US and complement results from ZPPR-9, a conventional LMFBR of similar size.

Brumbach, S.B.; Collins, P.J.; Carpenter, S.G.; Suzuki, S.; Kawashima, M.

1983-05-27T23:59:59.000Z

400

Moving from Status to Trends: Forest Inventory and Analysis Symposium 2012 46GTR-NRS-P-105 IMAGE-BASED CHANGE ESTIMATION FOR LAND COVER  

E-Print Network (OSTI)

Moving from Status to Trends: Forest Inventory and Analysis Symposium 2012 46GTR-NRS-P-105 IMAGE are core to applications including: carbon accounting, greenhouse gas emission reporting, biomass effects of natural disturbances and human activities. By extension, our ability to understand and model

Note: This page contains sample records for the topic "activity core analysis" 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

Analysis  

NLE Websites -- All DOE Office Websites (Extended Search)

Analysis Analysis of Short-Bunch Production with the APS Booster and a Bunch Compressor Michael Borland, AOD/OAG ∗ August 8, 2003 1 Abstract There is significant interest among x-ray scientists in short-pulse x-rays. The x-rays from the APS ring, although very bright, are produced by an electron bunch with an rms length of more than 30 ps. Typically, it is only a linear accelerator that can produce a very short bunch. An idea was brought to my attention by Glenn Decker that might allow us to produce a short bunch using the APS booster. This idea involves extracting the beam from the booster at 3 to 4 GeV, while it is still relatively short, then compressing it with a magnetic bunch compressor. In this note, we present a preliminary analysis of this idea, along with the related idea of using a nonequilibrium beam from the APS photoinjector. 2 Background We will begin with an examination of the ideal result

402

Assembly of large metagenome data sets using a Convey HC-1 hybrid core computer (7th Annual SFAF Meeting, 2012)  

ScienceCinema (OSTI)

Alex Copeland on "Assembly of large metagenome data sets using a Convey HC-1 hybrid core computer" at the 2012 Sequencing, Finishing, Analysis in the Future Meeting held June 5-7, 2012 in Santa Fe, New Mexico.

Copeland, Alex [DOE JGI

2013-02-11T23:59:59.000Z

403

Multicriteria Analysis of Economic Activity for Two Groups of European Countries by Decision Support System MKA-1*  

E-Print Network (OSTI)

. Five macro-economic criteria have been considered in the analysis: GDP per capita; Exports (% of GDP); Imports (% of GDP); Inflation rate (consumer prices); Unemployment rate. Keywords: multicriteria analysis of multicriteria sorting. Many real life problems in management practice may be formulated as problems of choice

Borissova, Daniela

404

510 Plant Disease / Vol. 97 No. 4 Etiology of Moldy Core, Core Browning, and Core Rot of Fuji Apple in China  

E-Print Network (OSTI)

510 Plant Disease / Vol. 97 No. 4 Etiology of Moldy Core, Core Browning, and Core Rot of Fuji Apple, and core rot of Fuji apple in China. Plant Dis. 97:510-516. `Fuji' apple fruit were collected in Shaanxi to species. Pathogenicity was determined by cutting apple fruit into halves and daubing spore suspensions

Biggs, Alan R.

405

Tank 241-B-108, cores 172 and 173 analytical results for the final report  

SciTech Connect

The Data Summary Table (Table 3) included in this report compiles analytical results in compliance with all applicable DQOS. Liquid subsamples that were prepared for analysis by an acid adjustment of the direct subsample are indicated by a `D` in the A column in Table 3. Solid subsamples that were prepared for analysis by performing a fusion digest are indicated by an `F` in the A column in Table 3. Solid subsamples that were prepared for analysis by performing a water digest are indicated by a I.wl. or an `I` in the A column of Table 3. Due to poor precision and accuracy in original analysis of both Lower Half Segment 2 of Core 173 and the core composite of Core 173, fusion and water digests were performed for a second time. Precision and accuracy improved with the repreparation of Core 173 Composite. Analyses with the repreparation of Lower Half Segment 2 of Core 173 did not show improvement and suggest sample heterogeneity. Results from both preparations are included in Table 3.

Nuzum, J.L., Fluoro Daniel Hanford

1997-03-04T23:59:59.000Z

406

Dynamic Inductance in Saturated Cores Fault Current Limiters  

Science Journals Connector (OSTI)

The saturated cores Fault Current Limiter (FCL) is one of the leading ... for providing a commercial robust solution to the fault current problem. Basically, the saturated cores FCL ... its saturated cores state ...

Y. Nikulshin; Y. Wolfus; A. Friedman…

2014-09-01T23:59:59.000Z

407

TCEQ-CoreDataForm | Open Energy Information  

Open Energy Info (EERE)

TCEQ-CoreDataForm Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: TCEQ-CoreDataForm Abstract This is the core data form from the Texas Commission on...

408

Unearthing the Composition of Our Planet's Core  

NLE Websites -- All DOE Office Websites (Extended Search)

Unearthing the Composition of Our Planet's Core Unearthing the Composition of Our Planet's Core The chemical composition of the Earth's core is surprisingly complicated, according to high-temperature, high-pressure experiments conducted by University of Chicago scientists using the William M. Keck High Pressure Laboratory at the GSECARS facility, APS sector 13. This research has produced experimental evidence suggesting that the Earth's inner core largely consists of two exotic forms of iron (rather than one as previously thought) that appear to be alloyed with silicon. Backscattered electron image of the quenched laser-heated diamond anvil cell sample from 31 GPa and 1976K. ( J.-F. Lin et al.) Above: Backscattered electron image of the quenched laser-heated diamond anvil cell sample from 31 GPa and 1976K. ( J.-F. Lin et al.)

409

GreenCore Capital | Open Energy Information  

Open Energy Info (EERE)

GreenCore Capital GreenCore Capital Jump to: navigation, search Logo: GreenCore Capital Name GreenCore Capital Address 10509 Vista Sorrento Parkway Place San Diego, California Zip 92121 Region Southern CA Area Product Invests in developing promising renewable energy companies Website http://www.greencorecapital.co Coordinates 32.898095°, -117.215736° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":32.898095,"lon":-117.215736,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

410

A New Greenland Deep Ice Core  

Science Journals Connector (OSTI)

...isotopic profile with that from camp Century and with a deep-sea foraminifera...deep-sea cores. The redated Camp Century record suggests a dramatic termination...CENTURIES OF CLIMATIC RECORD FROM CAMP CENTURY ON GREENLAND ICE SHEET, SCIENCE...

W. Dansgaard; H. B. Clausen; N. Gundestrup; C. U. Hammer; S. F. Johnsen; P. M. Kristinsdottir; N. Reeh

1982-12-24T23:59:59.000Z

411

ICE CORE RECORDS | Greenland Stable Isotopes  

Science Journals Connector (OSTI)

Abstract Greenland ice cores contain a wealth of information on past climatic conditions throughout the Northern Hemisphere. A historical perspective on the climatic interpretation of stable isotopes in water and ice is presented in the introduction, while the remainder of the article is devoted to the current interpretation of stable isotope data from Greenland ice cores. The progress in our understanding of stable isotope signals, on timescales from seasons to glacial cycles, is discussed and evaluated through numerous examples from Greenland ice cores. Stable isotope profiles from the Camp Century, Dye-3, GISP2, GRIP, NGRIP, and Renland deep ice cores are emphasized, as they all provide climatic information dating back into the Eemian period.

B.M. Vinther; S.J. Johnsen

2013-01-01T23:59:59.000Z

412

Bacterial Fouling in a Model Core System  

Science Journals Connector (OSTI)

...to reduce permeability. Therefore...aspects of reservoir rock, without...an "open" sandstone. Thus, especially...changes in permeability that occurred...22). The porosity of the cores...liquid storage reservoir with a capacity...

J. C. Shaw; B. Bramhill; N. C. Wardlaw; J. W. Costerton

1985-03-01T23:59:59.000Z

413

Crystallization of the crenarchaeal SRP core  

Science Journals Connector (OSTI)

The conserved ribonucleoprotein core of the signal recognition particle (SRP) has been crystallized. Both crystal forms are highly twinned and an explanation for the possible tetartohedral twinning is presented.

Rosendal, K.R.

2003-12-18T23:59:59.000Z

414

Xenon Oscillations in a VVÉR-1000 Core  

Science Journals Connector (OSTI)

Xenon oscillations – periodic redistribution of the power over ... the large size of this core. The xenon oscillations can be conventionally divided into axial, radial ... paper, methods are described for initiat...

V. A. Tereshonok; V. S. Stepanov; V. P. Povarov; O. V. Lebedev…

2002-10-01T23:59:59.000Z

415

Environmental impact of various kayak core materials  

E-Print Network (OSTI)

This thesis compares the environmental impact of fiberglass, Kevlar, carbon fiber, and cork. A kayak company is interested in using cork as a core material, and would like to claim that it is the most environmentally ...

Kirkland, David R. (David Roger)

2008-01-01T23:59:59.000Z

416

PRELIMINARY TIME ESTIMATES FOR CORING OPERATIONS  

E-Print Network (OSTI)

EQUATIONS 17 FIGURE 1. DRILL STRING ROUND TRIP 19 FIGURE 2. STANDARD ROTARY CORING (RCB) WIRELINE TRIP 21) WIRELINE TRIP 25 FIGURE 5. ESTIMATED RIGGING, WIRELINE, AND SCANNING TIME FOR REENTRY. 27 #12;Preliminary

417

MagLab - Magnetic Core Memory Tutorial  

NLE Websites -- All DOE Office Websites (Extended Search)

grid is made up of wires. The purpose of the horizontal and vertical X and Y Address Lines is to direct current to a specific core. The purpose of the diagonal Sense Lines is to...

418

Armor systems including coated core materials  

DOE Patents (OSTI)

An armor system and method involves providing a core material and a stream of atomized coating material that comprises a liquid fraction and a solid fraction. An initial layer is deposited on the core material by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is less than the liquid fraction of the stream of atomized coating material on a weight basis. An outer layer is then deposited on the initial layer by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is greater than the liquid fraction of the stream of atomized coating material on a weight basis.

2013-10-08T23:59:59.000Z

419

Armor systems including coated core materials  

DOE Patents (OSTI)

An armor system and method involves providing a core material and a stream of atomized coating material that comprises a liquid fraction and a solid fraction. An initial layer is deposited on the core material by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is less than the liquid fraction of the stream of atomized coating material on a weight basis. An outer layer is then deposited on the initial layer by positioning the core material in the stream of atomized coating material wherein the solid fraction of the stream of atomized coating material is greater than the liquid fraction of the stream of atomized coating material on a weight basis.

Chu, Henry S. (Idaho Falls, ID); Lillo, Thomas M. (Idaho Falls, ID); McHugh, Kevin M. (Idaho Falls, ID)

2012-07-31T23:59:59.000Z

420

Uranium - thorium series study on Yucatan slope cores  

E-Print Network (OSTI)

substance and a corresponding enrichment in another. Soils, on being eroded, 14 adhorb dissolved uranium from runoff and ocean water and show a progressive change in U "/U activity ratios from 0. 9 in soils to 0, 95 in river muds to 1. 15 in recently... URANIUM ? THORIUM SERIES STUDY ON YUCATAN SLOPE CORES A Thesis by Mary Elizabeth Exner Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE August, 1972...

Exner, Mary Elizabeth

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Hydrocarbons in age-dated sediment cores from two basins in the Southern California Bight  

Science Journals Connector (OSTI)

The distributions of hydrocarbons in sediment cores dated by 210Pb (1845–1977) from San Pedro and San Nicolas Basins in the Southern California Bight have been determined by gas Chromatographic and combined gas chromatographic-mass spectrometric analysis. The chromatograms of the hydrocarbons contain peaks of resolved alkanes and cycloalkanes, as well as an unresolved complex mixture which decrease in content with increasing depth in both of the cores. The concentrations of o,p' andp,p'-DDE are highest in the top 50 mm of the San Pedro core section. The 45–50 mm segment of this core was deposited in the 1945–1950 period when DDT (the precursor of DDE compounds) came into common use. The relatively high content of hydrocarbons and DDE in this core is attributable to the proximity of the site to the San Pedro Harbor which receives petroleum residues from shipping, sewage outfalls and industrial effluents. The presence of only traces of DDE throughout the San Nicolas core, and the low hydrocarbon content are explainable by the greater distance of this basin from anthropogenic inputs and probably a greater rate of degradation of deposited organic matter during bioturbation. ?13C, ?15N and electron-spin resonance analyses of kerogens and humic substances in these cores, indicate that most of this organic matter in these sediments is of a marine origin.

M.I Venkatesan; S Brenner; E Ruth; J Bonilla; I.R Kaplan

1980-01-01T23:59:59.000Z

422

Panelized wall system with foam core insulation  

DOE Patents (OSTI)

A wall system includes a plurality of wall members, the wall members having a first metal panel, a second metal panel, and an insulating core between the first panel and the second panel. At least one of the first panel and the second panel include ridge portions. The insulating core can be a foam, such as a polyurethane foam. The foam can include at least one opacifier to improve the k-factor of the foam.

Kosny, Jan (Oak Ridge, TN); Gaskin, Sally (Houston, TX)

2009-10-20T23:59:59.000Z

423

NETL: Control Technology: ElectroCore Separator  

NLE Websites -- All DOE Office Websites (Extended Search)

ElectroCore Separator ElectroCore Separator LSR Technologies and its subcontractors designed and installed a 8,500 m3/hr (5,000 acfm) Advanced ElectroCore system and a dry sulfur scrubber to test it using an exhaust gas slipstream at Alabama Power Company's Gaston Steam Plant. Shakedown is scheduled for August 15, 2001. The exhaust gas will be from Unit #4 of a 270 MWe sub-critical, pulverized coal boiler burning a low-sulfur bituminous coal. The Advanced ElectroCore system will consist of a conventional upstream ESP, a dry SO2 scrubber, a particle precharger and an Advanced ElectroCore separator. Particle concentrations and size distributions will be measured at the ESP inlet, at the dry scrubber outlet and at the ElectroCore outlet. The concentration of 12 common HAPs will be measured at these locations as well. For purposes of project organization and monitoring, the work will be divided into nine (9) tasks described below.

424

Formed Core Sampler Hydraulic Conductivity Testing  

SciTech Connect

A full-scale formed core sampler was designed and functionally tested for use in the Saltstone Disposal Facility (SDF). Savannah River National Laboratory (SRNL) was requested to compare properties of the formed core samples and core drilled samples taken from adjacent areas in the full-scale sampler. While several physical properties were evaluated, the primary property of interest was hydraulic conductivity. Differences in hydraulic conductivity between the samples from the formed core sampler and those representing the bulk material were noted with respect to the initial handling and storage of the samples. Due to testing conditions, the site port samples were exposed to uncontrolled temperature and humidity conditions prior to testing whereas the formed core samples were kept in sealed containers with minimal exposure to an uncontrolled environment prior to testing. Based on the results of the testing, no significant differences in porosity or density were found between the formed core samples and those representing the bulk material in the test stand.

Miller, D. H.; Reigel, M. M.

2012-09-25T23:59:59.000Z

425

Solid oxide fuel cell having monolithic core  

DOE Patents (OSTI)

A solid oxide fuel cell is described for electrochemically combining fuel and oxidant for generating galvanic output, wherein the cell core has an array of electrolyte and interconnect walls that are substantially devoid of any composite inert materials for support. Instead, the core is monolithic, where each electrolyte wall consists of thin layers of cathode and anode materials sandwiching a thin layer of electrolyte material therebetween. The electrolyte walls are arranged and backfolded between adjacent interconnect walls operable to define a plurality of core passageways alternately arranged where the inside faces thereof have only the anode material or only the cathode material exposed. Means direct the fuel to the anode-exposed core passageways and means direct the oxidant to the anode-exposed core passageways and means direct the oxidant to the cathode-exposed core passageway; and means also direct the galvanic output to an exterior circuit. Each layer of the electrolyte and interconnect materials is of the order of 0.002 to 0.01 cm thick; and each layer of the cathode and anode materials is of the order of 0.002 to 0.05 cm thick.

Ackerman, J.P.; Young, J.E.

1983-10-12T23:59:59.000Z

426

Early Type Galaxy Core Phase Densities  

E-Print Network (OSTI)

Early type galaxies, ellipticals and S0's, have two distinct core density profiles, either a power law or nearly flat in projection. The two core types are distributed with substantial overlap in luminosity, radius, mass and velocity dispersion, however, the cores separate into two distinct distributions in their coarse grain phase density, Q_0 = rho/sigma^3,suggesting that dynamical processes played a dominant role in their origin. The transition phase density separating the two elliptical types is approximately 0.003 M_sun pc^-3 km^-3 s^3,. The Q_0*M_c^2 vs M_c diagram shows that globular clusters, nuclear star clusters and power-law cores fall on what is likely a "collisional" sequence of inspiralling globular clusters. on which the relative core mass excess varies as the bulk stellar mass to the -0.34+/-0.08 power, close to predictions, albeit with a correlation coefficient of -0.46. Both power-law and cored galaxies lie on a single sequence of approximately Q_0 ~r_c^-2.2, suggesting that transport proces...

Carlbeg, Raymond

2014-01-01T23:59:59.000Z

427

Modern Records of Atmospheric Nitrous Oxide (N2O) and a 2000-year Ice-core  

NLE Websites -- All DOE Office Websites (Extended Search)

Modern Records of Atmospheric Nitrous Oxide (N2O) and a 2000-year Ice-core Modern Records of Atmospheric Nitrous Oxide (N2O) and a 2000-year Ice-core Record from Law Dome, Antarctica Introduction This page provides an introduction and links to records of atmospheric nitrous oxide (N2O) over the last 2000 years, emphasizing large data bases each representing currently active stations. Records in recent decades (time period depending on location) have been obtained from samples of ambient-air at remote locations, which represent changing global atmospheric conditions rather than influences of local sources. The longer (2000-year) record is from the Law Dome ice core in Antarctica. The ice-core record has been merged with modern annual data from Cape Grim, Tasmania to provide a 2000-year time series of annual values. A spline function has been fit to the data to provide a continuous time series of

428

Chains of dense cores in the Taurus L1495/B213 complex  

E-Print Network (OSTI)

(Abridged) We study the kinematics of the dense gas in the Taurus L1495/B213 filamentary region to investigate the mechanism of core formation. We use observations of N2H+(1-0) and C18O(2-1) carried out with the IRAM 30m telescope. We find that the dense cores in L1495/B213 are significantly clustered in linear chain-like groups about 0.5pc long. The internal motions in these chains are mostly subsonic and the velocity is continuous, indicating that turbulence dissipation in the cloud has occurred at the scale of the chains and not at the smaller scale of the individual cores. The chains also present an approximately constant abundance of N2H+ and radial intensity profiles that can be modeled with a density law that follows a softened power law. A simple analysis of the spacing between the cores using an isothermal cylinder model indicates that the cores have likely formed by gravitational fragmentation of velocity-coherent filaments. Combining our analysis of the cores with our previous study of the large-sc...

Tafalla, M

2014-01-01T23:59:59.000Z

429

The relation between extracurricular activities with academic and social competencies in school age children: a meta-analysis  

E-Print Network (OSTI)

/drama, student government, and Future Farmers of America. For the purposes of this study, extracurricular activities directly related to school curricula (i.e. Spanish club, tutoring, honor societies) were excluded. Academic Achievement The completion...

Lewis, Charla P.

2005-11-01T23:59:59.000Z

430

Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Observation of Waste Treatment and Immobilization Plant LAW Melter and Melter Off-gas Process System Hazards Analysis _Oct 21-31  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-10-21 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Observation of Waste Treatment and Immobilization Plant Low Activity Waste Melter and Melter Off-gas Process System Hazards Analysis Activities Dates of Activity : 10/21/13 - 10/31/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS), Office of Safety and Emergency Management Evaluations (Independent Oversight) reviewed the Insight software hazard evaluation (HE) tables for hazard analysis (HA) generated to date for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter and Off-gas systems, observed a

431

Synthesis of Lutetium Phosphate/Apoferritin Core-Shell Nanoparticles...  

NLE Websites -- All DOE Office Websites (Extended Search)

Core-Shell Nanoparticles for Potential Applications in Radioimmunoimaging and Synthesis of Lutetium PhosphateApoferritin Core-Shell Nanoparticles for Potential...

432

DOE CYBER SECURITY EBK: MINIMUM CORE COMPETENCY TRAINING REQUIREMENTS...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

DOE CYBER SECURITY EBK: MINIMUM CORE COMPETENCY TRAINING REQUIREMENTS DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS: CA Cybersecurity Program Manager (CSPM...

433

Smart” Diblock Copolymers as Templates for Magnetic-Core...  

NLE Websites -- All DOE Office Websites (Extended Search)

Smart” Diblock Copolymers as Templates for Magnetic-Core Gold-Shell Nanoparticle Synthesis. Smart” Diblock Copolymers as Templates for Magnetic-Core Gold-Shell...

434

OpenStudio Core Development and Deployment Support - 2014 BTO...  

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

Core Development and Deployment Support - 2014 BTO Peer Review OpenStudio Core Development and Deployment Support - 2014 BTO Peer Review Presenter: Larry Brackney, National...

435

E-Print Network 3.0 - air-suspended solid-core fibers Sample...  

NLE Websites -- All DOE Office Websites (Extended Search)

solid core subwavelength ber (a) and suspended porous core... December 2011 | 41 TERAHERTZ Suspended Core Subwavelength Plastic ... Source: Skorobogatiy, Maksim -...

436

Trace Analysis of Polar Pharmaceuticals in Wastewater by LC-MS-MS: Comparison of Membrane Bioreactor and Activated Sludge Systems  

Science Journals Connector (OSTI)

......Analysis of Polar Pharmaceuticals in Wastewater by LC-MS-MS: Comparison...compounds in three different wastewater recycling schemes in Australia. Chemosphere...fields irrigated with treated wastewater. J. Agric. Food. Chem. 53......

Mary Dawn Celiz; Sandra Pérez; Damià Barceló; Diana S. Aga

2009-01-01T23:59:59.000Z

437

Isotopic Analysis At Valles Caldera - Sulphur Springs Area (Woldegabriel &  

Open Energy Info (EERE)

Valles Caldera - Sulphur Springs Area (Woldegabriel & Valles Caldera - Sulphur Springs Area (Woldegabriel & Goff, 1992) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis At Valles Caldera - Sulphur Springs Area (Woldegabriel & Goff, 1992) Exploration Activity Details Location Valles Caldera - Sulphur Springs Area Exploration Technique Isotopic Analysis Activity Date Usefulness not indicated DOE-funding Unknown Notes Useful for age determinations - not indicated is useful for exploration. References Giday WoldeGabriel, Fraser Goff (1992) K-Ar Dates Of Hydrothermal Clays From Core Hole Vc-2B, Valles Caldera, New Mexico And Their Relation To Alteration In A Large Hydrothermal System Retrieved from "http://en.openei.org/w/index.php?title=Isotopic_Analysis_At_Valles_Caldera_-_Sulphur_Springs_Area_(Woldegabriel_%26_Goff,_1992)&oldid=510971"

438

Status of axial heterogeneous liquid-metal fast breeder reactor core design studies and research and development  

SciTech Connect

The current status of axial heterogeneous core (AHC) design development in Japan, which consists of an AHC core design in a pool-type demonstration fast breeder reactor (DFBR) and research and development activities supporting AHC core design, is presented. The DFBR core design objectives developed by The Japan Atomic Power Company include (a) favorable core seismic response, (b) core compactness, (c) high availability, and (d) lower fuel cycle cost. The AHC concept was selected as a reference pool-type DFBR core because it met these objectives more suitably than the homogeneous core (HOC). The AHC core layouts were optimized emphasizing the reduction of the burnup reactivity swing, peak fast fluence, and power peaking. The key performance parameters resulting from the AHC, such as flat axial power/flux distribution, lower peak fast fluence, lower burnup reactivity swing, etc., were evaluated in comparison with the HOC. The critical experiments at the Japan Atomic Energy Research Institute's Fast Critical Assembly facility demonstrate the key AHC performance characteristics. The large AHC engineering benchmark experiments using the zero-power plutonium reactor and the AHC fuel pin irradiation test program using the JOYO reactor are also presented.

Nakagawa, H.; Inagaki, T.; Yoshimi, H.; Shirakata, K.; Watari, Y.; Suzuki, M.; Inoue, K.

1988-11-01T23:59:59.000Z

439

Model-based Analysis of HER Activation in Cells Co-Expressing EGFR, HER2 and HER3.  

SciTech Connect

The HER/ErbB family of receptor tyrosine kinases drive critical responses in normal physiology and cancer, and the expression levels of the various HER receptors are critical determinants of clinical outcomes. HER activation is driven by the formation of various dimer complexes between members of this receptor family. The HER dimer types can have differential effects on downstream signaling and phenotypic outcomes. We constructed an integrated mathematical model of HER activation and trafficking to quantitatively link receptor expression levels to dimerization and activation. We parameterized the model with a comprehensive set of HER phosphorylation and abundance data collected in a panel of human mammary epithelial cells expressing varying levels of EGFR, HER2 and HER3. Although parameter estimation yielded multiple solutions, predictions for dimer phosphorylation were in agreement with each other. We validated the model using experiments where pertuzumab was used to block HER2 dimerization. We used the model to predict HER dimerization and activation patterns in a panel of epithelial cells lines with known HER expression levels. Simulations over the range of expression levels seen in various cell lines indicate that: i) EGFR phosphorylation is driven by HER1/1 and HER1/2 dimers, and not HER1/3 dimers, ii) HER1/2 and HER2/3 dimers both contribute significantly to HER2 activation with the EGFR expression level determining the relative importance of these species, and iii) the HER2/3 dimer is largely responsible for HER3 activation. The model can be used to predict phosphorylated dimer levels for any given HER expression profile. This information in turn can be used to quantify the potencies of the various HER dimers, and can potentially inform personalized therapeutic approaches.

Shankaran, Harish; Zhang, Yi; Tan, Yunbing; Resat, Haluk

2013-08-22T23:59:59.000Z

440

Core Holes At Steamboat Springs Area (Warpinski, Et Al., 2002) | Open  

Open Energy Info (EERE)

2) 2) Exploration Activity Details Location Steamboat Springs Area Exploration Technique Core Holes Activity Date Usefulness not indicated DOE-funding Unknown Notes Stratigraphic slim hole 24-33 was drilled in a lease area south of current production during March 2001. The well was continuously cored from 235 m to the total depth of 610 m. Several fracture zones were encountered with noticeably large fracture apertures and the maximum recorded temperature was comparable to nearby productive wells. A second well, slim hole 12-33, was drilled to a total depth of 297 m during April 2001. Continuous core was taken from 152 m to total depth. Numerous open fractures were also observed in this well and the maximum recorded temperature was similar to the 24-33 well.

Note: This page contains sample records for the topic "activity core analysis" 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

GIZ-Thailand-National energy efficiency plan as a core element for an  

Open Energy Info (EERE)

Thailand-National energy efficiency plan as a core element for an Thailand-National energy efficiency plan as a core element for an activity- and evidence-based mitigation strategy Jump to: navigation, search Name GIZ-Thailand-National energy efficiency plan as a core element for an activity- and evidence-based mitigation strategy Agency/Company /Organization Deutsche Gesellschaft für Internationale Zusammenarbeit (GIZ) GmbH Sector Climate Focus Area Renewable Energy, Energy Efficiency Topics Low emission development planning, -LEDS, -NAMA, Technology characterizations Website http://www.gtz.de/en/themen/28 Program End 2015 Country Thailand South-Eastern Asia References Deutsche Gesellschaft für Internationale Zusammenarbeit (GIZ) GmbH[1] Program Overview The project will support the formulation and implementation of a national

442

Development and Application of Hepatitis C Reporter Viruses with Genotype 1 to 7 Core-Nonstructural Protein 2 (NS2) Expressing Fluorescent Proteins or Luciferase in Modified JFH1 NS5A  

Science Journals Connector (OSTI)

...responses of genotype 1 to 7 core-NS2 RLuc viruses to IFN-alfa-2b...intergenotypic recombinants with core-NS2 of genotype 1 to 7 reference...genotype (isolate) of core-NS2: 1a(H77), 1a(TN), 1b...analysis using Sequencher (Gene Codes Corporation). HCV sequences...

Judith M. Gottwein; Tanja B. Jensen; Christian K. Mathiesen; Philip Meuleman; Stephanie B. N. Serre; Jacob B. Lademann; Lubna Ghanem; Troels K. H. Scheel; Geert Leroux-Roels; Jens Bukh

2011-06-22T23:59:59.000Z

443

Modeling and analysis of early events in T-lymphocyte antigen-activated intracellular-signaling pathways  

Science Journals Connector (OSTI)

The T-cell antigen-activated signaling pathway is a highly regulated intracellular biochemical system that is crucial for initiating an appropriate adaptive immune response. To improve the understanding of the complex regulatory mechanisms controlling ... Keywords: Bistability, Feedback regulation, Hysteresis, Mathematical modeling, T-cell signaling

Yanan Zheng; Venkataramanan Balakrishnan; Greg Buzzard; Robert Geahlen; Marietta Harrison; Ann Rundell

2005-12-01T23:59:59.000Z

444

Physical Activity Is Associated with Reduced Risk of Gastric Cancer: A Systematic Review and Meta-analysis  

Science Journals Connector (OSTI)

...modifiable aspect of energy expenditure, as...studies from the same Japan-Hawaii Cancer Study...with or without household) physical activity...Population; Japan (Japan Public Health Center...Population; Hawaii (Japan-Hawaii Cancer Study...172 Recreational (household) + occupational...

Siddharth Singh; Jithinraj Edakkanambeth Varayil; Swapna Devanna; Mohammad Hassan Murad; and Prasad G. Iyer

2014-01-01T23:59:59.000Z

445

Fragment Based Protein Active Site Analysis Using Markov Random Field Combinations of Stereochemical Feature-Based Classifications  

E-Print Network (OSTI)

of these methods have been able to account successfully for the diversity in the sequence and structural conformations observed in proteins that have the same function. An additional complication is the flexibility in both the protein active site and the ligand...

Pai Karkala, Reetal

2010-07-14T23:59:59.000Z

446

Core Analysis For The Development And Constraint Of Physical...  

Open Energy Info (EERE)

a fundamental understanding of the geophysical properties of reservoir rocks and fracture systems. Even in the best of circumstances, spatial variability in porosity, fracture...

447

Analysis and Stability of Bent–Core Liquid Crystal Fibers  

E-Print Network (OSTI)

Feb 21, 2011 ... Here Hl(E) is the l-dimensional Hausdorff measure of E. Elastic distortions. ... The energy required to create the interfaces at ?0 and ?1 is taken as. FSu = ?. ?0 ?0 +. ? ..... is a standard annulus, Br(o) \\ Br0 (o). Theorem 2.6.

2011-02-21T23:59:59.000Z

448

Core Analysis At Long Valley Caldera Geothermal Area (Sorey,...  

Open Energy Info (EERE)

studies, and seem to prove useful in most cases (Flexser, 1991; Goff et al., 1991; Smith and Suemnicht, 1991). Results from these studies are also summarized in Sorey et al....

449

CA Core Competency Worksheet August 2010  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CA Core Competency Worksheet August 2010 CA Core Competency Worksheet August 2010 1 DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS Key Cyber Security Role: Certification Agent (CA) (Also referred to as Security Control Assessor) Role Definition: The CA is the individual responsible for assessing the management, operational, assurance, and technical security controls implemented on an information system via security testing and evaluation (ST&E) methods. This individual must be independent of system development, operation, and deficiency mitigation. Competency Area: Data Security Functional Requirement: Design Competency Definition: Refers to the application of the principles, policies, and procedures necessary to ensure the confidentiality, integrity, availability, and privacy of data in all forms of media (i.e., electronic

450

Surface preparation of the S-1 Spheromak flux core liner  

Science Journals Connector (OSTI)

Different methods of preparing the S-1 Spheromak flux core liner for exposure to plasma (i.e. cleaning and polishing techniques) were studied with the goal of reducing the net impurity resources available for contaminating the plasma during Spheromak formation. The S-1 Inconel 601 liner is described together with an analysis of topography and surface and/or near-surface composition of various Inconel samples subjected to mechanical, electrochemical and chemical preparation techniques. The general conclusion based on the analysis of the samples is that the different techniques are roughly competitive on the basis of surface composition, while less preparation tends to give better results in terms of the criteria mentioned above. This has helped to simplify the liner preparation.

R. Moore; C. Macey; S. Cohen; A. Janos

1984-01-01T23:59:59.000Z

451

Analytical Chemistry Core Capability Assessment - Preliminary Report  

SciTech Connect

The concept of 'core capability' can be nebulous one. Even at a fairly specific level, where core capability equals maintaining essential services, it is highly dependent upon the perspective of the requestor. Samples are submitted to analytical services because the requesters do not have the capability to conduct adequate analyses themselves. Some requests are for general chemical information in support of R and D, process control, or process improvement. Many analyses, however, are part of a product certification package and must comply with higher-level customer quality assurance requirements. So which services are essential to that customer - just those for product certification? Does the customer also (indirectly) need services that support process control and improvement? And what is the timeframe? Capability is often expressed in terms of the currently utilized procedures, and most programmatic customers can only plan a few years out, at best. But should core capability consider the long term where new technologies, aging facilities, and personnel replacements must be considered? These questions, and a multitude of others, explain why attempts to gain long-term consensus on the definition of core capability have consistently failed. This preliminary report will not try to define core capability for any specific program or set of programs. Instead, it will try to address the underlying concerns that drive the desire to determine core capability. Essentially, programmatic customers want to be able to call upon analytical chemistry services to provide all the assays they need, and they don't want to pay for analytical chemistry services they don't currently use (or use infrequently). This report will focus on explaining how the current analytical capabilities and methods evolved to serve a variety of needs with a focus on why some analytes have multiple analytical techniques, and what determines the infrastructure for these analyses. This information will be useful in defining a roadmap for what future capability needs to look like.

Barr, Mary E. [Los Alamos National Laboratory; Farish, Thomas J. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

452

Reactor Core Assembly - HFIR Technical Parameters | ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Home › Facilities › HFIR › Reactor Core Assembly Home › Facilities › HFIR › Reactor Core Assembly Reactor Core Assembly The reactor core assembly is contained in an 8-ft (2.44-m)-diameter pressure vessel located in a pool of water. The top of the pressure vessel is 17 ft (5.18 m) below the pool surface, and the reactor horizontal mid-plane is 27.5 ft (8.38 m) below the pool surface. The control plate drive mechanisms are located in a subpile room beneath the pressure vessel. These features provide the necessary shielding for working above the reactor core and greatly facilitate access to the pressure vessel, core, and reflector regions. In-core irradiation and experiment locations (cross section at horizontal midplane) Reactor core assembly Reactor core assembly: (1) in-core irradiation and experiment locations,

453

SECA Core Technology Program Seal Workshop  

NLE Websites -- All DOE Office Websites (Extended Search)

SECA Core Technology Program Seal Workshop Workshop held at Hyatt Regency, San Antonio August 10, 2007 Workshop organized by: Dr. Ayyakkannu Manivannan, National Energy technology Laboratory Morgantown, WV Dr. Prabhakar Singh Pacific Northwest National Laboratory Richland, WA 1 2 Table of Content * Executive Summary * Meeting Agenda * Presentations * List of Attendees 3 Executive Summary SECA Core Technology Program (SECA CTP) led workshop on the topical area titled "SOFC seal: Technology, Challenges and Future Directions" was held on August 10, 2007 at Hyatt Regency, San Antonio, TX. The workshop was attended by scientists and engineers presently involved in the development, engineering, fabrication, and testing of

454

A new annotation system based on a semantic analysis of a learner's annotative activity to invoke web services  

Science Journals Connector (OSTI)

Many annotation systems proposed in the literature suffer from an under-exploitation of the annotation's semantic at the level of the assistance presented to the learner during annotative activity. Thus, these tools offer the same classic features to its users, such as management, search, sharing and storage of annotations. In this paper, we propose a new annotation system which differs in its novel features. The system tries to assist the learner via web services during learning activities. Therefore, from a user's annotation, our system is able to interpret a goal implicitly expressed and tries to discover and invoke a web service that can meet this annotation's objective. This system is based on an annotation model composed of an ontology and pattern annotation. This enrichment will provide advantages for both the provider, who will find his service within the consumer's reach, and the learner, who will have at his disposal an intelligent annotation tool.

Anis Kalboussi; Omar Mazhoud; Nizar Omheni; Ahmed Hadj Kacem

2014-01-01T23:59:59.000Z

455

Effects of preservice and inservice teacher knowledge on the analysis of spelling errors and choice of appropriate instructional activities  

E-Print Network (OSTI)

knowledge of literacy-related content. McCutchen, Harry, et al. examined teacher literacy-related content knowledge, teacher practice, and student achievement of 59 kindergarten, first-, and second-grade teachers. They found a significant correlation... between teachers? knowledge of phonology and their use of explicit phonological awareness activities. In terms of student learning, the researchers found a significant correlation between a kindergarten teacher?s knowledge of phonology and use...

Carreker, Suzanne Huff

2009-05-15T23:59:59.000Z

456

Performance Analysis of Positive-feedback-based Active Anti-islanding Schemes for Inverter-Based Distributed Generators  

SciTech Connect

Recently proposed positive-feedback-based anti-islanding schemes (AI) are highly effective in preventing islanding without causing any degradation in power quality. This paper aims to analyze the performance of these schemes quantitatively in the context of the dynamic models of inverter-based distributed generators (DG). In this study, the characteristics of these active anti-islanding methods are discussed and design guidelines are derived.

Du, Pengwei; Aponte, Erick E.; Nelson, J. Keith

2010-06-14T23:59:59.000Z

457

Core-Protected Platinum Monolayer Shell High-Stability Electrocatalysts for Fuel-Cell Cathodes  

SciTech Connect

Platinum monolayers can act as shells for palladium nanoparticles to lead to electrocatalysts with high activities and an ultralow platinum content, but high platinum utilization. The stability derives from the core protecting the shell from dissolution. In fuel-cell tests, no loss of platinum was observed in 200,000 potential cycles, whereas loss of palladium was significant.

K Sasaki; H Naohara; Y Cai; Y Choi; P Liu; M Vukmirovic; J Wang; R Adzic

2011-12-31T23:59:59.000Z

458

Control rod worth and related nuclear characteristics of an axially heterogeneous liquidmetal fast breeder reactor core  

SciTech Connect

An axially heterogeneous core (AHC) concept is applied to a 1000-MW(electric)-class tank-type liquidmetal fast breeder reactor (LMFBR). This AHC is characterized by a disk-shaped internal blanket with a radial thickness adjustment at the core midplane. The nuclear characteristics connected with control rod worth of the AHC are analyzed and compared with those of a homogeneous core (HOC) of the same power rating. The neutronics analysis shows that the reactivity insertion due to the vertical displacement of control rods relative to the core, which is an important safety characteristic of a tank-type LMFBR core, is significantly decreased in the AHC because of the reduced control worth requirement and smaller peakto-average differential worth in the primary control system. This allows the AHC to have a vertical displacement 50% greater than that of the HOC and may offer less rigid design conditions for roof slab stiffness and core support systems in a tank-type LMFBR. A reduction in the number of primary control rods is also possible because of a smaller control worth requirement and a better power peaking factor. The work was sponsored by a federation of Japanese electric power companies and performed under the guidance of the fast breeder reactor project office.

Kawashima, K.; Inayaki, T.; Inoue, K.; Kaneto, K.

1985-08-01T23:59:59.000Z

459

Utilization of Modified CoreGRID Ontology in an Agent-based Grid Resource Management System  

E-Print Network (OSTI)

-driven, and initially was based on an in-house developed mini-ontology of the Grid. Our re- cent analysis has indicatedUtilization of Modified CoreGRID Ontology in an Agent-based Grid Resource Management System M, Morocco Abstract The Agents in Grid project is devoted to the de- velopment of an agent-based intelligent

Paris-Sud XI, Université de

460

Review of pertinent thermal-hydraulic data for LMFBR core natural circulation analyses  

SciTech Connect

A literature review and summary of significant data is presented relative to LMFBR core natural convection cooling analysis. First, a brief review of computer codes and respective input data needs is made, significant data areas are then addressed and data for verifying the code calculations are described. Recommendations and conclusions with regard to the data are included.

Bishop, A. A.; Coffield, Jr., R. D.; Markley, R. A.

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity core analysis" 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

Isotopic Analysis At Kilauea East Rift Area (Quane, Et Al., 2000) | Open  

Open Energy Info (EERE)

source source History View New Pages Recent Changes All Special Pages Semantic Search/Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon » Isotopic Analysis At Kilauea East Rift Area (Quane, Et Al., 2000) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Isotopic Analysis- Rock At Kilauea East Rift Area (Quane, Et Al., 2000) Exploration Activity Details Location Kilauea East Rift Area Exploration Technique Isotopic Analysis- Rock Activity Date Usefulness not indicated DOE-funding Unknown References S. L. Quane, M. O. Garcia, H. Guillou, T. P. Hulsebosch (2000) Magmatic History Of The East Rift Zone Of Kilauea Volcano, Hawaii Based On Drill Core From Soh 1 Retrieved from "http://en.openei.org/w/index.php?title=Isotopic_Analysis_At_Kilauea_East_Rift_Area_(Quane,_Et_Al.,_2000)&oldid=687735"

462

Germania-Based Core Optical Fibers  

Science Journals Connector (OSTI)

Germania-glass-based core silica glass cladding single-mode fibers (Delta n up to 0.143) with a minimum loss of 20 dB/km at 1.9 µm were fabricated by the modified chemical vapor...

Dianov, Evgeny M; Mashinsky, Valery M

2005-01-01T23:59:59.000Z

463

Introduction What is the Common Core Curriculum?  

E-Print Network (OSTI)

been, and continue to be, of deeply profound significance to humankind, the core intellectual skills education, it is important that you choose your courses carefully. To this end, the handbook provides you. These learning outcomes are statements that specify precisely what you should be able to do at the end

Leung, Ka-Cheong

464

Introduction What is the Common Core Curriculum?  

E-Print Network (OSTI)

, it is important that you choose your courses carefully. To this end, the handbook provides you with detailed profound significance to humankind, the core intellectual skills that all HKU undergraduates should acquire are statements that specify precisely what you should be able to do at the end of a course, usually expressed

Leung, Ka-Cheong

465

Improving the economics of PWR cores  

SciTech Connect

Economic fuel cycles have become of paramount importance to the nuclear power industry due to the increasing impact of deregulation and competition. This paper describes the PWR core design techniques being employed at Entergy in the quest to meet the ever-decreasing fuel cost targets for these units.

Ober, T.G. [Entergy Operations, Jackson, MS (United States)

1996-08-01T23:59:59.000Z

466

Sediment resuspension effects on alkaline phosphatase activity  

Science Journals Connector (OSTI)

Sediment cores, including the associated lake water, were collected from a shallow hypereutrophic lake located in central Florida. Alkaline phosphatase activity (APA) was measured as an indicator of potential org...

S. Newman; K. R. Reddy

1992-10-07T23:59:59.000Z

467

Time-dependent restricted-active-space self-consistent-field theory for laser-driven many-electron dynamics. II. Extended formulation and numerical analysis  

E-Print Network (OSTI)

The time-dependent restricted-active-space self-consistent-field (TD-RASSCF) method is formulated based on the TD variational principle. In analogy with the configuration-interaction singles (CIS), singles-and-doubles (CISD), singles-doubles-and-triples (CISDT) methods in quantum chemistry, the TD-RASSCF-S, -SD, and -SDT methods are introduced as extensions of the TD-RASSCF dou- bles (-D) method [Phys. Rev. A 87, 062511 (2013)]. Based on an analysis of the numerical cost and test calculations for one-dimensional (1D) models of atomic helium, beryllium, and carbon, it is shown that the TD-RASSCF-S and -D methods are computationally feasible for systems with many electrons and more accurate than the TD Hartree-Fock (TDHF) and TDCIS methods. In addition to the discussion of methodology, an analysis of electron dynamics in the high-order harmonic generation (HHG) process is presented. For the 1D beryllium atom, a state-resolved analysis of the HHG spectrum based on the time-independent HF orbitals shows that while only single-orbital excitations are needed in the region below the cutoff, single- and double-orbital excitations are es- sential beyond, where accordingly the single-active-electron (SAE) approximation and the TDCIS method break down. On the other hand, the TD-RASSCF-S and -D methods accurately describe the multi-orbital excitation processes throughout the entire region of the HHG spectrum. For the 1D carbon atom, our calculations show that multi-orbital excitations are essential in the HHG process even below the cutoff. Hence, in this test system a very accurate treatment of electron correlation is required. The TD-RASSCF-S and -D approaches meet this demand, while the SAE approximation and the TDCIS method are inadequate.

Haruhide Miyagi; Lars Bojer Madsen

2014-05-21T23:59:59.000Z

468

Core Overshoot: An Improved Treatment and Constraints from Seismic Data  

E-Print Network (OSTI)

We present a comprehensive set of stellar evolution models for Procyon A in an effort to guide future measurements of both traditional stellar parameters and seismic frequencies towards constraining the amount of core overshoot in Procyon A and possibly other stars. Current observational measurements of Procyon A when combined with traditional stellar modeling only place a large upper limit on overshoot of alphaOV < 1.1. By carrying out a detailed pulsation analysis, we further demonstrate, how p- and g-mode averaged spacings can be used to gain better estimates of the core size. For both p- and g-modes, the frequency spacings for models without overshoot are clearly separated from the models with overshoot. In addition, measurements of the l=0 averaged small p-mode spacings could be used to establish Procyon A's evolutionary stage. For a fixed implementation of overshoot and under favorable circumstances, the g-mode spacings can be used to determine the overshoot extent to an accuracy of +-0.05 Hp. However, we stress that considerable confusion is added due to the unknown treatment of the overshoot region. This ambiguity might be removed by analyzing many different stars. A simple non-local convection theory developed by Kuhfuss is implemented in our stellar evolution code and contrasted with the traditional approaches. We show that this theory supports a moderate increase of the amount of convective overshoot with stellar mass of Delta(alphaOV) = +0.10 between 1.5 Msun and 15 Msun. This theory places an upper limit on Procyon A's core overshoot extent of ~0.4 Hp which matches the limit imposed by Roxburgh's integral criterion.

Christian W. Straka; Pierre Demarque; D. B. Guenther

2005-05-01T23:59:59.000Z

469

Analysis Of Macroscopic Fractures In Granite In The Hdr Geothermal Well  

Open Energy Info (EERE)

Macroscopic Fractures In Granite In The Hdr Geothermal Well Macroscopic Fractures In Granite In The Hdr Geothermal Well Eps-1, Soultz-Sous-Forets, France Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: Analysis Of Macroscopic Fractures In Granite In The Hdr Geothermal Well Eps-1, Soultz-Sous-Forets, France Details Activities (0) Areas (0) Regions (0) Abstract: An exhaustive analysis of 3000 macroscopic fractures encountered in the geothermal Hot Dry Rock borehole, EPS-1, located inside the Rhine graben (Soultz-sous-Forets, France), was done on a continuous core section over a depth interval from 1420 to 2230 m: 97% of the macroscopic structures were successfully reorientated with a good degree of confidence by comparison between core and acoustic borehole imagery. Detailed structural analysis of the fracture population indicates that fractures are

470

Assessment of Non-traditional Isotopic Ratios by Mass Spectrometry for Analysis of Nuclear Activities: Annual Report Year 2  

SciTech Connect

The objective of this work is to identify isotopic ratios suitable for analysis via mass spectrometry that distinguish between commercial nuclear reactor fuel cycles, fuel cycles for weapons grade plutonium, and products from nuclear weapons explosions. Methods will also be determined to distinguish the above from medical and industrial radionuclide sources. Mass spectrometry systems will be identified that are suitable for field measurement of such isotopes in an expedient manner. Significant progress has been made with this project within the past year: (1) Isotope production from commercial nuclear fuel cycles and nuclear weapons fuel cycles have been modeled with the ORIGEN and MCNPX codes. (2) MCNPX has been utilized to calculate isotopic inventories produced in a short burst fast bare sphere reactor (to approximate the signature of a nuclear weapon). (3) Isotopic ratios have been identified that are good for distinguishing between commercial and military fuel cycles as well as between nuclear weapons and commercial nuclear fuel cycles. (4) Mass spectrometry systems have been assessed for analysis of the fission products of interest. (5) A short-list of forensic ratios have been identified that are well suited for use in portable mass spectrometry systems.

Biegalski, S; Buchholz, B

2009-08-26T23:59:59.000Z

471

OPERATION OF A PUBLIC GEOLOGIC CORE AND SAMPLE REPOSITORY IN HOUSTON, TEXAS  

SciTech Connect

The Bureau of Economic Geology (BEG), building on an initial gift from BP, and with the continuing support of the Department of Energy (DOE), has established the first regional core and sample research center in Houston, Texas. The Houston Research Center (HRC) provides a state-of-the-art core layout facility, two fully equipped meeting rooms, and a comprehensive technical library, all available for public use. This document summarizes the activities, upkeep, increase in staff, and public impact on industry and the community that were accomplished at the Houston Research Center during its first two years of operation.

Scott W. Tinker; Laura C. Zahm; Beverly Blakeney DeJarnett

2004-04-01T23:59:59.000Z

472

Development and application of amorphous core-distribution transformers in Quebec  

SciTech Connect

This paper describes research and development activities at Hydro-Quebec over the last ten years for improving the efficiency of distribution transformers in Quebec. A shell-type (wound-core) design making optimum use of the properties of amorphous metals (Metglas TCA formerly known as Metglas 2605s-2, Allied Signal Inc., Morristown, NJ) was adopted. Dry and oil-cooled, amorphous-core transformer prototypes were built. The joint research and development project was initiated with Transformateurs Ferranti-Packard Ltee, a company of Rolls-Royce Industries Canada Inc., to build and test a few units of high performance transformers on the Hydro-Quebec power system.

Schulz, R.; Alexandrov, N.; Simoneau, R.; Roberge, R. [Hydro-Quebec Research Inst., Varennes, Quebec (Canada). Materials Technology Dept.; Tetreault, J. [Hydro-Quebec, Montreal, Quebec (Canada)

1995-08-01T23:59:59.000Z

473

Systems-level analysis of age-related macular degeneration reveals global biomarkers and phenotype-specific functional networks  

E-Print Network (OSTI)

derived from Homo sapiens, an IPA Core Analysis was run forin the RPE-choroid interactome, we restricted IPA results tothe highest scoring IPA network for a given Core Analysis.

2012-01-01T23:59:59.000Z

474

The Design and Analysis of Algorithms  

E-Print Network (OSTI)

serves a dual purpose: to cover core material in algorithms for graduate students in computer scienceThe Design and Analysis of Algorithms Dexter C. Kozen Cornell University December 1990 c Copyright in the design and analysis of algorithms. The material is thus a mixture of core and advanced topics. At rst I

Kozen, Dexter

475

Analysis and removal of assimilable organic carbon (AOC) from treated drinking water using a biological activated carbon filter system  

Science Journals Connector (OSTI)

Abstract This study is focused on reducing the concentration of assimilable organic carbon (AOC) in treated drinking water. Experiments were conducted to evaluate the efficiency of AOC removal by biological activated carbon filters (BACF) in a pilot-scale system. The results show that BACF reduces the total concentration of AOC. The concentration of AOC primarily indicates microorganism growth in a water supply network, and the amount of AOC in water is significantly reduced after BACF treatment. The predicted and measured values of AOC in output water treated by the BACF system show linear relationships, and their correlation coefficients are high. An AOC empirical equation was established by determining the relationship between water quality parameters such as total organic carbon, dissolved organic carbon, UV254, ammonia nitrogen, and total phosphorous. These findings may be relevant to conventional water treatment plants or to water distribution systems to provide treated drinking water with a high level of biological stability.

Jie-Chung Lou; Chih-Yuan Yang; Che-Jung Chang; Wei-Hsiang Chen; Wei-Bin Tseng; Jia-Yun Han

2014-01-01T23:59:59.000Z

476

OECD MCCI project long-term 2-D molten core concrete interaction test design report, Rev. 0. September 30, 2002.  

SciTech Connect

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core-concrete interaction when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. As a follow-on program to MACE, The Melt Coolability and Concrete Interaction Experiments (MCCI) project is conducting reactor material experiments and associated analysis to achieve the following two technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focuses on providing both confirmatory evidence and test data for the coolability mechanisms identified in MACE integral effects tests, and (2) address remaining uncertainties related to long-term two-dimensional molten core-concrete interactions under both wet and dry cavity conditions. Achievement of these two objectives will demonstrate the efficacy of severe accident management guidelines for existing plants, and provide the technical basis for better containment designs for future plants. In terms of the first program objective, the Small-Scale Water Ingression and Crust Strength (SSWICS) test series has been initiated to provide fundamental information on the ability of water to ingress into cracks and fissures that form in the debris during quench, thereby augmenting the otherwise conduction-limited heat transfer process. A test plan for Melt Eruption Separate Effects Tests (MESET) has also been developed to provide information on the extent of crust growth and melt eruptions as a function of gas sparging rate under well-controlled experiment conditions. In terms of the second program objective, the project Management Board (MB) has approved startup activities required to carry out experiments to address remaining uncertainties related to long-term two-dimensional molten core-concrete interaction. In particular, for both wet and dry cavity conditions, there is uncertainty insofar as evaluating the lateral vs. axial power split during a