Powered by Deep Web Technologies
Note: This page contains sample records for the topic "technique 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.


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 International Geothermal Area, Indonesia (Boitnott...  

Open Energy Info (EERE)

Indonesia (Boitnott, 2003) Exploration Activity Details Location International Geothermal Area Indonesia Exploration Technique Core Analysis Activity Date Usefulness not indicated...

3

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

Open Energy Info (EERE)

Alum Geothermal Area (DOE GTP) Exploration Activity Details Location Alum Geothermal Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding...

4

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

Open Energy Info (EERE)

Colrado Area (DOE GTP) Exploration Activity Details Location Colado Geothermal Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown...

5

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

Open Energy Info (EERE)

Mcgee Mountain Area (DOE GTP) Exploration Activity Details Location Mcgee Mountain Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding...

6

Core Analysis At Flint Geothermal Area (DOE GTP) | Open Energy...  

Open Energy Info (EERE)

Flint Geothermal Area (DOE GTP) Exploration Activity Details Location Flint Geothermal Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding...

7

HTTF Core Stress Analysis  

SciTech Connect

In accordance with the need to determine whether cracking of the ceramic core disks which will be constructed and used in the High Temperature Test Facility (HTTF) for heatup and cooldown experiments, a set of calculation were performed using Abaqus to investigate the thermal stresses levels and likelihood for cracking. The calculations showed that using the material properties provided for the Greencast 94F ceramic, cracking is predicted to occur. However, this modeling does not predict the size or length of the actual cracks. It is quite likely that cracks will be narrow with rough walls which would impede the flow of coolant gases entering the cracks. Based on data recorded at Oregon State University using Greencast 94F samples that were heated and cooled at prescribed rates, it was concluded that the likelihood that the cracks would be detrimental to the experimental objectives is small.

Brian D. Hawkes; Richard Schultz

2012-07-01T23:59:59.000Z

8

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

9

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

10

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

11

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

12

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

13

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"

14

Core Analysis At Black Warrior Area (DOE GTP) | Open Energy Informatio...  

Open Energy Info (EERE)

Black Warrior Area (DOE GTP) Exploration Activity Details Location Black Warrior Area Exploration Technique Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown...

15

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

16

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

17

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

18

Core Analysis At Geysers Area (Boitnott, 2003) | Open Energy...  

Open Energy Info (EERE)

Core Analysis Activity Date Usefulness not indicated DOE-funding Unknown References Greg N. Boitnott (2003) Core Analysis For The Development And Constraint Of Physical Models Of...

19

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

20

Multi-core Performance Analysis  

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

* Functional on SeaStar (XT) Machines * Performance AnalysisTuning - CrayPAT, Cray Apprentice 2 * Scientific Libraries 43 Cray Scientific Libraries 44 FFT CRAFFT FFTW P-CRAFFT...

Note: This page contains sample records for the topic "technique 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

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

22

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

23

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

24

Power excursion analysis for high burnup cores  

SciTech Connect

A study was undertaken of power excursions in high burnup cores. There were three objectives in this study. One was to identify boiling water reactor (BWR) and pressurized water reactor (PWR) transients in which there is significant energy deposition in the fuel. Another was to analyze the response of BWRs to the rod drop accident (RDA) and other transients in which there is a power excursion. The last objective was to investigate the sources of uncertainty in the RDA analysis. In a boiling water reactor, the events identified as having significant energy deposition in the fuel were a rod drop accident, a recirculation flow control failure, and the overpressure events; in a pressurized water reactor, they were a rod ejection accident and boron dilution events. The RDA analysis was done with RAMONA-4B, a computer code that models the space- dependent neutron kinetics throughout the core along with the thermal hydraulics in the core, vessel, and steamline. The results showed that the calculated maximum fuel enthalpy in high burnup fuel will be affected by core design, initial conditions, and modeling assumptions. The important uncertainties in each of these categories are discussed in the report.

Diamond, D.J.; Neymotin, L.; Kohut, P. [Brookhaven National Lab., Upton, NY (United States)

1996-02-01T23:59:59.000Z

25

Tools & Techniques for Failure Analysis  

Science Conference Proceedings (OSTI)

Oct 31, 2013 ... Failure Analysis and Prevention: Tools & Techniques for Failure ... As lithium-ion battery technology continues to advance and is adopted in diverse markets, ... fracture origin and an understanding of the fracture event energy.

26

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

27

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

28

Core Analysis For The Development And Constraint Of Physical...  

Open Energy Info (EERE)

At Geysers Area (Boitnott, 2003) Core Analysis At International Geothermal Area, Indonesia (Boitnott, 2003) Geysers Geothermal Area International Geothermal Area Indonesia...

29

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

30

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"

31

Core Analysis At Valles Caldera - Sulphur Springs Area (Ito ...  

Open Energy Info (EERE)

On The Thermal History Of The Valles Caldera, New Mexico- Evidence From Zircon Fission-Track Analysis Retrieved from "http:en.openei.orgwindex.php?titleCoreAnalysisA...

32

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

33

Topics and Techniques in Forensic DNA Analysis  

Science Conference Proceedings (OSTI)

... Topics and Techniques for Forensic DNA Analysis NYC OCME Dept of Forensic Biology ... NIST Human Identity Project Leader (1999-present) ...

2012-04-17T23:59:59.000Z

34

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

35

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

36

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

37

The Synthetic Dual-Doppler Analysis Technique  

Science Conference Proceedings (OSTI)

Synthetic dual-Doppler (SDD) is a single-Doppler analysis technique that combines measurements from two different times, provided the viewing angle changes significantly. In this study, the viability of the SDD technique is investigated through ...

Brian A. Klimowski; John D. Marwitz

1992-12-01T23:59:59.000Z

38

TMI-2 accident: core heat-up analysis  

SciTech Connect

This report summarizes NSAC study of reactor core thermal conditions during the accident at Three Mile Island, Unit 2. The study focuses primarily on the time period from core uncovery (approximately 113 minutes after turbine trip) through the initiation of sustained high pressure injection (after 202 minutes). The transient analysis is based upon established sequences of events; plant data; post-accident measurements; interpretation or indirect use of instrument responses to accident conditions.

Ardron, K.H.; Cain, D.G.

1981-01-01T23:59:59.000Z

39

Trace Element Analysis Core Lab methods  

E-Print Network (OSTI)

), Hg and Pb (no gas mode). Selenium and Fe are analysed in collision mode with H2. The sample strem a weighed sample is placed in either a 15 ml or 50 ml centrifuge tube and an appropriate volume of optima analysis is performed in the 15 ml centrifuge tubes with addition of 0.5 mls HNO3. For sediment/soils 0

Lotko, William

40

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

Note: This page contains sample records for the topic "technique 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

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

Open Energy Info (EERE)

Page Edit History Facebook icon Twitter icon Core Analysis At Fort Bliss Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core...

42

Definition: Lab Analysis Techniques | Open Energy Information  

Open Energy Info (EERE)

Definition Definition Edit with form History Facebook icon Twitter icon » Definition: Lab Analysis Techniques Jump to: navigation, search Dictionary.png Lab Analysis Techniques Lab Analysis Techniques encompass a broad array of analytical methods that can be used to characterize the chemical and physical properties of rock and fluid samples. The reliability of laboratory analyses depends strongly on both adherence to standard sampling procedures in the field when collecting materials for examination and on the application of appropriate sample preparation techniques in the lab. Ret Like Like You like this.Sign Up to see what your friends like. rieved from "http://en.openei.org/w/index.php?title=Definition:Lab_Analysis_Techniques&oldid=688298" Category:

43

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

44

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.,

45

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

46

A Unified Analysis-Initialization Technique  

Science Conference Proceedings (OSTI)

A unified analysis-initialization technique is introduced and tested in the framework of the shallow water equations. It consists of iterating multivariate optimal interpolation and nonlinear normal mode initialization. For extratropical regions, ...

David L. Williamson; Roger Daley

1983-08-01T23:59:59.000Z

47

ECONOMIC ANALYSIS OF REPLACEMENT CORES FOR SM AND PM TYPE REACTORS  

SciTech Connect

An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies. The analysis indicates that major savings are possible by utilizing Type 3 cores (40-mil plates, 25 wt% UO/sub 2/, welded assembly) in all SM and PM type reactors, and that significant savings are possible by multiple core procurement and reprocessing, and relaxation of cobalt and tantalum requirements in Type 347 stainless steel. (auth)

Wilder, A.S.

1961-10-01T23:59:59.000Z

48

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

Science Conference Proceedings (OSTI)

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

49

Neutronic analysis of pebble-bed cores with transuranics  

E-Print Network (OSTI)

At the brink of nuclear waste repository crises, viable alternatives for the long term radiotoxic wastes are seriously being considered worldwide. Minor actinides serve as one of these targeted wastes. Partitioning and transmutation in fission reactors is one possible incineration option and could potentially serve as a source of nuclear fuel required for sustainability of energy resources. The objective of this research was to evaluate the neutronic performance of the pebble-bed Very High Temperature Reactor (VHTR) configurations with various fuel loadings. The configuration adjustments and design sensitivity studies specifically targeted the achievability of spectral variations. The development of several realistic full-core 3D models and validation of all modeling techniques used was a major part of this research effort. In addition, investigating design sensitivities helped identify the parameters of primary interest. The full-core 3D models representing the prototype and large scale cores were created for use with SCALE 5.0 and SCALE 5.1 code systems. Initially the models required the external calculation of a Dancoff correction factor; however, the recent release of SCALE 5.1 encompassed inherent double heterogeneity modeling capabilities. The full core 3D models with multi-heterogeneity treatments are in agreement with available pebble-bed High Temperature Test Reactor data and were validated through benchmark studies. Analyses of configurations with various fuel loadings have indicated promising performance and safety characteristics. It was found that through small configuration adjustments, the pebble-bed design can be tweaked to produce desirable spectral shifts. The future operation of Generation IV nuclear energy systems would be greatly facilitated by the utilization of minor actinides as a fuel component. This would offer development of new fuel cycles, and support sustainability of a fuel source.

Pritchard, Megan Leigh

2007-12-01T23:59:59.000Z

50

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 1 Techniques and Applications in Lipid Analysis  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 1 Techniques and Applications in Lipid Analysis Methods and Analyses eChapters Methods - Analyses Books 6BFA9B7918529F3FEC884BD9D5F59B4A AOCS Press D

51

Analysis of dynamic power management on multi-core processors  

Science Conference Proceedings (OSTI)

Power management of multi-core processors is extremely important because it allows power/energy savings when all cores are not used. OS directed power management according to ACPI (Advanced Power and Configurations Interface) specifications is the common ... Keywords: ACPI, multi-core, operating system, performance, power management

W. Lloyd Bircher; Lizy K. John

2008-06-01T23:59:59.000Z

52

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

53

Modeling shared cache and bus in multi-cores for timing analysis  

Science Conference Proceedings (OSTI)

Timing analysis of concurrent programs running on multi-core platforms is currently an important problem. The key to solving this problem is to accurately model the timing effects of shared resources in multi-cores, namely shared cache and bus. In this ... Keywords: WCET, multi-core, shared bus, shared cache

Sudipta Chattopadhyay; Abhik Roychoudhury; Tulika Mitra

2010-06-01T23:59:59.000Z

54

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...

55

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

Open Energy Info (EERE)

H. Mariner, Terry E. C. Keith (1987) Isotope Geochemistry Of Minerals And Fluids From Newberry Volcano, Oregon Retrieved from "http:en.openei.orgwindex.php?titleCoreAnaly...

56

100-KE REACTOR CORE REMOVAL PROJECT ALTERNATIVE ANALYSIS WORKSHOP REPORT  

Science Conference Proceedings (OSTI)

On December 15-16, 2009, a 100-KE Reactor Core Removal Project Alternative Analysis Workshop was conducted at the Washington State University Consolidated Information Center, Room 214. Colburn Kennedy, Project Director, CH2M HILL Plateau Remediation Company (CHPRC) requested the workshop and Richard Harrington provided facilitation. The purpose of the session was to select the preferred Bio Shield Alternative, for integration with the Thermal Shield and Core Removal and develop the path forward to proceed with project delivery. Prior to this workshop, the S.A. Robotics (SAR) Obstruction Removal Alternatives Analysis (565-DLV-062) report was issued, for use prior to and throughout the session, to all the team members. The multidisciplinary team consisted ofrepresentatives from 100-KE Project Management, Engineering, Radcon, Nuclear Safety, Fire Protection, Crane/Rigging, SAR Project Engineering, the Department of Energy Richland Field Office, Environmental Protection Agency, Washington State Department of Ecology, Defense Nuclear Facility Safety Board, and Deactivation and Decommission subject matter experts from corporate CH2M HILL and Lucas. Appendix D contains the workshop agenda, guidelines and expectations, opening remarks, and attendance roster going into followed throughout the workshop. The team was successful in selecting the preferred alternative and developing an eight-point path forward action plan to proceed with conceptual design. Conventional Demolition was selected as the preferred alternative over two other alternatives: Diamond Wire with Options, and Harmonic Delamination with Conventional Demolition. The teams preferred alternative aligned with the SAR Obstruction Removal Alternative Analysis report conclusion. However, the team identified several Path Forward actions, in Appendix A, which upon completion will solidify and potentially enhance the Conventional Demolition alternative with multiple options and approaches to achieve project delivery. In brief, the Path Forward was developed to reconsider potential open air demolition areas; characterize to determine if any zircaloy exists, evaluate existing concrete data to determine additional characterization needs, size the new building to accommodate human machine interface and tooling, consider bucket thumb and use ofshape-charges in design, and finally to utilize complex-wide and industry explosive demolition lessons learned in the design approach. Appendix B documents these results from the team's use ofValue Engineering process tools entitled Weighted Analysis Alternative Matrix, Matrix Conclusions, Evaluation Criteria, and Alternative Advantages and Disadvantages. These results were further supported with the team's validation of parking-lot information sheets: memories (potential ideas to consider), issues/concerns, and assumptions, contained in Appendix C. Appendix C also includes the recorded workshop flipchart notes taken from the SAR Alternatives and Project Overview presentations. The SAR workshop presentations, including a 3-D graphic illustration demonstration video have been retained in the CHPRC project file, and were not included in this report due to size limitations. The workshop concluded with a round robin close-out where each member was engaged for any last minute items and meeting utility. In summary, the team felt the session was value added and looked forward to proceeding with the recommended actions and conceptual design.

HARRINGTON RA

2010-01-15T23:59:59.000Z

57

ANALYSIS OF THE SALT FEED TANK CORE SAMPLE  

Science Conference Proceedings (OSTI)

The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank (SFT) at the Saltstone Production Facility (SPF) holds approximately 6500 gallons of low level waste from Tank 50 as well as drain water returned from the Saltstone Disposal Facility (SDF) vaults. Over the past several years, Saltstone Engineering has noted the accumulation of solids in the SFT. The solids are causing issues with pump performance, agitator performance, density/level monitoring, as well as taking up volume in the tank. The tank has been sounded at the same location multiple times to determine the level of the solids. The readings have been 12, 25 and 15 inches. The SFT is 8.5 feet high and 12 feet in diameter, therefore the solids account for approximately 10 % of the tank volume. Saltstone Engineering has unsuccessfully attempted to obtain scrape samples of the solids for analysis. As a result, Savannah River National Laboratory (SRNL) was tasked with developing a soft core sampler to obtain a sample of the solids and to analyze the core sample to aid in determining a path forward for removing the solids from the SFT. The source of the material in the SFT is the drain water return system where excess liquid from the Saltstone disposal vaults is pumped back to the SFT for reprocessing. It has been shown that fresh grout from the vault enter the drain water system piping. Once these grout solids return to the SFT, they settle in the tank, set up, and can't be reprocessed, causing buildup in the tank over time. The composition of the material indicates that it is potentially toxic for chromium and mercury and the primary radionuclide is cesium-137. Qualitative measurements show that the material is not cohesive and will break apart with some force.

Reigel, M.; Cheng, W.

2012-01-26T23:59:59.000Z

58

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

59

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

Open Energy Info (EERE)

Activity Date Usefulness useful DOE-funding Unknown Notes A few cores (see Table I), cuttings collected at 1.5- or 3-m intervals, and random samples from a "junk basket" run...

60

Evaluation of Counter-Based Dynamic Load Balancing Schemes for Massive Contingency Analysis on Over 10,000 Cores  

SciTech Connect

Contingency analysis studies are necessary to assess the impact of possible power system component failures. The results of the contingency analysis are used to ensure the grid reliability, and in power market operation for the feasibility test of market solutions. Currently, these studies are performed in real time based on the current operating conditions of the grid with a set of pre-selected contingency list, which might result in overlooking some critical contingencies caused by variable system status. To have a complete picture of a power grid, more contingencies need to be studied to improve grid reliability. High-performance computing techniques hold the promise of being able to perform the analysis for more contingency cases within a much shorter time frame. This paper evaluates the performance of counter-based dynamic load balancing schemes for a massive contingency analysis program on 10,000+ cores. One million N-2 contingency analysis cases with a Western Electricity Coordinating Council power grid model have been used to demonstrate the performance. The speedup of 3964 with 4096 cores and 7877 with 10240 cores are obtained. This paper reports the performance of the load balancing scheme with a single counter and two counters, describes disk I/O issues, and discusses other potential techniques for further improving the performance.

Chen, Yousu; Huang, Zhenyu; Rice, Mark J.

2012-12-27T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

An analysis of some time-sharing techniques  

Science Conference Proceedings (OSTI)

The effectiveness of certain time-sharing techniques such as program relocation, disk rotational delay minimization, and swap volume minimization is investigated. Summary data is presented, and the findings are discussed. The vehicle for this investigation ... Keywords: B6500, bulk core usage, operating system model, relocation, rotational delay minimization, simulation, swap volume minimization, system simulation, time-sharing

Norman R. Nielsen

1971-02-01T23:59:59.000Z

62

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

63

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

64

Analysis of Traffic Scheduling Technique for Smart Grid Mesh ...  

Science Conference Proceedings (OSTI)

Analysis of Traffic Scheduling Technique for Smart Grid Mesh Networks ... In this paper, we present a multi-gate mesh network architecture that has ...

2012-01-03T23:59:59.000Z

65

Lipid Analysis and Lipidomics: New Techniques and Application  

Science Conference Proceedings (OSTI)

Lipid Analysis will offer the lipid analyst an array of essential analytical tools in the fields of chromatography, mass spectrometry, spectroscopy, magnetic resonance, and chemometrics. Lipid Analysis and Lipidomics: New Techniques and Application Method

66

Full core reactor analysis: Running Denovo on Jaguar  

Science Conference Proceedings (OSTI)

Fully-consistent, full-core, 3D, deterministic neutron transport simulations using the orthogonal mesh code Denovo were run on the massively parallel computing architecture Jaguar XT5. Using energy and spatial parallelization schemes, Denovo was able to efficiently scale to more than 160 k processors. Cell-homogenized cross sections were used with step-characteristics, linear-discontinuous finite element, and trilinear-discontinuous finite element spatial methods. It was determined that using the finite element methods gave considerably more accurate eigenvalue solutions for large-aspect ratio meshes than using step-characteristics. (authors)

Jarrell, J. J.; Godfrey, A. T.; Evans, T. M.; Davidson, G. G. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831 (United States)

2012-07-01T23:59:59.000Z

67

VLBI FOR GRAVITY PROBE B. IV. A NEW ASTROMETRIC ANALYSIS TECHNIQUE AND A COMPARISON WITH RESULTS FROM OTHER TECHNIQUES  

Science Conference Proceedings (OSTI)

When very long baseline interferometry (VLBI) observations are used to determine the position or motion of a radio source relative to reference sources nearby on the sky, the astrometric information is usually obtained via (1) phase-referenced maps or (2) parametric model fits to measured fringe phases or multiband delays. In this paper, we describe a 'merged' analysis technique which combines some of the most important advantages of these other two approaches. In particular, our merged technique combines the superior model-correction capabilities of parametric model fits with the ability of phase-referenced maps to yield astrometric measurements of sources that are too weak to be used in parametric model fits. We compare the results from this merged technique with the results from phase-referenced maps and from parametric model fits in the analysis of astrometric VLBI observations of the radio-bright star IM Pegasi (HR 8703) and the radio source B2252+172 nearby on the sky. In these studies we use central-core components of radio sources 3C 454.3 and B2250+194 as our positional references. We obtain astrometric results for IM Peg with our merged technique even when the source is too weak to be used in parametric model fits, and we find that our merged technique yields astrometric results superior to the phase-referenced mapping technique. We used our merged technique to estimate the proper motion and other astrometric parameters of IM Peg in support of the NASA/Stanford Gravity Probe B mission.

Lebach, D. E.; Ratner, M. I.; Shapiro, I. I. [Harvard-Smithsonian Center for Astrophysics, 60 Garden Street, Cambridge, MA 02138 (United States); Bartel, N.; Bietenholz, M. F.; Lederman, J. I.; Ransom, R. R. [Department of Physics and Astronomy, York University, 4700 Keele Street, Toronto, ON M3J 1P3 (Canada); Campbell, R. M. [Joint Institute for VLBI in Europe, Oude Hoogeveensedijk 4, 7991 PD Dwingeloo (Netherlands); Gordon, D. [NVI Inc./NASA Goddard Space Flight Center, Greenbelt, MD 20771 (United States); Lestrade, J.-F. [Observatoire de Paris, Centre National de la Recherche Scientifique, 77 Av. Denfert Rochereau, 75014 Paris (France)

2012-07-01T23:59:59.000Z

68

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

Science Conference Proceedings (OSTI)

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

69

An Objective Isobaric/Isentropic Technique for Upper Air Analysis  

Science Conference Proceedings (OSTI)

An objective meteorological analysis technique has been developed to provide both horizontal and vertical (cross-sectional) upper air analyses. The horizontal analyses are made at grid points that lie on isobaric levels in a conventional manner. ...

Robert L. Mancuso; Roy M. Endlich; L. J. Ehernberger

1981-06-01T23:59:59.000Z

70

PWR core design, neutronics evaluation and fuel cycle analysis for thorium-uranium breeding recycle  

Science Conference Proceedings (OSTI)

This paper was focused on core design, neutronics evaluation and fuel cycle analysis for Thorium-Uranium Breeding Recycle in current PWRs, without any major change to the fuel lattice and the core internals, but substituting the UOX pellet with Thorium-based pellet. The fuel cycle analysis indicates that Thorium-Uranium Breeding Recycle is technically feasible in current PWRs. A 4-loop, 193-assembly PWR core utilizing 17 x 17 fuel assemblies (FAs) was taken as the model core. Two mixed cores were investigated respectively loaded with mixed reactor grade Plutonium-Thorium (PuThOX) FAs and mixed reactor grade {sup 233}U-Thorium (U{sub 3}ThOX) FAs on the basis of reference full Uranium oxide (UOX) equilibrium-cycle core. The UOX/PuThOX mixed core consists of 121 UOX FAs and 72 PuThOX FAs. The reactor grade {sup 233}U extracted from burnt PuThOX fuel was used to fabrication of U{sub 3}ThOX for starting Thorium-. Uranium breeding recycle. In UOX/U{sub 3}ThOX mixed core, the well designed U{sub 3}ThOX FAs with 1.94 w/o fissile uranium (mainly {sup 233}U) were located on the periphery of core as a blanket region. U{sub 3}ThOX FAs remained in-core for 6 cycles with the discharged burnup achieving 28 GWD/tHM. Compared with initially loading, the fissile material inventory in U{sub 3}ThOX fuel has increased by 7% via 1-year cooling after discharge. 157 UOX fuel assemblies were located in the inner of UOX/U{sub 3}ThOX mixed core refueling with 64 FAs at each cycle. The designed UOX/PuThOX and UOX/U{sub 3}ThOX mixed core satisfied related nuclear design criteria. The full core performance analyses have shown that mixed core with PuThOX loading has similar impacts as MOX on several neutronic characteristic parameters, such as reduced differential boron worth, higher critical boron concentration, more negative moderator temperature coefficient, reduced control rod worth, reduced shutdown margin, etc.; while mixed core with U{sub 3}ThOX loading on the periphery of core has no visible impacts on neutronic characteristics compared with reference full UOX core. The fuel cycle analysis has shown that {sup 233}U mono-recycling with U{sub 3}ThOX fuel could save 13% of natural uranium resource compared with UOX once through fuel cycle, slightly more than that of Plutonium single-recycling with MOX fuel. If {sup 233}U multi-recycling with U{sub 3}ThOX fuel is implemented, more natural uranium resource would be saved. (authors)

Bi, G.; Liu, C.; Si, S. [Shanghai Nuclear Engineering Research and Design Inst., No. 29, Hongcao Road, Shanghai, 200233 (China)

2012-07-01T23:59:59.000Z

71

Process, Techniques, and Successes in Welding the Dry Shielded Canister Welds of the TMI-2 Reactor Core Debris  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is operated by Bechtel-BWXT Idaho LLC (BBWI), which recently completed a very successful $100 million Three-Mile Island-2 (TMI-2) program for the Department of Energy (DOE). This complex and challenging program used an integrated multidisciplinary team approach that loaded, welded, and transported an unprecedented 25 dry shielded canisters (DSC) in seven months, and did so ahead of schedule. The program moved over 340 canisters of TMI-2 core debris that had been in wet storage into a dry storage facility at the INEEL. The main thrust of this paper is relating the innovations, techniques, approaches, and lessons learned associated to welding of the DSC's. This paper shows the synergism of elements to meet program success and shares these lessons learned that will facilitate success with welding of dry shielded canisters in other DOE complex dry storage programs.

Zirker, Laurence R; Rankin, Richard Allen; Ferrell, Larry Joseph

2002-02-01T23:59:59.000Z

72

Processes, Techniques, and Successes in Welding the Dry Shielded Canisters of the TMI-2 Reactor Core Debris  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is operated by Bechtel-BWXT Idaho LLC (BBWI), which recently completed a very successful $100 million Three-Mile Island-2 (TMI-2) program for the Department of Energy (DOE). This complex and challenging program used an integrated multidisciplinary team approach that loaded, welded, and transported an unprecedented 25 dry shielded canisters (DSC) in seven months, and did so ahead of schedule. The program moved over 340 canisters of TMI-2 core debris that had been in wet storage into a dry storage facility at the INEEL. The main thrust of this paper is relating the innovations, techniques, approaches, and lessons learned associated to welding of the DSC's. This paper shows the synergism of elements to meet program success and shares these lessons learned that will facilitate success with welding of dry shielded canisters in other DOE complex dry storage programs.

Zirker, L.R.; Rankin, R.A.; Ferrell, L.J.

2002-01-29T23:59:59.000Z

73

Techniques for Debugging Parallel Programs with Flowback Analysis  

E-Print Network (OSTI)

Flowback analysis is a powerful technique for debugging programs. It allows the programmer to examine dynamic dependences in a program's execution history without having to re-execute the program. The goal is to present to the programmer a graphical view of the dynamic program dependences. We are building a system, called PPD, that performs flowback analysis while keeping the execution time overhead low. We also extend the semantics of flowback analysis to parallel programs. This paper describes details of the graphs and algorithms needed to implement efficient flowback analysis for parallel programs. Execution time overhead is kept low by recording only a small amount of trace during a program's execution. We use semantic analysis and a technique called incremental tracing to keep the time and space overhead low. As part of the semantic analysis, PPD uses a static program dependence graph structure that reduces the amount of work done at compile time and takes advantage of the dynamic...

Jong-deok Choi; Barton P. Miller; Robert H.B. Netzer

1991-01-01T23:59:59.000Z

74

An efficient FE model based on combined theory for the analysis of soft core sandwich plate  

Science Conference Proceedings (OSTI)

An efficient C0 continuous finite element (FE) model is developed based on combined theory (refine higher order shear deformation theory (RHSDT) and least square error (LSE) method) for the static analysis of soft core sandwich plate. In this ... Keywords: Composites, Finite element, Laminate, Plates, Sandwich materials

Ravi Prakash Khandelwal; Anupam Chakrabarti; Pradeep Bhargava

2013-05-01T23:59:59.000Z

75

LDRD ER Final Report: Recreating Planetary Cores in the Laboratory: New Techniques to Extremely High Density States  

DOE Green Energy (OSTI)

An accurate equation of state (EOS) for planetary constituents at extreme conditions is the key to any credible model of planets or low mass stars. However, very few materials have their high pressure (>few Mbar) EOS experimentally validated, and even then, only on the principal Hugoniot. For planetary and stellar interiors, compression occurs from gravitational force so that material states follow a line of isotropic compression (ignoring phase separation) to ultra-high densities. An example of the hydrogen phase space composing Jupiter and one particular Brown Dwarf is shown. At extreme densities, material states are predicted to have quite unearthly properties such as high temperature superconductivity and low temperature fusion. High density experiments on Earth are achieved with either static compression techniques (i.e. diamond anvil cells) or dynamic compression techniques using large laser facilities, gas guns, or explosives. The ultimate goal of this multi-directorate and multi-institutional proposal was to develop techniques that will enable us to understand material states that previously only existed at the core of giant planets, stars, or speculative theories. Our effort was a complete success, meeting all of the objectives set out in our proposals. First we focused on developing accurate Hugoniot techniques to be used for constraining the equation of state at high pressure/temperature. We mapped out an accurate water EOS and measured that the ionic->electronic conduction transition occurs at lower pressures than models predict. These data and their impact are fully described in the first enclosed paper ''The Equation of State and Optical Properties of Water Compressed by Strong Shock Waves.'' Currently models used to construct planetary isentropes are constrained by only the planet radius, outer atmospheric spectroscopy, and space probe gravitational moment and magnetic field data. Thus these data, which provide rigid constraints to these models, will have a significant impact on a broad community of planetary and condensed matter scientists, as well as our fundamental understanding of the giant planets. We then developed and tested precompressed and multiple shock techniques on water. Scientists around the world have teamed with us to conduct these complex and seminal high density experiments which allow access to the extreme core states of giant plants. Double shock experiments using a variety of anvils to compress water to densities higher and temperatures lower than accessible by single shock Hugoniot techniques. First a clear determination of the EOS and optical properties of the anvils needed to be measured. These properties for LiF and A1203 are written up in the second attached article, ''Shock-Induced Transformation of Sapphire and Lithium Fluoride into Semiconducting Liquids.'' An example double shock data record for water is shown. This data is being written up for publication.

Collins, G; Celliers, P; Hicks, D; Cauble, R; Bradley, D; MacKinnon, A; Moon, S; Young, D; Chau, R; Eggert, J; Willi, P; Pasley, J; Jeanloz, R; Lee, K; Bennedetti, R; Koenig, M; Benuzzi-Mounaix, A; Batani, D; Loubeyre, P; Hubbard, W

2003-02-07T23:59:59.000Z

76

DANDE: a linked code system for core neutronics/depletion analysis  

SciTech Connect

This report describes DANDE - a modular neutronics, depletion code system for reactor analysis. It consists of nuclear data processing, core physics, and fuel depletion modules, and allows one to use diffusion and transport methods interchangeably in core neutronics calculations. This latter capability is especially important in the design of small modular cores. Additional unique features include the capability of updating the nuclear data file during a calculation; a detailed treatment of depletion, burnable poisons as well as fuel; and the ability to make geometric changes such as control rod repositioning and fuel relocation in the course of a calculation. The detailed treatment of reactor fuel burnup, fission-product creation and decay, as well as inventories of higher-order actinides is a necessity when predicting the behavior of reactor fuel under increased burn conditions. The operation of the code system is made clear in this report by following a sample problem.

LaBauve, R.J.; England, T.R.; George, D.C.; MacFarlane, R.E.; Wilson, W.B.

1985-06-01T23:59:59.000Z

77

PWR core and spent fuel pool analysis using scale and nestle  

SciTech Connect

The SCALE nuclear analysis code system [SCALE, 2011], developed and maintained at Oak Ridge National Laboratory (ORNL) is widely recognized as high quality software for analyzing nuclear systems. The SCALE code system is composed of several validated computer codes and methods with standard control sequences, such as the TRITON/NEWT lattice physics sequence, which supplies dependable and accurate analyses for industry, regulators, and academia. Although TRITON generates energy-collapsed and space-homogenized few group cross sections, SCALE does not include a full-core nodal neutron diffusion simulation module within. However, in the past few years, the open-source NESTLE core simulator [NESTLE, 2003], originally developed at North Carolina State Univ. (NCSU), has been updated and upgraded via collaboration between ORNL and the Univ. of Tennessee (UT), so it now has a growingly seamless coupling to the TRITON/NEWT lattice physics [Galloway, 2010]. This study presents the methodology used to couple lattice physics data between TRITON and NESTLE in order to perform a three-dimensional full-core analysis employing a 'real-life' Duke Energy PWR as the test bed. The focus for this step was to compare the key parameters of core reactivity and radial power distribution versus plant data. Following the core analysis, following a three cycle burn, a spent fuel pool analysis was done using information generated from NESTLE for the discharged bundles and was compared to Duke Energy spent fuel pool models. The KENO control module from SCALE was employed for this latter stage of the project. (authors)

Murphy, J. E.; Maldonado, G. I. [Dept. of Nuclear Engineering, Univ. of Tennessee, Knoxville, TN 37996-2300 (United States); St Clair, R.; Orr, D. [Duke Energy, 526 S. Church St, Charlotte, NC 28202 (United States)

2012-07-01T23:59:59.000Z

78

Nondestructive analysis of oil shales with PGNAA technique  

DOE Green Energy (OSTI)

The feasibility of nondestructive analysis of oil shales using the prompt gamma neutron activation analysis (PGNAA) technique was studied. The PGNAA technique, developed originally for continuous analysis of coal on the belt, was applied to the analysis of eight oil-shale samples, containing between 9 and 60 gallons of oil per ton and 0.8% to 3.4% hydrogen. The PGNAA technique was modified using four neutron moderation conditions: non-moderated neutrons; non-moderated and partially moderated neutrons reflected from a water box behind the source; neutrons moderated in a water box behind and in front of the source; and neutrons strongly moderated in a polyethylene block placed in front of the source and with reflected neutrons from a water box behind the source. The studied oil shales were measured in their aluminum or wooden (masonite) boxes. The obtained Ge-Li spectra were processed by LSI-11/23 computer, using the modified programs previously developed by SAI for continuous coal analysis. The results of such processing (the peak areas for several gamma lines) were corrected and plotted against the weight percent of each analyzed element (from the chemical analysis). Response curves developed for H, C, N, S, Na, Mg, Al, Si, Ti, Ca, Fe and K show generally good linear proportions of peak area to the weight percent of the element. For hydrogen determination, NMD conditions had to be used where the response curve was not linear, but followed a curve whose slope rose with hydrogen concentration. This effect is caused by improving neutron self-moderation in sample boxes of rich oil shales, as compared to poor self-moderation of neutrons in very lean oil shales. The moisture in oil shales was measured by microwave absorption technique in small masonite boxes. This method was calibrated four times using oil-shale samples mixed gradually with larger and larger amounts of water.

Maly, J.; Bozorgmanesh, H.

1984-02-01T23:59:59.000Z

79

ANALYSIS OF FUEL ELEMENT CORE BLANKS FOR ARGONNE LOW POWER REACTOR BY GAMMA COUNTING  

SciTech Connect

A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inches, and thickness, 0.200 inch. The gamma- ray spectrum emitied by uranium is rather complex. Using a scintillation spectrometer and scanning the spectrum, the energy is found to be concentrated primarily in two regions, at 184 and 90 kev. The 184-kev gamma rays result primarily from the decay of U/sup 235/ The gammas in the 90-kev region result from the U/sup 235/ decay and daughter products of U/sup 238/ and U/sup 235/. Using a pulse-height analyzer, it is possibie to select the desired radiation emitted from the source and determine the counting rate for a given source. In this work the 184-kev gamma radiation was counted to determine the amount of U/ sup 235/ present in the individual core blanks. (auth)

McGonnagle, W.J.; Perry, R.B.

1959-12-01T23:59:59.000Z

80

Experimental thin film deposition and surface analysis techniques  

DOE Green Energy (OSTI)

An attempt has been made to present some of the thin-film deposition and surface analysis techniques which may be useful in growing superionic conducting materials. Emphasis is made on the importance of being careful in selecting process parameters and materials in order to produce films with properties outlined in this article. Also, special care should be given to proper consideration of grain boundary effects.

Collins, W.E.; Rambabu, B.

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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 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

82

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

83

Analysis of Fracture in Cores from the Tuff Confining Unit beneath Yucca Flat, Nevada Test Site  

SciTech Connect

The role fractures play in the movement of groundwater through zeolitic tuffs that form the tuff confining unit (TCU) beneath Yucca Flat, Nevada Test Site, is poorly known. This is an important uncertainty, because beneath most of Yucca Flat the TCU lies between the sources of radionuclide contaminants produced by historic underground nuclear testing and the regional carbonate aquifer. To gain a better understanding of the role fractures play in the movement of groundwater and radionuclides through the TCU beneath Yucca Flat, a fracture analysis focusing on hydraulic properties was performed on conventional cores from four vertical exploratory holes in Area 7 of Yucca Flat that fully penetrate the TCU. The results of this study indicate that the TCU is poorly fractured. Fracture density for all fractures is 0.27 fractures per vertical meter of core. For open fractures, or those observed to have some aperture, the density is only 0.06 fractures per vertical meter of core. Open fractures are characterized by apertures ranging from 0.1 to 10 millimeter, and averaging 1.1 millimeter. Aperture typically occurs as small isolated openings along the fracture, accounting for only 10 percent of the fracture volume, the rest being completely healed by secondary minerals. Zeolite is the most common secondary mineral occurring in 48 percent of the fractures observed.

Lance Prothro

2008-03-01T23:59:59.000Z

84

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

85

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

Science Conference Proceedings (OSTI)

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

86

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

87

BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis, Version III  

Science Conference Proceedings (OSTI)

This report is a condensed documentation for VERSION III of the BOLD VENTURE COMPUTATION SYSTEM for nuclear reactor core analysis. An experienced analyst should be able to use this system routinely for solving problems by referring to this document. Individual reports must be referenced for details. This report covers basic input instructions and describes recent extensions to the modules as well as to the interface data file specifications. Some application considerations are discussed and an elaborate sample problem is used as an instruction aid. Instructions for creating the system on IBM computers are also given.

Vondy, D.R.; Fowler, T.B.; Cunningham, G.W. III.

1981-06-01T23:59:59.000Z

88

Sensitivity analysis techniques for models of human behavior.  

SciTech Connect

Human and social modeling has emerged as an important research area at Sandia National Laboratories due to its potential to improve national defense-related decision-making in the presence of uncertainty. To learn about which sensitivity analysis techniques are most suitable for models of human behavior, different promising methods were applied to an example model, tested, and compared. The example model simulates cognitive, behavioral, and social processes and interactions, and involves substantial nonlinearity, uncertainty, and variability. Results showed that some sensitivity analysis methods create similar results, and can thus be considered redundant. However, other methods, such as global methods that consider interactions between inputs, can generate insight not gained from traditional methods.

Bier, Asmeret Brooke

2010-09-01T23:59:59.000Z

89

Structural properties of Zn-ZnO core-shell microspheres grown by hot-filament CVD technique  

Science Conference Proceedings (OSTI)

We report the hot-filament chemical vapor deposition (HFCVD) growth of Zn-ZnO core-shell microspheres in the temperature range of 350-650C only using ZnO pellets as raw material. The samples were characterized by scanning electron microscope (SEM), ...

R. Lpez; T. Daz; G. Garca; R. Galeazzi; E. Rosendo; A. Coyopol; M. Pacio; H. Jurez; A. I. Oliva

2012-01-01T23:59:59.000Z

90

Partial Safety Analysis for a Reduced Uranium Enrichment Core for the High Flux Isotope Reactor  

SciTech Connect

A computational model of the reactor core of the High Flux Isotope Rector (HFIR) was developed in order to analyze non-destructive accidents caused by transients during reactor operation. The reactor model was built for the latest version of the nuclear analysis software package called Program for the Analysis of Reactor Transients (PARET). Analyses performed with the model constructed were compared with previous data obtained with other tools in order to benchmark the code. Finally, the model was used to analyze the behavior of the reactor under transients using a different nuclear fuel with lower enrichment of uranium (LEU) than the fuel currently used, which has a high enrichment of uranium (HEU). The study shows that the presence of fertile isotopes in LEU fuel, which increases the neutron resonance absorption, reduces the impact of transients on the fuel and enhances the negative reactivity feedback, thus, within the limitations of this study, making LEU fuel appear to be a safe alternative fuel for the reactor core.

Primm, Trent [ORNL; Gehin, Jess C [ORNL

2009-04-01T23:59:59.000Z

91

Evaluation of energy system analysis techniques for identifying underground facilities  

Science Conference Proceedings (OSTI)

This report describes the results of a study to determine the feasibility and potential usefulness of applying energy system analysis techniques to help detect and characterize underground facilities that could be used for clandestine activities. Four off-the-shelf energy system modeling tools were considered: (1) ENPEP (Energy and Power Evaluation Program) - a total energy system supply/demand model, (2) ICARUS (Investigation of Costs and Reliability in Utility Systems) - an electric utility system dispatching (or production cost and reliability) model, (3) SMN (Spot Market Network) - an aggregate electric power transmission network model, and (4) PECO/LF (Philadelphia Electric Company/Load Flow) - a detailed electricity load flow model. For the purposes of most of this work, underground facilities were assumed to consume about 500 kW to 3 MW of electricity. For some of the work, facilities as large as 10-20 MW were considered. The analysis of each model was conducted in three stages: data evaluation, base-case analysis, and comparative case analysis. For ENPEP and ICARUS, open source data from Pakistan were used for the evaluations. For SMN and PECO/LF, the country data were not readily available, so data for the state of Arizona were used to test the general concept.

VanKuiken, J.C.; Kavicky, J.A.; Portante, E.C. [and others

1996-03-01T23:59:59.000Z

92

PVUSA instrumentation and data analysis techniques for photovoltaic systems  

DOE Green Energy (OSTI)

The Photovoltaics for Utility Scale Applications (PVUSA) project tests two types of PV systems at the main test site in Davis, California: new module technologies fielded as 20-kW Emerging Module Technology (EMT) arrays and more mature technologies fielded as 70- to 500-kW turnkey Utility-Scale (US) systems. PVUSA members have also installed systems in their service areas. Designed appropriately, data acquisition systems (DASs) can be a convenient and reliable means of assessing system performance, value, and health. Improperly designed, they can be complicated, difficult to use and maintain, and provide data of questionable validity. This report documents PVUSA PV system instrumentation and data analysis techniques and lessons learned. The report is intended to assist utility engineers, PV system designers, and project managers in establishing an objective, then, through a logical series of topics, facilitate selection and design of a DAS to meet the objective. Report sections include Performance Reporting Objectives (including operational versus research DAS), Recommended Measurements, Measurement Techniques, Calibration Issues, and Data Processing and Analysis Techniques. Conclusions and recommendations based on the several years of operation and performance monitoring are offered. This report is one in a series of 1994--1995 PVUSA reports documenting PVUSA lessons learned at the demonstration sites in Davis and Kerman, California. Other topical reports address: five-year assessment of EMTs; validation of the Kerman 500-kW grid support PV plant benefits; construction and safety experience in installing and operating PV systems; balance-of-system design and costs; procurement, acceptance, and rating practices for PV power plants; experience with power conditioning units and power quality.

Newmiller, J.; Hutchinson, P.; Townsend, T.; Whitaker, C.

1995-10-01T23:59:59.000Z

93

Modern Methods for Lipid AnalysisChapter 1 Atmospheric Pressure Ionization Techniques in Modern Lipid Analysis  

Science Conference Proceedings (OSTI)

Modern Methods for Lipid Analysis Chapter 1 Atmospheric Pressure Ionization Techniques in Modern Lipid Analysis Health Nutrition Biochemistry eChapters Methods - Analyses Books AOCS Press 2F9B8A831F53D269EADF2AB8911EFA88 AOCS Pr

94

Analysis of core-concrete interaction event with flooding for the Advanced Neutron Source reactor  

SciTech Connect

This paper discusses salient aspects of the methodology, assumptions, and modeling of various features related to estimation of source terms from an accident involving a molten core-concrete interaction event (with and without flooding) in the Advanced Neutron Source (ANS) reactor at the Oak Ridge National Laboratory. Various containment configurations are considered for this postulated severe accident. Several design features (such as rupture disks) are examined to study containment response during this severe accident. Also, thermal-hydraulic response of the containment and radionuclide transport and retention in the containment are studied. The results are described as transient variations of source terms, which are then used for studying off-site radiological consequences and health effects for the support of the Conceptual Safety Analysis Report for ANS. The results are also to be used to examine the effectiveness of subpile room flooding during this type of severe accident.

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

1993-11-01T23:59:59.000Z

95

Techniques for debugging parallel programs with flowback analysis  

Science Conference Proceedings (OSTI)

Keywords: debugging, flowback analysis, incremental tracing, parallel program, program dependence graph, semantic analysis

Jong-Deok Choi; Barton P. Miller; Robert H. B. Netzer

1991-10-01T23:59:59.000Z

96

Multivariate analysis of remote LIBS spectra using partial least squares, principal component analysis, and related techniques  

Science Conference Proceedings (OSTI)

Quantitative analysis with LIBS traditionally employs calibration curves that are complicated by the chemical matrix effects. These chemical matrix effects influence the LIBS plasma and the ratio of elemental composition to elemental emission line intensity. Consequently, LIBS calibration typically requires a priori knowledge of the unknown, in order for a series of calibration standards similar to the unknown to be employed. In this paper, three new Multivariate Analysis (MV A) techniques are employed to analyze the LIBS spectra of 18 disparate igneous and highly-metamorphosed rock samples. Partial Least Squares (PLS) analysis is used to generate a calibration model from which unknown samples can be analyzed. Principal Components Analysis (PCA) and Soft Independent Modeling of Class Analogy (SIMCA) are employed to generate a model and predict the rock type of the samples. These MV A techniques appear to exploit the matrix effects associated with the chemistries of these 18 samples.

Clegg, Samuel M [Los Alamos National Laboratory; Barefield, James E [Los Alamos National Laboratory; Wiens, Roger C [Los Alamos National Laboratory; Sklute, Elizabeth [MT HOLYOKE COLLEGE; Dyare, Melinda D [MT HOLYOKE COLLEGE

2008-01-01T23:59:59.000Z

97

Two-dimensional Imaging Velocity Interferometry: Technique and Data Analysis  

Science Conference Proceedings (OSTI)

We describe the data analysis procedures for an emerging interferometric technique for measuring motion across a two-dimensional image at a moment in time, i.e. a snapshot 2d-VISAR. Velocity interferometers (VISAR) measuring target motion to high precision have been an important diagnostic in shockwave physics for many years Until recently, this diagnostic has been limited to measuring motion at points or lines across a target. We introduce an emerging interferometric technique for measuring motion across a two-dimensional image, which could be called a snapshot 2d-VISAR. If a sufficiently fast movie camera technology existed, it could be placed behind a traditional VISAR optical system and record a 2d image vs time. But since that technology is not yet available, we use a CCD detector to record a single 2d image, with the pulsed nature of the illumination providing the time resolution. Consequently, since we are using pulsed illumination having a coherence length shorter than the VISAR interferometer delay ({approx}0.1 ns), we must use the white light velocimetry configuration to produce fringes with significant visibility. In this scheme, two interferometers (illuminating, detecting) having nearly identical delays are used in series, with one before the target and one after. This produces fringes with at most 50% visibility, but otherwise has the same fringe shift per target motion of a traditional VISAR. The 2d-VISAR observes a new world of information about shock behavior not readily accessible by traditional point or 1d-VISARS, simultaneously providing both a velocity map and an 'ordinary' snapshot photograph of the target. The 2d-VISAR has been used to observe nonuniformities in NIF related targets (polycrystalline diamond, Be), and in Si and Al.

Erskine, D J; Smith, R F; Bolme, C; Celliers, P; Collins, G

2011-03-23T23:59:59.000Z

98

Imaging Technique for a Neutron Based Elemental Analysis Interrogation System  

E-Print Network (OSTI)

: · fundamental properties of the neutron, · neutrino physics, · physics of nuclear fission, · neutron neutrons because it "sees" the reactor core. It will be used for nuclear physics. Investigation of PREACTOR PIK WHAT ARE NEUTRONS NEEDED FOR If you want to see an object, you have to illuminate it

Koltick, David

99

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

Science Conference Proceedings (OSTI)

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

100

An evaluation of wind turbine blade cross section analysis techniques.  

SciTech Connect

The blades of a modern wind turbine are critical components central to capturing and transmitting most of the load experienced by the system. They are complex structural items composed of many layers of fiber and resin composite material and typically, one or more shear webs. Large turbine blades being developed today are beyond the point of effective trial-and-error design of the past and design for reliability is always extremely important. Section analysis tools are used to reduce the three-dimensional continuum blade structure to a simpler beam representation for use in system response calculations to support full system design and certification. One model simplification approach is to analyze the two-dimensional blade cross sections to determine the properties for the beam. Another technique is to determine beam properties using static deflections of a full three-dimensional finite element model of a blade. This paper provides insight into discrepancies observed in outputs from each approach. Simple two-dimensional geometries and three-dimensional blade models are analyzed in this investigation. Finally, a subset of computational and experimental section properties for a full turbine blade are compared.

Paquette, Joshua A.; Griffith, Daniel Todd; Laird, Daniel L.; Resor, Brian Ray

2010-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

Analysis of core damage frequency due to external events at the DOE (Department of Energy) N-Reactor  

SciTech Connect

A complete external events probabilistic risk assessment has been performed for the N-Reactor power plant, making full use of all insights gained during the past ten years' developments in risk assessment methodologies. A detailed screening analysis was performed which showed that all external events had negligible contribution to core damage frequency except fires, seismic events, and external flooding. A limited scope analysis of the external flooding risk indicated that it is not a major risk contributor. Detailed analyses of the fire and seismic risks resulted in total (mean) core damage frequencies of 1.96E-5 and 4.60E-05 per reactor year, respectively. Detailed uncertainty analyses were performed for both fire and seismic risks. These results show that the core damage frequency profile for these events is comparable to that found for existing commercial power plants if proposed fixes are completed as part of the restart program. 108 refs., 85 figs., 80 tabs.

Lambright, J.A.; Bohn, M.P.; Daniel, S.L. (Sandia National Labs., Albuquerque, NM (USA)); Baxter, J.T. (Westinghouse Hanford Co., Richland, WA (USA)); Johnson, J.J.; Ravindra, M.K.; Hashimoto, P.O.; Mraz, M.J.; Tong, W.H.; Conoscente, J.P. (EQE, Inc., San Francisco, CA (USA)); Brosseau, D.A. (ERCE, Inc., Albuquerque, NM (USA))

1990-11-01T23:59:59.000Z

102

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

103

Pointer analysis for Java programs : novel techniques and applications  

E-Print Network (OSTI)

This dissertation presents a pointer analysis for Java programs, together with several practical analysis applications. For each program point, the analysis is able to construct a points-to graph that describes how local ...

S?lcianu, Alexandru D. (Alexandru Doru), 1975-

2006-01-01T23:59:59.000Z

104

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)

during the core recovery, gas and water are produced.Gas produced will displace some water, reducing the density

Kneafsey, Timothy J.

2010-01-01T23:59:59.000Z

105

Comparative analysis of core drilling and rotary drilling in volcanic terrane  

DOE Green Energy (OSTI)

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

106

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.

107

Rapid analysis of steels using laser-based techniques  

SciTech Connect

Based on the data obtained by this study, we conclude that laser-based techniques can be used to provide at least semi-quantitative information about the elemental composition of molten steel. Of the two techniques investigated here, the Sample-Only method appears preferable to the LIBS (laser-induced breakdown spectroscopy) method because of its superior analytical performance. In addition, the Sample-Only method would probably be easier to incorporate into a steel plant environment. However, before either technique can be applied to steel monitoring, additional research is needed.

Cremers, D.A.; Archuleta, F.L.; Dilworth, H.C.

1985-01-01T23:59:59.000Z

108

African Easterly Waves during 2004Analysis Using Objective Techniques  

Science Conference Proceedings (OSTI)

African easterly waves (AEWs) are identified in numerical model analyses using an objective technique based on the 700-hPa streamfunction field. This method has been developed to (i) reduce the amount of manual data interpretation, (ii) reduce ...

Gareth Berry; Chris Thorncroft; Tim Hewson

2007-04-01T23:59:59.000Z

109

Engineering product usability: a review and analysis techniques  

Science Conference Proceedings (OSTI)

This paper presents the need and importance of usability engineering, usability-related facts and figures, and a total of eleven usability analysis methods. Keywords: analysis methods, computer, human error, human factors, software, usability, usability engineering

B. S. Dhillon

2005-03-01T23:59:59.000Z

110

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

111

Weighted graph comparison techniques for brain connectivity analysis  

Science Conference Proceedings (OSTI)

The analysis of brain connectivity is a vast field in neuroscience with a frequent use of visual representations and an increasing need for visual analysis tools. Based on an in-depth literature review and interviews with neuroscientists, we explore ... Keywords: brain connectivity analysis, brain connectivity visualization, graph comparison

Basak Alper; Benjamin Bach; Nathalie Henry Riche; Tobias Isenberg; Jean-Daniel Fekete

2013-04-01T23:59:59.000Z

112

Drilling Techniques | Open Energy Information  

Open Energy Info (EERE)

Page Page Edit with form History Facebook icon Twitter icon » Drilling Techniques Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Drilling Techniques Details Activities (0) Areas (0) Regions (0) NEPA(20) Exploration Technique Information Exploration Group: Drilling Techniques Exploration Sub Group: None Parent Exploration Technique: Exploration Techniques Information Provided by Technique Lithology: Identify lithology and mineralization, provide core samples and rock cuttings Stratigraphic/Structural: Retrieved samples can be used to identify stratigraphy and structural features such as fracture networks or faults Hydrological: -Water samples can be used for geochemical analysis -Fluid pressures can be used to estimate flow rates

113

Measurement uncertainty analysis techniques applied to PV performance measurements  

DOE Green Energy (OSTI)

The purpose of this presentation is to provide a brief introduction to measurement uncertainty analysis, outline how it is done, and illustrate uncertainty analysis with examples drawn from the PV field, with particular emphasis toward its use in PV performance measurements. The uncertainty information we know and state concerning a PV performance measurement or a module test result determines, to a significant extent, the value and quality of that result. What is measurement uncertainty analysis It is an outgrowth of what has commonly been called error analysis. But uncertainty analysis, a more recent development, gives greater insight into measurement processes and tests, experiments, or calibration results. Uncertainty analysis gives us an estimate of the I interval about a measured value or an experiment's final result within which we believe the true value of that quantity will lie. Why should we take the time to perform an uncertainty analysis A rigorous measurement uncertainty analysis: Increases the credibility and value of research results; allows comparisons of results from different labs; helps improve experiment design and identifies where changes are needed to achieve stated objectives (through use of the pre-test analysis); plays a significant role in validating measurements and experimental results, and in demonstrating (through the post-test analysis) that valid data have been acquired; reduces the risk of making erroneous decisions; demonstrates quality assurance and quality control measures have been accomplished; define Valid Data as data having known and documented paths of: Origin, including theory; measurements; traceability to measurement standards; computations; uncertainty analysis of results.

Wells, C.

1992-10-01T23:59:59.000Z

114

Development of optimized core design and analysis methods for high power density BWRs  

E-Print Network (OSTI)

Increasing the economic competitiveness of nuclear energy is vital to its future. Improving the economics of BWRs is the main goal of this work, focusing on designing cores with higher power density, to reduce the BWR ...

Shirvan, Koroush

2013-01-01T23:59:59.000Z

115

BNL program in support of LWR degraded-core accident analysis  

SciTech Connect

Two major sources of loading on dry watr reactor containments are steam generatin from core debris water thermal interactions and molten core-concrete interactions. Experiments are in progress at BNL in support of analytical model development related to aspects of the above containment loading mechanisms. The work supports development and evaluation of the CORCON (Muir, 1981) and MARCH (Wooton, 1980) computer codes. Progress in the two programs is described in this paper. 8 figures.

Ginsberg, T.; Greene, G.A.

1982-01-01T23:59:59.000Z

116

Healthful LipidsChapter 5 Analysis of Lipids by New Hyphenated Techniques  

Science Conference Proceedings (OSTI)

Healthful Lipids Chapter 5 Analysis of Lipids by New Hyphenated Techniques Health Nutrition Biochemistry eChapters Health - Nutrition - Biochemistry AOCS Press Downloadable pdf of Chapter 5 Analysis of Lipids by

117

Measurement uncertainty analysis techniques applied to PV performance measurements  

DOE Green Energy (OSTI)

The purpose of this presentation is to provide a brief introduction to measurement uncertainty analysis, outline how it is done, and illustrate uncertainty analysis with examples drawn from the PV field, with particular emphasis toward its use in PV performance measurements. The uncertainty information we know and state concerning a PV performance measurement or a module test result determines, to a significant extent, the value and quality of that result. What is measurement uncertainty analysis? It is an outgrowth of what has commonly been called error analysis. But uncertainty analysis, a more recent development, gives greater insight into measurement processes and tests, experiments, or calibration results. Uncertainty analysis gives us an estimate of the I interval about a measured value or an experiment`s final result within which we believe the true value of that quantity will lie. Why should we take the time to perform an uncertainty analysis? A rigorous measurement uncertainty analysis: Increases the credibility and value of research results; allows comparisons of results from different labs; helps improve experiment design and identifies where changes are needed to achieve stated objectives (through use of the pre-test analysis); plays a significant role in validating measurements and experimental results, and in demonstrating (through the post-test analysis) that valid data have been acquired; reduces the risk of making erroneous decisions; demonstrates quality assurance and quality control measures have been accomplished; define Valid Data as data having known and documented paths of: Origin, including theory; measurements; traceability to measurement standards; computations; uncertainty analysis of results.

Wells, C.

1992-10-01T23:59:59.000Z

118

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

119

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

Science Conference Proceedings (OSTI)

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

120

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

Science Conference Proceedings (OSTI)

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

Note: This page contains sample records for the topic "technique 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

Application of the normalization data analysis technique for single specimen R-curve determination  

SciTech Connect

The authors conclude that the normalization technique for single specimen R-curve and J{sub IC} determination can be very effective. Much like EPD, this technique requires some user interpretation/judgement during data analysis and may be difficult to standardize or fully automate even with strict analysis rules.

Porr, W.C.; Mills, W.J.

1999-03-01T23:59:59.000Z

122

General Approach To Materials Classification Using Neutron Analysis Techniques  

Science Conference Proceedings (OSTI)

The 'neutron in, gamma out' method of elemental analysis has been known and used in many applications as an elemental analysis tool. This method is non-intrusive, non-destructive, fast and precise. This set of advantages makes neutron analysis attractive for even wider variety of uses beyond simple elemental analysis. The question that is addressed within this study is under what conditions neutron analysis can be used to differentiate materials of interest from a group or class of materials in the face of knowing that what is truly of interest is the molecular content of any sample under interrogation. Purpose of the study was to develop a neutron-based scanner for rapid differentiation of classes of materials sealed in small bottles. Developed scanner employs D-T neutron generator as a neutron source and HPGe gamma detectors. Materials can be placed into classes by many different properties. However, neutron analysis method can be used only few of them, such as elemental content, stoichiometric ratios and density of the scanned material. Set of parameters obtainable through neutron analysis serves as a basis for a hyperspace, where each point corresponds to a certain scanned material. Sub-volumes of the hyperspace correspond to different classes of materials. One of the most important properties of the materials are stoichiometric ratios of the elements comprising the materials. Constructing an algorithm for converting the observed gamma ray counts into quantities of the elements in the scanned sample is a crucial part of the analysis. Gamma rays produced in both fast inelastic scatterings and neutron captures are considered. Presence of certain elements in materials, such as hydrogen and chlorine can significantly change neutron dynamics within the sample, and, in turn, characteristic gamma lines development. These effects have been studied and corresponding algorithms have been developed to account for them.

Solovyev, Vladimir G. [Saint Gobain Crystals and Detectors, 12345 Kinsman Rd, Newbury, OH 44124 (United States); Koltick, David S. [Department of Physics, Purdue University, 525 Northwestern Avenue, West Lafayette, IN 47907 (United States)

2006-03-13T23:59:59.000Z

123

Analysis of hydrogen production during a BWR6 core heatup transient  

DOE Green Energy (OSTI)

An extensive study was performed for the prediction of hydrogen production during a BWR6 core heatup transient. Hydrogen production was found to be strongly affected by the transient core heat transfer and vessel hydrodynamics. Various sources important for steam generation and hydrogen production were identified. The results of the study were used by the NRC staff in their evaluation of the adequacy of the H/sub 2/ release histories suggested by the Hydrogen Control Owner's Group (HCOG). The owners group are sponsoring a 1/4 scale test program to investigate the adequacy of H/sub 2/ control during a degraded event. 1 ref., 2 figs.

Yang, J.W.; Pratt, W.T.

1986-01-01T23:59:59.000Z

124

Geospatial Products and Techniques at the Center for Transportation Analysis  

Science Conference Proceedings (OSTI)

This paper highlights geospatial science-related innovations and developments conducted by the Center for Transportation Analysis (CTA) at the Oak Ridge National Laboratory. CTA researchers have been developing integrated inter-modal transportation solutions through innovative and cost-effective research and development for many years. Specifically, this paper profiles CTA-developed Geographic Information System (GIS) products that are publicly available. Examples of these GIS-related products include: the CTA Transportation Networks; GeoFreight system; and the web-based Multi-Modal Routing Analysis System. In addition, an application on assessment of railroad Hazmat routing alternatives is also discussed.

Chin, Shih-Miao [ORNL; Hwang, Ho-Ling [ORNL; Peterson, Bruce E [ORNL

2008-01-01T23:59:59.000Z

125

Comparative analysis of evaluation techniques for transport policies  

Science Conference Proceedings (OSTI)

The objective of this paper is to examine and compare the use of a number of policy evaluation tools, which can be used to measure the impact of transport policies and programmes as part of a strategic environmental assessment (SEA) or sustainability appraisal. The evaluation tools that were examined include cost-benefit analysis (CBA), cost-effectiveness analysis (CEA) and multi-criteria decision analysis (MCDA). It was concluded that both CEA and CBA are useful for estimating the costs and/or benefits associated with transport policies but are constrained by the difficulty in quantifying non-market impacts and monetising total costs and benefits. Furthermore, CEA is limited to identifying the most 'cost-effective policy' for achieving a single, narrowly defined objective, usually greenhouse gas (GHG) reduction and is, therefore, not suitable for evaluating policy options with ancillary costs or a variety of potential benefits. Thus, CBA or CEA evaluation should be complemented by a complete environmental and socio-economic impact assessment approach such as MCDA. This method allows for participatory analysis and qualitative assessment but is subject to caveats such as subjectivity and value-laden judgments.

Browne, David, E-mail: davidbrowne2@gmail.co [Department of Civil, Structural and Environmental Engineering, Trinity College, Dublin (TCD), Dublin 2 (Ireland); Ryan, Lisa, E-mail: Lisa.RYAN@iea.or [International Energy Agency (IEA), Paris (France)

2011-04-15T23:59:59.000Z

126

Incorporation of phenomenological uncertainties in probabilistic safety analysis - application to LMFBR core disruptive accident energetics  

SciTech Connect

This report describes a method for quantifying frequency and consequence uncertainty distribution associated with core disruptive accidents (CDAs). The method was developed to estimate the frequency and magnitude of energy impacting the reactor vessel head of the Clinch River Breeder Plant (CRBRP) given the occurrence of hypothetical CDAs. The methodology is illustrated using the CRBR example.

Najafi, B.; Theofanous, T.G.; Rumble, E.T.; Atefi, B.

1984-08-01T23:59:59.000Z

127

Analysis of pulse-shape discrimination techniques for BC501A using GHz digital signal processing  

SciTech Connect

A comparison study of pulse-shape analysis techniques was conducted for a BC501A scintillator using digital signal processing (DSP). In this study, output signals from a preamplifier were input directly into a 1 GHz analog-to-digital converter. The digitized data obtained with this method was post-processed for both pulse-height and pulse-shape information. Several different analysis techniques were evaluated for neutron and gamma-ray pulse-shape discrimination. It was surprising that one of the simplest and fastest techniques resulted in some of the best pulse-shape discrimination results. This technique, referred to here as the Integral Ratio technique, was able to effectively process several thousand detector pulses per second. This paper presents the results and findings of this study for various pulse-shape analysis techniques with digitized detector signals.

Rooney, B. D. (Brian D.); Dinwiddie, D. R. (Derek R.); Nelson, M. A. (Mark A.); Rawool-Sullivan, Mohini W.

2001-01-01T23:59:59.000Z

128

WIMS/PANTHER analysis of UO{sub 2}/MOX cores using embedded super-cells  

Science Conference Proceedings (OSTI)

This paper describes a method of analysing PWR UO{sub 2}MOX cores with WIMS/PANTHER. Embedded super-cells, run within the reactor code, are used to correct the standard methodology of using 2-group smeared data from single assembly lattice calculations. In many other codes the weakness of this standard approach has been improved for MOX by imposing a more realistic environment in the lattice code, or by improving the sophistication of the reactor code. In this approach an intermediate set of calculations is introduced, leaving both lattice and reactor calculations broadly unchanged. The essence of the approach is that the whole core is broken down into a set of 'embedded' super-cells, each extending over just four quarter assemblies, with zero leakage imposed at the assembly mid-lines. Each supercell is solved twice, first with a detailed multi-group pin-by-pin solution, and then with the standard single assembly approach. Correction factors are defined by comparing the two solutions, and these can be applied in whole core calculations. The restriction that all such calculations are modelled with zero leakage means that they are independent of each other and of the core-wide flux shape. This allows parallel pre-calculation for the entire cycle once the loading pattern has been determined, in much the same way that single assembly lattice calculations can be pre-calculated once the range of fuel types is known. Comparisons against a whole core pin-by-pin reference demonstrates that the embedding process does not introduce a significant error, even after burnup and refuelling. Comparisons against a WIMS reference demonstrate that a pin-by-pin multi-group diffusion solution is capable of capturing the main interface effects. This therefore defines a practical approach for achieving results close to lattice code accuracy, but broadly at the cost of a standard reactor calculation. (authors)

Knight, M.; Bryce, P. [EDF Energy, Barnett Way, Barnwood, Gloucester (United Kingdom); Hall, S. [Advanced Modelling and Computation Group, Imperial College, London (United Kingdom)

2012-07-01T23:59:59.000Z

129

Time-frequency resolved ultrafast spectroscopy techniques using wavelet analysis  

E-Print Network (OSTI)

New experimental techniques based on non-linear ultrafast spectroscopies have been developed over the last few years, and have been demonstrated to provide powerful probes of quantum dynamics in different types of molecular aggregates, including both natural and artificial light harvesting complexes. Fourier transform-based spectroscopies have been particularly successful, yet 'complete' spectral information normally necessitates the loss of all information on the temporal sequence of events in a signal. This information though is particularly important in transient or multi-stage processes, in which the spectral decomposition of the data evolves in time. By going through several examples of ultrafast quantum dynamics, we demonstrate that the use of wavelets provide an efficient and accurate way to simultaneously acquire both temporal and frequency information about a signal, and argue that this greatly aids the elucidation and interpretation of physical process responsible for non-stationary spectroscopic features, such as those encountered in coherent excitonic energy transport.

Javier Prior; Enrique Castro; Alex W. Chin; Javier Almeida; Susana F. Huelga; Martin B. Plenio

2013-08-21T23:59:59.000Z

130

An analysis of radionuclide behavior in water pools during accidents at the Annular Core Research Reactor  

SciTech Connect

Physical and chemical phenomena that will affect the behavior of radionuclides released from fuel in the Annular Core Research Reactor during a hypothetical, core disruptive accident are described. The phenomena include boiling of water on heated clad, metal-water reactions, vapor nucleation to form aerosol particles, coagulation of aerosol particles, aerosol deposition within bubbles rising through the shield pool, vapor dissolution in the shield pool, and revaporization of radionuclides from the shield pool. A model of these phenomena is developed and applied to predict the release of radionuclides to the confinement building of the Annular Core Research Reactor. It is found that the shield pool provides overall decontamination factors for particulate of about 2.8 {times} 10{sup 5} and decontamination factors for noble gases of about 2.5--3.7. These results are found to be sensitive to the predicted clad temperature and bubble behavior in the shield pool. Slow revalorization of krypton, xenon and iodine from the shield pool is shown to create a prolonged, low-intensity source term of radioactive material to the confinement atmosphere.

Powers, D.A.

1992-08-01T23:59:59.000Z

131

Methods for magnetic resonance analysis using magic angle technique  

DOE Patents (OSTI)

Methods of performing a magnetic resonance analysis of a biological object are disclosed that include placing the object in a main magnetic field (that has a static field direction) and in a radio frequency field; rotating the object at a frequency of less than about 100 Hz around an axis positioned at an angle of about 54.degree.44' relative to the main magnetic static field direction; pulsing the radio frequency to provide a sequence that includes a phase-corrected magic angle turning pulse segment; and collecting data generated by the pulsed radio frequency. In particular embodiments the method includes pulsing the radio frequency to provide at least two of a spatially selective read pulse, a spatially selective phase pulse, and a spatially selective storage pulse. Further disclosed methods provide pulse sequences that provide extended imaging capabilities, such as chemical shift imaging or multiple-voxel data acquisition.

Hu, Jian Zhi (Richland, WA); Wind, Robert A. (Kennewick, WA); Minard, Kevin R. (Kennewick, WA); Majors, Paul D. (Kennewick, WA)

2011-11-22T23:59:59.000Z

132

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 monolithic UMo fuel. The design of an optimum LEU core for the ...

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

2008-01-01T23:59:59.000Z

133

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

134

A Comparison of Analysis and Forecast Correction Techniques:Impact of Negative Dissipation  

Science Conference Proceedings (OSTI)

The impact of negative dissipation on posttime analysis and forecast correction techniques is examined in a simplified context. The experiments are conducted using a three-level quasigeostrophic model (with a nonsingular tangent propagator matrix)...

Carolyn A. Reynolds

1999-11-01T23:59:59.000Z

135

Chemical analysis and sampling techniques for geothermal fluids and gases at the Fenton Hill Laboratory  

DOE Green Energy (OSTI)

A general description of methods, techniques, and apparatus used for the sampling, chemical analysis, and data reporting of geothermal gases and fluids is given. Step-by-step descriptions of the procedures are included in the appendixes.

Trujillo, P.E.; Counce, D.; Grigsby, C.O.; Goff, F.; Shevenell, L.

1987-06-01T23:59:59.000Z

136

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 17 Fat Replacers: An Overview  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 17 Fat Replacers: An Overview Methods and Analyses eChapters Methods - Analyses Books Downloadable pdf of Chapter 17 Fat Replacers: An Overview from

137

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 4 LC/MS and Chiral Separation  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 4 LC/MS and Chiral Separation Methods and Analyses eChapters Methods - Analyses Books AOCS Press Downloadable pdf of Chapter 4 LC/MS and Chiral S

138

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 19 Waxes and Sterols: Structures and Chemistry  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 19 Waxes and Sterols: Structures and Chemistry Methods and Analyses eChapters Methods - Analyses Books AOCS Press Downloadable pdf of Chapter 19

139

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 5 LC/MS and Lipid Oxidation  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 5 LC/MS and Lipid Oxidation Methods and Analyses eChapters Methods - Analyses Books Downloadable pdf of Chapter 5 LC/MS and Lipid Oxidation from

140

Analysis of Geostationary Satellite Imagery Using a Temporal-Differencing Technique  

Science Conference Proceedings (OSTI)

A new and innovative cloud analysis technique has been developed that exploits the temporal information content of geostationary satellite imagery. The algorithm is designed to identify new cloud development and moving cloud systems by comparing ...

Robert Paul d'Entremont; Gary B. Gustafson

2003-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

A Lagrangian Objective Analysis Technique for Assimilating In Situ Observations with Multiple-Radar-Derived Airflow  

Science Conference Proceedings (OSTI)

A new Lagrangian analysis technique is developed to assimilate in situ boundary layer measurements using multi-Doppler-derived wind fields, providing output fields of water vapor mixing ratio, potential temperature, and virtual potential ...

Conrad L. Ziegler; Michael S. Buban; Erik N. Rasmussen

2007-07-01T23:59:59.000Z

142

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

DOE Green Energy (OSTI)

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

143

KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS  

SciTech Connect

The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program utilizes the space-independent neutron kinetics equations with any number of delayed neutron groups to determine the reactivity in the reactor from the power and its derivative. The third program solves the space-independent kinetics equations for the neutron flux from an input reactivity or initial period. Up to 50 reactivity feedback equations includirg delayed neutrons are provided for in this program. A mathematical model of the reactor investigated extensively was one containing six delayed neutron groups, conventional treatment of temperature reactivity compensation, and void compensation of reactivity induced by radiolytic gas void growth proportional to the product of reactor power and energy release. Partial mathematical solutions to the kinetic equations were derived for reactivity feedback proportional to prompt temperature and void growth according to the product of power and energy. These solutions apply where delayed neutrons can be neglected, which is the region of major interest. Expressions are available relating power and energy and defining the peak power and energy release to peak power in terms of basic reactor parameters. Experimental evidence, particularly the experimental inlmour curve, of another reactivity influencing mechanism was found present in the reactor at periods shorter than 10 msec. This mechanism was shown to behave as a delayed neutron group, having a mean delay time of approximately 2 msec and an abundance of 2%. A plausible origin of such neutrons was shown to be the reflector which thermalizes core neutrons and returns them to the core following a delay. (auth)

Dunenfeld, M. comp.

1962-02-01T23:59:59.000Z

144

Scanning angle Raman spectroscopy: Investigation of Raman scatter enhancement techniques for chemical analysis  

SciTech Connect

This thesis outlines advancements in Raman scatter enhancement techniques by applying evanescent fields, standing-waves (waveguides) and surface enhancements to increase the generated mean square electric field, which is directly related to the intensity of Raman scattering. These techniques are accomplished by employing scanning angle Raman spectroscopy and surface enhanced Raman spectroscopy. A 1064 nm multichannel Raman spectrometer is discussed for chemical analysis of lignin. Extending dispersive multichannel Raman spectroscopy to 1064 nm reduces the fluorescence interference that can mask the weaker Raman scattering. Overall, these techniques help address the major obstacles in Raman spectroscopy for chemical analysis, which include the inherently weak Raman cross section and susceptibility to fluorescence interference.

Meyer, Matthew W. [Ames Laboratory

2013-03-14T23:59:59.000Z

145

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 12 Fast GC for Cellular FAME Analysis of Bacteria  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 12 Fast GC for Cellular FAME Analysis of Bacteria Methods and Analyses eChapters Methods - Analyses Books 1FEE4C7C73C70C0CBEFB8C79B2926801 AOCS Press

146

ABWR start-up test analysis using BWR core simulator with three-dimensional direct response matrix method  

Science Conference Proceedings (OSTI)

The ABWR start-up test analysis has been done with the BWR core simulator using the three--dimensional direct response matrix (3D-DRM) method. The Monte Carlo code VMONT made the sub-response matrices for the 3D-DRM method. Each boundary surface was subdivided by 4 x 4 for transverse segments, by 4 for angular segments and by 4 for axial zones in a node. For the calculation speedup, the 3D-DRM code used the divided sub-response matrices data set. The code used the MPI and OpenMP for the parallelized method. The median value is set as the average critical eigenvalues. The changes from the maximum value to the minimum value are 0.34 %{Delta}k with the spectral history method and 0.40 %{Delta}k without it, and the respective standard deviations were 0.12 % and 0.14 %. Using the spectral history method decreased the variation by 0.06 %{Delta}k. The root mean square differences of the axial power distribution were about 6 % between the analysis results and the plant data. Using the currents which converged in the previous exposure step reduced the number of iterations when the CR pattern changed only slightly. The averaged calculation time for each exposure step was about 5 hours on 12 PC Linux cluster servers with Core 2 Quad 3 GHz. (authors)

Mitsuyasu, T.; Ishii, K.; Hino, T.; Aoyama, M. [Hitachi, Ltd., Hitachi Research Laboratory, 2-1 Omika-cho 7-chome, Hitachi-shi Ibaraki-ken, 319-1221 (Japan)

2012-07-01T23:59:59.000Z

147

Core analysis of Chattanooga shale structures west of Pine Mountain fault, Whitley County, Kentucky  

SciTech Connect

A 100-ft oriented core from the Chandler 1 well in Whitley County, Kentucky, sampled the entire Chattanooga Shale section 10 mi west of the Pine Mountain fault. Cored slickenlined structures include 76 bedding-plane faults, four strike-slip faults, and 44 thrust faults. One interpreted kink band was encountered. Slickenline trends, fault geometry, interpreted paleo-stress fields, and chronology of structural evolution do not reflect the N30/sup 0/W transposition direction of the Pine Mountain sheet (seated in Chattanooga Shale) or N60/sup 0/E strike of the Pine Mountain fault. For example, 62% of 81 bedding-fault slickenline orientations trend N20/sup 0/-90/sup 0/W with N60/sup 0/-70/sup 0/W dominant. A secondary direction (32% of bedding slickenlines) strikes N40/sup 0/-80/sup 0/E with N60/sup 0/-70/sup 0/E dominant. Only 9% of bedding-fault slickenlines trend N25/sup 0/-35/sup 0/W. In addition, northwest-trending slickenlines formed first on four of five bedding faults containing both major trends. Thrust faults group into five mean attitudes. Four orientations (N31/sup 0/W, 38/sup 0/NE); N40/sup 0/W, 36/sup 0/SW; N15/sup 0/E, 45/sup 0/SE); and N46/sup 0/1E, 42/sup 0/NW) may define two conjugate shear sets that imply horizontal maximum compressive stress directions of N58/sup 0/W and N54/sup 0/E, respectively. The fifth trend (N88/sup 0/W, 48/sup 0/NE) may relate genetically to strike-slip faults oriented N20/sup 0/W and N60/sup 0/E that indicate horizontal maximum compressive stresses oriented N2/sup 0/-18/sup 0/E. Overprinted thrust-fault slickenlines and faults offsetting faults suggest that maximum compressive stresses first acted northwest-southeast, then northeast-southwest and, finally in a north-northeast-south-southwest direction. Furthermore, bedding faults preceded thrust faults. Differences between Pine Mountain sheet structures and those in the core may reflect local Chattanooga thickness variations or the absence of Chattanooga decollement structures.

Kulander, B.R.; Dean, S.L.; Kirr, J.; Feiler, J.

1987-09-01T23:59:59.000Z

148

Convergence acceleration techniques in CAD systems for grounding analysis in layered soils  

E-Print Network (OSTI)

by ground rods vertically thrusted in certain places of the substation site. Thus, when a fault conditionConvergence acceleration techniques in CAD systems for grounding analysis in layered soils I a numerical formulation based on the Boundary Element Method for the analysis of grounding systems embedded

Colominas, Ignasi

149

Solid phase microextraction analysis of B83 SLTS and Core B compatibility test units  

SciTech Connect

Solid phase microextraction has permitted the efficient collection and analysis of a broad range of volatile and semivolatile compounds outgassed from materials. In 1998, we implemented a microextraction protocol at Mason and Hanger, Pantex Plant, for the analysis of weapons and compatibility test units. The chemical information that was obtained from this work is interpreted by determining the source and outgas mechanism for each compound in the weapon signature, which is a task only accomplished by analysis of material standards.

Chambers, D M; Ithaca, J; King, H A; Malcolm, S

1999-03-26T23:59:59.000Z

150

Recent developments in pressure coring  

SciTech Connect

The current rapid growth in the number of enhanced oil and gas recovery projects has created a strong demand for reservoir data such as true residual oil saturations. The companies providing pressure coring services have moved to fill this need. Two recent developments have emerged with the potential of significantly improving the present performance of pressure coring. Coring bits utilizing synthetic diamond cutters have demonstrated coring rates of one-foot per minute while improving core recovery. It is also apparent that cores of a near-unconsolidated nature are more easily recovered. In addition, a special low invasion fluid that is placed in the core retriever has demonstrated reduced core washing by the drilling mud and a decrease in the complexity of preparing cores for analysis. This paper describes the design, laboratory, and field testing efforts that led to these coring improvements. Also, experience in utilizing these developments while recovering over 100 cores is discussed.

McFall, A. L.

1980-01-01T23:59:59.000Z

151

SIMMER-II: A computer program for LMFBR disrupted core analysis  

SciTech Connect

SIMMER-2 (Version 12) is a computer program to predict the coupled neutronic and fluid-dynamics behavior of liquid-metal fast reactors during core-disruptive accident transients. The modeling philosophy is based on the use of general, but approximate, physics to represent interactions of accident phenomena and regimes rather than a detailed representation of specialized situations. Reactor neutronic behavior is predicted by solving space (r,z), energy, and time-dependent neutron conservation equations (discrete ordinates transport or diffusion). The neutronics and the fluid dynamics are coupled via temperature- and background-dependent cross sections and the reactor power distribution. The fluid-dynamics calculation solves multicomponent, multiphase, multifield equations for mass, momentum, and energy conservation in (r,z) or (x,y) geometry. A structure field with nine density and five energy components; a liquid field with eight density and six energy components; and a vapor field with six density and on energy component are coupled by exchange functions representing a modified-dispersed flow regime with a zero-dimensional intra-cell structure model.

Bohl, W.R.; Luck, L.B.

1990-06-01T23:59:59.000Z

152

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

153

Analysis of Accidents at the Pakistan Research Reactor-1 Using Proposed Mixed-Fuel (HEU and LEU) Core  

Science Conference Proceedings (OSTI)

The Pakistan Research Reactor-1 (PARR-1) was converted from highly enriched uranium (HEU) to low-enriched uranium (LEU) fuel in 1991. The reactor is running successfully, with an upgraded power level of 10 MW. To save money on the purchase of costly fresh LEU fuel elements, the use of less burnt HEU spent fuel elements along with the present LEU fuel elements is being considered. The proposal calls for the HEU fuel elements to be placed near the thermal column to gain the required excess reactivity. In the present study the safety analysis of a proposed mixed-fuel core has been carried out at a calculated steady-state power level of 9.8 MW. Standard computer codes and correlations were employed to compute various parameters. Initiating events in reactivity-induced accidents involve various modes of reactivity insertion, namely, start-up accident, accidental drop of a fuel element on the core, flooding of a beam tube with water, and removal of an in-pile experiment during reactor operation. For each of these transients, time histories of reactor power, energy released, temperature, and reactivity were determined.

Bokhari, Ishtiaq H. [Pakistan Institute of Nuclear Science and Technology (Pakistan)

2004-12-15T23:59:59.000Z

154

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

155

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 effect. The bypass flow occurs when the coolant flow into gaps between fuel blocks. These gaps are formed as a result of carbon expansion and shrinkage induced by radiations and manufacturing and installation errors. Hot spots may appear in the core if the large portion of the coolant flows into bypass gaps instead of coolant channels in which the cooling efficiency is much higher. A preliminary three dimensional steady-state CFD analysis was performed with commercial code STARCCM+ 6.04 to investigate the bypass flow and crossflow phenomenon in the prismatic VHTR core. The k-? turbulence model was selected because of its robustness and low computational cost with respect to a decent accuracy for varied flow patterns. The wall treatment used in the present work is two-layer all y+ wall treatment to blend the wall laws to estimate the shear stress. Uniform mass flow rate was chose as the inlet condition and the outlet condition was zero gauge pressure outlet. Grid independence study was performed and the results indicated that the discrepancy of the solution due to the mesh density was within 2% of the bypass flow fraction. The computational results showed that the bypass flow fraction was around 12%. Furthermore, the presence of the crossflow gap resulted in a up to 28% reduction of the coolant in the bypass flow gap while mass flow rate of coolant in coolant channels increased by around 5%. The pressure drop at the inlet due to the sudden contraction in area could be around 1kpa while the value was about 180 Pa around the crossflow gap region. The error analysis was also performed to evaluate the accumulated errors from the process of discretization and iteration. It was found that the total error was around 4% and the variation for the bypass flow fraction was within 1%.

Wang, Huhu 1985-

2012-12-01T23:59:59.000Z

156

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.

157

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.

158

An interactive parallel coordinates technique applied to a tropical cyclone climate analysis  

Science Conference Proceedings (OSTI)

A highly interactive visual analysis system is presented that is based on an enhanced variant of parallel coordinates - a multivariate information visualization technique. The system combines many variations of previously described visual interaction ... Keywords: Climate study, Geovisualization, Hurricane, Multivariate information visualization, Parallel coordinates

Chad A. Steed; Patrick J. Fitzpatrick; T. J. Jankun-Kelly; Amber N. Yancey; J. Edward Swan II

2009-07-01T23:59:59.000Z

159

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 18 Phospholipids: Structures and Physicochemical Activities  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 18 Phospholipids: Structures and Physicochemical Activities Methods and Analyses eChapters Methods - Analyses Books 7F901335BDC265F6CD236F34E0A1D72F AOCS Press ...

160

Presented at the National Conference on Applied Techniques for Analysis and Management of the  

E-Print Network (OSTI)

1/ Presented at the National Conference on Applied Techniques for Analysis and Management Management (VRM) processes for their own agencies. Training Course The Federal Highway Administration contracted with Jones & Jones, a Seattle planning and design firm, to develop and conduct the training course

Standiford, Richard B.

Note: This page contains sample records for the topic "technique 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

High efficient numerical techniques for the earthing design and the analysis of grounded phenomena  

E-Print Network (OSTI)

" or "earthing" system of an electrical substation comprises all interconnected grounding fa- cilitiesHigh efficient numerical techniques for the earthing design and the analysis of grounded phenomena for the computational design of grounding systems of electrical installations in uniform and layered soils

Colominas, Ignasi

162

Evaluation of fluid-modeling techniques in the seismic analysis of LMFBR reactors  

Science Conference Proceedings (OSTI)

Fluid modeling is of great importance in the seismic analysis of the LMFBR primary system. If the fluid model used in the analysis is too simplified, the results could be very uncertain. On the other hand, if the model is too detailed, considerable difficulty might be encountered in the analysis. The objectives of this study are to examine the validity of the two commonly used fluid modeling techniques. i.e. simplified added mass method and lumped mass method and to provide some useful information on the treatment of fluid in seismic analysis. The validity of these two methods of analysis is examined by comparing the calculated seismic responses of a fluid-structure system based on these two methods with that calculated from a coupled fluid-structure interaction analysis in which the fluid is treated by continuum fluid elements.

Ma, D.C.; Gvildys, J.; Chang, Y.W.

1983-01-01T23:59:59.000Z

163

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

Science Conference Proceedings (OSTI)

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

164

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 8 Analysis of trans-18:1 Fatty Acids by Silver Ion HPLC  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 8 Analysis of trans-18:1 Fatty Acids by Silver Ion HPLC eChapters Methods - Analyses Books AOCS Press Downloadable pdf of Chapter 8 Analysis of tr

165

An analysis of the proposed MITR-III core to establish thermal-hydraulic limits at 10 MW. Final report  

Science Conference Proceedings (OSTI)

The 5 MW Massachusetts Institute of Technology Research Reactor (MITR-II) is expected to operate under a new license beginning in 1999. Among the options being considered is an upgrade in the heat removal system to allow operation at 10 MW. The purpose of this study is to predict the Limiting Safety System Settings and Safety Limits for the upgraded reactor (MITR-III). The MITR Multi-Channel Analysis Code was written to analyze the response of the MITR system to a series of anticipated transients in order to determine the Limiting Safety System Settings and Safety Limits under various operating conditions. The MIT Multi-Channel Analysis Code models the primary and secondary systems, with special emphasis placed on analyzing the thermal-hydraulic conditions in the core. The code models each MITR fuel element explicitly in order to predict the behavior of the system during flow instabilities. The results of the code are compared to experimental data from MITR-II and other sources. New definitions are suggested for the Limiting Safety System Settings and Safety Limits. MITR Limit Diagrams are included for three different heat removal system configurations. It is concluded that safe, year-round operating at 10 MW is possible, given that the primary and secondary flow rates are both increased by approximately 40%.

Harling, O.K.; Lanning, D.D.; Bernard, J.A.; Meyer, J.E.; Henry, A.F.

1997-06-01T23:59:59.000Z

166

A Second Look at Neutron Resonance Transmission Analysis as a Spent Fuel NDA Technique  

Science Conference Proceedings (OSTI)

Many different nondestructive analysis techniques are currently being investigated as a part of the United States Department of Energy's Next Generation Safeguards Initiative (NGSI) seeking methods to quantify plutonium in spent fuel. Neutron Resonance Transmission Analysis (NRTA) is one of these techniques. Having first been explored in the mid-1970s for the analysis of individual spent-fuel pins a second look, using advanced simulation and modeling methods, is now underway to investigate the suitability of the NRTA technique for assaying complete spent nuclear fuel assemblies. The technique is similar to neutron time-of-flight methods used for cross-section determinations but operates over only the narrow 0.1-20 eV range where strong, distinguishable resonances exist for both the plutonium (239, 240, 241,242Pu) and uranium (235,236,238U) isotopes of interest in spent fuel. Additionally, in this energy range resonances exists for six important fission products (99Tc, 103Rh, 131Xe, 133Cs, 145Nd, and 152Sm) which provide additional information to support spent fuel plutonium assay determinations. Initial modeling shows excellent agreement with previously published experimental data for measurements of individual spent-fuel pins where plutonium assays were demonstrated to have a precision of 2-4%. Within the simulation and modeling analyses of this project scoping studies have explored fourteen different aspects of the technique including the neutron source, drift tube configurations, and gross neutron transmission as well as the impacts of fuel burn up, cooling time, and fission-product interferences. These results show that NRTA may be a very capable experimental technique for spent-fuel assay measurements. The results suggest sufficient transmission strength and signal differentiability is possible for assays through up to 8 pins. For an 8-pin assay (looking at an assembly diagonally), 64% of the pins in a typical 17 ? 17 array of a pressurized water reactor fuel assembly can be part of a complete transmission assay measurement with high precision. Analysis of rows with up to 12 pins may also be feasible but with diminished precision. Preliminary data analysis of an NRTA simulation has demonstrated the simplicity of the technique.

James W .Sterbentz; David L. Chichester

2011-07-01T23:59:59.000Z

167

A generalized fitting technique for the LIFE2 fatigue analysis code  

DOE Green Energy (OSTI)

The analysis of component fatigue lifetime for a wind energy conversion system (WECS) requires that the component load spectrum be formulated in terms of stress cycles. Typically, these stress cycles are obtained from time series data using a cycle identification scheme. As discussed by many authors, the matrix or matrices of cycle counts that describe the stresses on a turbine are constructed from relatively short, representative samples of time series data. The ability to correctly represent the long-term behavior of the distribution of stress cycles from these representative samples is critical to the analysis of service lifetimes. Several techniques are currently used to convert representative samples to the lifetime cyclic loads on the turbine. There has been recently developed a set of fitting algorithms that is particularly useful for matching the body of the distribution of fatigue stress cycles on a turbine component. Fitting techniques are now incorporated into the LIFE2 fatigue/fracture analysis code for wind turbines. In this paper, the authors provide an overview of the fitting algorithms and describe the pre- and post-count algorithms developed to permit their use in the LIFE2 code. Typical case studies are used to illustrate the use of the technique.

Sutherland, H.J. [Sandia National Labs., Albuquerque, NM (United States). Wind Energy Research Dept.; Wilson, T. [Univ. of New Mexico, Albuquerque, NM (United States). New Mexico Engineering Research Inst.

1996-08-01T23:59:59.000Z

168

Phase-locked antiguided multiple-core ribbon fiber - IEEE ...  

With the evanescent technique, the field energy is localized on the gain cores, and nearest neighbor cores are cou- ... guide components as discussed above, ...

169

High Temperature Reactor (HTR) Deep Burn Core and Fuel Analysis: Design Selection for the Prismatic Block Reactor With Results from FY-2011 Activities  

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.

Michael A. Pope

2011-10-01T23:59:59.000Z

170

WAYPOINT: scaling coherence to thousand-core architectures  

Science Conference Proceedings (OSTI)

In this paper, we evaluate a set of coherence architectures in the context of a 1024-core chip multiprocessor (CMP) tailored to throughput-oriented parallel workloads. Based on our analysis, we develop and evaluate two techniques for scaling coherence ... Keywords: accelerator architecture, cache coherence, probe filtering

John H. Kelm; Matthew R. Johnson; Steven S. Lumettta; Sanjay J. Patel

2010-09-01T23:59:59.000Z

171

Spectrum shape-analysis techniques applied to the Hanford Tank Farms spectral gamma logs  

SciTech Connect

Gamma-ray spectra acquired with high-energy resolution by the spectral gamma logging systems (SGLSs) at the U.S. Department of Energy Hanford Tank Farms, Richland, Washington, are being analyzed for spectral shape characteristics. These spectral shapes, together with a conventional peak-area analysis, enable an analyst not only to identify the gamma-emitting species but also to determine in many instances its spatial distribution around a borehole and to identify the presence of the bremsstrahlung-producing contaminant {sup 90}Sr. The analysis relies primarily on the results of computer simulations of gamma spectra from the predominant radionuclide {sup 137}Cs for various spatial distributions. This log analysis methodology has evolved through an examination of spectral features from spectral logs taken at the SX, BY, and U Tank Farms at the Hanford Site. Initial results determined with this technique show it is possible, in most cases, to distinguish between concentrations of {sup 137}Cs. Work is continuing by experimentally measuring shape factors, incorporating spectrum shape processing in routine log analysis, and extending the techniques to additional radionuclides.

Wilson, R.D.

1997-05-01T23:59:59.000Z

172

Modern Methods for Lipid AnalysisChapter 7 Qualitative and Quantitative Analysis of Triacylglycerolsby Atmospheric Pressure Ionization (APCI and ESI) Mass Spectrometry Techniques  

Science Conference Proceedings (OSTI)

Modern Methods for Lipid Analysis Chapter 7 Qualitative and Quantitative Analysis of Triacylglycerolsby Atmospheric Pressure Ionization (APCI and ESI) Mass Spectrometry Techniques Methods and Analyses eChapters Methods - Analyses Books AO

173

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 9 High-Performance Size-Exclusion Chromatography for Lipid Analysis in Organic Media  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 9 High-Performance Size-Exclusion Chromatography for Lipid Analysis in Organic Media Methods and Analyses eChapters Methods - Analyses Books Downloadable pdf

174

Lipid Analysis and Lipidomics: New Techniques & Application-Ch 6Structural Analysis of Unsaturated Fatty Acid Methyl Ester Isomers with Acetonitrile Covalent Adduct Chemical Ionization  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application-Ch 6 Structural Analysis of Unsaturated Fatty Acid Methyl Ester Isomers with Acetonitrile Covalent Adduct Chemical Ionization Methods and Analyses eChapters Methods - Analyses Book

175

CORCON-MOD3: An integrated computer model for analysis of molten core-concrete interactions. User`s manual  

SciTech Connect

The CORCON-Mod3 computer code was developed to mechanistically model the important core-concrete interaction phenomena, including those phenomena relevant to the assessment of containment failure and radionuclide release. The code can be applied to a wide range of severe accident scenarios and reactor plants. The code represents the current state of the art for simulating core debris interactions with concrete. This document comprises the user`s manual and gives a brief description of the models and the assumptions and limitations in the code. Also discussed are the input parameters and the code output. Two sample problems are also given.

Bradley, D.R.; Gardner, D.R.; Brockmann, J.E.; Griffith, R.O. [Sandia National Labs., Albuquerque, NM (United States)

1993-10-01T23:59:59.000Z

176

Further Evaluation of the Neutron Resonance Transmission Analysis (NRTA) Technique for Assaying Plutonium in Spent Fuel  

Science Conference Proceedings (OSTI)

This is an end-of-year report (Fiscal Year (FY) 2011) for the second year of effort on a project funded by the National Nuclear Security Administration's Office of Nuclear Safeguards (NA-241). The goal of this project is to investigate the feasibility of using Neutron Resonance Transmission Analysis (NRTA) to assay plutonium in commercial light-water-reactor spent fuel. This project is part of a larger research effort within the Next-Generation Safeguards Initiative (NGSI) to evaluate methods for assaying plutonium in spent fuel, the Plutonium Assay Challenge. The second-year goals for this project included: (1) assessing the neutron source strength needed for the NRTA technique, (2) estimating count times, (3) assessing the effect of temperature on the transmitted signal, (4) estimating plutonium content in a spent fuel assembly, (5) providing a preliminary assessment of the neutron detectors, and (6) documenting this work in an end of the year report (this report). Research teams at Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), Pacific Northwest National Laboratory (PNNL), and at several universities are also working to investigate plutonium assay methods for spent-fuel safeguards. While the NRTA technique is well proven in the scientific literature for assaying individual spent fuel pins, it is a newcomer to the current NGSI efforts studying Pu assay method techniques having just started in March 2010; several analytical techniques have been under investigation within this program for two to three years or more. This report summarizes work performed over a nine month period from January-September 2011 and is to be considered a follow-on or add-on report to our previous published summary report from December 2010 (INL/EXT-10-20620).

J. W. Sterbentz; D. L. Chichester

2011-09-01T23:59:59.000Z

177

Fuel fabrication acceptance report FSV: initial core  

SciTech Connect

The fabrication of the Fort St. Vrain initial core is described. Detailed summaries of the final fuel element metal loadings and other properties are given. Problems that occurred during fabrication and their resolutions have been given special attention, including the results of analyses made prior to their adoption. A final substantiation for the Fort St. Vrain initial core was provided by a full-core, three-dimensional analysis considering control rod insertion and fuel depletion and with explicit representation of the as-built fuel elements. The calculated power distributions from the three dimensional analysis are well within the limits specified for the reference design. During fabrication of the initial core fuel elements, some difficulties with assayed quantities of uranium and thorium were encountered. These difficulties resulted from changes in the fuel rod standards used in assay equipment calibration and in the techniques employed for assaying fuel particles and fuel rods. As a result the apparent values for the average metal loadings for some fuel rods and fuel elements changed. For certain blends some already-assembled fuel elements were outside the tolerances given in the fuel specification. A study was undertaken to make recommendations on the disposition of already-fabricated fuel and adjustments for the remainder of fuel fabrication. This study focused on utilizing, as much as possible, already-fabricated fuel without compromising the performance of the core. A variety of adjustments were considered and used in some instances, but the most successful method was the imposition of a layer location on fuel elements. By use of this additional core assembly requirement, a distribution of high metal load and low metal load fuel elements was obtained that assured that power perturbations would be small and localized and that temperature perturbations would be small and confined to axial layers where temperatures are nominally low. (auth)

Kapernick, R.J.; Nirschl, R.J.

1973-12-01T23:59:59.000Z

178

Supporting technology for enhanced recovery, Annex V: evaluate application of recently developed techniques in the areas of drilling, coring, and telemetry. Venezuela-MEM/USA-DOE fossil-energy report V-1  

Science Conference Proceedings (OSTI)

The Agreement between the United States and Venezuela was designed to further energy research and development in six areas. This report focuses on Annex V - Drilling, Coring, and Telemetry as supporting technology for enhanced oil recovery projects in the United States and Venezuela. Annex V consists of 18 tasks to perform these three projects. This report completes the work for Annex V. Energy research and development in the area of Enhanced Oil Recovery has as its goal the more efficient and complete production of the third crop of oil. Methods and techniques must be developed to assist in the implementation of EOR projects. Technology development that reduces costs and provides better reservoir information often has a direct impact on the economic viability of EOR projects and Annex V addresses these areas. Each of the three areas covered by Annex V are separate entities and are presented in this report as different sections. Each has its own Abstract. The drilling and coring tests were highly successful but only a limited amount of work was necessary in the Telemetry area because a field test was not feasible.

Williams, C.R.; Lichaa, P.; Van Domselaar, H.

1983-04-01T23:59:59.000Z

179

Analysis of in-core experiment activities for the MIT Research Reactor using the ORIGEN computer code  

E-Print Network (OSTI)

The objective of this study is to devise a method for utilizing the ORIGEN-S computer code to calculate the activation products generated in in-core experimental assemblies at the MIT Research Reactor (MITR-II). ORIGEN-S ...

Helvenston, Edward M. (Edward March)

2006-01-01T23:59:59.000Z

180

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 16 Investigation of Protein-Lipid Interactions by Vibrational Spectroscopy  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 16 Investigation of Protein-Lipid Interactions by Vibrational Spectroscopy Methods and Analyses eChapters Methods - Analyses Books AOCS Press Downloadable

Note: This page contains sample records for the topic "technique 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

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 10 Lipid Separations Using Packed-Column Supercritical Fluid Chromatography  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 10 Lipid Separations Using Packed-Column Supercritical Fluid Chromatography Methods and Analyses eChapters Methods - Analyses Books AOCS Press Downloadabl

182

Extreme Chromatography: Faster, Hotter, SmallerChapter 8 Multiple Parallel Mass Spectrometry Techniques for Lipid and Vitamin D Analysis  

Science Conference Proceedings (OSTI)

Extreme Chromatography: Faster, Hotter, Smaller Chapter 8 Multiple Parallel Mass Spectrometry Techniques for Lipid and Vitamin D Analysis Methods and Analyses eChapters Methods - Analyses Books AOCS Press Downloadable pdf...

183

A Diabatic Lagrangian Technique for the Analysis of Convective Storms. Part II: Application to a radar-observed storm  

Science Conference Proceedings (OSTI)

A new diabatic Lagrangian analysis (DLA) technique that derives predicted fields of potential temperature, water vapor and cloud water mixing ratios, and virtual buoyancy from three-dimensional, time-dependent wind and reflectivity fields (see ...

Conrad L. Ziegler

184

Using digital filtering techniques as an aid in wind turbine data analysis  

DOE Green Energy (OSTI)

Research involving very large sets of digital data is often difficult due to the enormity of the database. In the case of a wind turbine operating under varying environmental conditions, determining which data are representative of the blade aerodynamics and which are due to transient flow ingestion effects or errors in instrumentation, operation, and data collection is of primary concern to researchers. The National Renewable Energy Laboratory in Golden, Colorado collected extensive data on a downwind horizontal axis wind turbine (HAWT) during a turbine test project called the Combined Experiment. A principal objective of this experiment was to provide a means to predict HAWT aerodynamic, mechanical, and electrical operational loads based upon analytical models of aerodynamic performance related to blade design and inflow conditions. In a collaborative effort with the Aerospace Engineering Department at the University of Colorado at Boulder, a team of researchers has evolved and utilized various digital filtering techniques in analyzing the data from the Combined Experiment. A preliminary analysis of the data set was performed to determine how to best approach the data. The reduced data set emphasized selection of inflow conditions such that the aerodynamic data could be compared directly to wind tunnel data obtained for the same airfoil design as used for the HAWT`s blades. It will be shown that this reduced data set has yielded valid, reproducible results that a simple averaging technique or a random selection approach cannot achieve. These findings provide a stable baseline against which operational HAWT data can be compared.

Young, T. [Univ. of Colorado, Boulder, CO (United States). BioServe Space Technologies

1994-11-01T23:59:59.000Z

185

Fabrication of Highly Luminescent Graded Core/Shell ...  

Paul Alivisatos, Erik Scher, and Liberato Manna have grown graded shells on CdSe core nanorods. Traditional techniques have ...

186

Development of MELCOR Input Techniques for High Temperature Gas-Cooled Reactor Analysis  

E-Print Network (OSTI)

High Temperature Gas-cooled Reactors (HTGRs) can provide clean electricity,as well as process heat that can be used to produce hydrogen for transportation and other sectors. A prototypic HTGR, the Next Generation Nuclear Plant (NGNP),will be built at Idaho National Laboratory.The need for HTGR analysis tools and methods has led to the addition of gas-cooled reactor (GCR) capabilities to the light water reactor code MELCOR. MELCOR will be used by the Nuclear Regulatory Commission licensing of the NGNP and other HTGRs. In the present study, new input techniques have been developed for MELCOR HTGR analysis. These new techniques include methods for modeling radiation heat transfer between solid surfaces in an HTGR, calculating fuel and cladding geometric parameters for pebble bed and prismatic block-type HTGRs, and selecting appropriate input parameters for the reflector component in MELCOR. The above methods have been applied to input decks for a water-cooled reactor cavity cooling system (RCCS); the 400 MW Pebble Bed Modular Reactor (PBMR), the input for which is based on a code-to-code benchmark activity; and the High Temperature Test Facility (HTTF), which is currently in the design phase at Oregon State University. RCCS results show that MELCOR accurately predicts radiation heat transfer rates from the vessel but may overpredict convective heat transfer rates and RCCS coolant flow rates. PBMR results show that thermal striping from hot jets in the lower plenum during steady-state operations, and in the upper plenum during a pressurized loss of forced cooling accident, may be a major design concern. Hot jets could potentially melt control rod drive mechanisms or cause thermal stresses in plenum structures. For the HTTF, results will provide data to validate MELCOR for HTGR analyses. Validation will be accomplished by comparing results from the MELCOR representation of the HTTF to experimental results from the facility. The validation process can be automated using a modular code written in Python, which is described here.

Corson, James

2010-05-01T23:59:59.000Z

187

Workshop: Tcnicas Avanadas de Anlise de Imagens de Sensoriamento Remoto (Recent Advances in Image Analysis Techniques for Remote Sensing)  

E-Print Network (OSTI)

in Image Analysis Techniques for Remote Sensing) Coordenadores: Leila Maria G. Fonseca (INPE) e João Paulo in remote sensing technology, especially improved spectral, spatial, and temporal resolutions, have put different from more conventional approaches for remote sensing image analysis. Hora Título das Palestras

188

Compound Specific Stable Nitrogen Isotope Analysis of Amino Acids: What can this Novel Technique tell us about  

E-Print Network (OSTI)

Compound Specific Stable Nitrogen Isotope Analysis of Amino Acids: What can this Novel Technique, Jeff Seminoff2 1Department of Geology and Geophysics, University of Hawaii 2Southwest Fisheries Science trophic models, but relationships often complex and dynamic #12;· Bulk tissue nitrogen isotope analysis

Hawai'i at Manoa, University of

189

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

Science Conference Proceedings (OSTI)

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

190

Combined analysis of solar neutrino and solar irradiance data: further evidence for variability of the solar neutrino flux and its implications concerning the solar core  

E-Print Network (OSTI)

A search for any particular feature in any single solar neutrino dataset is unlikely to establish variability of the solar neutrino flux since the count rates are very low. It helps to combine datasets, and in this article we examine data from both the Homestake and GALLEX experiments. These show evidence of modulation with a frequency of 11.85 yr-1, which could be indicative of rotational modulation originating in the solar core. We find that precisely the same frequency is prominent in power spectrum analyses of the ACRIM irradiance data for both the Homestake and GALLEX time intervals. These results suggest that the solar core is inhomogeneous and rotates with sidereal frequency 12.85 yr-1. We find, by Monte Carlo calculations, that the probability that the neutrino data would by chance match the irradiance data in this way is only 2 parts in 10,000. This rotation rate is significantly lower than that of the inner radiative zone (13.97 yr-1) as recently inferred from analysis of Super-Kamiokande data, suggesting that there may be a second, inner tachocline separating the core from the radiative zone. This opens up the possibility that there may be an inner dynamo that could produce a strong internal magnetic field and a second solar cycle.

P. A. Sturrock

2008-05-23T23:59:59.000Z

191

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

192

Analysis of Paraho oil shale products and effluents: an example of the multi-technique approach  

DOE Green Energy (OSTI)

Inorganic analysis of solid, liquid and gaseous samples from the Paraho Semiworks Retort was completed using a multitechnique approach. The data were statistically analyzed to determine both the precision of each method and to see how closely the various techniques compared. The data were also used to determine the redistribution of 31 trace and major elements in the various effluents, including the offgas for the Paraho Retort operating in the direct mode. The computed mass balances show that approximately 1% or greater fractions of the As, Co, Hg, N, Ni, S and Se are released during retorting and redistributed to the product shale oil, retort water or product offgas. The fraction for these seven elements ranged from almost 1% for Co and Ni to 50 to 60% for Hg and N. Approximately 20% of the S and 5% of the As and Se are released. The mass balance redistribution during retorting for Al, Fe, Mg, V and Zn was observed to be no greater than .05%. These redistribution figures are generally in agreement with previous mass balance studies made for a limited number of elements on laboratory or smaller scale pilot retorts. 7 tables.

Fruchter, J. S.; Wilkerson, C. L.; Evans, J. C.; Sanders, R. W.

1979-06-10T23:59:59.000Z

193

A Dosimetric Analysis of IMRT and Multistatic Fields Techniques for Left Breast Radiotherapy  

Science Conference Proceedings (OSTI)

The purpose of this study was to analyze the dosimetric difference between intensity-modulated radiation therapy (IMRT) using 3 or 5 beams and multistatic field technique (MSF) in radiotherapy of the left breast. We made comparative analysis of two kinds of radiotherapy that can achieve improved dose homogeneity. First is a MSF that uses both major and small irradiation fields at the same time. The other is IMRT using 3 or 5 beams with an inverse planning system using multiple static multileaf collimators. We made treatment plans for 16 early left breast cancer patients who were randomly selected and had undergone breast conserving surgery and radiotherapy, and analyzed them in the dosimetric aspect. For the mean values of V{sub 95} and dose homogeneity index, no statistically significant difference was observed among the three therapies. Extreme hot spots receiving >110% of prescribed dose were not found in any of the three methods. Using Tukey's test, IMRT showed a significantly larger increase in exposure dose to the ipsilateral lung and the heart than MSF in the low-dose area, but in the high-dose area, MSF showed a slight increase. To improve dose homogeneity, the application of MSF, which can be easily planned and applied more widely, is considered optimal as an alternative to IMRT for radiotherapy of early left breast cancer.

Moon, Seong Kwon [Department of Radiation Oncology, Soonchunhyang University Hospital, Bucheon-Si, Gyeonggi-do (Korea, Republic of); Kim, Yeon Sil [Department of Radiation Oncology, Catholic University of Korea, Seoul St. Mary's Hospital, Seoul (Korea, Republic of); Kim, Soo Young [Department of Preventive Medicine, Eulji University Hospital, Daejeon (Korea, Republic of); Lee, Mi Jo; Keum, Hyun Sup; Kim, Seung Jin; Youn, Seon Min [Department of Radiation Oncology, Eulji University Hospital, Daejeon (Korea, Republic of)

2011-10-01T23:59:59.000Z

194

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

195

Results of transient /accident analysis for the HEU, first mixed HEU-LEU and for the first full LEU cores of the WWR-SM reactor at INP AS RUZ  

SciTech Connect

The WWR-SM reactor in Uzbekistan is preparing for the conversion from HEU (36%) fuel to LEU (19.8%) fuel. During this conversion, the HEU fuel assemblies (IRT-3M FA) being discharged at the end of each cycle will be replaced by LEU fuel assemblies (IRT-4M FA); this gradual conversion requires 9 cycles. The safety analysis report for this conversion process has been prepared. This paper presents selected results for postulated transient/accidents during this conversion process; results for transient analysis for the HEU core, the 1st mixed (HEU-LEU) core, and for the first full LEU core are presented for the following initiators: control rod motion (2 cases), loss of power, and FA blockage. These results show that safety is maintained for all transients analyzed and that the behavior of all the analyzed cores is essentially the same. (author)

Baytelesov, S.A.; Dosimbaev, A.A.; Kungurov, F.R.; Salikhbaev, U.S. [Institute of Nuclear Physics, Ulugbek, 100214 Tashkent (Uzbekistan)

2008-07-15T23:59:59.000Z

196

Matrix Acidizing Core Flooding Apparatus: Equipment and Procedure Description  

E-Print Network (OSTI)

Core flooding is a commonly used experimental procedure in the petroleum industry. It involves pressurizing a reservoir rock and flowing fluid through it in the laboratory. The cylindrical rock, called a core, can be cut from the reservoir during a separate core drilling operation or a formation outcrop. A core flooding apparatus suitable for matrix acidizing was designed and assembled. Matrix acidizing is a stimulation technique in which hydrochloric acid (HCl) is injected down the wellbore below formation fracture pressure to dissolve carbonate (CaCO3) rock creating high permeability streaks called wormholes. The main components of the apparatus include a continuous flow syringe pump, three core holders, a hydraulic hand pump, two accumulators, a back pressure regulator, and two pressure transducers connected through a series of tubing and valves. Due to the corrosive nature of the acid, the apparatus features Hastelloy which is a corrosion resistant metal alloy. Another substantial feature of the apparatus is the ability to apply 3000psi back pressure. This is the pressure necessary to keep CO2, a product of the CaCO3 and HCl reaction, in solution at elevated temperatures. To perform experiments at temperature, the core holder is wrapped with heating tape and surrounded by insulation. Tubing is wrapped around a heating band with insulation to heat the fluid before it enters the core. A LabVIEW graphical programming code was written to control heaters as well as record temperature and pressure drop across the core. Other considerations for the design include minimizing footprint, operational ease by the user, vertical placement of the accumulators and core holders to minimize gravity effects, and air release valves. Core floods can be performed at varying injection rates, temperatures and pressures up to 5000psi and 250 degF. The apparatus can handle small core plugs, 1 diameter X 1 length, up to 4 X 20 cores. The equipment description includes the purpose, relevant features, and connections to the system for each component. Finally documented is the procedure to run a core flooding test to determine permeability and inject acid complete with an analysis of pressure response data.

Grabski, Elizabeth 1985-

2012-12-01T23:59:59.000Z

197

ANALYSIS OF EMERGING NDE TECHNIQUES: METHODS FOR EVALUATING AND IMPLEMENTING CONTINUOUS ONLINE MONITORING  

SciTech Connect

One of the goals of the program for the proactive management of materials degradation (PMMD) is to manage proactively the in-service degradation of metallic components in aging NPPs. As some forms of degradation, such as stress corrosion cracking, are characterized by a long initiation time followed by a rapid growth phase, new inspection or monitoring technologies may be required. New nondestructive evaluation (NDE) techniques that may be needed include techniques to find stress corrosion cracking (SCC) precursors, on-line monitoring techniques to detect cracks as they initiate and grow, as well as advances in NDE technologies. This paper reports on the first part of the development of a methodology to determine the effectiveness of these emerging NDE techniques for managing metallic degradation. This methodology will draw from experience derived from evaluating techniques that have "emerged" in the past. The methodology will follow five stages: a definition of inspection parameters, a technical evaluation, laboratory testing, round robin testing, and the design of a performance demonstration program. This methodology will formalize the path taken for previous techniques and set a predictable course for future NDE techniques. This paper then applies the expert review section of the methodology to the acoustic emission technique to evaluate the use of acoustic emission in performing continuous online monitoring of reactor components.

Cumblidge, Stephen E.; Doctor, Steven R.; Bond, Leonard J.; Taylor, Theodore T.; Lupold, Timothy R.; Hull, Amy; Malik, Shah

2009-08-05T23:59:59.000Z

198

TITAN : an advanced three dimensional coupled neutronicthermal-hydraulics code for light water nuclear reactor core analysis  

E-Print Network (OSTI)

The accurate analysis of nuclear reactor transients frequently requires that neutronics, thermal-hydraulics and feedback be included. A number of coupled neutronics/thermal-hydraulics codes have been developed for this ...

Griggs, D. P.

1984-01-01T23:59:59.000Z

199

Combined analysis of solar neutrino and solar irradiance data: further evidence for variability of the solar neutrino flux and its implications concerning the solar core  

E-Print Network (OSTI)

A search for any particular feature in any single solar neutrino dataset is unlikely to establish variability of the solar neutrino flux since the count rates are very low. It helps to combine datasets, and in this article we examine data from both the Homestake and GALLEX experiments. These show evidence of modulation with a frequency of 11.85 yr-1, which could be indicative of rotational modulation originating in the solar core. We find that precisely the same frequency is prominent in power spectrum analyses of the ACRIM irradiance data for both the Homestake and GALLEX time intervals. These results suggest that the solar core is inhomogeneous and rotates with sidereal frequency 12.85 yr-1. We find, by Monte Carlo calculations, that the probability that the neutrino data would by chance match the irradiance data in this way is only 2 parts in 10,000. This rotation rate is significantly lower than that of the inner radiative zone (13.97 yr-1) as recently inferred from analysis of Super-Kamiokande data, sugg...

Sturrock, P A

2008-01-01T23:59:59.000Z

200

Experimental and Analytic Study on the Core Bypass Flow in a Very High Temperature Reactor  

SciTech Connect

Core bypass flow has been one of key issues in the very high temperature reactor (VHTR) design for securing core thermal margins and achieving target temperatures at the core exit. The bypass flow in a prismatic VHTR core occurs through the control element holes and the radial and axial gaps between the graphite blocks for manufacturing and refueling tolerances. These gaps vary with the core life cycles because of the irradiation swelling/shrinkage characteristic of the graphite blocks such as fuel and reflector blocks, which are main components of a core's structure. Thus, the core bypass flow occurs in a complicated multidimensional way. The accurate prediction of this bypass flow and counter-measures to minimize it are thus of major importance in assuring core thermal margins and securing higher core efficiency. Even with this importance, there has not been much effort in quantifying and accurately modeling the effect of the core bypass flow. The main objectives of this project were to generate experimental data for validating the software to be used to calculate the bypass flow in a prismatic VHTR core, validate thermofluid analysis tools and their model improvements, and identify and assess measures for reducing the bypass flow. To achieve these objectives, tasks were defined to (1) design and construct experiments to generate validation data for software analysis tools, (2) determine the experimental conditions and define the measurement requirements and techniques, (3) generate and analyze the experimental data, (4) validate and improve the thermofluid analysis tools, and (5) identify measures to control the bypass flow and assess its performance in the experiment.

Richard Schultz

2012-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

Routine application of the in situ soil analysis technique by the Yankee Atomic Environmental Laboratory  

Science Conference Proceedings (OSTI)

Using a technique developed by the Environmental Measurements Laboratory (EML) for field spectrometry, the Yankee Atomic Environmental Laboratory (YAEL) has routinely performed in situ soil measurements in the vicinity of five nuclear power stations for more than a decade. As a special research endeavor, several locations at the FURNAS Angra 1 site in Brazil having high natural backgrounds were also measured in 1987. The technical basis of the technique, a comparison of soil radionuclide concentrations predicted by the in situ technique to soil radionuclide concentrations predicted by the in situ technique to soil analyses from the same sites, the advantages and disadvantages of the in situ methodology, and the evolution of the portable equipment utilized at YAEL for the field measurements are presented in this paper.

Murray, J.C.; McCurdy, D.E.; Laurenzo, E.L.

1989-01-01T23:59:59.000Z

202

Multimodel Combination Techniques for Analysis of Hydrological Simulations: Application to Distributed Model Intercomparison Project Results  

Science Conference Proceedings (OSTI)

This paper examines several multimodel combination techniques that are used for streamflow forecasting: the simple model average (SMA), the multimodel superensemble (MMSE), modified multimodel superensemble (M3SE), and the weighted average method ...

Newsha K. Ajami; Qingyun Duan; Xiaogang Gao; Soroosh Sorooshian

2006-08-01T23:59:59.000Z

203

High-Resolution Stratospheric Tracer Fields Reconstructed with Lagrangian Techniques: A Comparative Analysis of Predictive Skill  

Science Conference Proceedings (OSTI)

Numerical experiments and statistical analyses are conducted to determine the skill of different Lagrangian techniques for the construction of tracer distributions. High-resolution potential vorticity (PV) maps are calculated from simulations of ...

R. Dragani; G. Redaelli; G. Visconti; A. Mariotti; V. Rudakov; A. R. MacKenzie; L. Stefanutti

2002-06-01T23:59:59.000Z

204

CORE-BASED INTEGRATED SEDIMENTOLOGIC, STRATIGRAPHIC, AND GEOCHEMICAL ANALYSIS OF THE OIL SHALE BEARING GREEN RIVER FORMATION, UINTA BASIN, UTAH  

Science Conference Proceedings (OSTI)

An integrated detailed sedimentologic, stratigraphic, and geochemical study of Utah's Green River Formation has found that Lake Uinta evolved in three phases (1) a freshwater rising lake phase below the Mahogany zone, (2) an anoxic deep lake phase above the base of the Mahogany zone and (3) a hypersaline lake phase within the middle and upper R-8. This long term lake evolution was driven by tectonic basin development and the balance of sediment and water fill with the neighboring basins, as postulated by models developed from the Greater Green River Basin by Carroll and Bohacs (1999). Early Eocene abrupt global-warming events may have had significant control on deposition through the amount of sediment production and deposition rates, such that lean zones below the Mahogany zone record hyperthermal events and rich zones record periods between hyperthermals. This type of climatic control on short-term and long-term lake evolution and deposition has been previously overlooked. This geologic history contains key points relevant to oil shale development and engineering design including: (1) Stratigraphic changes in oil shale quality and composition are systematic and can be related to spatial and temporal changes in the depositional environment and basin dynamics. (2) The inorganic mineral matrix of oil shale units changes significantly from clay mineral/dolomite dominated to calcite above the base of the Mahogany zone. This variation may result in significant differences in pyrolysis products and geomechanical properties relevant to development and should be incorporated into engineering experiments. (3) This study includes a region in the Uinta Basin that would be highly prospective for application of in-situ production techniques. Stratigraphic targets for in-situ recovery techniques should extend above and below the Mahogany zone and include the upper R-6 and lower R-8.

Lauren P. Birgenheier; Michael D. Vanden Berg,

2011-04-11T23:59:59.000Z

205

A Shell/3D Modeling Technique for the Analysis of Delaminated Composite Laminates  

E-Print Network (OSTI)

A shell/3D modeling technique developed which local three-dimensional solid finite element model used only immediate vicinity delamination front. The goal was combine the accuracy the three-dimensional solution with the computational efficiency plate shell finite element model. Multi-point constraints provided kinematically compatible interface between local three-dimensional model global structural model which has been meshed with plate shell finite elements. Double Cantilever Beam (DCB), Notched Flexure (ENF), Single Bending (SLB) specimens were modeled using shell/3D technique study feasibility pure mode (DCB), mode (ENF) mixed mode I/II (SLB) cases. Mixed mode strain energy release rate distributions were computed across the width specimens using virtual crack closure technique. Specimens a unidirectional layup and with multidirectional layup where delamination located between two non-zero degree plies were simulated. For a local three-dimensional model, extending minimum about thr...

Ronald Krueger; T. Kevin O' Brien

2001-01-01T23:59:59.000Z

206

Computer shadow analysis technique for tilted windows shaded by overhangs, vertical projections, and side fins  

SciTech Connect

This paper expands upon previously published techniques for calculating window shadow areas by computer to include tilted and horizontal glazing systems as well as vertical glazing systems. This methodology may be used for any rectangular window shaded by rectangular overhangs and/or side fins perpendicular to the plane of the window. Rectangular projections suspended from the end of an overhang are also accommodated. The technique yields a precise solution and requires minimum input. Computer processing is rapid because iterative algorithms are avoided. Shadow overlaps and end effects are completely treated. The glazing system may have any degree of tilt from horizontal (looking upward) through vertical to horizontal (looking downward). Techniques for sorting window shadow shapes and equations for calculating shadow areas are included.

Bekooy, R.G.

1983-01-01T23:59:59.000Z

207

Three-dimensional mapping techniques in the analysis of a mature steam drive  

SciTech Connect

The use of interactive volumetric modeling (IVM), a three-dimensional mapping software package that employs a three-dimensional gridding algorithm, greatly assisted in evaluating the efficiency of a mature steam drive in the South Belridge field, Kern County, California. The productive horizon consists of Pleistocene-aged unconsolidated oil sands interbedded with impermeable shales. The sand-shale architecture is controlled by a prograding of fluviodeltaic depositional system. For mapping convenience, the Tulare reservoir has been divided into five zones, the lowermost E zone to the uppermost A zone. In ascending order the reservoir can be characterized by the following description: lowest in the section are isolated to coalescing mouth bars, followed by fairly continuous lower delta plain interdistributary channels, isolated meandering stream channels of the upper delta plain, and uppermost, a braided stream complex of amalgamated channel sands. A drilling program consisting of 68 wells evenly distributed over 100 acres supplied ample log and core information and in effect presented a snap-shot of the reservoir in its maturity. Drilling revealed zones with excellent sweep and, conversely, zones that had been bypassed by the steam drive. By using well-log data tied to core data three-dimensional maps of individual sands incorporating structure, sand thicknesses in a multicolored format were generated to show the changing oil saturation values throughout the reservoir. The graphic presentation of these data on the CRT allows the user to rotate and cut through the sand body of interest revealing virtually an infinite number of perspectives. A hard copy option gives the user a printed map of any perspective of interest. The software is also capable of precise volumetric calculations of the oil remaining in the reservoir.

Barrett, R.A. (Mobil Exploration and Producing, Denver, CO (USA))

1990-06-01T23:59:59.000Z

208

Analysis of the optics of the Final Focus Test Beam using Lie algebra based techniques  

Science Conference Proceedings (OSTI)

This report discusses the analysis of the beam optics of the final focus test beam at the Stanford Linear Collider using Lie algebra. (LSP).

Roy, G.J.

1992-09-01T23:59:59.000Z

209

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)

The coolant flow instability, apparent in the coolant mass flow fluctuations in the separate parallel heating channels and also in a closed loop of the primary circuit under some operating conditions, is observed in the core fuel assemblies of light water reactors. In some ways this phenomenon is identical with the fluctuations in the once-through steam generators pipes, and changes of the coolant mass flows and length of flow patterns are initiating this phenomenon. The parameters at the core output and the secondary circuit parameters have influence on each other. These parameter changes have significant influences on the operating processes, operating and control algorithms, operating and control system design, and reliability of the operating power plant's machines and equipment. Changes of heating surface temperatures, displacement borders of the flow patterns, and critical heat flux entail changes of the coolant flow parameters, finally causing changes of the initial primary system 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. Additionally, these local side-to-side power irregularities in sub-zones may appear due to the influence of various hydrodynamic instabilities. The local side-to-side power in these sub-zones may differ significantly from each other. The aforesaid arguments are correct for the both light water reactor types. But, as is shown by our investigations and operational practice of low-boiling reactors, behavior of the core-circuit hydrodynamic system is significantly different from its behavior in the boiling or pressurized reactors with pumping circulation. The coolant flow regimes in typical reactors are defined through pump operating regimes and are not adjustable inside a certain power range. The objective of this thesis is to understand more precisely the influence and the nature of these phenomena. After analyzing the problem from different points of view and showing the necessity of its comprehensive understanding, we present recommendations for engineering solutions and plans for further investigations. We will try to determine limits of their reliable practical application with modern low-to-medium power reactor design and investigate this dynamic system behavior. Finally, it is necessary to take into consideration not separate phenomena, but their complex influence on the whole primary system (i.e. a kind of macro-system is examined without being separated into its individual elements). But, the analysis of every phenomenon is fulfilled separately and a process of formation of a block-scheme, consisting of several sub-systems, is given in this thesis. The final block-scheme is presented as a simulator model, taking into consideration design components chosen for the analysis of system dynamics as the first step of model development.

Rezvyi, Aleksey

2002-01-01T23:59:59.000Z

210

An Auto-Adaptive Multidomain Spectral Technique for Linear Stability Analysis: Application to Viscous Compressible Flows  

Science Conference Proceedings (OSTI)

An auto-adaptive multidomain pseudo-spectral technique is considered in order to solve the linear stability problem of viscous compressible flows. Both the locations of the interfaces and the parameters of the mappings in each subdomain are adapted by ... Keywords: RayleighTaylor instability, compressible viscous flows, spectral multidomain method

Eric Serre; Serge Gauthier

2002-12-01T23:59:59.000Z

211

Research on memory access vulnerability analysis technique in SCADA protocol implementation  

Science Conference Proceedings (OSTI)

SCADA systems play key roles in monitor and control of the critical infrastructures, the vulnerabilities existed in them may destroy the controlled critical infrastructures. This paper proposes an analysis method of memory access vulnerability in SCADA ... Keywords: SCADA protocol implementation, dynamic analysis, memory access vulnerability

Fang Lan; Wang Chunlei; He Ronghui

2010-07-01T23:59:59.000Z

212

Analysis of electricity consumption profiles in public buildings with dimensionality reduction techniques  

Science Conference Proceedings (OSTI)

The analysis of the daily electricity consumption profile of a building and its correlation with environmental factors makes it possible to examine and estimate its electricity demand. As an alternative to the traditional correlation analysis, a new ... Keywords: Dimensionality reduction, Electricity consumption profiles, Energy efficiency, Information visualization

Antonio MorN, Juan J. Fuertes, Miguel A. Prada, SerafN Alonso, Pablo Barrientos, Ignacio DAz, Manuel DomNguez

2013-09-01T23:59:59.000Z

213

DRDU: A data reuse analysis technique for efficient scratch-pad memory management  

Science Conference Proceedings (OSTI)

In multimedia and other streaming applications, a significant portion of energy is spent on data transfers. Exploiting data reuse opportunities in the application, we can reduce this energy by making copies of frequently used data in a small local memory ... Keywords: Scratch-pad memory management, compiler analysis, data reuse analysis, memory hierarchy

Ilya Issenin; Erik Brockmeyer; Miguel Miranda; Nikil Dutt

2007-04-01T23:59:59.000Z

214

Using sensitivity analysis and visualization techniques to open black box data mining models  

Science Conference Proceedings (OSTI)

In this paper, we propose a new visualization approach based on a Sensitivity Analysis (SA) to extract human understandable knowledge from supervised learning black box data mining models, such as Neural Networks (NNs), Support Vector Machines (SVMs) ... Keywords: Classification, Input importance, Regression, Sensitivity analysis, Supervised data mining, Visualization

Paulo Cortez; Mark J. Embrechts

2013-03-01T23:59:59.000Z

215

A review on vision techniques applied to Human Behaviour Analysis for Ambient-Assisted Living  

Science Conference Proceedings (OSTI)

Human Behaviour Analysis (HBA) is more and more being of interest for computer vision and artificial intelligence researchers. Its main application areas, like Video Surveillance and Ambient-Assisted Living (AAL), have been in great demand in recent ... Keywords: Action recognition, Activities of daily living (ADLs), Activity recognition, Ambient-Assisted Living, Computer vision, Human behaviour, Motion analysis

Alexandros Andr Chaaraoui; Pau Climent-Prez; Francisco Flrez-Revuelta

2012-09-01T23:59:59.000Z

216

Neutron Resonance Transmission Analysis (NRTA): A Nondestructive Assay Technique for the Next Generation Safeguards Initiatives Plutonium Assay Challenge  

SciTech Connect

This is an end-of-year report for a project funded by the National Nuclear Security Administration's Office of Nuclear Safeguards (NA-241). The goal of this project is to investigate the feasibility of using Neutron Resonance Transmission Analysis (NRTA) to assay plutonium in commercial light-water-reactor spent fuel. This project is part of a larger research effort within the Next-Generation Safeguards Initiative (NGSI) to evaluate methods for assaying plutonium in spent fuel, the Plutonium Assay Challenge. The first-year goals for this project were modest and included: 1) developing a zero-order MCNP model for the NRTA technique, simulating data results presented in the literature, 2) completing a preliminary set of studies investigating important design and performance characteristics for the NRTA measurement technique, and 3) documentation of this work in an end of the year report (this report). Research teams at Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), Pacific Northwest National Laboratory (PNNL), and at several universities are also working to investigate plutonium assay methods for spent-fuel safeguards. While the NRTA technique is well proven in the scientific literature for assaying individual spent fuel pins, it is a newcomer to the current NGSI efforts studying Pu assay method techniques having just started in March 2010; several analytical techniques have been under investigation within this program for two to three years or more. This report summarizes a nine month period of work.

J. W. Sterbentz; D. L. Chichester

2010-12-01T23:59:59.000Z

217

A Unified Technique for Dynamic Modeling and Stability Analysis of Microgrid Systems.  

E-Print Network (OSTI)

??This work presents a unified method for dynamic modeling and stability analysis of microgrid power systems. Using the automated state-model generation algorithm, a state-space model (more)

Johnson, Brian B.

2010-01-01T23:59:59.000Z

218

A Comparison of Two Objective Analysis Techniques for Profiler Time-Height Data  

Science Conference Proceedings (OSTI)

Two methods for objective analysis of wind profiler data in time-height space are proposed and compared. One is a straightforward adaptation of a procedure developed by Doswell for introducing time continuity into a sequence of spatial analyses. ...

Frederick H. Carr; Phillip L. Spencer; Charles A. Doswell III; Jeffrey D. Powell

1995-07-01T23:59:59.000Z

219

Evaluation of the Optimum Interpolation and Nudging Techniques for Soil Moisture Analysis Using FIFE Data  

Science Conference Proceedings (OSTI)

Initialization of land surface prognostic variables is a crucial issue for short- and medium-range forecasting as well as at seasonal timescales. In this study, two sequential soil moisture analysis schemes are tested, both based on the ...

Herv Douville; Pedro Viterbo; Jean-Franois Mahfouf; Anton C. M. Beljaars

2000-06-01T23:59:59.000Z

220

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

Note: This page contains sample records for the topic "technique 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

An Empirical Analysis of Semantic Techniques Applied to a Network Management Classification Problem  

Science Conference Proceedings (OSTI)

Semantic technologies are increasingly being employed to integrate, relate and classify heterogeneous data from various problem domains. To date, however, little empirical analysis has been carried out to help identify the benefits and limitations of ... Keywords: OWL, SWRL, SPARQL, axioms, rules, queries, network performance management

Aidan Boran; Ivan Bedini; Christopher J. Matheus; Peter F. Patel-Schneider; Stefan Bischof

2012-12-01T23:59:59.000Z

222

Organizational Epidemiology and Energy Facilities: Statistical Techniques for Empirical Analysis and Prediction of Human Performance Trends  

Science Conference Proceedings (OSTI)

This report describes an empirical study of the prediction of human performance and energy facility performance based on analysis of historical data relating to worker-, workplace-, management-, and organization-centered factors. Findings verify the relationship between antecedent conditions of human performance and facility productivity, reliability, and safety.

2002-07-23T23:59:59.000Z

223

Combining statistical data analysis techniques to extract topical keyword classes from corpora  

Science Conference Proceedings (OSTI)

We present an unsupervised method for the generation from a textual corpus of sets of keywords, that is, words whose occurrences in a text are strongly connected with the presence of a given topic. Each of these classes is associated with one of the ... Keywords: Statistical Data Analysis, Topic Characterization, Topic Detection, Unsupervised Classification

Mathias Rossignol; Pascale Sbillot

2005-01-01T23:59:59.000Z

224

Analysis of cache-coherence bottlenecks with hybrid hardware/software techniques  

Science Conference Proceedings (OSTI)

Application performance on high-performance shared-memory systems is often limited by sharing patterns resulting in cache-coherence bottlenecks. Current approaches to identify coherence bottlenecks incur considerable run-time overhead and do not scale. ... Keywords: Hardware performance monitoring, SMPs, cache analysis, coherence protocols, dynamic binary rewriting, program instrumentation

Jaydeep Marathe; Frank Mueller; Bronis R. de Supinski

2006-12-01T23:59:59.000Z

225

A survey on automated dynamic malware-analysis techniques and tools  

Science Conference Proceedings (OSTI)

Anti-virus vendors are confronted with a multitude of potentially malicious samples today. Receiving thousands of new samples every day is not uncommon. The signatures that detect confirmed malicious threats are mainly still created manually, so it is ... Keywords: Dynamic analysis, malware

Manuel Egele; Theodoor Scholte; Engin Kirda; Christopher Kruegel

2012-02-01T23:59:59.000Z

226

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 INLs LOFT (Loss of Fluid Test) reactor project and other sources.

Layne Pincock; Wendell Hintze

2013-01-01T23:59:59.000Z

227

New technique for phase shift analysis: multi-energy solution of inverse scattering problem  

E-Print Network (OSTI)

We demonstrate a new approach to the analysis of extensive multi-energy data. For the case of d + He-4, we produce a phase shift analysis covering for the energy range 3 to 11 MeV. The key idea is the use of iterative perturbative data-to-potential inversion which can produce potentials which reproduce the data simultaneously over a range of energies. It thus effectively regularizes the extraction of phase shifts from diverse, incomplete and possibly somewhat contradictory data sets. In doing so, it will provide guidance to experimentalists as to what further measurements should be made. This study is limited to vector spin observables and spin-orbit interactions. We discuss alternative ways in which the theory can be implemented and which provide insight into the ambiguity problems. We compare the extrapolation of these solutions to other energies. Majorana terms are presented for each potential component.

S. G. Cooper; V. I. Kukulin; R. S. Mackintosh; E. V. Kuznetsova

1998-03-05T23:59:59.000Z

228

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)

229

HYDRGN - a computerized technique for the analysis of thermochemical water-splitting cycles  

DOE Green Energy (OSTI)

The HYDRGN computer program was designed to analyze closed thermochemical cycles for the production of hydrogen from water. This report includes the basic theory, assumptions, and methods of calculation used in this analysis along with a description of the program and its use. The source program and necessary data bank are available from the University of Kentucky. These may be obtained by sending a magnetic tape (minimum length 1200 ft) and a written request specifying the type of computer and recording characteristics of the tape. A small fee is charged for the recording and handling of the tape.

Carty, R. H.; Conger, W. L.; Funk, J. E.; Barker, R.

1977-06-01T23:59:59.000Z

230

HPC Usage Behavior Analysis and Performance Estimation with Machine Learning Techniques  

Science Conference Proceedings (OSTI)

Most researchers with little high performance computing (HPC) experience have difficulties productively using the supercomputing resources. To address this issue, we investigated usage behaviors of the world s fastest academic Kraken supercomputer, and built a knowledge-based recommendation system to improve user productivity. Six clustering techniques, along with three cluster validation measures, were implemented to investigate the underlying patterns of usage behaviors. Besides manually defining a category for very large job submissions, six behavior categories were identified, which cleanly separated the data intensive jobs and computational intensive jobs. Then, job statistics of each behavior category were used to develop a knowledge-based recommendation system that can provide users with instructions about choosing appropriate software packages, setting job parameter values, and estimating job queuing time and runtime. Experiments were conducted to evaluate the performance of the proposed recommendation system, which included 127 job submissions by users from different research fields. Great feedback indicated the usefulness of the provided information. The average runtime estimation accuracy of 64.2%, with 28.9% job termination rate, was achieved in the experiments, which almost doubled the average accuracy in the Kraken dataset.

Zhang, Hao [ORNL; You, Haihang [ORNL; Hadri, Bilel [ORNL; Fahey, Mark R [ORNL

2012-01-01T23:59:59.000Z

231

Using `core documents' for the representation of clusters and topics  

Science Conference Proceedings (OSTI)

The notion of `core documents', first introduced in the context of co-citation analysis and later re-introduced for bibliographic coupling, refers to the representation of the core of a publication set according to given criteria. In the present study, ... Keywords: Bibliographic coupling, Cluster analysis, Core documents, Hybrid clustering, Text mining

Wolfgang Glnzel; Bart Thijs

2011-07-01T23:59:59.000Z

232

New analysis techniques for estimating impacts of federal appliance efficiency standards  

SciTech Connect

Impacts of U.S. appliance and equipment standards have been described previously. Since 2000, the U.S. Department of Energy (DOE) has updated standards for clothes washers, water heaters, and residential central air conditioners and heat pumps. A revised estimate of the aggregate impacts of all the residential appliance standards in the United States shows that existing standards will reduce residential primary energy consumption and associated carbon dioxide (CO{sub 2}) emissions by 89 percent in 2020 compared to the levels expected without any standards. Studies of possible new standards are underway for residential furnaces and boilers, as well as a number of products in the commercial (tertiary) sector, such as distribution transformers and unitary air conditioners. The analysis of standards has evolved in response to critiques and in an attempt to develop more precise estimates of costs and benefits of these regulations. The newer analysis elements include: (1) valuing energy savings by using marginal (rather than average) energy prices specific to an end-use; (2) simulating the impacts of energy efficiency increases over a sample population of consumers to quantify the proportion of households having net benefits or net costs over the life of the appliance; and (3) calculating marginal markups in distribution channels to derive the incremental change in retail prices associated with increased manufacturing costs for improving energy efficiency.

McMahon, James E.

2003-06-24T23:59:59.000Z

233

Rugged fiber optic probes and sampling systems for remote chemical analysis via the Raman technique  

DOE Green Energy (OSTI)

Recent advances in fiber optics, diode lasers, CCD detectors, dielectric and holographic optical filters, grating spectrometers, and chemometric data analysis have greatly simplified Raman spectroscopy. In order to make a rugged fiber optic Raman probe for solids/slurries like these at Savannah River, we have designed a probe that eliminates as many optical elements and surfaces as possible. The diffuse reflectance probe tip is modified for Raman scattering by installing thin dielectric in-line filters. Effects of each filter are shown for the NaNO{sub 3} Raman spectrum. By using a diode laser excitation at 780 nm, fluorescence is greatly reduced, and excellent spectra may be obtained from organic solids. At SRS, fiber optic Raman probes are being developed for in situ chemical mapping of radioactive waste storage tanks. Radiation darkening of silica fiber optics is negligible beyond 700 nm. Corrosion resistance is being evaluated. Analysis of process gas (off-gas from SRS processes) is investigated in some detail: hydrogen in nitrogen with NO{sub 2} interference. Other applications and the advantages of the method are pointed out briefly.

Nave, S.E.

1996-07-01T23:59:59.000Z

234

Residential Utility Core Wall System - ResCore  

SciTech Connect

This paper describes activities associated with the RESidential utility CORE wall system (ResCore) developed by students and faculty in the Department of Industrial Design at Auburn University between 1996 and 1998. These activities analyize three operational prototype units installed in Habitat for Humanity Houses. The paper contains two Parts: 1) analysis of the three operational prototype units, 2) exploration of alternative design solutions. ResCore is a manufactured construction component designed to expedite home building by decreasing the need for skilled labor at the work site. The unit concentrates untility elements into a wall unit(s), which is shipped to the construction site and installed in minimum time. The ResCore unit is intended to be built off-site in a manufacturing environment where the impact of vagaries of weather and work-crew coordination and scheduling are minimized. The controlled environment of the factory enhances efficient production of building components through material and labor throughput controls, enabling the production of components at a substantially reduced per-unit cost. The ResCore unit when compared to traditional "stick-built" utility wall components is in may ways analogous to the factory built roof truss compared to on-site "stick-Built" roof framing.

Boyd, G.; Lundell, C.; Wendt, R.

1999-06-01T23:59:59.000Z

235

An Analysis Technique for Active Neutron Multiplicity Measurements Based on First Principles  

SciTech Connect

Passive neutron multiplicity counting is commonly used to quantify the total mass of plutonium in a sample, without prior knowledge of the sample geometry. However, passive neutron counting is less applicable to uranium measurements due to the low spontaneous fission rates of uranium. Active neutron multiplicity measurements are therefore used to determine the {sup 235}U mass in a sample. Unfortunately, there are still additional challenges to overcome for uranium measurements, such as the coupling of the active source and the uranium sample. Techniques, such as the coupling method, have been developed to help reduce the dependence of calibration curves for active measurements on uranium samples; although, they still require similar geometry known standards. An advanced active neutron multiplicity measurement method is being developed by Texas A&M University, in collaboration with Los Alamos National Laboratory (LANL) in an attempt to overcome the calibration curve requirements. This method can be used to quantify the {sup 235}U mass in a sample containing uranium without using calibration curves. Furthermore, this method is based on existing detectors and nondestructive assay (NDA) systems, such as the LANL Epithermal Neutron Multiplicity Counter (ENMC). This method uses an inexpensive boron carbide liner to shield the uranium sample from thermal and epithermal neutrons while allowing fast neutrons to reach the sample. Due to the relatively low and constant fission and absorption energy dependent cross-sections at high neutron energies for uranium isotopes, fast neutrons can penetrate the sample without significant attenuation. Fast neutron interrogation therefore creates a homogeneous fission rate in the sample, allowing for first principle methods to be used to determine the {sup 235}U mass in the sample. This paper discusses the measurement method concept and development, including measurements and simulations performed to date, as well as the potential limitations.

Evans, Louise G [Los Alamos National Laboratory; Goddard, Braden [Los Alamos National Laboratory; Charlton, William S [Los Alamos National Laboratory; Peerani, Paolo [European Commission, EC-JRC-IPSC

2012-08-13T23:59:59.000Z

236

Variability of biomass chemical composition and rapid analysis using FT-NIR techniques  

Science Conference Proceedings (OSTI)

A quick method for analyzing the chemical composition of renewable energy biomass feedstock was developed by using Fourier transform near-infrared (FT-NIR) spectroscopy coupled with multivariate analysis. The study presents the broad-based model hypothesis that a single FT-NIR predictive model can be developed to analyze multiple types of biomass feedstock. The two most important biomass feedstocks corn stover and switchgrass were evaluated for the variability in their concentrations of the following components: glucan, xylan, galactan, arabinan, mannan, lignin, and ash. A hypothesis test was developed based upon these two species. Both cross-validation and independent validation results showed that the broad-based model developed is promising for future chemical prediction of both biomass species; in addition, the results also showed the method's prediction potential for wheat straw.

Liu, Lu [University of Tennessee, Knoxville (UTK); Ye, Philip [University of Tennessee, Knoxville (UTK); Womac, A.R. [University of Tennessee; Sokhansanj, Shahabaddine [ORNL

2010-04-01T23:59:59.000Z

237

Aiding Air Force budget analysis with expert system tools and techniques  

SciTech Connect

A system to capture US Air Force financial expertise is currently under development. To accomplish its mission of costing Air Force programs, the Director of the Budget utilizes the services of budget analysts. Analysts are required to prepare three cost exercises during the year: the Program Objective Memorandum (POM), the Budget Estimation Submission (BES), and the President's Budget (PB). Additionally, during budget calls and budget execution, analysts must make decisions regarding funding obligations and outlays. Analysis and modification of outlay projection plans require the use of operational and procedural heuristics. These problem-solving steps followed by analysts are being used to develop a prototype. Information regarding the prototype, the tool, and its capabilities are presented. Additional features of the program are described including integration with existing information management systems.

Hardee, H.K.; Jones, K.A.; Morris, J.D.; Emrich, M.L.; Ali, H.

1987-09-14T23:59:59.000Z

238

Complex Retrieval of Embedded IVC Filters: Alternative Techniques and Histologic Tissue Analysis  

SciTech Connect

Purpose: We evaluated the safety and effectiveness of alternative endovascular methods to retrieve embedded optional and permanent filters in order to manage or reduce risk of long-term complications from implantation. Histologic tissue analysis was performed to elucidate the pathologic effects of chronic filter implantation. Methods: We studied the safety and effectiveness of alternative endovascular methods for removing embedded inferior vena cava (IVC) filters in 10 consecutive patients over 12 months. Indications for retrieval were symptomatic chronic IVC occlusion, caval and aortic perforation, and/or acute PE (pulmonary embolism) from filter-related thrombus. Retrieval was also performed to reduce risk of complications from long-term filter implantation and to eliminate the need for lifelong anticoagulation. All retrieved specimens were sent for histologic analysis. Results: Retrieval was successful in all 10 patients. Filter types and implantation times were as follows: one Venatech (1,495 days), one Simon-Nitinol (1,485 days), one Optease (300 days), one G2 (416 days), five Guenther-Tulip (GTF; mean 606 days, range 154-1,010 days), and one Celect (124 days). There were no procedural complications or adverse events at a mean follow-up of 304 days after removal (range 196-529 days). Histology revealed scant native intima surrounded by a predominance of neointimal hyperplasia and dense fibrosis in all specimens. Histologic evidence of photothermal tissue ablation was confirmed in three laser-treated specimens. Conclusion: Complex retrieval methods can now be used in select patients to safely remove embedded optional and permanent IVC filters previously considered irretrievable. Neointimal hyperplasia and dense fibrosis are the major components that must be separated to achieve successful retrieval of chronic filter implants.

Kuo, William T., E-mail: wkuo@stanford.edu [Stanford University Medical Center, Division of Vascular and Interventional Radiology, Department of Radiology (United States); Cupp, John S. [Stanford University Medical Center, Department of Pathology (United States); Louie, John D.; Kothary, Nishita; Hofmann, Lawrence V.; Sze, Daniel Y.; Hovsepian, David M. [Stanford University Medical Center, Division of Vascular and Interventional Radiology, Department of Radiology (United States)

2012-06-15T23:59:59.000Z

239

Analysis techniques for power substation grounding systems. Volume 2. User's manual  

SciTech Connect

This User's Manual is provided as an adjunct to the final report on EPRI Research Project 1494-2. The manual is a self-contained document intended to provide detailed and complete instruction on the use of the computer programs developed by the research project. The manual includes user documentation on the two computer programs, entitled SGSYS and SMECC, developed on the contract. Brief program descriptions are followed by operational instructions, data formats, and output specifications. Preceding the program documentation is an introductory section which defines terms and outlines basic elements of grounding system analysis. Following this, a simple but detailed example is given which may be used as a guide in program utilization and also as a test case for individual program users. Following the user documentation is a completed practical example which shows data preparation for a specific substation and computer results obtained for that substation. The example also provides suggested procedures in approaching the problem of substation design using the methodologies developed by this project.

Joy, E.B.; Meliopoulos, A.P.; Webb, R.P.

1983-08-01T23:59:59.000Z

240

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 3 Global Cellular Lipidome Analyses by Shotgun Lipidomics Using Multidimensional Mass Spectrometry  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 3 Global Cellular Lipidome Analyses by Shotgun Lipidomics Using Multidimensional Mass Spectrometry Methods and Analyses eChapters Methods - Analyses Books 2D17DD82D1DB9F2

Note: This page contains sample records for the topic "technique 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

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 2 An Overview of Modern Mass Spectrometry Methods in the Toolbox of Lipid Chemists and Biochemists  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 2 An Overview of Modern Mass Spectrometry Methods in the Toolbox of Lipid Chemists and Biochemists Methods and Analyses eChapters Methods - Analyses Books Dow

242

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 13 Use of Cellular Fatty Acids to Identify Food-Borne Pathogens by Infrared Spectroscopy & Capillary GasChromatography  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 13 Use of Cellular Fatty Acids to Identify Food-Borne Pathogens by Infrared Spectroscopy & Capillary GasChromatography Methods and Analyses eChapters Methods - Analyses Bo

243

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 15 Infrared Spectroscopy and Partial Least Square Calibration in Simultaneous Quantification of Isolated trans & CLA  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 15 Infrared Spectroscopy and Partial Least Square Calibration in Simultaneous Quantification of Isolated trans & CLA Methods and Analyses eChapters Methods - Analyses Book

244

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 14 Application of FT-NIR for Rapid Determination of the Trans Fatty Acid Composition in Fats and Oils  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 14 Application of FT-NIR for Rapid Determination of the Trans Fatty Acid Composition in Fats and Oils Methods and Analyses eChapters Methods - Analyses Books

245

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 11 TLC-FID with Special Reference to Marine Lipids and Other High-Molecular-Weight Organic Compounds  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 11 TLC-FID with Special Reference to Marine Lipids and Other High-Molecular-Weight Organic Compounds Methods and Analyses eChapters Methods - Analyses Books D

246

A Diabatic Lagrangian Technique for the Analysis of Convective Storms. Part I: Description and validation via an observing system simulation experiment  

Science Conference Proceedings (OSTI)

A diabatic Lagrangian analysis (DLA) technique for deriving potential temperature, water vapor and cloud water mixing ratios, and virtual buoyancy from three-dimensional, time-dependent Doppler radar wind and reflectivity fields in storms is ...

Conrad L. Ziegler

247

Interaction of loading pattern and nuclear data uncertainties in reactor core calculations  

Science Conference Proceedings (OSTI)

Along with best-estimate calculations for design and safety analysis, understanding uncertainties is important to determine appropriate design margins. In this framework, nuclear data uncertainties and their propagation to full core calculations are a critical issue. To deal with this task, different error propagation techniques, deterministic and stochastic are currently developed to evaluate the uncertainties in the output quantities. Among these is the sampling based uncertainty and sensitivity software XSUSA which is able to quantify the influence of nuclear data covariance on reactor core calculations. In the present work, this software is used to investigate systematically the uncertainties in the power distributions of two PWR core loadings specified in the OECD UAM-Benchmark suite. With help of a statistical sensitivity analysis, the main contributors to the uncertainty are determined. Using this information a method is studied with which loading patterns of reactor cores can be optimized with regard to minimizing power distribution uncertainties. It is shown that this technique is able to halve the calculation uncertainties of a MOX/UOX core configuration. (authors)

Klein, M.; Gallner, L.; Krzykacz-Hausmann, B.; Pautz, A.; Velkov, K.; Zwermann, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS MbH, Boltzmannstr. 14, D- 85748 Garching b. Muenchen (Germany)

2012-07-01T23:59:59.000Z

248

DOE-STD-1027-92; Hazard Categorization and Accident Analysis Techniques For Compliance With DOE Order 5480.23, Nuclear Safety Analysis Reports  

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

7-92 7-92 December 1992 CHANGE NOTICE NO.1 September 1997 DOE STANDARD HAZARD CATEGORIZATION AND ACCIDENT ANALYSIS TECHNIQUES FOR COMPLIANCE WITH DOE ORDER 5480.23, NUCLEAR SAFETY ANALYSIS REPORTS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 487-4650. Order No. DE98001283 Change Notice No. 1 DOE-STD-1027-92

249

Analysis of Data from the Barnett Shale with Conventional Statistical and Virtual Intelligence Techniques  

E-Print Network (OSTI)

Water production is a challenge in production operations because it is generally costly to produce, treat, and it can hamper hydrocarbon production. This is especially true for gas wells in unconventional reservoirs like shale because the relatively low gas rates increase the economic impact of water handling costs. Therefore, we have considered the following questions regarding water production from shale gas wells: (1) What is the effect of water production on gas production? (2) What are the different water producing mechanisms? and (3) What is the water production potential of a new well in a given gas shale province. The first question was answered by reviewing relevant literature, highlighting observed deficiencies in previous approaches, and making recommendations for future work. The second question was answered using a spreadsheet based Water-Gas-Ratio analysis tool while the third question was investigated by using artificial neural networks (ANN) to decipher the relationship between completion, fracturing, and water production data. We will consequently use the defined relationship to predict the average water production for a new well drilled in the Barnett Shale. This study also derived additional insight into the production trends in the Barnett shale using standard statistical methods. The following conclusions were reached at the end of the study: 1) The observation that water production does not have long term deleterious effect on gas production from fractured wells in tight gas sands cannot be directly extended to fractured wells in gas shales because the two reservoir types do not have analogous production mechanisms. 2) Based on average operating conditions of well in the Barnett Shale, liquid loading was found to be an important phenomenon; especially for vertical wells. 3) A neural network was successfully used to predict average water production potential from a well drilled in the Barnett shale. Similar methodology can be used to predict average gas production potential. Results from this work can be utilized to mitigate risk of water problems in new Barnett Shale wells and predict water issues in other shale plays. Engineers will be provided a tool to predict potential for water production in new wells.

Awoleke, Obadare O.

2009-12-01T23:59:59.000Z

250

Bayesian reconstruction of gravitational wave burst signals from simulations of rotating stellar core collapse and bounce  

SciTech Connect

Presented in this paper is a technique that we propose for extracting the physical parameters of a rotating stellar core collapse from the observation of the associated gravitational wave signal from the collapse and core bounce. Data from interferometric gravitational wave detectors can be used to provide information on the mass of the progenitor model, precollapse rotation, and the nuclear equation of state. We use waveform libraries provided by the latest numerical simulations of rotating stellar core collapse models in general relativity, and from them create an orthogonal set of eigenvectors using principal component analysis. Bayesian inference techniques are then used to reconstruct the associated gravitational wave signal that is assumed to be detected by an interferometric detector. Posterior probability distribution functions are derived for the amplitudes of the principal component analysis eigenvectors, and the pulse arrival time. We show how the reconstructed signal and the principal component analysis eigenvector amplitude estimates may provide information on the physical parameters associated with the core collapse event.

Roever, Christian [Max-Planck-Institut fuer Gravitationsphysik (Albert-Einstein-Institut), 30167 Hannover (Germany); Bizouard, Marie-Anne [Laboratoire de l'Accelerateur Lineaire, Universite Paris Sud, 91898 Orsay (France); Christensen, Nelson [Physics and Astronomy, Carleton College, Northfield, Minnesota 55057 (United States); Dimmelmeier, Harald [Department of Physics, Aristotle University of Thessaloniki, 54124 Thessaloniki (Greece); Heng, Ik Siong [Department of Physics and Astronomy, University of Glasgow, Glasgow G12 8QQ (United Kingdom); Meyer, Renate [Department of Statistics, University of Auckland, Auckland 1142 (New Zealand)

2009-11-15T23:59:59.000Z

251

Advanced techniques for safety analysis applied to the gas turbine control system of ICARO co-generative plant  

E-Print Network (OSTI)

The paper describes two complementary and integrable approaches, a probabilistic one and a deterministic one, based on classic and advanced modelling techniques for safety analysis of complex computer based systems. The probabilistic approach is based on classical and innovative probabilistic analysis methods. The deterministic approach is based on formal verification methods. Such approaches are applied to the gas turbine control system of ICARO co generative plant, in operation at ENEA CR Casaccia. The main difference between the two approaches, behind the underlining different theories, is that the probabilistic one addresses the control system by itself, as the set of sensors, processing units and actuators, while the deterministic one also includes the behaviour of the equipment under control which interacts with the control system. The final aim of the research, documented in this paper, is to explore an innovative method which put the probabilistic and deterministic approaches in a strong relation to overcome the drawbacks of their isolated, selective and fragmented use which can lead to inconsistencies in the evaluation results. 1.

Ro Bologna; Ester Ciancamerla; Piero Incalcaterra; Michele Minichino; Andrea Bobbio; Universit Del Piemonte Orientale; Enrico Tronci

2001-01-01T23:59:59.000Z

252

Using `core documents' for detecting and labelling new emerging topics  

Science Conference Proceedings (OSTI)

The notion of `core documents', first introduced in the context of co-citation analysis and later re-introduced for bibliographic coupling and extended to hybrid approaches, refers to the representation of the core of a document set according to given ... Keywords: Bibliographic coupling, Core documents, Emerging topics, Hybrid clustering, Text mining

Wolfgang Glnzel; Bart Thijs

2012-05-01T23:59:59.000Z

253

Sea bottom coring apparatus  

SciTech Connect

A marine bottom coring apparatus for drilling into and obtaining core samples from subsea formations is described. It is particularly useful for obtaining core samples from hard rock formations. The apparatus includes a frame having buoyancy, which has sufficient capacity to float the apparatus in the unballast condition. Ballasting means are also connected to the frame and having ballast capacity sufficient to overcome a buoyancy of the buoyancy means. Release means are provided for releasing the ballast at a predetermined time. The frame has the core drilling means attached to it and is supported on the sea bottom, whereby the apparatus may be sunk to the sea bottom by the ballast, a core sample drilled from the subsea formation, and the apparatus floated to the surface upon release of the ballast. (11 claims)

Williamson, T.N.

1969-05-06T23:59:59.000Z

254

Nitrate analysis of snow and ice core samples collected in the vicinity of a waste detonation event, McMurdo Station, Antarctica  

Science Conference Proceedings (OSTI)

On December 30, 1991, a small quantity of hazardous materials was detonated at a site near McMurdo Station, Antarctica. The materials involved in the detonation represented highly reactive or explosive wastes that could not be transported safely for disposal in the United States. Detonation was therefore considered the safest and most effective means for disposing these hazardous materials. One concern regarding the detonation of these substances was that the process could generate or distribute measurable quantities of contaminants to the area surrounding the detonation site. Nitrate was selected as a tracer to document the distribution of contaminants from the detonation. Snow and ice cores were collected about 4 months after the event. These cores were analyzed for nitrate concentrations in May 1993, and a map was generated to show the extent of nitrate contamination. This report describes the collection of these samples and summarizes the analytical results.

White, G.J.; Lugar, R.M.; Crockett, A.B.

1994-07-01T23:59:59.000Z

255

KSI's Cross Insulated Core Transformer Technology  

Science Conference Proceedings (OSTI)

Cross Insulated Core Transformer (CCT) technology improves on Insulated Core Transformer (ICT) implementations. ICT systems are widely used in very high voltage, high power, power supply systems. In an ICT transformer ferrite core sections are insulated from their neighboring ferrite cores. Flux leakage is present at each of these insulated gaps. The flux loss is raised to the power of stages in the ICT design causing output voltage efficiency to taper off with increasing stages. KSI's CCT technology utilizes a patented technique to compensate the flux loss at each stage of an ICT system. Design equations to calculate the flux compensation capacitor value are presented. CCT provides corona free operation of the HV stack. KSI's CCT based High Voltage power supply systems offer high efficiency operation, high frequency switching, low stored energy and smaller size over comparable ICT systems.

Uhmeyer, Uwe [Kaiser Systems, Inc, 126 Sohier Road, Beverly, MA 01915 (United States)

2009-08-04T23:59:59.000Z

256

Implementation of an analytical verification technique on three building energy-analysis codes: SUNCAT 2. 4, DOE 2. 1, and DEROB III  

DOE Green Energy (OSTI)

An analytical verification technique for building energy analysis codes has been developed. For this technique, building models are developed that can be both solved analytically and modeled using the analysis codes. The output of the codes is then compared with the analytical solutions. In this way, the accuracy of selected mechanisms in the codes can be verified. The procedure consists of several tests and was run on SUNCAT 2.4, DOE 2.1, and DEROB III. The results are presented and analyzed.

Wortman, D.; O'Doherty, B.; Judkoff, R.

1981-01-01T23:59:59.000Z

257

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

258

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 5: Analysis of core damage frequency from seismic events for plant operational state 5 during a refueling outage  

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 Sandia National Laboratories studying a boiling water reactor (Grand Gulf), and the other at Brookhaven National Laboratory studying a pressurized water reactor (Surry Unit 1). Both the Sandia and Brookhaven 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 outage conditions, is complementary to the internal-initiator analyses at Brookhaven and Sandia. This report covers the seismic analysis at Grand Gulf. All of the many systems modeling assumptions, component non-seismic failure rates, and human effort rates that were used in the internal-initiator study at Grand Gulf have been adopted here, so that the results of the study can be as comparable as possible. Both the Sandia study and this study examine only one shutdown plant operating state (POS) at Grand Gulf, namely POS 5 representing cold shutdown during a refueling outage. 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 POS 5. The results of the analysis are that the core-damage frequency for earthquake-initiated accidents during refueling outages in POS 5 is found to be quite low in absolute terms, less than 10{sup {minus}7}/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

259

Analysis and optimization of gyrokinetic toroidal simulations on homogenous and heterogenous platforms  

Science Conference Proceedings (OSTI)

The Gyrokinetic Toroidal Code (GTC) uses the particle-in-cell method to efficiently simulate plasma microturbulence. This work presents novel analysis and optimization techniques to enhance the performance of GTC on large-scale machines. We introduce ... Keywords: GPU programming, Particle-in-cell, hybrid programming, memory-centric multi-core tuning, multi-core optimization

Khaled Z Ibrahim, Kamesh Madduri, Samuel Williams, Bei Wang, Stephane Ethier, Leonid Oliker

2013-11-01T23:59:59.000Z

260

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 "technique 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

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

262

Curing of Compacted Cores  

Science Conference Proceedings (OSTI)

...dry for 1 min. Add water and mull for 1 min. Add oil and mull for 4 min. These materials are mixed in a muller as follows: Sand (by weight), 95.80% Cereal flour, 1.01% Core oil, 1.17% Water, 1.86% Bentonite, 0.16% Oil-sand mixtures are used for cores in sand molds, and by varying their

263

MCNP LWR Core Generator  

Science Conference Proceedings (OSTI)

The reactor core input generator allows for MCNP input files to be tailored to design specifications and generated in seconds. Full reactor models can now easily be created by specifying a small set of parameters and generating an MCNP input for a full reactor core. Axial zoning of the core will allow for density variation in the fuel and moderator, with pin-by-pin fidelity, so that BWR cores can more accurately be modeled. LWR core work in progress: (1) Reflectivity option for specifying 1/4, 1/2, or full core simulation; (2) Axial zoning for moderator densities that vary with height; (3) Generating multiple types of assemblies for different fuel enrichments; and (4) Parameters for specifying BWR box walls. Fuel pin work in progress: (1) Radial and azimuthal zoning for generating further unique materials in fuel rods; (2) Options for specifying different types of fuel for MOX or multiple burn assemblies; (3) Additional options for replacing fuel rods with burnable poison rods; and (4) Control rod/blade modeling.

Fischer, Noah A. [Los Alamos National Laboratory

2012-08-14T23:59:59.000Z

264

Emergency core cooling system  

DOE Patents (OSTI)

A liquid metal cooled fast breeder reactor provided with an emergency core cooling system includes a reactor vessel which contains a reactor core comprising an array of fuel assemblies and a plurality of blanket assemblies. The reactor core is immersed in a pool of liquid metal coolant. The reactor also includes a primary coolant system comprising a pump and conduits for circulating liquid metal coolant to the reactor core and through the fuel and blanket assemblies of the core. A converging-diverging venturi nozzle with an intermediate throat section is provided in between the assemblies and the pump. The intermediate throat section of the nozzle is provided with at least one opening which is in fluid communication with the pool of liquid sodium. In normal operation, coolant flows from the pump through the nozzle to the assemblies with very little fluid flowing through the opening in the throat. However, when the pump is not running, residual heat in the core causes fluid from the pool to flow through the opening in the throat of the nozzle and outwardly through the nozzle to the assemblies, thus providing a means of removing decay heat.

Schenewerk, William E. (Sherman Oaks, CA); Glasgow, Lyle E. (Westlake Village, CA)

1983-01-01T23:59:59.000Z

265

Lipid Analysis and Lipidomics: New Techniques & ApplicationChapter 7 Recent Advances in Silver-Ion HPLC Utilizing Acetonitrile in Hexane as Solvent  

Science Conference Proceedings (OSTI)

Lipid Analysis and Lipidomics: New Techniques & Application Chapter 7 Recent Advances in Silver-Ion HPLC Utilizing Acetonitrile in Hexane as Solvent Methods and Analyses eChapters Methods - Analyses Books F98F563E606CED1FD3744F0D6362BAB2

266

Geochemical Techniques | Open Energy Information  

Open Energy Info (EERE)

Geochemical Techniques Geochemical Techniques Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Geochemical Techniques Details Activities (0) Areas (0) Regions (0) NEPA(1) Exploration Technique Information Exploration Group: Geochemical Techniques Exploration Sub Group: None Parent Exploration Technique: Exploration Techniques Information Provided by Technique Lithology: Stratigraphic/Structural: Hydrological: Thermal: Dictionary.png Geochemical Techniques: No definition has been provided for this term. Add a Definition Related Techniques Geochemical Techniques Geochemical Data Analysis Geothermometry Gas Geothermometry Isotope Geothermometry Liquid Geothermometry Cation Geothermometers Multicomponent Geothermometers Silica Geothermometers Thermal Ion Dispersion

267

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

268

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

269

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.

270

Rapid Characterization of Drill Core and Cutting Mineralogy using Infrared  

Open Energy Info (EERE)

Rapid Characterization of Drill Core and Cutting Mineralogy using Infrared Rapid Characterization of Drill Core and Cutting Mineralogy using Infrared Spectroscopy Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article: Rapid Characterization of Drill Core and Cutting Mineralogy using Infrared Spectroscopy Abstract Infrared spectroscopy is particularly good at identifying awide variety of hydrothermally altered minerals with no samplepreparation, and is especially helpful in discrimination amongclay minerals. We have performed several promising pilot studieson geothermal drill core and cuttings that suggest the efficiencyof the technique to sample continuously and provide alterationlogs similar to geophysical logs. We have successfully identifiedlayered silicates, zeolites, opal, calcite, and iron oxides and

271

CORE SATURATION BLOCKING OSCILLATOR  

DOE Patents (OSTI)

A blocking oscillator which relies on core saturation regulation to control the output pulse width is described. In this arrangement an external magnetic loop is provided in which a saturable portion forms the core of a feedback transformer used with the thermionic or semi-conductor active element. A first stationary magnetic loop establishes a level of flux through the saturation portion of the loop. A second adjustable magnet moves the flux level to select a saturation point giving the desired output pulse width. (AEC)

Spinrad, R.J.

1961-10-17T23:59:59.000Z

272

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,

273

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

274

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

275

Development of a core design optimization tool and analysis in support of the planned LEU 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 of a global effort to minimize the availability of ...

Connaway, Heather M. (Heather Moira)

2012-01-01T23:59:59.000Z

276

A comparison of two data analysis techniques and their applications for modeling the carbon dioxide capture process  

Science Conference Proceedings (OSTI)

Improving the efficiency of the carbon dioxide (CO"2) capture process requires a good understanding of the intricate relationships among parameters involved in the process. The objective of this research is to study the nature of relationships among ... Keywords: CO2 capture process, Data modeling, Neural network, Sensitivity analysis, Statistical analysis

Yuxiang Wu; Qing Zhou; Christine W. Chan

2010-12-01T23:59:59.000Z

277

Comparison of acoustic impedance and time-amplitude analysis techniques for reservoir description of a Gulf of Mexico shelf edge Clastic Field  

SciTech Connect

Post-stack, time-amplitude techniques are routinely used in the estimation of reserves and the positioning of wells in low impedance, unconsolidated reservoir sands in the offshore Gulf of Mexico (Texas and Louisiana). Time amplitude analysis of 3D seismic data, when properly calibrated, can yield reliable estimates of net hydrocarbon pay, reservoir distribution, and volumetrics. Acoustic impedance (Al) analysis can also be used for such prospect appraisal and development work. However, the combined use of both techniques for reservoir description is not common. Some advantages in acoustic impedance (over amplitude analysis) are: (1) properly constrained Al traces better image the reservoir rock configuration (that is, they provide a more [open quotes]geologic[close quotes] view) thereby facilitating interpretation of reservoir distribution and interconnectivity, and (2) Al volumetrics methodology can provide more accurate estimates of average pay for reservoirs that are not seismically isolated from one another. A possible disadvantage is the difficulty in incorporating a proper baseline (low frequency) constraint for the required Al trace inversion. This paper reports the advantages and disadvantages of both techniques in characterizing net pay, volumetrics, and reservoir continuity in a producing Gulf of Mexico oil field in a shelf-edge delta depositional system.

Rowlett, H.E.; Holcombe, H.T.; Cohn, B.P.; Wilson, W.W.; Mills, W.H. (BP Exploration Inc., Houston, TX (United States))

1993-02-01T23:59:59.000Z

278

Improved core recovery in laminated sand and shale sequences  

SciTech Connect

Coring and core analysis are essential to the exploration, development, and production phases of the oil and gas industry. Large-diameter (4-in. (10-cm)) core provides engineers and geologists with direct means to measure physical properties of reservoir rocks at both the microscopic and macroscopic levels. This information provides engineers with clues to improve their understanding of the reservoir and prediction of its performance. If stored properly, core may assist in development of the reservoir many years after the well is drilled. In microlaminated reservoirs, laboratory core analysis is very important because of inherent limitations in wireline log resolution. In these cases, petrophysical information, such as saturation, porosity, and net feet of pay, cannot be calculated from wireline data. Instead, these data must be measured directly from core plugs in the laboratory. Historically, core recovery in these types of reservoirs has not been good (Fig. 1A) using methods designed for firmly consolidated formations. These methods did not achieve satisfactory recovery in unconsolidated sand interbedded with hard shale stringers for two reasons: unconsolidated sand was eroded by mechanical or hydraulic means and shale ''jammed'' in the core barrel, thereby preventing more core from entering. Changes in coring strategies and equipment have nearly eliminated recovery problems in unconsolidated sand while reducing jams in shale (Fig. 1B). This paper discusses several of these changes and presents ideas for further improvements.

Bradburn, F.R.; Cheatham, C.A. (Shell Offshore Inc. (US))

1988-12-01T23:59:59.000Z

279

Category:Rock Lab Analysis | Open Energy Information  

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 Category Edit History Facebook icon Twitter icon » Category:Rock Lab Analysis Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermalpower.jpg Looking for the Rock Lab Analysis page? For detailed information on exploration techniques, click here. Category:Rock Lab Analysis Add.png Add a new Rock Lab Analysis Technique Pages in category "Rock Lab Analysis" The following 9 pages are in this category, out of 9 total. C Core Analysis Cuttings Analysis I Isotopic Analysis- Rock O Over Core Stress P Paleomagnetic Measurements Petrography Analysis R Rock Density X X-Ray Diffraction (XRD) X-Ray Fluorescence (XRF)

280

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

Note: This page contains sample records for the topic "technique 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

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 F-H, Volume 2, Part 4  

Science Conference Proceedings (OSTI)

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. 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 scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence 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

282

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 E (Sections E.9-E.16), Volume 2, Part 3B  

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. 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 scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis.

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

1994-06-01T23:59:59.000Z

283

Analysis of the Window Side Thermal Environment Formed by Air Barrier Technique in Winter Conditions and Its Economy  

E-Print Network (OSTI)

The air barrier technique applies airflow through a window fan to decrease the heat load of a window surface and avoid dewfall in winter and decrease heat radiation from the window surface in summer. This paper uses numerical simulation to predict the energy-saving potential and thermal comfort of the air barrier technique used in office buildings. It also analyzes the surface temperature of the window by using the simulation software Airpak. According to the results, we can obtain the key control strategy of this technology. It can be found that the air barrier technique, instead of the heating-supply around outside-zone for office building, can avoid dewfall in winter and decrease the cold radiation, which has a great effect on thermal environment around the window. Characteristics such as outer air temperature, indoor load, thermal characteristics of structure, and air-supply parameters through window fans are analyzed in detail to measure their effects on energy consumption, window side environment and PMV values. The paper provides theoretical reference and technical guidance for applying air barrier technology correctly, improving the window side environment and reducing energy consumption.

Huang, C.; Jia, Y.; Liu, L.; Wang, X.

2006-01-01T23:59:59.000Z

284

SWN Nets as a Framework for the Specification and the Analysis of FT Techniques Adopted in Electric Plant Automation  

Science Conference Proceedings (OSTI)

The use of formal methods for specification and analysis of dependable systems is considered a promising opportunity to support the evaluation of critical issues since the early design phases. Stochastic Petri nets can play an important role not only ...

Lorenzo Capra; Rossano Gaeta; Oliver Botti

1999-06-01T23:59:59.000Z

285

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

286

Critical CRBR core pressure  

Science Conference Proceedings (OSTI)

The conditions are detailed under which gas pressure will cause or initiate failure in the structural containment of the fuel core. The Clinch River Breeder Reactor Plant is the prototype structure. Two general classes of problems have been studied, representing two entirely distinct configurations of containment failure. The first model determines the minimum pressure to lift a portion or the entire core from its containment. The second model estimates the critical pressure above which the fuel rods interior to the hexagonal fuel can warp, leading to blockage of the gas passages. Such blockage might cause further buildup of the gas pressure to a level causing the failure of the fuel rod containment in the hexagonal fuel container.

Ju, F.D.

1980-06-01T23:59:59.000Z

287

A one-group parametric sensitivity analysis for the graphite isotope ratio method and other related techniques using ORIGEN 2.2  

E-Print Network (OSTI)

Several methods have been developed previously for estimating cumulative energy production and plutonium production from graphite-moderated reactors. The Graphite Isotope Ratio Method (GIRM) is one well-known technique. This method is based on the measurement of trace isotopes in the reactors graphite matrix to determine the change in their isotopic ratios due to burnup. These measurements are then coupled with reactor calculations to determine the total plutonium and energy production of the reactor. To facilitate sensitivity analysis of these methods, a one-group cross section and fission product yield library for the fuel and graphite activation products has been developed for MAGNOX-style reactors. This library is intended for use in the ORIGEN computer code, which calculates the buildup, decay, and processing of radioactive materials. The library was developed using a fuel cell model in Monteburns. This model consisted of a single fuel rod including natural uranium metal fuel, magnesium cladding, carbon dioxide coolant, and Grade A United Kingdom (UK) graphite. Using this library a complete sensitivity analysis can be performed for GIRM and other techniques. The sensitivity analysis conducted in this study assessed various input parameters including 235U and 238U cross section values, aluminum alloy concentration in the fuel, and initial concentrations of trace elements in the graphite moderator. The results of the analysis yield insight into the GIRM method and the isotopic ratios the method uses as well as the level of uncertainty that may be found in the system results.

Chesson, Kristin Elaine

2007-08-01T23:59:59.000Z

288

Toroidal core winder  

DOE Patents (OSTI)

The disclosure is directed to an apparatus for placing wire windings on a toroidal body, such as a transformer core, having an orifice in its center. The apparatus comprises a wire storage spool, a wire loop holding continuous belt maintained in a C-shaped loop by a belt supporting structure and provision for turning the belt to place and tighten loops of wire on a toroidal body, which is disposed within the gap of the C-shaped belt loop.

Potthoff, Clifford M. (Livermore, CA)

1978-01-01T23:59:59.000Z

289

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

290

The morpho-topographic and cartographic analysis of the archaeological site Cornesti "Iarcuri", Timis County, Romania, using computer sciences methods (GIS and Remote Sensing techniques)  

E-Print Network (OSTI)

The archaeological site Cornesti "Iarcuri" is the largest earth fortification in Romania, made out of four concentric compounds, spreading over 1780 hectares. It is known since 1700, but it had only a few small attempts of systematic research, the fortress gained interest only after the publishing of some satellite images by Google Earth. It is located in an area of high fields and it occupies three interfluves and contains two streams. Our paper contains a geomorphologic, topographic and cartographic analysis of the site in order to determine the limits, the structure, the morphology, the construction technique and the functionality of such a fortification.Our research is based on satellite image analysis, on archaeological topography, on soil, climate and vegetation analysis as a way to offer a complex image, through this interdisciplinary study of landscape archaeology. Through our work we try not to date the site as this objective will be achieved only after completing the systematic excavations which sta...

Micle, Dorel; Maruia, Liviu

2009-01-01T23:59:59.000Z

291

Benchmarking a new closed-form thermal analysis technique against a traditional lumped parameter, finite-difference method  

Science Conference Proceedings (OSTI)

A benchmarking effort was conducted to determine the accuracy of a new analytic generic geology thermal repository model developed at LLNL relative to a more traditional, numerical, lumped parameter technique. The fast-running analytical thermal transport model assumes uniform thermal properties throughout a homogenous storage medium. Arrays of time-dependent heat sources are included geometrically as arrays of line segments and points. The solver uses a source-based linear superposition of closed form analytical functions from each contributing point or line to arrive at an estimate of the thermal evolution of a generic geologic repository. Temperature rise throughout the storage medium is computed as a linear superposition of temperature rises. It is modeled using the MathCAD mathematical engine and is parameterized to allow myriad gridded repository geometries and geologic characteristics [4]. It was anticipated that the accuracy and utility of the temperature field calculated with the LLNL analytical model would provide an accurate 'birds-eye' view in regions that are many tunnel radii away from actual storage units; i.e., at distances where tunnels and individual storage units could realistically be approximated as physical lines or points. However, geometrically explicit storage units, waste packages, tunnel walls and close-in rock are not included in the MathCAD model. The present benchmarking effort therefore focuses on the ability of the analytical model to accurately represent the close-in temperature field. Specifically, close-in temperatures computed with the LLNL MathCAD model were benchmarked against temperatures computed using geometrically-explicit lumped-parameter, repository thermal modeling technique developed over several years at ANL using the SINDAG thermal modeling code [5]. Application of this numerical modeling technique to underground storage of heat generating nuclear waste streams within the proposed YMR Site has been widely reported [6]. New SINDAG thermal models presented here share this same basic modeling approach.

Huff, K. D.; Bauer, T. H. (Nuclear Engineering Division)

2012-08-20T23:59:59.000Z

292

Recurrence Plot and Recurrence Quantification Analysis Techniques for Detecting a Critical Regime. Examples from Financial Market Indices  

E-Print Network (OSTI)

Recurrence Plot (RP) and Recurrence Quantification Analysis (RQA) are signal numerical analysis methodologies able to work with non linear dynamical systems and non stationarity. Moreover they well evidence changes in the states of a dynamical system. We recall their features and give practical recipes. It is shown that RP and RQA detect the critical regime in financial indices (in analogy with phase transition) before a bubble bursts, whence allowing to estimate the bubble initial time. The analysis is made on DAX and NASDAQ daily closing price between Jan. 1998 and Nov. 2003. DAX is studied in order to set-up overall considerations, and as a support for deducing technical rules. The NASDAQ bubble initial time has been estimated to be on Oct. 19, 1999.

A. Fabretti; M. Ausloos

2004-12-31T23:59:59.000Z

293

A finite element analysis technique for predicting as-sprayed residual stresses generated by the plasma spray coating process  

Science Conference Proceedings (OSTI)

It is essential to analyze the residual stresses during the deposition of plasma sprayed coatings since they adversely affect the coatings' performance during their service. In this article, finite element coupled heat transfer and elastic-plastic thermal ... Keywords: Finite element analysis, Heat transfer, Plasma spraying, Residual stresses, Thermal barrier coatings

H. W. Ng; Z. Gan

2005-07-01T23:59:59.000Z

294

DIVISION S-10--NOTES plexiglas to facilitate entry into the sediment. Often,A NEW IDEA IN MARSH CORING  

E-Print Network (OSTI)

Cappellen ference, and can even allow rapid inspection of the core with the removable side panel (Craswell and Castillo, Abstract 1979). However, because these designs utilize an open- Standard coring techniques

Florida, University of

295

Analytical Chemistry Core Capability Assessment - Preliminary Report  

Science Conference Proceedings (OSTI)

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

296

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

297

Analysis of the Galvanostatic Intermittent Titration Technique (GITT) as applied to a lithium-Ion porous electrode.  

SciTech Connect

Galvanostatic Intermittent Titration Technique (GITT) experiments were conducted to determine the lithium diffusion coefficient of LiNi{sub 0.8}Co{sub 0.15}Al{sub 0.05}O{sub 2}, used as the active material in a lithium-ion battery porous composite positive electrode. An electrochemical model, based on concentrated solution porous electrode theory, was developed to analyze the GITT experimental results and compare to the original GITT analytical theory. The GITT experimental studies on the oxide active material were conducted between 3.5 and 4.5 V vs. lithium, with the maximum lithium diffusion coefficient value being 10{sup -10} cm{sup 2} s{sup -1} at 3.85 V. The lithium diffusion coefficient values obtained from this study agree favorably with the values obtained from an earlier electrochemical impedance spectroscopy study.

Dees, D. W.; Kawauchi, S.; Abraham, D. P.; Prakash, J.; Chemical Sciences and Engineering Division; Toyota Central R& D Labs Inc.; Illinois Inst. of Tech.

2009-04-01T23:59:59.000Z

298

The Application of Artificial Intelligence Techniques to the Analysis of Waste Assay Data Susan Bridges Julia Hodges Charles Sparrow  

E-Print Network (OSTI)

This report describes an expert system that is being developed to investigate the issues involved in incorporating artificial intelligence techniques into a system that can analyze and characterize containerized radiological waste. The expert system is being developed by scientists at the Mississippi State University Diagnostic and Instrumentation Laboratory in collaboration with scientists at the Idaho National Engineering Laboratory. The goal is to develop an expert system that will be a component of the Waste Assay Measurement Integration System (WAMIS); WAMIS is intended to help the staff at the Stored Waste Examination Pilot Plant (SWEPP) determine proper disposition of the containers. The expert system must combine information from a variety of sources to determine if the waste meets the criteria for shipment that are defined in the quality assurance objectives for the program. An exploratory version of the expert system will be used to evaluate the applicability of different art...

Susan Bridges; Susan Bridges; Julia Hodges; Julia Hodges; Charles Sparrow; Charles Sparrow

1996-01-01T23:59:59.000Z

299

Caltech Faint Galaxy Redshift Survey VII: Data Analysis Techniques and Redshifts in the Field J0053+1234  

E-Print Network (OSTI)

We present the techniques used to determine redshifts and to characterize the spectra of objects in the Caltech Faint Galaxy Redshift Survey in terms of spectral classes and redshift quality classes. These are then applied to spectra from an investigation of a complete sample of objects with $K_s<20$ mag in a 2 by 7.3 arcmin^2 field at J005325+1234. Redshifts were successfully obtained for 163 of the 195 objects in the sample; these redshifts lie in the range [0.173, 1.44] and have a median of 0.58 (excluding 24 Galactic stars). The sample includes two broad lined AGNs and one QSO.

Judith G. Cohen; David W. Hogg; Michael A. Pahre; Roger Blandford; Patrick L. Shopbell; Kevin Richberg

1998-09-05T23:59:59.000Z

300

Partial core pulse transformer  

DOE Patents (OSTI)

A light-weight partial-core pule transformer is provided for generating high voltage output pulses with low distortion. The transformer includes sets of ferrite bars arranged so as to extend longitudinally along the inside and outside surfaces of a high frequency cylindrical coil winding-pair. The ferrite bars are arranged in pairs with the bars of each pair being located on opposite sides of winding-pair. The bars are preferably disposed in a radially symmetric arrangement around the winding-pair, and each has a length at least equal to the width of the winding-pair.

Lawson, R.N.; Rohwein, G.J.

1991-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

Permanent prostate brachytherapy: Dosimetric results and analysis of a learning curve with a dynamic dose-feedback technique  

SciTech Connect

Purpose: A permanent prostate brachytherapy (PPB) program utilizing intraoperative inverse-planned dynamic dose-feedback was initiated without prior firsthand experience of alternative techniques. The purpose of this study is to assess the dosimetric learning curve associated with this approach. Methods and Materials: A total of 77 patients underwent PPB implants as monotherapy for localized prostate cancer to a prescription dose of 145 Gy with loose 125I seeds between December 2003 and June 2004. Intraoperative and postoperative dosimetric values, total implanted radioactivity, and operating room (OR) times were compared by sequential case number for all cases. Results: The median intraoperative dosimetric values were: D90 (the minimum dose to 90% of the prostate) = 170 Gy (range, 135-203 Gy), V100 (the volume of the prostate that receives 100% of the prescription dose) = 96% (range, 86-100), V150 = 66% (range, 34-86). Median postoperative dosimetric values were as follows: D90 = 168 Gy (range, 132-197 Gy), V100 = 95% (range, 86-99), V150 = 74% (range, 51-84). Median implanted activity was 0.79 mCi per cubic centimeter of prostate (range, 0.541-1.13). There was no significant correlation by case number on any postoperative dosimetric parameter studied. Door-to-door OR time was reduced from median 138 to 97.5 min per case at the end of the series with a correlation coefficient of -0.76 for the initial 28 cases. Conclusion: Satisfactory dosimetric parameters can be achieved from the outset without a learning curve effect in an appropriately trained environment. The learning curve for dynamic dose-feedback PPB in a clinic naive to other techniques is apparent in terms of OR time.

Acher, Peter [Department of Urology, Guy's and St. Thomas' NHS Foundation Trust, London (United Kingdom)]. E-mail: peter.acher@gstt.nhs.uk; Popert, Rick [Department of Urology, Guy's and St. Thomas' NHS Foundation Trust, London (United Kingdom); Nichol, Janette [Department of Urology, Guy's Hospital, London (United Kingdom); Potters, Louis [New York Prostate Institute, South Nassau Communities Hospital, Oceanside, NY (United States); Morris, Stephen [Department of Clinical Oncology, Guy's and St. Thomas' NHS Foundation Trust, London (United Kingdom); Beaney, Ronald [Department of Clinical Oncology, Guy's and St. Thomas' NHS Foundation Trust, London (United Kingdom)

2006-07-01T23:59:59.000Z

302

Diagnostics Techniques of Power Transformer  

Science Conference Proceedings (OSTI)

This paper provides the information on the diagnostics techniques for condition monitoring of power transformer (PT). This paper deals with the practical importance of the transformer diagnostic in the Electrical Engineering field. A review has been ... Keywords: temperature, condition monitoring, diagnostics methods, paper analysis techniques, oil analysis techniques

Piush Verma; Y. R. Sood; Jashandeep Singh

2009-12-01T23:59:59.000Z

303

Evaluation of the Partial Discharge and Electromagnetic Interference Analysis Techniques for Condition Monitoring of 4160-V Motors  

Science Conference Proceedings (OSTI)

This report provides a brief description of the different activities that occurred during a three-year project encompassing the use of two of the more advanced toolsthe technologies of partial discharge analysis and electromagnetic interference (EMI) analysisfor determining the electrical condition of large electric motors in the utility industry. The project's principal focus was on hardware and determining how to effectively use the technologies in electrical generation facilities. This focus included ...

2008-11-03T23:59:59.000Z

304

Device and technique for in-process sampling and analysis of molten metals and other liquids presenting harsh sampling conditions  

DOE Patents (OSTI)

An apparatus and method for continuously analyzing liquids by creating a supersonic spray which is shaped and sized prior to delivery of the spray to a analysis apparatus. The gas and liquid are mixed in a converging-diverging nozzle where the liquid is sheared into small particles which are of a size and uniformly to form a spray which can be controlled through adjustment of pressures and gas velocity. The spray is shaped by a concentric supplemental flow of gas.

Alvarez, Joseph L. (Idaho Falls, ID); Watson, Lloyd D. (Rigby, ID)

1989-01-01T23:59:59.000Z

305

Device and technique for in-process sampling and analysis of molten metals and other liquids presenting harsh sampling conditions  

DOE Patents (OSTI)

An apparatus and method for continuously analyzing liquids by creating a supersonic spray which is shaped and sized prior to delivery of the spray to a analysis apparatus. The gas and liquid is sheared into small particles which are of a size and uniformity to form a spray which can be controlled through adjustment of pressures and gas velocity. The spray is shaped by a concentric supplemental flow of gas. 5 figs.

Alvarez, J.L.; Watson, L.D.

1988-01-21T23:59:59.000Z

306

Out-of-Core Progressive Lossless Compression and Selective Decompression of Large Triangle Meshes  

Science Conference Proceedings (OSTI)

In this paper we propose a novel {\\em out-of-core} technique for{\\em progressive} lossless compression and {\\em selective}decompression of 3D triangle meshes larger than main memory. Most existing compression methods, in order to optimize compression ... Keywords: Progressive Lossless Compression, Selective Decompression, Out-of-Core Techniques, Triangle Meshes

Zhiyan Du; Pavel Jaromersky; Yi-Jen Chiang; Nasir Memon

2009-03-01T23:59:59.000Z

307

Core-tube data logger  

DOE Green Energy (OSTI)

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

308

Analysis of communication costs for domain decomposed Monte Carlo methods in nuclear reactor analysis  

Science Conference Proceedings (OSTI)

A domain decomposed Monte Carlo communication kernel is used to carry out performance tests to establish the feasibility of using Monte Carlo techniques for practical Light Water Reactor (LWR) core analyses. The results of the prototype code are interpreted ... Keywords: Monte Carlo, Neutron transport, Performance modeling, Reactor analysis

A. Siegel; K. Smith; P. Fischer; V. Mahadevan

2012-04-01T23:59:59.000Z

309

Engineering task plan for upgrades to the leveling jacks on core sample trucks number 3 and 4  

Science Conference Proceedings (OSTI)

Characterizing the waste in underground storage tanks at the Hanford Site is accomplished by obtaining a representative core sample for analysis. Core sampling is one of the numerous techniques that have been developed for use given the environmental and field conditions at the Hanford Site. Core sampling is currently accomplished using either Push Mode Core Sample Truck No.1 or; Rotary Mode Core Sample Trucks No.2, 3 or 4. Past analysis (WHC 1994) has indicated that the Core Sample Truck (CST) leveling jacks are structurally inadequate when lateral loads are applied. WHC 1994 identifies many areas where failure could occur. All these failures are based on exceeding the allowable stresses listed in the American Institute of Steel Construction (AISC) code. The mode of failure is for the outrigger attachments to the truck frame to fail resulting in dropping of the CST and possible overturning (Ref. Ziada and Hundal, 1996). Out of level deployment of the truck can exceed the code allowable stresses in the structure. Calculations have been performed to establish limits for maintaining the truck level when lifting. The calculations and the associated limits are included in appendix A. The need for future operations of the CSTS is limited. Sampling is expected to be complete in FY-2001. Since there is limited time at risk for continued use of the CSTS with the leveling controls without correcting the structural problems, there are several design changes that could give incremental improvements to the operational safety of the CSTS with limited impact on available operating time. The improvements focus on making the truck easier to control during lifting and leveling. Not all of the tasks identified in this ETP need to be performed. Each task alone can improve the safety. This engineering task plan is the management plan document for implementing the necessary additional structural analysis. Any additional changes to meet requirements of standing orders shall require a Letter of Instruction from Numatec Hanford Company (NHC).

KOSTELNIK, A.J.

1999-02-24T23:59:59.000Z

310

Opening criteria for accelerated paving techniques  

E-Print Network (OSTI)

Fast track paving or accelerated pavement design is the rapid replacement of portland cement concrete pavement, allowing for the reopening to traffic under specific time requirements. The purpose of this research is to develop opening criteria for accelerated paving and implementing these criteria into a set of guidelines for fast track paving. This report is broken into three specific sections; review of practice, an analysis of field and lab research, and finally design guidelines for the opening criteria for accelerated paving techniques. A review of practice was developed to update the reader on the current "state of the art". This review outlines contruction techniques, fast track mix design, pavement design, and joint design. The analysis of field and lab research provides a synopsis of the experimentation used to develop design guidelines for opening criteria. This section includes crack surveys, coring tests, FWD testing, maturity testing, penetration testing and consistency testing. The design guidelines for early opening criteria provides guidelines for use in intersection design. The guideline outlines requirements for design, design of concrete pavement materials, mixture design, construction considerations, and requirements for opening criteria. This document will update the reader on the subject of fast track paving and the methods used to research it. Finally, with a design guidelines the reader will be able to apply the methods of analysis described in the field and lab testing section to create better pavements more efficiently.

Johnson, Jason Leonard

1993-01-01T23:59:59.000Z

311

NETL: Carbon Storage - Core R&D  

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

Core R&D Carbon Storage Core R&D The Core Research and Development (Core R&D) focuses on developing new carbon capture and storage (CCS) technologies to a pre-commercial...

312

Applied Science/Techniques  

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

Applied Science/Techniques Applied Science/Techniques Applied Science/Techniques Print The ALS is an excellent incubator of new scientific techniques and instrumentation. Many of the technical advances that make the ALS a world-class soft x-ray facility are developed at the ALS itself. The optical components in use at the ALS-mirrors and lenses optimized for x-ray wavelengths-require incredibly high-precision surfaces and patterns (often formed through extreme ultraviolet lithography at the ALS) and must undergo rigorous calibration and testing provided by beamlines and equipment from the ALS's Optical Metrology Lab and Berkeley Lab's Center for X-Ray Optics. New and/or continuously improved experimental techniques are also a crucial element of a thriving scientific facility. At the ALS, examples of such "technique" highlights include developments in lensless imaging, soft x-ray tomography, high-throughput protein analysis, and high-power coherent terahertz radiation.

313

Use of thermal analysis techniques (TG-DSC) for the characterization of diverse organic municipal waste streams to predict biological stability prior to land application  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer Thermal analysis was used to assess stability and composition of organic matter in three diverse municipal waste streams. Black-Right-Pointing-Pointer Results were compared with C mineralization during 90-day incubation, FTIR and {sup 13}C NMR. Black-Right-Pointing-Pointer Thermal analysis reflected the differences between the organic wastes before and after the incubation. Black-Right-Pointing-Pointer The calculated energy density showed a strong correlation with cumulative respiration. Black-Right-Pointing-Pointer Conventional and thermal methods provide complimentary means of characterizing organic wastes. - Abstract: The use of organic municipal wastes as soil amendments is an increasing practice that can divert significant amounts of waste from landfill, and provides a potential source of nutrients and organic matter to ameliorate degraded soils. Due to the high heterogeneity of organic municipal waste streams, it is difficult to rapidly and cost-effectively establish their suitability as soil amendments using a single method. Thermal analysis has been proposed as an evolving technique to assess the stability and composition of the organic matter present in these wastes. In this study, three different organic municipal waste streams (i.e., a municipal waste compost (MC), a composted sewage sludge (CS) and a thermally dried sewage sludge (TS)) were characterized using conventional and thermal methods. The conventional methods used to test organic matter stability included laboratory incubation with measurement of respired C, and spectroscopic methods to characterize chemical composition. Carbon mineralization was measured during a 90-day incubation, and samples before and after incubation were analyzed by chemical (elemental analysis) and spectroscopic (infrared and nuclear magnetic resonance) methods. Results were compared with those obtained by thermogravimetry (TG) and differential scanning calorimetry (DSC) techniques. Total amounts of CO{sub 2} respired indicated that the organic matter in the TS was the least stable, while that in the CS was the most stable. This was confirmed by changes detected with the spectroscopic methods in the composition of the organic wastes due to C mineralization. Differences were especially pronounced for TS, which showed a remarkable loss of aliphatic and proteinaceous compounds during the incubation process. TG, and especially DSC analysis, clearly reflected these differences between the three organic wastes before and after the incubation. Furthermore, the calculated energy density, which represents the energy available per unit of organic matter, showed a strong correlation with cumulative respiration. Results obtained support the hypothesis of a potential link between the thermal and biological stability of the studied organic materials, and consequently the ability of thermal analysis to characterize the maturity of municipal organic wastes and composts.

Fernandez, Jose M., E-mail: joseman@sas.upenn.edu [Department of Earth and Environmental Science, University of Pennsylvania, Philadelphia, PA 19104-6316 (United States); Plaza, Cesar; Polo, Alfredo [Instituto de Ciencias Agrarias, Consejo Superior de Investigaciones Cientificas, Serrano 115 dpdo., 28006 Madrid (Spain); Plante, Alain F. [Department of Earth and Environmental Science, University of Pennsylvania, Philadelphia, PA 19104-6316 (United States)

2012-01-15T23:59:59.000Z

314

Interferometer Techniques for Gravitational-Wave Detection  

E-Print Network (OSTI)

Several km-scale gravitational-wave detectors have been constructed world wide. These instruments combine a number of advanced technologies to push the limits of precision length measurement. The core devices are laser interferometers of a new kind; developed from the classical Michelson topology these interferometers integrate additional optical elements, which significantly change the properties of the optical system. Much of the design and analysis of these laser interferometers can be performed using well-known classical optical techniques, however, the complex optical layouts provide a new challenge. In this review we give a textbook-style introduction to the optical science required for the understanding of modern gravitational wave detectors, as well as other high-precision laser interferometers. In addition, we provide a number of examples for a freely available interferometer simulation software and encourage the reader to use these examples to gain hands-on experience with the discussed optical methods.

Andreas Freise; Kenneth Strain

2009-09-21T23:59:59.000Z

315

Active galactic nuclei and massive galaxy cores  

E-Print Network (OSTI)

(Context) Central active galactic nuclei (AGN) are supposed to play a key role in the evolution of their host galaxies. In particular, the dynamical and physical properties of the gas core must be affected by the injected energy. (Aims) Our aim is to study the effects of an AGN on the dark matter profile and on the central stellar light distribution in massive early type galaxies. (Methods) By performing self-consistent N-body simulations, we assume in our analysis that periodic bipolar outbursts from a central AGN can induce harmonic oscillatory motions on both sides of the gas core. (Results) Using realistic AGN properties, we find that the motions of the gas core, driven by such feedback processes, can flatten the dark matter and/or stellar profiles after 4-5 Gyr. These results are consistent with recent observational studies that suggest that most giant elliptical galaxies have cores or are "missing light" in their inner part. Since stars behave as a "collisionless" fluid similar to dark matter, the density profile both of stars and dark matter should be affected in a similar way, leading to an effective reduction in the central brightness.

Sebastien Peirani; Scott Kay; Joe Silk

2006-12-16T23:59:59.000Z

316

SNAP II REACTOR CORE MATERIALS  

SciTech Connect

A survey was made to select the construction materials for the SDR-1 reactor core vessel and grid plates. Hastelloy C was selected for the reactor vessel, top grid plate, and bottom grid plate. Inconel X was selected for the core hold-down springs. (C.J.G.)

Facha, J.V.

1960-04-11T23:59:59.000Z

317

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

318

Applied Science/Techniques  

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

Applied Science/Techniques Print Applied Science/Techniques Print The ALS is an excellent incubator of new scientific techniques and instrumentation. Many of the technical advances that make the ALS a world-class soft x-ray facility are developed at the ALS itself. The optical components in use at the ALS-mirrors and lenses optimized for x-ray wavelengths-require incredibly high-precision surfaces and patterns (often formed through extreme ultraviolet lithography at the ALS) and must undergo rigorous calibration and testing provided by beamlines and equipment from the ALS's Optical Metrology Lab and Berkeley Lab's Center for X-Ray Optics. New and/or continuously improved experimental techniques are also a crucial element of a thriving scientific facility. At the ALS, examples of such "technique" highlights include developments in lensless imaging, soft x-ray tomography, high-throughput protein analysis, and high-power coherent terahertz radiation.

319

Preliminary engineering design of sodium-cooled CANDLE core  

Science Conference Proceedings (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 CANDLE core by using conventional codes while satisfying some realistic engineering design constraints assuming that recladding at certain time interval is technically feasible.

Takaki, Naoyuki; Namekawa, Azuma; Yoda, Tomoyuki; Mizutani, Akihiko; Sekimoto, Hiroshi [Department of Nuclear Engineering, Tokai University, Kitakaname, Hiratsuka, Kanagawa 259-1292 (Japan); AISA, Fuchu, Ishioka, Ibaraki 315-0013 (Japan); Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, Ookayama, Meguro-ku, Tokyo, 152-8550 (Japan)

2012-06-06T23:59:59.000Z

320

MAAP5 BWR Core Melt Progression Model Enhancement Description  

Science Conference Proceedings (OSTI)

This report describes proposed enhancements to the Modular Accident Analysis Program (MAAP) core melt progression model for BWRs. MAAP is an EPRI-owned and -licensed computer program that simulates the operation of light water and heavy water moderated nuclear power plants for both current and advanced light water reactor (ALWR) designs. The Fukushima accidentthe first full-scale accident for a BWR designposes challenges to the current core model that must be addressed.The ...

2013-02-25T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

Reflector modelling of small high leakage cores making use of multi-group nodal equivalence theory  

SciTech Connect

This research focuses on modelling reflectors in typical material testing reactors (MTRs). Equivalence theory is used to homogenise and collapse detailed transport solutions to generate equivalent nodal parameters and albedo boundary conditions for reflectors, for subsequent use in full core nodal diffusion codes. This approach to reflector modelling has been shown to be accurate for two-group large commercial light water reactor (LWR) analysis, but has not been investigated for MTRs. MTRs are smaller, with much larger leakage, environment sensitivity and multi-group spectrum dependencies than LWRs. This study aims to determine if this approach to reflector modelling is an accurate and plausible homogenisation technique for the modelling of small MTR cores. The successful implementation will result in simplified core models, better accuracy and improved efficiency of computer simulations. Codes used in this study include SCALE 6.1, OSCAR-4 and EQUIVA (the last two codes are developed and used at Necsa). The results show a five times reduction in calculational time for the proposed reduced reactor model compared to the traditional explicit model. The calculated equivalent parameters however show some sensitivity to the environment used to generate them. Differences in the results compared to the current explicit model, require more careful investigation including comparisons with a reference result, before its implementation can be recommended. (authors)

Theron, S. A. [South African Nuclear Energy Corporation (Necsa), PO Box 582, Pretoria, 0001 (South Africa); Reitsma, F. [Calvera Consultants, PO Box 150, Strubensvallei, 1735 (South Africa)

2012-07-01T23:59:59.000Z

322

Program on Technology Innovation: Feasibility Assessment of a Core Vacuum for Foreign Material and Activity Removal  

Science Conference Proceedings (OSTI)

The need for increased fuel reliability and radioactive source term reduction motivated EPRI to investigate methods for removing small foreign material and activated corrosion products from reactor vessels. Several methods exist to remove these materials from above the core plate of the reactor vessel, but there has been limited research and development of techniques to remove them from underneath the core plate. This report investigates the development of a core vacuum to remove debris and corrosion pro...

2008-09-30T23:59:59.000Z

323

Optimization of Core Point Detection in Fingerprints  

Science Conference Proceedings (OSTI)

This paper compares and documents the work of an optimized fingerprint core point determination algorithm. This work focuses to present an efficient and precise way for the extraction of core point. Core Point is detected using least mean square algorithm. ...

Nabeel Younus Khan; M. Younus Javed; Naveed Khattak; Umer Munir Yongjun Chang

2007-12-01T23:59:59.000Z

324

Field Techniques | Open Energy Information  

Open Energy Info (EERE)

Field Techniques Field Techniques Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Technique: Field Techniques Details Activities (0) Areas (0) Regions (0) NEPA(0) Exploration Technique Information Exploration Group: Field Techniques Exploration Sub Group: None Parent Exploration Technique: Exploration Techniques Information Provided by Technique Lithology: Map surface geology and hydrothermal alteration. Rock samples are used to define lithology. Field and lab analyses can be used to measure the chemical and isotopic constituents of rock samples. Bulk and trace element analysis of rocks, minerals, and sediments. Identify and document surface geology and mineralogy. Rapid and unambiguous identification of unknown minerals.[1] Stratigraphic/Structural: Locates active faults in the area of interest. Map fault and fracture patterns, kinematic information. Can reveal relatively high permeability zones. Provides information about the time and environment which formed a particular geologic unit. Microscopic rock textures can be used to estimate the history of stress and strain, and/or faulting.

325

Audit of Departmental Integrated Standardized Core Accounting...  

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

Audit of Departmental Integrated Standardized Core Accounting System (DISCAS) Operations at Selected Field Sites, AP-FS-97-02 Audit of Departmental Integrated Standardized Core...

326

Sandia National Laboratories: Research: Facilities: Annular Core...  

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

Annular Core Research Reactor facility Nuclear science photo At the Annular Core Research Reactor (ACRR) facility, Sandia researchers can subject various test objects to a mixed...

327

On the Power of Bitslice Implementation on Intel Core2 Processor  

Science Conference Proceedings (OSTI)

This paper discusses the state-of-the-art fast software implementation of block ciphers on Intel's new microprocessor Core2, particularly concentrating on "bitslice implementation". The bitslice parallel encryption technique, initially proposed by Biham ... Keywords: AES, Bitslice, Core2, Fast Software Encryption, KASUMI

Mitsuru Matsui; Junko Nakajima

2007-09-01T23:59:59.000Z

328

Evaluation of lineament analysis as an exploration technique for geothermal energy, western and central Nevada. Final report, June 1976--October 1978  

DOE Green Energy (OSTI)

Lineament analysis as an exploration technique for geothermal energy using multi-scale, multi-format imagery and geophysical data is investigated and evaluated. Two areas in Nevada, each having distinct differences in structural style were studied. One area, which encompasses a portion of the Battle Mountain Heat Flow High, was studied to determine the relationship between regional and local structural controls and geothermal activity. Four geothermal sites within this area (Winnemucca AMS) were selected and studied in detail. These sites include: 1) Leach Hot Springs, 2) Kyle Hot Springs, 3) Beowawe geothermal area and Buffalo Valley Hot Springs. A second area encompassed by the Reno AMS Sheet was selected for further study in a region dominated by three diverse tectonic styles; these are: 1) the Sierra Nevada Front, 2) the Walker Lane, and 3) basin-and-range structures. Geothermal sites analyzed at site specific scales within the Reno AMS Sheet included Steamboat Hot Springs in the Sierra Nevada Front subprovince, Dixie Valley Hot Springs located in typical basin-and-range terrain and the Brady's-Desert Peak area which is marginal to the Walker Lane. Data products employed included LANDSAT imagery, SKYLAB photography, gravity, and aeromagnetic maps. Results of this investigation indicate that in north-central Nevada the major sites of geothermal activity are associated with northeast trending structures related to the Midas Trench lineament and that the most viable geothermal area (Beowawe is located at the intersection of the northeast trend of the Oregon-Nevada Lineament.

Trexler, D.T.; Bell, E.J.; Roquemore, G.R.

1978-10-01T23:59:59.000Z

329

Investigating the effectiveness of many-core network processors for high performance cyber protection systems. Part I, FY2011.  

SciTech Connect

This report documents our first year efforts to address the use of many-core processors for high performance cyber protection. As the demands grow for higher bandwidth (beyond 1 Gbits/sec) on network connections, the need to provide faster and more efficient solution to cyber security grows. Fortunately, in recent years, the development of many-core network processors have seen increased interest. Prior working experiences with many-core processors have led us to investigate its effectiveness for cyber protection tools, with particular emphasis on high performance firewalls. Although advanced algorithms for smarter cyber protection of high-speed network traffic are being developed, these advanced analysis techniques require significantly more computational capabilities than static techniques. Moreover, many locations where cyber protections are deployed have limited power, space and cooling resources. This makes the use of traditionally large computing systems impractical for the front-end systems that process large network streams; hence, the drive for this study which could potentially yield a highly reconfigurable and rapidly scalable solution.

Wheeler, Kyle Bruce; Naegle, John Hunt; Wright, Brian J.; Benner, Robert E., Jr.; Shelburg, Jeffrey Scott; Pearson, David Benjamin; Johnson, Joshua Alan; Onunkwo, Uzoma A.; Zage, David John; Patel, Jay S.

2011-09-01T23:59:59.000Z

330

Effects of core barrel on vessel seismic loadings. [LMFBR  

Science Conference Proceedings (OSTI)

Reliability of reactor systems under seismic events is a major concern for the safety of the nuclear power plants. This paper deals with the effects of the core barrel on the seismic response of reactor tanks. The main emphases are the effects of core barrel on the free-surface wave height and the fluid coupling effects between the core barrel and primary tank. This study represents an initial step to investigate the effects of in-tank components, structures on the seismically-induced hydrodynamic behavior of the reactor tanks. To simplify the analysis, the tank used in the study is simulated by a two-dimensional model. Two parametric studies were carried out in which the wall flexibility and location of core barrel were used as parameters respectively.

Ma, D.C.; Gvildys, J.; Chang, Y.W.

1983-01-01T23:59:59.000Z

331

Union soluble oil flood in El Dorado cores  

Science Conference Proceedings (OSTI)

Results are presented of laboratory experiments using Union's soluble oil flood process in El Dorado cores. The core flood is to provide complete information on fluid compositions and phase behavior of the effluents such that adequate core flood match using the chemical flood simulator can be made. This step is essential for evaluating reservoir performance on the South Pattern of the El Dorado Micellar-Polymer Project. The results show the caustic preflush in the flood process causes face plugging of the field cores. The problem was controlled by using chelating agents along with the caustic fluid to keep divalent cations in solution. The required amount of chelating agent was determined to be ca 25 times as strong as the original design for the field test. Liquid chromatography analysis of sulfonate provides valuable information on selective fractionation of monosulfonate in the micellar fluid. 10 references.

Chiou, C.S.

1983-02-01T23:59:59.000Z

332

Efficient Fingerprint Matching Technique Using Wavelet Based Features  

Science Conference Proceedings (OSTI)

This paper details the work of an efficient fingerprint matching technique via the use of wavelet based features. It is a kind of image based processing technique. So first core point is detected via using the hybrid technique. Then wavelet is applied ...

Nabeel Younus Khan; Muhammad Younus Javed

2007-12-01T23:59:59.000Z

333

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.

334

Reactor core isolation cooling system  

DOE Patents (OSTI)

A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom. 1 figure.

Cooke, F.E.

1992-12-08T23:59:59.000Z

335

Reactor core isolation cooling system  

DOE Patents (OSTI)

A reactor core isolation cooling system includes a reactor pressure vessel containing a reactor core, a drywell vessel, a containment vessel, and an isolation pool containing an isolation condenser. A turbine is operatively joined to the pressure vessel outlet steamline and powers a pump operatively joined to the pressure vessel feedwater line. In operation, steam from the pressure vessel powers the turbine which in turn powers the pump to pump makeup water from a pool to the feedwater line into the pressure vessel for maintaining water level over the reactor core. Steam discharged from the turbine is channeled to the isolation condenser and is condensed therein. The resulting heat is discharged into the isolation pool and vented to the atmosphere outside the containment vessel for removing heat therefrom.

Cooke, Franklin E. (San Jose, CA)

1992-01-01T23:59:59.000Z

336

Interactive out-of-core isosurface extraction  

Science Conference Proceedings (OSTI)

Keywords: interval tree, isosurface extraction, marching cubes, out-of-core computation, scientific visualization

Yi-Jen Chiang; Cludio T. Silva; William J. Schroeder

1998-10-01T23:59:59.000Z

337

Free-fall core sampler  

SciTech Connect

The described free-fall corer apparatus consists of an expendable, elongated casing having an annular-shaped ballast member secured to it. A cylindrical housing surmounts this ballast member and accommodates a float which is tied to the core liner. During descent of the apparatus, the float is latched to the ballast element, but when the apparatus strikes bottom, a pilot weight suspended from the float latching means moves upward and allows the float to freely ascend within the ocean. This ascent unlatches the core liner from the expendable casing and the liner is thereafter raised to the surface. (13 claims)

Raymond, S.O.; Sachs, P.L.

1968-03-12T23:59:59.000Z

338

Many-core key-value store  

Science Conference Proceedings (OSTI)

Scaling data centers to handle task-parallel work-loads requires balancing the cost of hardware, operations, and power. Low-power, low-core-count servers reduce costs in one of these dimensions, but may require additional nodes to provide the required ... Keywords: 64-core Tilera TILEPro64, many-core key-value store, data centers, task-parallel workloads, low-core-count servers, low-power servers, under-utilizing memory, power consumption, high-core-count processor, clock rate, 4-core Intel Xeon L5520, 8-core AMD Opteron 6128 HE

M. Berezecki; E. Frachtenberg; M. Paleczny; K. Steele

2011-07-01T23:59:59.000Z

339

Core-melt source reduction system  

DOE Patents (OSTI)

A core-melt source reduction system for ending the progression of a molten core during a core-melt accident and resulting in a stable solid cool matrix. The system includes alternating layers of a core debris absorbing material and a barrier material. The core debris absorbing material serves to react with and absorb the molten core such that containment overpressurization and/or failure does not occur. The barrier material slows the progression of the molten core debris through the system such that the molten core has sufficient time to react with the core absorbing material. The system includes a provision for cooling the glass/molten core mass after the reaction such that a stable solid cool matrix results.

Forsberg, Charles W. (Oak Ridge, TN); Beahm, Edward C. (Oak Ridge, TN); Parker, George W. (Concord, TN)

1995-01-01T23:59:59.000Z

340

Core-melt source reduction system  

DOE Patents (OSTI)

A core-melt source reduction system for ending the progression of a molten core during a core-melt accident and resulting in a stable solid cool matrix. The system includes alternating layers of a core debris absorbing material and a barrier material. The core debris absorbing material serves to react with and absorb the molten core such that containment overpressurization and/or failure does not occur. The barrier material slows the progression of the molten core debris through the system such that the molten core has sufficient time to react with the core absorbing material. The system includes a provision for cooling the glass/molten core mass after the reaction such that a stable solid cool matrix results. 4 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-04-25T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

Full Core 3-D Simulation of a Partial MOX LWR Core  

Science Conference Proceedings (OSTI)

A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D full core nodal calculations, in the frame of MOX fuel design, was conducted. This study revealed a set of advantages and disadvantages, with respect to each method, which can be used to guide the level of accuracy desired for future fuel and fuel cycle calculations. For the purpose of isotopic generation for fuel cycle analyses, the approach of using a 2-D lattice code (i.e., fuel assembly in infinite lattice) gave reasonable predictions of uranium and plutonium isotope concentrations at the predicted 3-D core simulation batch average discharge burnup. However, it was found that the 2-D lattice calculation can under-predict the power of pins located along a shared edge between MOX and UO2 by as much as 20%. In this analysis, this error did not occur in the peak pin. However, this was a coincidence and does not rule out the possibility that the peak pin could occur in a lattice position with high calculation uncertainty in future un-optimized studies. Another important consideration in realistic fuel design is the prediction of the peak axial burnup and neutron fluence. The use of 3-D core simulation gave peak burnup conditions, at the pellet level, to be approximately 1.4 times greater than what can be predicted using back-of-the-envelope assumptions of average specific power and irradiation time.

S. Bays; W. Skerjanc; M. Pope

2009-05-01T23:59:59.000Z

342

Laminated grid and web magnetic cores  

DOE Patents (OSTI)

A laminated magnetic core characterized by an electromagnetic core having core legs which comprise elongated apertures and edge notches disposed transversely to the longitudinal axis of the legs, such as high reluctance cores with linear magnetization characteristics for high voltage shunt reactors. In one embodiment the apertures include compact bodies of microlaminations for more flexibility and control in adjusting permeability and/or core reluctance.

Sefko, John (Monroeville, PA); Pavlik, Norman M. (Plum Borough, PA)

1984-01-01T23:59:59.000Z

343

Graphite Modular Reactor with Cooled Metal Core Outlet End Support Plate  

SciTech Connect

The modular designs appear attractive in that the reactor core lateral support is provided by the modules themselves rather than externally as with a bundled core. Types B and C provide a means of reducing the inter-element and intermodular leakage flow. This tends to enhance the reliability of the reactor core by decreasing the probability of a progressive overall failure of the core initiated by a mid-core rupture of one of the fuel elements. The graphite inner reflector and lateral support mechnism are eliminated in this design. The assembly of the modular core design is probably simplified by the smaller number of modular elements to be handled and by the elimination of the lateral support mechanism. The modular core has several potential problem areas which will be examined by further analysis and testing.

Jackson, L.

1963-08-01T23:59:59.000Z

344

Stress corrosion cracking of austenitic stainless steel core internal welds.  

SciTech Connect

Microstructural analyses by several advanced metallographic techniques were conducted on austenitic stainless steel mockup and core shroud welds that had cracked in boiling water reactors. Contrary to previous beliefs, heat-affected zones of the cracked Type 304L, as well as 304 SS core shroud welds and mockup shielded-metal-arc welds, were free of grain-boundary carbides, which shows that core shroud failure cannot be explained by classical intergranular stress corrosion cracking. Neither martensite nor delta-ferrite films were present on the grain boundaries. However, as a result of exposure to welding fumes, the heat-affected zones of the core shroud welds were significantly contaminated by oxygen and fluorine, which migrate to grain boundaries. Significant oxygen contamination seems to promote fluorine contamination and suppress thermal sensitization. Results of slow-strain-rate tensile tests also indicate that fluorine exacerbates the susceptibility of irradiated steels to intergranular stress corrosion cracking. These observations, combined with previous reports on the strong influence of weld flux, indicate that oxygen and fluorine contamination and fluorine-catalyzed stress corrosion play a major role in cracking of core shroud welds.

Chung, H. M.; Park, J.-H.; Ruther, W. E.; Sanecki, J. E.; Strain, R. V.; Zaluzec, N. J.

1999-04-14T23:59:59.000Z

345

Hydrologic characterization of four cores from the Geysers Coring Project  

DOE Green Energy (OSTI)

Results of hydrologic tests on 4 representative core plugs from Geysers Coring Project drill hole SB-15-D were related to mineralogy and texture. Permeability measurements were made on 3 plugs from caprock and one plug from the steam reservoir. Late-stage microfractures present in 2 of the plugs contributed to greater permeability, but the values for the 2 other plugs indicate a typical matrix permeability of 1 to 2 {times} 10{sup {minus}21}m{sup 2}. Klinkenberg slip factor b for these plugs is generally consistent with the inverse relation between slip factor and permeability observed by Jones (1972) for plugs of much more permeable material. The caprock and reservoir samples are nearly identical metagraywackes with slight mineralogical differences which appear to have little effect on hydrology. The late stage microfractures are suspected of being artifacts. The capillary pressure curves for 3 cores are fit by power-law relations which can be used to estimate relative permeability curves for the matrix rocks.

Persoff, P. [Lawrence Berkeley National Lab., CA (United States); Hulen, J.B. [Univ. of Utah, Salt Lake City, UT (United States). Earth Sciences and Resources Institute

1996-01-01T23:59:59.000Z

346

Global Precipitation Estimates Based on a Technique for Combining Satellite-Based Estimates, Rain Gauge Analysis, and NWP Model Precipitation Information  

Science Conference Proceedings (OSTI)

The satellite-gauge-model (SGM) technique is described for combining precipitation estimates from microwave satellite data, infrared satellite data, rain gauge analyses, and numerical weather prediction models into improved estimates of global ...

George J. Huffman; Robert F. Adler; Bruno Rudolf; Udo Schneider; Peter R. Keehn

1995-05-01T23:59:59.000Z

347

Strategic Energy Analysis at NREL (Presentation)  

3. Some Key Themes for Analysis. Core Areas: Market, Technology and Policy Analysis. Energy Modeling Analysis. Renewables, Hydrogen, Alt. Fuels. Risk, ...

348

Use of solid-state NMR techniques for the analysis of water in coal and the effect of different coal drying techniques on the structure and reactivity of coal  

SciTech Connect

The overall objectives of this study are to develop an NMR method for measuring the water in coal, to measure the changes in coal structure that occur during coal drying, to determine what effect water has on retrograde/condensation reactions, and to determine the mechanism by which water may enhance coal reactivity toward liquefaction. Different methods of drying will be investigated to determine if drying can be accomplished without destroying coal reactivity toward liquefaction, thereby making coal drying an attractive and economical method for coal pretreatment. Coal drying methods will include thermal drying under different atmospheres and temperatures, drying with microwave radiation, and low-temperature chemical dehydration. The objective for this quarterly report were (1) to determine the limit of detection of water by NMR, (2) to determine the reproducibility of the NMR integration method using the Lab Cal {sup {trademark}} PC software, (3) to determine the amount of water in standard solutions, and (4) to determine the amount of water in a coal sample. The studies performed this last quarter have shown that the {sup 1}H NMR method for determining water in a coal sample via the reaction with 2,2-dimethoxypropane will be suitable for determining the water content in coals. The method should be most suitable for coals having low moisture content; that is, those coals which have been subjected to other drying techniques. 9 refs., 1 tab.

Netzel, D.A.

1991-01-01T23:59:59.000Z

349

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

350

Coring in deep hardrock formations  

DOE Green Energy (OSTI)

The United States Department of Energy is involved in a variety of scientific and engineering feasibility studies requiring extensive drilling in hard crystalline rock. In many cases well depths extend from 6000 to 20,000 feet in high-temperature, granitic formations. Examples of such projects are the Hot Dry Rock well system at Fenton Hill, New Mexico and the planned exploratory magma well near Mammoth Lakes, California. In addition to these programs, there is also continuing interest in supporting programs to reduce drilling costs associated with the production of geothermal energy from underground sources such as the Geysers area near San Francisco, California. The overall progression in these efforts is to drill deeper holes in higher temperature, harder formations. In conjunction with this trend is a desire to improve the capability to recover geological information. Spot coring and continuous coring are important elements in this effort. It is the purpose of this report to examine the current methods used to obtain core from deep wells and to suggest projects which will improve existing capabilities. 28 refs., 8 figs., 2 tabs.

Drumheller, D.S.

1988-08-01T23:59:59.000Z

351

HyCore | Open Energy Information  

Open Energy Info (EERE)

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

352

Definition: Core Holes | Open Energy Information  

Open Energy Info (EERE)

Holes Jump to: navigation, search 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...

353

The use of solid-state NMR techniques for the analysis of water in coal and the effect of different coal drying techniques on the structure and reactivity of coal. Quarterly report, December 1, 1993--February 28, 1994  

SciTech Connect

The overall objectives of this study are to develop a nuclear magnetic resonance (NMR) method for measuring the water in coal, to measure the changes in coal structure that occur during coal drying, to determine what effect water has on retrograde/condensation reactions, to determine the mechanism by which water may impact coal reactivity toward liquefaction, and to conduct D{sub 2}O exchange studies to ascertain the role of water in coal liquefaction. The objectives for this quarterly report period were (1) to train students in the operation of the coal liquefaction reactor, gas analysis, extraction of the coal residue and coal liquids, and to calculate the percent conversion from the coal liquefaction data; and (2) to implement the changes in the coal liquefaction experimental procedure.

Netzel, D.A.

1994-06-01T23:59:59.000Z

354

Using Vulcan to Recreate Planetary Cores  

Science Conference Proceedings (OSTI)

An accurate equation of state (EOS) for planetary constituents at extreme conditions is the key to any credible model of planets or low mass stars. However, experimental validation has been carried out on at high pressure (>few Mbar), and then only on the principal Hugoniot. For planetary and stellar interiors, compression occurs from gravitational force so that material states follow a line of isentropic compression (ignoring phase separation) to ultra-high densities. An example of the predicted states for water along the isentrope for Neptune is shown in a figure. The cutaway figure on the left is from Hubbard, and the phase diagram on the right is from Cavazzoni et al. Clearly these states lie at quite a bit lower temperature and higher density than single shock Hugoniot states but they are at higher temperature than can be achieved with accurate diamond anvil experiments. At extreme densities, material states are predicted to have quite unearthly properties such as high temperature superconductivity and low temperature fusion. High density experiments on Earth are achieved with either static compression techniques (i.e.diamond anvil cells) or dynamic compression techniques using large laser facilities, gas guns, or explosives. A major thrust of this work is to develop techniques to create and characterize material states that exists primarily at the core of giant planets and brown dwarf stars. Typically, models used to construct planetary isentropes are constrained by only the planet radius, outer atmospheric spectroscopy, and space probe gravitational moment and magnetic field data. Thus any data, which provide rigid constraints for these models will have a significant impact on a broad community of planetary and condensed matter scientists. Recent laser shock wave experiments have made great strides in recreating material states that exist in the outer 25% (in radius) of the Jovian planets and at the exterior of low-mass stars. Large laser facilities have been used to compressed materials to ultra-high pressures and characterize their thermodynamic and transport properties (plastic Hugoniot to 40 Mbar, deuterium Hugoniot to 3 Mbar, metallization of ''atomic'' deuterium on the Hugoniot). To probe materials properties at these high pressures, several experimental techniques were developed high resolution radiography, optical reflectance, pyrometry, and velocity/displacement sensitive interferometry are some of the diagnostics currently used in laser-generated shock EOS experiments. During our experiments at Vulcan we developed and tested precompressed and multiple shock experimental techniques which allowed us to recreate the extreme core states of giant plants. These experiments compressed water to densities higher than accessible by single shock Hugoniot techniques and showed that the metal-insulator transition of shocked precompressed water is suppressed significantly as compared to uncompressed water. Further, as predicted the temperature of shocked precompressed water is lower than the temperature of uncompressed water enabling us to determine the metallization mechanism for water near the Hugoniot.

Collins, G.W.; Celliers, P.M.; Hicks, D.G.; Mackinnon, A.J.; Moon, S.J.; Cauble, R.; DaSilva, L.B.; Koening, M.; Benuzzi-Mounaix, A.; Huser, G.; Jeanloz, R.; Lee, K.M.; Benedetti, L.R.; Henry, E.; Batani, D.; Willi, O.; Pasley, J.; Gessner, H.; Neely, D.; Notley, M.; Danson, C.

2001-08-15T23:59:59.000Z

355

Imaging techniques applied to the study of fluids in porous media  

Science Conference Proceedings (OSTI)

Improved imaging techniques were used to study the dynamics of fluid flow and trapping at various scales in porous media. Two-phase and three-phase floods were performed and monitored by computed tomography (CT) scanning and/or nuclear magnetic resonance imaging (NMRI) microscopy. Permeability-porosity correlations obtained from image analysis were combined with porosity distributions from CT scanning to generate spatial permeability distributions within the core which were used in simulations of two-phase floods. Simulation-derived saturation distributions of two-phase processes showed very good agreement with the CT measured values.

Tomutsa, L.; Doughty, D.; Brinkmeyer, A.; Mahmood, S.

1992-06-01T23:59:59.000Z

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  

Science Conference Proceedings (OSTI)

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

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 E (Sections E.1--E.8). Volume 2, Part 3A  

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. The authors 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.

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

1994-06-01T23:59:59.000Z

358

Feasibility of monitoring the strength of HTGR core support graphite: Part III  

Science Conference Proceedings (OSTI)

Methods are being developed to monitor, in-situ, the strength changes of graphite core-support components in a High-Temperature Gas-Cooled Reactor (HTGR). The results reported herein pertain to the development of techniques for monitoring the core-support blocks; the PGX graphite used in these studies is the grade used for the core-support blocks of the Fort St. Vrain HTGR, and is coarser-grained than the grades used in our previous investigations. The through-transmission ultrasonic velocity technique, developed for monitoring strength of the core-support posts, is not suitable for use on the core-support blocks. Eddy-current and ultrasonic backscattering techniques have been shown to be capable of measuring the density-depth profile in oxidized PGX and, combined with a correlation of strength versus density, could yield an estimate of the strength-depth profile of in-service HTGR core support blocks. Correlations of strength versus density and other properties, and progress on the development of the eddy-current and ultrasonic backscattering techniques are reported.

Morgan, W.C.; Davis, T.J.; Thomas, M.T.

1983-02-01T23:59:59.000Z

359

Evaluation of Relap5 Reactor Core Modeling Capability  

E-Print Network (OSTI)

of Thesis Presented to the Graduate School of the University of Florida in Partial Fulfillment of the Requirements for the Degree of Master of Science EVALUATION OF RELAP5 REACTOR CORE MODELING CAPABILITY By Vincent J.-P. Roux August 2001 Chairman: Professor Samim Anghaie Major Department: Nuclear and Radiological Engineering RELAP5 is a one-dimensional reactor-system simulation code with additional cross-flow calculation capability to include two- and three-dimensional effects in light water nuclear reactor cores. The code is used to model the core, steam generator, and the balance of the Surry reactor, which is a three-loop Westinghouse Pressurized Water Reactor (PWR) system. A detailed RELAP5 model including full nodalization of the system is developed and implemented for this study. The RELAP5 Surry core model uses one or several parallel channels to compare and assess the performance of the cross-flow model. Several inlet flow rates and core power distributions are considered and modeled. Results of the analysis showed the significant contribution of cross-flow in overall temperature and flow distributions in the core. Results of the study also showed that the RELAP5 predictions of cross-flow, at least for single-phase cases, are not consistent with the theory. xi To evaluate the accuracy of RELAP5 cross-flow model, an industry standard Computational Fluid Dynamics code, FLUENT, is used to perform two- and threedimensional calculations. Initial and boundary conditions for the RELAP5 model are used to develop a high-resolution FLUENT model for a pair of parallel reactor core channels. Two models were developed for FLUENT calculation of cross-flow. The first model is a simple tube with axisymmetric non-uniform inlet flow velocities. The second model included differen...

Vincent J. -p. Roux

2001-01-01T23:59:59.000Z

360

Identification of human gene core promoters in silico  

E-Print Network (OSTI)

Identification of the 5-end of human genes requires identification of functional promoter elements. In silico identification of those elements is difficult because of the hierarchical and modular nature of promoter architecture. To address this problem, I propose a new stepwise strategy based on initial localization of a functional promoter into a 1-2 kb (extended-promoter) region from within a large genomic DNA sequence of 100 kb or larger, and further localization of a Transcriptional Start Site (TSS) into a 50-100 bp (core-promoter) region. Using positional dependent 5-tuple measures, a Quadratic Discriminant Analysis (QDA) method has been implemented in a new program- CorePromoter. Our experiments indicate that when given a 1-2 kb extended promoter, CorePromoter will correctly localize the TSS to a 100 bp interval approximately 60 % of the time.

Michael Q. Zhang

1998-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

Heatup of the TMI-2 lower head during core relocation  

SciTech Connect

An analysis has been carried out to assess the potential of a melting attack upon the reactor vessel lower head and incore instrument nozzle penetration weldments during the TMI core relocation event at 224 minutes. Calculations were performed to determine the potential for molten corium to undergo breakup into droplets which freeze and form a debris bed versus impinging upon the lower head as one or more coherent streams. The effects of thermal-hydraulic interactions between corium streams and water inside the lower plenum, the effects of the core support assembly structure upon the corium, and the consequences of corium relocation by way of the core former region were examined. 19 refs., 24 figs.

Wang, S.K.; Sienicki, J.J.; Spencer, B.W.

1989-01-01T23:59:59.000Z

362

Comment on Cerenkov radiation by neutrinos in a supernova core  

E-Print Network (OSTI)

It had been pointed out by Mohanty and Samal[1] that the helicity flipping Cerenkov process ?L ? ?R +? or ? +?L ? ?R could be an important cooling mechanism for the supernova core. Comparing the neutrino emissivity by the Cerenkov process with observations of SN1987A, a restrictive bound on the neutrino magnetic moment was established. Subsequently it was pointed out by Raffelt[2] that, this result was based on a numerical error in the calculation of the refractive index of the SN core and using the correct numbers it was shown that the photons in a SN core do not have a space-like dispersion relation, so the Cerenkov helicity flip process would not occur. Here we show that the earlier estimate of refractive index was based on the thermodynamic formula for susceptibility which turns out to be invalid for real photons or plasmons even in the static limit. However an analysis of the dispersion relations of plasmons in an

Subhendra Mohanty; Sarira Sahu

1997-01-01T23:59:59.000Z

363

Office of Fossil EnergyDetailed Core Procedures Manual Volume 1 Core Acquisition  

E-Print Network (OSTI)

This Core Procedures Manual, Volume 1 contains a description of proposed best practices for use during coring operations for the Barrow Gas Hydrate Test Well Program. This document is designed to describe the responsibilities of well site operations personnel, primarily the core acquisition contractor and coring fluids contractor, Weatherford/Omni and Halliburton/Baroid

Barrow Gas Fields

2009-01-01T23:59:59.000Z

364

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

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

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

365

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...

366

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

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

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

367

Hanford People Core (HCP) PIA, Richland Operations Office | Department...  

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

Hanford People Core (HCP) PIA, Richland Operations Office Hanford People Core (HCP) PIA, Richland Operations Office Hanford People Core (HCP) PIA, Richland Operations Office...

368

Hanford People Core (HCP) PIA, Richland Operations Office | Department...  

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

People Core (HCP) PIA, Richland Operations Office Hanford People Core (HCP) PIA, Richland Operations Office Hanford People Core (HCP) PIA, Richland Operations Office Hanford People...

369

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

370

Yankee Rowe simulator core model validation  

Science Conference Proceedings (OSTI)

This paper presents the validation of the Yankee Rowe simulator core model. Link-Miles Simulation Corporation is developing the Yankee Rowe simulator and Yankee Atomic Electric Company is involved in input and benchmark data generation, as well as simulator validation. Core model validation by Yankee comprises three tasks: (1) careful generation of fuel reactivity characteristics (B constants); (2) nonintegrated core model testing; and (3) fully integrated core model testing. Simulator core model validation and verification is a multistage process involving input and benchmark data generation as well as interactive debugging. Core characteristics were brought within acceptable criteria by this process. This process was achieved through constant communication between Link-Miles and Yankee engineers. Based on this validation, the Yankee Rowe simulator core model is found to be acceptable for training purposes.

Napolitano, M.E.

1990-01-01T23:59:59.000Z

371

DIODE STEERED MANGETIC-CORE MEMORY  

DOE Patents (OSTI)

A word-arranged magnetic-core memory is designed for use in a digital computer utilizing the reverse or back current property of the semi-conductor diodes to restore the information in the memory after read-out. In order to ob tain a read-out signal from a magnetic core storage unit, it is necessary to change the states of some of the magnetic cores. In order to retain the information in the memory after read-out it is then necessary to provide a means to return the switched cores to their states before read-out. A rewrite driver passes a pulse back through each row of cores in which some switching has taken place. This pulse combines with the reverse current pulses of diodes for each column in which a core is switched during read-out to cause the particular cores to be switched back into their states prior to read-out. (AEC)

Melmed, A.S.; Shevlin, R.T.; Laupheimer, R.

1962-09-18T23:59:59.000Z

372

Core Level Spectroscopies Surface Science and X-Ray Spectroscopy Group  

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

Core Level Spectroscopy Creation and Decay of Core Holes Spectroscopic Techniques X-ray Photoelectron (XPS) X-ray Absorption (XAS) X-ray Emission (XES) Auger Electron (AES) Core holes are created by the ionization of a core electron in XPS and by excitation in XAS . The XPS and XAS final states are highly unstable and the core hole decays by non-radiant Auger relaxation (AES) or by radiant x-ray emission processes (XES). XPS and AES probe the unoccupied electronic stru cture, while XAS projects the unoccupied valence states of the system onto a particular atom. A brief description of the each of the different spectroscopies illustrated by schematic pictures of the creation and decay with data measured for N2 adsorbed on Ni(100) can be found by scrolling

373

Unified nuclear core activity map reconstruction using heterogeneous instruments with data assimilation  

E-Print Network (OSTI)

Evaluating the neutronic state of the whole nuclear core is a very important topic that have strong implication for nuclear core management and for security monitoring. The core state is evaluated using measurements. Usually, part of the measurements are used, and only one kind of instruments are taken into account. However, the core state evaluation should be more accurate when more measurements are collected in the core. But using information from heterogeneous sources is at glance a difficult task. This difficulty can be overcome by Data Assimilation techniques. Such a method allows to combine in a coherent framework the information coming from model and the one coming from various type of observations. Beyond the inner advantage to use heterogeneous instruments, this leads to obtain a significant increasing of the quality of neutronic global state reconstruction with respect to individual use of measures. In order to present this approach, we will introduce here the basic principles of data assimilation f...

Bouriquet, Bertrand; Erhard, Patrick; Ponot, Anglique

2011-01-01T23:59:59.000Z

374

Manufactured residential utility wall system (ResCore), overview  

SciTech Connect

This paper provides an overview of the design and development of a manufactured residential utility wall system referred to as ResCore. ResCore is a self-contained, manufactured, residential utility wall that provides complete rough-in of utilities (power, gas, water, and phone) and other functions (exhaust, combustion make-up air, refrigerant lines, etc.) to serve the residential kitchen, bath, utility, and laundry rooms. Auburn University, Department of Industrial Design faculty and students, supported by a team of graduate student researchers and the project`s advisory team, developed the ResCore. The project was accomplished through a research subcontract from the US Department of Energy administered by the Oak Ridge National Laboratory. The ResCore wall system features a ``layered`` manufacturing technique that allows each major component group--structural, cold water, hot water, drain, gas, electric, etc.--to be built as a separate subassembly and easily brought together for final assembly. The two structural layers are reinforced with bridging that adds strength and also permits firm attachment of plumbing pipes and other systems to the wall frame.

Wendt, R. [Oak Ridge National Lab., TN (United States); Lundell, C.; Lau, T.M. [Auburn Univ., AL (United States)

1997-05-01T23:59:59.000Z

375

Manufactured Residential Utility Wall System (ResCore),  

SciTech Connect

This paper describes the design and development of a manufactured residential utility wall system referred to as ResCore. ResCore is a self contained, manufactured, residential utility wall that provides complete rough-in of utilities (power, gas, water, and phone) and other functions (exhaust, combustion make-up air, refrigerant lines, etc.) to serve the kitchen, bath, utility, and laundry rooms. Auburn University, Department of Industrial Design faculty, students, supported by a team of graduate student researchers and the project`s advisory team, developed the ResCore. The project was accomplished through a research subcontract from the U.S. Department of Energy administered by the Oak Ridge National Laboratory. The ResCore wall system features a layered manufacturing technique that allows each major component group: structural, cold water, hot water, drain, gas, electric, etc. to be built as a separate subassembly and easily brought together for final assembly. The two structural layers are reinforced with bridging that adds strength and also permits firm attachment of plumbing pipes and other systems to the wall frame.

Wendt, Robert [Oak Ridge National Lab., TN (United States); Lundell, Clark; Lau, Tin Man [Auburn Univ., AL (United States)

1997-12-31T23:59:59.000Z

376

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:

377

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

378

Core/Shell Nanophosphors for LED Lighting  

Science Conference Proceedings (OSTI)

Symposium, Symposium H: Advanced Ceramics. Presentation Title, Core/Shell Nanophosphors for LED Lighting. Author(s), Jinkyu Han, Gustavo Hirata, Jan B...

379

Material with core-shell structure  

DOE Patents (OSTI)

Disclosed is a material having a composite particle, the composite particle including an outer shell and a core. The core is made from a lithium alloying material and the outer shell has an inner volume that is greater in size than the core of the lithium alloying material. In some instances, the outer mean diameter of the outer shell is less than 500 nanometers and the core occupies between 5 and 99% of the inner volume. In addition, the outer shell can have an average wall thickness of less than 100 nanometers.

Luhrs, Claudia (Rio Rancho, NM); Richard, Monique N. (Ann Arbor, MI); Dehne, Aaron (Maumee, OH); Phillips, Jonathan (Rio Rancho, NM); Stamm, Kimber L. (Ann Arbor, MI); Fanson, Paul T. (Brighton, MI)

2011-11-15T23:59:59.000Z

380

SECA Core Technology Program Seal Workshop  

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

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...

Note: This page contains sample records for the topic "technique 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

SECA Core Technology Program - SOFC Interconnect Meeting  

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

Core Technology Program - SOFC Interconnect Meeting July 28-29, 2004 Table of Contents Disclaimer Participants PDF-17KB Presentations Products Disclaimer This report was prepared...

382

Technique for information retrieval using enhanced latent semantic analysis generating rank approximation matrix by factorizing the weighted morpheme-by-document matrix  

SciTech Connect

A technique for information retrieval includes parsing a corpus to identify a number of wordform instances within each document of the corpus. A weighted morpheme-by-document matrix is generated based at least in part on the number of wordform instances within each document of the corpus and based at least in part on a weighting function. The weighted morpheme-by-document matrix separately enumerates instances of stems and affixes. Additionally or alternatively, a term-by-term alignment matrix may be generated based at least in part on the number of wordform instances within each document of the corpus. At least one lower rank approximation matrix is generated by factorizing the weighted morpheme-by-document matrix and/or the term-by-term alignment matrix.

Chew, Peter A; Bader, Brett W

2012-10-16T23:59:59.000Z

383

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

384

Definition: Drilling Techniques | Open Energy Information  

Open Energy Info (EERE)

Techniques Techniques Jump to: navigation, search Dictionary.png Drilling Techniques There are a variety of drilling techniques which can be used to sink a borehole into the ground. Each has its advantages and disadvantages, in terms of the depth to which it can drill, the type of sample returned, the costs involved and penetration rates achieved. There are two basic types of drills: drills which produce rock chips, and drills which produce core samples.[1] View on Wikipedia Wikipedia Definition Well drilling is the process of drilling a hole in the ground for the extraction of a natural resource such as ground water, brine, natural gas, or petroleum, for the injection of a fluid from surface to a subsurface reservoir or for subsurface formations evaluation or monitoring.

385

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Analysis of core damage frequency from internal events for plant operational state 5 during a refueling outage. Internal events appendices K to M  

Science Conference Proceedings (OSTI)

This report provides supporting documentation for various tasks associated with the performance of the probabilistic risk assessment for Plant Operational State 5 (approximately Cold Shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143. The report contains the following appendices: K - HEP Locator Files; L - Supporting Information for the Plant Damage State Analysis; M - Summary of Results from the Coarse Screening Analysis - Phase 1A.

Forester, J.; Yakle, J.; Walsh, B. [Science Applications International Corp., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Whitehead, D.; Staple, B.; Brown, T. [Sandia National Labs., Albuquerque, NM (United States)

1994-07-01T23:59:59.000Z

386

1. Exploratory Data Analysis  

Science Conference Proceedings (OSTI)

1. Exploratory Data Analysis. This chapter presents the assumptions, principles, and techniques necessary to gain insight ...

2013-10-30T23:59:59.000Z

387

An Examination of Failure Modes and Investigation Techniques in ...  

Science Conference Proceedings (OSTI)

Accident Investigation and Materials Failure Analysis at the Transportation Safety ... Experimental Technique to Conduct Thermal Shock Test on Refractories...

388

Dynamism in the solar core  

E-Print Network (OSTI)

Recent results of a mixed shell model heated asymmetrically by transient increases in nuclear burning indicate the transient generation of small hot spots inside the Sun somewhere between 0.1 and 0.2 solar radii. These hot bubbles are followed by a nonlinear differential equation system with finite amplitude non-homologous perturbations which is solved in a solar model. Our results show the possibility of a direct connection between the dynamic phenomena of the solar core and the atmospheric activity. Namely, an initial heating about DQ_0 ~ 10^{31}-10^{37} ergs can be enough for a bubble to reach the outer convective zone. Our calculations show that a hot bubble can arrive into subphotospheric regions with DQ_final ~ 10^{28} - 10^{34} ergs with a high speed, up to 10 km s-1, approaching the local sound speed. We point out that the developing sonic boom transforms the shock front into accelerated particle beam injected upwards into the top of loop carried out by the hot bubble above its forefront traveling fro...

Grandpierre, Attila

2010-01-01T23:59:59.000Z

389

Method and apparatus for recovering unstable cores  

DOE Patents (OSTI)

A method and apparatus suitable for stabilizing hydrocarbon cores are given. Such stabilized cores have not previously been obtainable for laboratory study, and such study is believed to be required before the hydrate reserves can become a utilizable resource. The apparatus can be built using commercially available parts and is very simple and safe to operate.

McGuire, P.L.; Barraclough, B.L.

1981-04-01T23:59:59.000Z

390

Core equivalence in economy for modal logic  

Science Conference Proceedings (OSTI)

We investigate a pure exchange economy under uncertainty with emphasis on the logical point of view; the traders are assumed to have a multi-modal logic with non-partitional information structures.We propose a generalized notion of rational expectations ... Keywords: core equivalence theorem, ex-post core, multi-modal logic, pure exchange economy under reflexive information structure, rational expectations equilibrium

Takashi Matsuhisa

2003-06-01T23:59:59.000Z

391

Moving core beam energy absorber and converter  

SciTech Connect

A method and apparatus for the prevention of overheating of laser or particle beam impact zones through the use of a moving-in-the-coolant-flow arrangement for the energy absorbing core of the device. Moving of the core spreads the energy deposition in it in 1, 2, or 3 dimensions, thus increasing the effective cooling area of the device.

Degtiarenko, Pavel V.

2012-12-18T23:59:59.000Z

392

Module Handbook Core Univ. of Oldenburg  

E-Print Network (OSTI)

, DMS (strain gauge?) Test bridge, Fatigue Extrapolation · Wind Diesel Systeme in kleinen Inselnetzen/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

393

Method and apparatus for recovering unstable cores  

SciTech Connect

A method and apparatus suitable for stabilizing hydrocarbon cores are given. Such stabilized cores have not previously been obtainable for laboratory study, and such study is believed to be required before the hydrate reserves can become a utilizable resource. The apparatus can be built using commercially available parts and is very simple and safe to operate.

McGuire, Patrick L. (Los Alamos, NM); Barraclough, Bruce L. (Los Alamos, NM)

1983-01-01T23:59:59.000Z

394

Core Science Requirement Final Document Page 1 THE CORE SCIENCE REQUIREMENT and  

E-Print Network (OSTI)

Core Science Requirement ­ Final Document ­ Page 1 THE CORE SCIENCE REQUIREMENT and MENDEL SCIENCE EXPERIENCE COURSES Core requirement of 2 semesters of science with laboratory; requirement to be met by the end of the sophomore year Rationale Science literacy is an integral part of the intellectual

Lagalante, Anthony F.

395

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

396

Magnetic nuclear core restraint and control  

DOE Patents (OSTI)

A lateral restraint and control system for a nuclear reactor core adaptable to provide an inherent decrease of core reactivity in response to abnormally high reactor coolant fluid temperatures. An electromagnet is associated with structure for radially compressing the core during normal reactor conditions. A portion of the structures forming a magnetic circuit are composed of ferromagnetic material having a curie temperature corresponding to a selected coolant fluid temperature. Upon a selected signal, or inherently upon a preselected rise in coolant temperature, the magnetic force is decreased a given amount sufficient to relieve the compression force so as to allow core radial expansion. The expanded core configuration provides a decreased reactivity, tending to shut down the nuclear reaction.

Cooper, Martin H. (Monroeville, PA)

1979-01-01T23:59:59.000Z

397

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

398

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

399

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

400

CORE LEVITATION IN THE EGCR IN CASE OF MAIN COOLANT PIPE FAILURE  

SciTech Connect

Results of an analysis to determine the extent of displacement of the EGCR core due to blowdown in case of several postulated hot main gas coolant pipe failures are summarized. Results show that the core will be damaged for ary hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing prior to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect. (auth)

Fontana, M.H.

1959-08-04T23:59:59.000Z

Note: This page contains sample records for the topic "technique 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

A DOUBLE CLUSTER AT THE CORE OF 30 DORADUS  

SciTech Connect

Based on an analysis of data obtained with the Wide Field Camera 3 on the Hubble Space Telescope we report the identification of two distinct stellar populations in the core of the giant H II region 30 Doradus in the Large Magellanic Cloud. The most compact and richest component coincides with the center of R136 and is {approx}1 Myr younger than a second more diffuse clump, located {approx}5.4 pc toward the northeast. We note that published spectral types of massive stars in these two clumps lend support to the proposed age difference. The morphology and age difference between the two sub-clusters suggests that an ongoing merger may be occurring within the core of 30 Doradus. This finding is consistent with the predictions of models of hierarchical fragmentation of turbulent giant molecular clouds, according to which star clusters would be the final products of merging smaller sub-structures.

Sabbi, E.; De Mink, S. E.; Walborn, N. R.; Anderson, J.; Bellini, A.; Panagia, N.; Van der Marel, R. [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States); Lennon, D. J. [ESA/STScI, 3700 San Martin Drive, Baltimore, MD 21218 (United States); Gieles, M. [Institute of Astronomy, University of Cambridge, Madingley Road, Cambridge CB3 0HA (United Kingdom); Apellaniz, J. Maiz, E-mail: sabbi@stsci.edu [Instituto de Astrofisica de Andalucia-CSIC, Glorieta de la Astronomia s/n, E-18008, Granada (Spain)

2012-08-01T23:59:59.000Z

402

CELL POPULATIONS AND CELL PROLIFERATION IN THE IN VITRO RESPONSE OF NORMAL MOUSE SPLEEN TO HETEROLOGOUS ERYTHROCYTES*,$ ANALYSIS BY "1i1 ~ HOT PULSE TECHNIQUE  

E-Print Network (OSTI)

It has been shown in the accompanying paper (1) that spleen cell suspensions from normal mice can be immunized to heterologous erythrocytes in an in vitro system. When sheep erythrocytes are added at the initiation of culture, the number of antibody-forming cells (as determined by the hemolytic plaque assay) rises from an initial value of approximately 1 per 106 to 1,000 per 10 e recovered cells 4 days later in a typical experiment. The kinetics of the response follow an approximately exponential form at least in the later time periods. The assay system measures 19S antibodyforming cells (2) and the response is "primary " in the sense that it follows the first experimental exposure to antigen. Previous in vivo studies have indicated that the increase is largely the result of proliferation of precursor cells and they have further suggested that cell proliferation begins after an 18-24 hr lag period (for a review see reference 3). These studies, however, leave some room for doubt, as will be discussed below, and the problem has been reinvestigated in this in vitro system as part of a more general analysis of the cellular response to antigen. The questions asked here are: (a) at what times during the

W. Dutton, Ph.D.; Robert; I. Mishell

1967-01-01T23:59:59.000Z

403

Oak Ridge National Laboratory Core Competencies  

Science Conference Proceedings (OSTI)

A core competency is a distinguishing integration of capabilities which enables an organization to deliver mission results. Core competencies represent the collective learning of an organization and provide the capacity to perform present and future missions. Core competencies are distinguishing characteristics which offer comparative advantage and are difficult to reproduce. They exhibit customer focus, mission relevance, and vertical integration from research through applications. They are demonstrable by metrics such as level of investment, uniqueness of facilities and expertise, and national impact. The Oak Ridge National Laboratory (ORNL) has identified four core competencies which satisfy the above criteria. Each core competency represents an annual investment of at least $100M and is characterized by an integration of Laboratory technical foundations in physical, chemical, and materials sciences; biological, environmental, and social sciences; engineering sciences; and computational sciences and informatics. The ability to integrate broad technical foundations to develop and sustain core competencies in support of national R&D goals is a distinguishing strength of the national laboratories. The ORNL core competencies are: 9 Energy Production and End-Use Technologies o Biological and Environmental Sciences and Technology o Advanced Materials Synthesis, Processing, and Characterization & Neutron-Based Science and Technology. The distinguishing characteristics of each ORNL core competency are described. In addition, written material is provided for two emerging competencies: Manufacturing Technologies and Computational Science and Advanced Computing. Distinguishing institutional competencies in the Development and Operation of National Research Facilities, R&D Integration and Partnerships, Technology Transfer, and Science Education are also described. Finally, financial data for the ORNL core competencies are summarized in the appendices.

Roberto, J.B.; Anderson, T.D.; Berven, B.A.; Hildebrand, S.G.; Hartman, F.C.; Honea, R.B.; Jones, J.E. Jr.; Moon, R.M. Jr.; Saltmarsh, M.J.; Shelton, R.B. [and others

1994-12-01T23:59:59.000Z

404

Development of SRC-I product analysis. Volume 2. Evaluation of analytical techniques for SRC-I characterization, recycle solvent studies, and product fractionation studies  

Science Conference Proceedings (OSTI)

A data analysis was performed to determine the relationship between the Wilsonville Solvent Quality test result and SRC liquefaction process parameters. The data base studied covers the years 1979 to 1982, Wilsonville runs 133 to 234. Only process-defined material balance data sets were included to best represent steady-state operation. Each material balance period provided 48 variables from which common process conditions were selected by imposing a range of acceptable deviations from a norm, e.g., a reactor hydrogen pressure of 2000 +- 100 psi. Data for all variables vs. solvent quality were plotted, and in some cases variables were compared with each other to determine common trends, e.g. gas production vs. hydrogen consumption. The plotted data produced no discernible trends. Separating the data by coal type (mine location) and identifying common process conditions with coal types still provided no absolute correlations with solvent quality. However, the effect of the weight percent pyrite present in the feed coal produced a consistent trend. A coal containing more than 1.2% pyrite and less than 0.1% sulfate sulfur yielded results in which any one correlation would cluster about a central point. It was observed that, on average, Kentucky Fies and Pyro mine coal and Indiana V coal clustered together, while Kentucky Lafayette and Dotiki mine coals clustered together. These data point clusters for the variables tested were nearly independent of reactor pressure, space rate, and temperature. One unusual observation of all the data points, independent of process conditions, was that at each change of feed coal, the sum of hydrocarbon and heteroatom gas production was greatest for the first 30 days, after which gas production reached a steady state dependent on process conditions, primarily temperature.

Schweighardt, F.K.; Kingsley, I.S.; Cooper, F.E.; Kamzelski, A.Z.; Parees, D.M.

1983-09-01T23:59:59.000Z

405

Apparatus for controlling molten core debris. [LMFBR  

DOE Patents (OSTI)

Disclosed is an apparatus for containing, cooling, diluting, dispersing and maintaining subcritical the molten core debris assumed to melt through the bottom of a nuclear reactor pressure vessel in the unlikely event of a core meltdown. The apparatus is basically a sacrificial bed system which includes an inverted conical funnel, a core debris receptacle including a spherical dome, a spherically layered bed of primarily magnesia bricks, a cooling system of zig-zag piping in graphite blocks about and below the bed and a cylindrical liner surrounding the graphite blocks including a steel shell surrounded by firebrick. Tantalum absorber rods are used in the receptacle and bed. 9 claims, 22 figures.

Golden, M.P.; Tilbrook, R.W.; Heylmun, N.F.

1977-07-19T23:59:59.000Z

406

Apparatus for controlling molten core debris  

DOE Patents (OSTI)

Apparatus for containing, cooling, diluting, dispersing and maintaining subcritical the molten core debris assumed to melt through the bottom of a nuclear reactor pressure vessel in the unlikely event of a core meltdown. The apparatus is basically a sacrificial bed system which includes an inverted conical funnel, a core debris receptacle including a spherical dome, a spherically layered bed of primarily magnesia bricks, a cooling system of zig-zag piping in graphite blocks about and below the bed and a cylindrical liner surrounding the graphite blocks including a steel shell surrounded by firebrick. Tantalum absorber rods are used in the receptacle and bed.

Golden, Martin P. (Trafford, PA); Tilbrook, Roger W. (Monroeville, PA); Heylmun, Neal F. (Pittsburgh, PA)

1977-07-19T23:59:59.000Z

407

Category:Geochemical Techniques | Open Energy Information  

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 Category Edit History Facebook icon Twitter icon » Category:Geochemical Techniques Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermalpower.jpg Looking for the Geochemical Techniques page? For detailed information on exploration techniques, click here. Category:Geochemical Techniques Add.png Add a new Geochemical Techniques Technique Subcategories This category has only the following subcategory. G [×] Geochemical Data Analysis‎ 3 pages Pages in category "Geochemical Techniques" This category contains only the following page. G Geochemical Data Analysis Retrieved from "http://en.openei.org/w/index.php?title=Category:Geochemical_Techniques&oldid=689823"

408

Real-Time Out-of-Core Rendering  

E-Print Network (OSTI)

Hierarchical levels of details (HLODs) have proven to be an efficient way to visualize complex environments and models even in an out-of-core system. Large objects are partitioned into a spatial hierarchy and for each node a level of detail is generated for efficient view-dependent rendering. To ensure correct matching between adjacent nodes in the hierarchy care has to be taken to prevent cracks along the cuts. This either leads to severe simplification constraints at the cuts and thus to a significantly higher number of triangles or the need for a costly runtime stitching of these nodes. In this paper we present an out-of-core visualization algorithm that overcomes this problem by filling the cracks generated by the simplification algorithm with appropriately shaded Fat Borders. Furthermore, several minor yet important improvements of previous approaches are made. This way we come up with a simple nevertheless efficient viewdependent rendering technique which allows for the natural incorporation of state-of-theart culling, simplification, compression and prefetching techniques leading to real-time rendering performance of the overall system. Several examples demonstrate the efficiency of our approach.

Michael Guthe; Pavel Borodin; Reinhard Klein

2004-01-01T23:59:59.000Z

409

Efficient view-dependent out-of-core visualization  

E-Print Network (OSTI)

Hierarchical levels of details (HLODs) have proven to be an efficient way to visualize complex environments and models even in an out-of-core system. Large objects are partitioned into a spatial hierarchy and on each node a level of detail is generated for efficient view-dependent rendering. To ensure correct matching between adjacent nodes in the hierarchy care has to be taken to prevent cracks along the cuts. This either leads to severe simplification constraints at the cuts and thus to a significantly higher number of triangles or the need for a costly runtime stitching of these nodes. In this paper we present an out-of-core visualization algorithm that overcomes this problem by filling the cracks generated by the simplification algorithm with appropriately shaded fat borders. Furthermore, several minor yet important improvements of previous approaches are made. This way we come up with a simple nevertheless efficient view-dependent rendering technique which allows for the natural incorporation of state-of-the-art culling, simplification, compression and prefetching techniques. 1.

Michael Guthe; Pavel Borodin; Reinhard Klein

2003-01-01T23:59:59.000Z

410

Melting temperature of iron in the core diamond cell experiments Guoyin Shen  

E-Print Network (OSTI)

, Washington DC, 1998. 3. Boehler, R., High pressure experiments and the phase diagram of lower mantle and core. Manghnani and Y. Syono (Terra Scientific Publishing Company/American Geophysical Union, Tokyo, Washington DC materials, Rev. Geophysics, 38, 221-245, 2000. Diamond cell technique Diamond as anvil and window Diamond

Shen, Guoyin

411

Core Measure Average KTR Results  

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

Measure Measure Average KTR Results FY 12 Target FY 12 DOE M&O CONTRACTOR (KTR) BSC RESULTS FY 2012 Customer Perspective and level of communication provided by the procurement office 95 92 Internal Business Perspective: Assessment (%) of the degree to which the purchasing system is in compliance with stakeholder requirements 97 Local Goals % Delivery on-time (includes JIT, excludes Purchase Cards) 88 84 % of total dollars obligated, on actions > $150K , that were awarded using effective competition 73 Local Goals Rapid Purchasing Techniques: -% of transactions placed by users 77 Local Goals -% of transactions placed through electronic commerce 62 Local Goals Average Cycle Time: -Average cycle time for <= $150K 8 6 to 9 days

412

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":""}]}

413

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.)

414

Policy Core Information Model (PCIM) Extensions  

Science Conference Proceedings (OSTI)

This document specifies a number of changes to the Policy Core Information Model (PCIM, RFC 3060). Two types of changes are included. First, several completely new elements are introduced, for example, classes for header filtering, that extend PCIM ...

B. Moore

2003-01-01T23:59:59.000Z

415

The systems biology simulation core algorithm  

E-Print Network (OSTI)

Keller et al. : The systems biology simulation core algo-rithm. BMC Systems Biology 2013 7:55. Page 16 of 16 SubmitMacilwain C: Systems biology: evolving into the mainstream.

2013-01-01T23:59:59.000Z

416

Multiple network interface core apparatus and method  

DOE Patents (OSTI)

A network interface controller and network interface control method comprising providing a single integrated circuit as a network interface controller and employing a plurality of network interface cores on the single integrated circuit.

Underwood, Keith D. (Albuquerque, NM); Hemmert, Karl Scott (Albuquerque, NM)

2011-04-26T23:59:59.000Z

417

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

418

Armor systems including coated core materials  

SciTech Connect

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

Inner Core Strength of Atlantic Tropical Cyclones  

Science Conference Proceedings (OSTI)

The evolution of the wind field beyond the radius of maximum winds is studied for 18 Atlantic tropical cyclones (TCs) with 989 research and reconnaissance flight legs. Inner core strength, defined as the storm relative mean tangential wind from ...

Mark Croxford; Gary M. Barnes

2002-01-01T23:59:59.000Z

420

RADIOACTIVITY IN EARTH'S CORE Definition ... - Springer  

Science Conference Proceedings (OSTI)

pressures: implications for uranium solubility in planetary cores. ...... Kamiokande cavity in a horizontal mine drift in the Japa- nese Alps. The detector is ...... in aerial or space imagery. Tectonics. A field of study within geology concerned gen

Note: This page contains sample records for the topic "technique 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

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

422

Granular Dynamics in Pebble Bed Reactor Cores  

E-Print Network (OSTI)

flow in a pebble-bed nuclear reactor, Phys. Rev. E, vol.from the current fleet of nuclear reactors far outweigh thethrough the core of a nuclear reactor. This regime includes

Laufer, Michael Robert

2013-01-01T23:59:59.000Z

423

MODULAR CORE UNITS FOR A NEUTRONIC REACTOR  

DOE Patents (OSTI)

A modular core unit for use in a nuclear reactor is described. Many identical core modules can be placed next to each other to make up a complete core. Such a module includes a cylinder of moderator material surrounding a fuel- containing re-entrant coolant channel. The re-entrant channel provides for the circulation of coolant such as liquid sodium from one end of the core unit, through the fuel region, and back out through the same end as it entered. Thermal insulation surrounds the moderator exterior wall inducing heat to travel inwardly to the coolant channel. Spaces between units may be used to accommodate control rods and support structure, which may be cooled by a secondary gas coolant, independently of the main coolant. (AEC)

Gage, J.F. Jr.; Sherer, D.B.

1964-04-01T23:59:59.000Z

424

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

425

Incorporation of silica into baroplastic core-shell nanoparticles  

E-Print Network (OSTI)

Core-shell baroplastics are nanophase materials that exhibit pressure-induced flow at low temperatures and high pressures. Core-shell baroplastics used in this work are comprised of a low Tg poly(butyl acrylate) (PBA) core ...

Hewlett, Sheldon A

2006-01-01T23:59:59.000Z

426

Argonne CNM Highlight: Complexity in Core-Shell Nanomagnets  

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

Complexity in Core-Shell Nanomagnets Magnetgic hysteresis of core-shell nanoparticles (curves) Magnetic hysteresis of core-shell Fe@Fe3O4 nanoparticles at 5 K under field cooling...

427

Probing Core-Hole Localization in Molecular Nitrogen  

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

Probing Core-Hole Localization in Molecular Nitrogen Probing Core-Hole Localization in Molecular Nitrogen Print Wednesday, 25 February 2009 00:00 The behavior of the core hole...

428

Electron Based Techniques  

Science Conference Proceedings (OSTI)

Mar 5, 2013 ... Characterization of Materials through High Resolution Coherent Imaging: Electron Based Techniques Sponsored by: TMS Structural Materials...

429

Milling Techniques - TMS  

Science Conference Proceedings (OSTI)

February 4-8 1996 TMS ANNUAL MEETING Anaheim, California. SYNTHESIS AND PROCESSING OF NANOCRYSTALLINE POWDER III: Milling Techniques...

430

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.

431

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

432

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.; Reigel, M.

2012-09-25T23:59:59.000Z

433

Core-Shell Structured Magnetic Ternary Nanocubes  

DOE Green Energy (OSTI)

While transition metal-doped ferrite nanoparticles constitute an important class of soft magnetic nanomaterials with spinel structures, the ability to control the shape and composition would enable a wide range of applications in homogeneous or heterogeneous reactions such as catalysis and magnetic separation of biomolecules. This report describes novel findings of an investigation of core-shell structured MnZn ferrite nanocubes synthesized in organic solvents by manipulating the reaction temperature and capping agent composition in the absence of the conventionally-used reducing agents. The core-shell structure of the highly-monodispersed nanocubes (~20 nm) are shown to consist of an Fe3O4 core and an (Mn0.5Zn0.5)(Fe0.9, Mn1.1)O4 shell. In comparison with Fe3O4 and other binary ferrite nanoparticles, the core-shell structured nanocubes were shown to display magnetic properties regulated by a combination of the core-shell composition, leading to a higher coercivity (~350 Oe) and field-cool/zero-field-cool characteristics drastically different from many regular MnZn ferrite nanoparticles. The findings are discussed in terms of the unique core-shell composition, the understanding of which has important implication to the exploration of this class of soft magnetic nanomaterials in many potential applications such as magnetic resonance imaging, fuel cells, and batteries.

Wang, Lingyan; Wang, Xin; Luo, Jin; Wanjala, Bridgid N.; Wang, Chong M.; Chernova, Natalya; Engelhard, Mark H.; Liu, Yao; Bae, In-Tae; Zhong, Chuan-Jian

2010-12-01T23:59:59.000Z

434

Operational dose rate visualization techniques  

SciTech Connect

The analysis of the gamma ray dose rate in the vicinity of a radiation source can be greatly aided by the use of recent state-of-the-art visualization techniques. The method involves calculating dose rates at thousands of locations within a complex geometry system. This information is then processed to create contour plots of the dose rate. Additionally, when these contour plots are created, animations can be created that dynamically display the dose rate as the shields or sources are moved.

Schwarz, R.A.; Morford, R.J.; Carter, L.L.; Jones, G.B.; Greenborg, J.

1994-01-01T23:59:59.000Z

435

Structural mechanics of fast spectrum nuclear reactor cores  

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

mechanics of fast spectrum nuclear reactor cores A fast reactor core is composed of a closely packed hexagonal arrangement of fuel, control, blanket , and shielding assemblies....

436

Recovery Act - Solid-State Lighting Core Technologies Funding...  

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

Act - Solid-State Lighting Core Technologies Funding Opportunity Recovery Act - Solid-State Lighting Core Technologies Funding Opportunity A report detailling the Solid State...

437

Historical Carbon Dioxide Record from the Vostok Ice Core  

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

Vostok Ice Core Historical Carbon Dioxide Record from the Vostok Ice Core graphics Graphics data Data Investigators J.-M. Barnola, D. Raynaud, C. Lorius Laboratoire de Glaciologie...

438

Historical Carbon Dioxide Record from the Siple Station Ice Core  

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

Siple Station Ice Core Historical Carbon Dioxide Record from the Siple Station Ice Core graphics Graphics data Data Investigators A. Neftel, H. Friedli, E. Moor, H. Ltscher, H....

439

Probing Core-Hole Localization in Molecular Nitrogen  

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

Probing Core-Hole Localization in Molecular Nitrogen Print The behavior of the core hole created in molecular x-ray photoemission experiments has provided molecular scientists with...

440

SECURITY CORE FUNCTION AND DEFINITION REPORT | Department of...  

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

SECURITY CORE FUNCTION AND DEFINITION REPORT SECURITY CORE FUNCTION AND DEFINITION REPORT The first phase of the Lemnos Interoperable Security Program shall lay the foundation for...

Note: This page contains sample records for the topic "technique 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

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

442

Compound and Elemental Analysis At Fenton Hill Hdr Geothermal Area  

Open Energy Info (EERE)

Fenton Hill Hdr Fenton Hill Hdr Area (Laughlin, Et Al., 1983) Exploration Activity Details Location Fenton Hill Hdr Area Exploration Technique Compound and Elemental Analysis Activity Date Usefulness useful DOE-funding Unknown Notes Thin sections were prepared of the different lithologies from each core. Standard petrographic techniques were used to identify constituent minerals and to obtain modal analyses. The number of points counted varied from about 500 to several thousand, depending upon the grain size of the rock. Whole-rock chemical analysis was performed by John Husler, University of New Mexico, using a variety of techniques (Laughlin and Eddy, 1977). The precision for SiO2 is + 1% relative; for the other oxides it is + 2% relative. Accuracy was monitored by using USGS standard rock samples. Where

443

Low-Wavenumber Structure and Evolution of the Hurricane Inner Core Observed by Airborne Dual-Doppler Radar  

Science Conference Proceedings (OSTI)

The asymmetric dynamics of the hurricane inner-core region is examined through a novel analysis of high temporal resolution, three-dimensional wind fields derived from airborne dual-Doppler radar. Seven consecutive composites of Hurricane Olivia...

Paul D. Reasor; Michael T. Montgomery; Frank D. Marks Jr.; John F. Gamache

2000-06-01T23:59:59.000Z

444

Assembly of large metagenome data sets using a Convey HC-1 hybrid core computer ( 7th Annual SFAF Meeting, 2012)  

SciTech Connect

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

2012-06-01T23:59:59.000Z

445

Unified nuclear core activity map reconstruction using heterogeneous instruments with data assimilation  

E-Print Network (OSTI)

Evaluating the neutronic state of the whole nuclear core is a very important topic that have strong implication for nuclear core management and for security monitoring. The core state is evaluated using measurements. Usually, part of the measurements are used, and only one kind of instruments are taken into account. However, the core state evaluation should be more accurate when more measurements are collected in the core. But using information from heterogeneous sources is at glance a difficult task. This difficulty can be overcome by Data Assimilation techniques. Such a method allows to combine in a coherent framework the information coming from model and the one coming from various type of observations. Beyond the inner advantage to use heterogeneous instruments, this leads to obtain a significant increasing of the quality of neutronic global state reconstruction with respect to individual use of measures. In order to present this approach, we will introduce here the basic principles of data assimilation focusing on BLUE (Best Unbiased Linear Estimation). Then we will present the configuration of the method within the nuclear core problematic. Finally, we will present the results obtained on nuclear measurement coming from various instruments.

Bertrand Bouriquet; Jean-Philippe Argaud; Patrick Erhard; Anglique Ponot

2011-08-30T23:59:59.000Z

446

LMR design concepts for transuranic management in low sodium void worth cores  

Science Conference Proceedings (OSTI)

The fuel cycle processing techniques and hard neuron spectrum of the Integral Fast Reactor (IFR) metal fuel cycle have favorable characteristics for the management of transuranics; and the wide range of breeding characteristics available in metal fuelled cores provides for flexibility in transuranic management strategy. Previous studies indicate that most design options which decrease the breeding ratio also show a decrease in sodium void worth; therefore, low void worths are achievable in transuranic burning (low breeding ratio) core designs. This paper describes numerous trade studies assessing various design options for a low void worth transuranic burner core