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1

Core Analysis | Open Energy Information  

Open Energy Info (EERE)

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

2

Core Analysis At 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...

3

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...

4

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...

5

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...

6

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...

7

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...

8

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

9

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

10

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

11

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

12

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

13

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...

14

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

15

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"

16

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

17

IS ACTIVE REGION CORE VARIABILITY AGE DEPENDENT?  

Science Conference Proceedings (OSTI)

The presence of both steady and transient loops in active region cores has been reported from soft X-ray and extreme-ultraviolet observations of the solar corona. The relationship between the different loop populations, however, remains an open question. We present an investigation of the short-term variability of loops in the core of two active regions in the context of their long-term evolution. We take advantage of the nearly full Sun observations of STEREO and Solar Dynamics Observatory spacecraft to track these active regions as they rotate around the Sun multiple times. We then diagnose the variability of the active region cores at several instances of their lifetime using EIS/Hinode spectral capabilities. We inspect a broad range of temperatures, including for the first time spatially and temporally resolved images of Ca XIV and Ca XV lines. We find that the active region cores become fainter and steadier with time. The significant emission measure at high temperatures that is not correlated with a comparable increase at low temperatures suggests that high-frequency heating is viable. The presence, however, during the early stages, of an enhanced emission measure in the ''hot'' (3.0-4.5 MK) and ''cool'' (0.6-0.9 MK) components suggests that low-frequency heating also plays a significant role. Our results explain why there have been recent studies supporting both heating scenarios.

Ugarte-Urra, Ignacio [College of Science, George Mason University, 4400 University Drive, Fairfax, VA 22030 (United States); Warren, Harry P. [Space Science Division, Naval Research Laboratory, Washington, DC 20375 (United States)

2012-12-10T23:59:59.000Z

18

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...

19

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

20

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

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


21

Core Analysis At 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

22

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

23

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...

24

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

25

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

26

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...

27

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

28

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

29

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

30

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

31

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

32

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...

33

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

34

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"

35

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...

36

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

37

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...

38

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

39

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

40

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

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


41

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

42

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

43

Carbon-Supported IrNi Core-Shell Nanoparticles: Synthesis Characterization and Catalytic Activity  

Science Conference Proceedings (OSTI)

We synthesized carbon-supported IrNi core-shell nanoparticles by chemical reduction and subsequent thermal annealing in H{sub 2}, and verified the formation of Ir shells on IrNi solid solution alloy cores by various experimental methods. The EXAFS analysis is consistent with the model wherein the IrNi nanoparticles are composed of two-layer Ir shells and IrNi alloy cores. In situ XAS revealed that the Ir shells completely protect Ni atoms in the cores from oxidation or dissolution in an acid electrolyte under elevated potentials. The formation of Ir shell during annealing due to thermal segregation is monitored by time-resolved synchrotron XRD measurements, coupled with Rietveld refinement analyses. The H{sub 2} oxidation activity of the IrNi nanoparticles was found to be higher than that of a commercial Pt/C catalyst. This is predominantly due to Ni-core-induced Ir shell contraction that makes the surface less reactive for IrOH formation, and the resulting more metallic Ir surface becomes more active for H{sub 2} oxidation. This new class of core-shell nanoparticles appears promising for application as hydrogen anode fuel cell electrocatalysts.

K Sasaki; K Kuttiyiel; L Barrio; D Su; A Frenkel; N Marinkovic; D Mahajan; R Adzic

2011-12-31T23:59:59.000Z

44

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

45

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.,

46

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

47

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

48

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

49

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

50

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

51

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

52

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

53

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...

54

SECA Core Program - Recent Development of Modeling Activities at PNNL  

DOE Green Energy (OSTI)

This presentation discusses recent modeling activities at the Pacific Northwest National Laboratory.

Khaleel, M.A.; Recknagle, K.P.; Koeppel, B.; Vetrano, J.; Sun, X.; Korolev, V.; Johnson, K.I.; Nguygen, N.; Rector, D.; Singh, P.

2005-01-27T23:59:59.000Z

55

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

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

New LLNL research shows the moon's core was active later than...  

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

013moon 05102013 New LLNL research shows the moon's core was active later than original estimates Anne M Stark, LLNL, (925) 422-9799, stark8@llnl.gov Printer-friendly East limb...

59

Core-Level Activity Prediction for Multi-Core Power Management  

E-Print Network (OSTI)

/idle patterns. Transitions to active or idle states and the resultant power level can be predicted by tracking in order to weigh the power and performance cost of transitioning to low power states or changing the DVFS, performance may be less than optimal. Similarly, power consumption is sub-optimal on transitions from high

John, Lizy Kurian

60

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

SciTech Connect

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

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

1980-08-01T23:59:59.000Z

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


61

Core Analysis 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

62

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

63

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

64

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

65

The true role of active communicators: an empirical study of Jazz core developers  

Science Conference Proceedings (OSTI)

Context: Interest in software engineering (SE) methodologies and tools has been complemented in recent years by research efforts oriented towards understanding the human processes involved in software development. This shift has been imperative ... Keywords: Jazz, behaviors, content analysis, core developers, psycholinguistics, roles, software development

Sherlock A. Licorish; Stephen G. MacDonell

2013-04-01T23:59:59.000Z

66

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

67

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

68

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

69

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

70

Can a Long Nanoflare Storm Explain the Observed Emission Measure Distributions in Active Region Cores?  

E-Print Network (OSTI)

All theories that attempt to explain the heating of the high temperature plasma observed in the solar corona are based on short bursts of energy. The intensities and velocities measured in the cores of quiescent active regions, however, can be steady over many hours of observation. One heating scenario that has been proposed to reconcile such observations with impulsive heating models is the "long nanoflare storm," where short duration heating events occur infrequently on many sub-resolutions strands; the emission of the strands is then averaged together to explain the observed steady structures. In this Letter, we examine the emission measure distribution predicted for such a long nanoflare storm by modeling an arcade of strands in an active region core. Comparisons of the computed emission measure distributions with recent observations indicate that that the long nanoflare storm scenario implies greater than 5 times more 1 MK emission than is actually observed for all plausible combinations of loop lengths,...

Mulu-Moore, Fana M; Warren, Harry P

2012-01-01T23:59:59.000Z

71

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

72

Risk Analysis & Security Rule Compliance Activities  

Science Conference Proceedings (OSTI)

... Risk Analysis & Security Rule Compliance Activities Marissa Gordon- Nguyen, JD, MPH Health Information Privacy Specialist ...

2010-05-13T23:59:59.000Z

73

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

74

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

75

CAN A LONG NANOFLARE STORM EXPLAIN THE OBSERVED EMISSION MEASURE DISTRIBUTIONS IN ACTIVE REGION CORES?  

Science Conference Proceedings (OSTI)

All theories that attempt to explain the heating of the high-temperature plasma observed in the solar corona are based on short bursts of energy. The intensities and velocities measured in the cores of quiescent active regions, however, can be steady over many hours of observation. One heating scenario that has been proposed to reconcile such observations with impulsive heating models is the 'long nanoflare storm', where short-duration heating events occur infrequently on many sub-resolution strands; the emission of the strands is then averaged together to explain the observed steady structures. In this Letter, we examine the emission measure distribution predicted for such a long nanoflare storm by modeling an arcade of strands in an active region core. Comparisons of the computed emission measure distributions with recent observations indicate that the long nanoflare storm scenario implies greater than five times more 1 MK emission than is actually observed for all plausible combinations of loop lengths, heating rates, and abundances. We conjecture that if the plasma had 'super coronal' abundances, the model may be able to match the observations at low temperatures.

Mulu-Moore, Fana M.; Winebarger, Amy R. [NASA Marshall Space Flight Center, VP 62, Huntsville, AL 35812 (United States); Warren, Harry P., E-mail: fanamariam.mulumoore@nasa.gov [Space Science Division, Naval Research Laboratory, Washington, DC 20375 (United States)

2011-11-20T23:59:59.000Z

76

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

SciTech Connect

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

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

2013-03-10T23:59:59.000Z

77

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

78

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

79

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

80

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

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


81

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

82

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

83

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; Ponçot, Angélique

2011-01-01T23:59:59.000Z

84

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

DOE Green Energy (OSTI)

We present a combined experimental and theoretical approach to demonstrate how lattice strain can be used to continuously tune the catalytic activity of the oxygen reduction reaction (ORR) on bimetallic nanoparticles that have been dealloyed. The sluggish kinetics of the ORR is a key barrier to the adaptation of fuel cells and currently limits their widespread use. Dealloyed Pt-Cu bimetallic nanoparticles, however, have been shown to exhibit uniquely high reactivity for this reaction. We first present evidence for the formation of a core-shell structure during dealloying, which involves removal of Cu from the surface and subsurface of the precursor nanoparticles. We then show that the resulting Pt-rich surface shell exhibits compressive strain that depends on the composition of the precursor alloy. We next demonstrate the existence of a downward shift of the Pt d-band, resulting in weakening of the bond strength of intermediate oxygenated species due to strain. Finally, we combine synthesis, strain, and catalytic reactivity in an experimental/theoretical reactivity-strain relationship which provides guidelines for the rational design of strained oxygen reduction electrocatalysts. The stoichiometry of the precursor, together with the dealloying conditions, provides experimental control over the resulting surface strain and thereby allows continuous tuning of the surface electrocatalytic reactivity - a concept that can be generalized to other catalytic reactions.

Strasser, Peter

2011-08-19T23:59:59.000Z

85

Transportation activity analysis using smartphones  

E-Print Network (OSTI)

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

Xiao, Yu

86

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

87

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; Angélique Ponçot

2011-08-30T23:59:59.000Z

88

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

89

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

90

Highly Active Pt(3)Pb and Core-Shell Pt(3)Pb-Pt Electrocatalysts for Formic Acid Oxidation  

DOE Green Energy (OSTI)

Formic acid is a promising chemical fuel for fuel cell applications. However, due to the dominance of the indirect reaction pathway and strong poisoning effects, the development of direct formic acid fuel cells has been impeded by the low activity of existing electrocatalysts at desirable operating voltage. We report the first synthesis of Pt{sub 3}Pb nanocrystals through solution phase synthesis and show they are highly efficient formic acid oxidation electrocatalysts. The activity can be further improved by manipulating the Pt{sub 3}Pb-Pt core-shell structure. Combined experimental and theoretical studies suggest that the high activity from Pt{sub 3}Pb and the Pt-Pb core-shell nanocrystals results from the elimination of CO poisoning and decreased barriers for the dehydrogenation steps. Therefore, the Pt{sub 3}Pb and Pt-Pb core-shell nanocrystals can improve the performance of direct formic acid fuel cells at desired operating voltage to enable their practical application.

Kang Y.; Stach E.; Qi L.; Li M.; Diaz R.E.; Su D.; Adzic R.R.; Li J.; Murray C.B.

2012-03-27T23:59:59.000Z

91

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

92

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

93

Recent Advances in Pt Monolayer Electrocatalysts for Oxygen Reduction Reaction: Scale-up Synthesis, Structure, and Activity of Pt Shells on Pd Cores  

Science Conference Proceedings (OSTI)

We have established a scale-up synthesis method to produce gram-quantities of Pt monolayer electrocatalysts. The core-shell structure of the Pt/Pd/C electrocatalyst has been verified using the HAADF-STEM Z-contrast images, STEM/EELS, and STEM/EDS line profile analysis. The atomic structure of this electrocatalyst and formation of a Pt monolayer on Pd nanoparticle surfaces were examined using in situ EXAFS. The Pt mass activity of the Pt/Pd/C electrocatalyst for ORR is considerably higher than that of commercial Pt/C electrocatalysts. The results with Pt monolayer electrocatalysts may significantly impact science of electrocatalysis and fuel-cell technology, as they have demonstrated an exceptionally effective way of using Pt that can resolve problems of other approaches, including electrocatalysts inadequate activity and high Pt content.

Sasaki, K. [Brookhaven National Laboratory (BNL); Wang, J.X. [Brookhaven National Laboratory (BNL); Naohara, H. [Toyota Motor Corp.; Marinkovic, N. [University of Delaware; More, Karren Leslie [ORNL; Inada, H. [Hitachi High Technologies America; Adzic, R.R. [Brookhaven National Laboratory (BNL)

2010-01-01T23:59:59.000Z

94

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

95

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

96

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

97

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

98

Analysis Activities at Argonne National Laboratory  

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

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

99

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

100

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

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


101

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

102

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

103

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

104

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

105

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

106

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

107

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

108

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

109

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

110

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

111

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

112

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

Science Conference Proceedings (OSTI)

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

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

2012-10-10T23:59:59.000Z

113

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

114

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

115

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

116

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

117

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

118

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

119

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

120

CHARACTERISTICS AND EVOLUTION OF THE MAGNETIC FIELD AND CHROMOSPHERIC EMISSION IN AN ACTIVE REGION CORE OBSERVED BY HINODE  

Science Conference Proceedings (OSTI)

We describe the characteristics and evolution of the magnetic field and chromospheric emission in an active region core observed by the Solar Optical Telescope (SOT) on Hinode. Consistent with previous studies, we find that the moss is unipolar, the spatial distribution of magnetic flux evolves slowly, and that the magnetic field is only moderately inclined. We also show that the field-line inclination and horizontal component are coherent, and that the magnetic field is mostly sheared in the inter-moss regions where the highest magnetic flux variability is seen. Using extrapolations from spectropolarimeter magnetograms, we show that the magnetic connectivity in the moss is different from that in the quiet Sun because most of the magnetic field extends to significant coronal heights. The magnetic flux, field vector, and chromospheric emission in the moss also appear highly dynamic but actually show only small-scale variations in magnitude on timescales longer than the cooling times for hydrodynamic loops computed from our extrapolations, suggesting high-frequency (continuous) heating events. Some evidence is found for flux (Ca II intensity) changes on the order of 100-200 G (DN) on timescales of 20-30 minutes that could be taken as indicative of low-frequency heating. We find, however, that only a small fraction (10%) of our simulated loops would be expected to cool on these timescales, and we do not find clear evidence that the flux changes consistently produce intensity changes in the chromosphere. Using observations from the EUV Imaging Spectrometer (EIS), we also determine that the filling factor in the moss is {approx}16%, consistent with previous studies and larger than the size of an SOT pixel. The magnetic flux and chromospheric intensity in most individual SOT pixels in the moss vary by less than {approx}20% and {approx}10%, respectively, on loop cooling timescales. In view of the high energy requirements of the chromosphere, we suggest that these variations could be sufficient for the heating of 'warm' EUV loops, but that the high basal levels may be more important for powering the hot core loops rooted in the moss. The magnetic field and chromospheric emission appear to evolve gradually on spatial scales comparable to the cross-field scale of the fundamental coronal structures inferred from EIS measurements.

Brooks, David H.; Warren, Harry P. [Space Science Division, Code 7673, Naval Research Laboratory, Washington, DC 20375 (United States); Winebarger, Amy R., E-mail: dhbrooks@ssd5.nrl.navy.mi [Department of Physics, Alabama A and M, 4900 Meridian Street, Normal, AL 35762 (United States)

2010-09-10T23:59:59.000Z

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


121

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

122

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

123

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.

124

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.

125

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

126

Use of high performance computing in neutronics analysis activities  

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

high performance computing in neutronics analysis activities M.A. Smith Argonne National Laboratory 9700 South Cass Avenue, Argonne Illinois 60439, USA Abstract Reactor design is...

127

Analysis Activities at National Renewable Energy Laboratory  

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

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

128

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

129

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

130

Analysis Activities at Pacific Northwest National Laboratory  

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

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

131

Analysis Activities at Lawrence Livermore National Laboratory  

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

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

132

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

SciTech Connect

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

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

1987-04-01T23:59:59.000Z

133

Analysis Activities at Oak Ridge National Laboratory  

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

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

134

Severe Degradation of BWR Fuel Failures: Coolant Activity Analysis  

Science Conference Proceedings (OSTI)

Analysis of coolant activities offers considerable insight into the phenomena leading to the degradation of failed BWR fuel. This report provides operational guidelines to help utilities manage failed fuel and mitigate the impact of degradation.

1993-12-01T23:59:59.000Z

135

Passive versus active mitigation cost analysis  

DOE Green Energy (OSTI)

The scope of this task is to assess the impact of mitigation alternatives for Tanks 241-SY-101 and 241-SY-103 on the Project W-236A Multi-Function Waste Tank Facility. This assessment and other related tasks are part of an Action Plan Path Forward prepared by the Tank Waste Remediation System (TWRS) Life Extension and Transition Program. Task 3.7 of the Action Plan for Project W-236A MWTF analyzed the comparative cost/risk of two hydrogen gas mitigation alternatives (active versus passive) to recommend the most appropriate course of action to resolve the hydrogen gas safety issue. The qualitative success of active mitigation has been demonstrated through Tank 241-SY-101 testing. Passive mitigation has not been demonstrated but will be validated by laboratory test work performed under Task 3.1 of the Action Plan. It is assumed for this assessment that the uncertainties associated with the performance of either alternative is comparable. Determining alternative specific performance measures beyond those noted are not in the scope of this effort.

Parazin, R.J.; Galbraith, J.D.

1995-04-01T23:59:59.000Z

136

Activity analysis based on low sample rate smart meters  

Science Conference Proceedings (OSTI)

Activity analysis disaggregates utility consumption from smart meters into specific usage that associates with human activities. It can not only help residents better manage their consumption for sustainable lifestyle, but also allow utility managers ... Keywords: classification, disaggregation, gaussian mixture model, hidden markov model, low sample rate, smart meter

Feng Chen; Jing Dai; Bingsheng Wang; Sambit Sahu; Milind Naphade; Chang-Tien Lu

2011-08-01T23:59:59.000Z

137

Neutron activation analysis applied to energy and environment  

SciTech Connect

Neutron activation analysis was applied to a number of problems concerned with energy production and the environment. Burning of fossil fuel, the search for new sources of uranium, possible presence of toxic elements in food and water, and the relationship of trace elements to cardiovascular disease are some of the problems in which neutron activation was used. (auth)

Lyon, W.S.

1975-01-01T23:59:59.000Z

138

Instrumental neutron activation analysis (INAA) characterization of pre-contact basalt quarries on the American Samoan Island of Tutuila  

E-Print Network (OSTI)

This thesis presents a material-centered characterization of 120 geologic samples from four fine-grained basalt quarries on the Samoan Island of Tutuila. Previous unsuccessful attempts at definitive Tutuilan quarry differentiation have utilized x-ray fluorescence (XRF). In this study, clear differentiation of each analyzed quarry was achieved using instrumental neutron activation analysis (INAA). Biplots of canonical discriminant function scores for the INAA data illustrate clear separation based on the variation in chemical composition between each quarry. The samples analyzed not only define quarry separation, but also provide the "core group" for a preliminary baseline necessary for future artifact-centered provenance studies. Inclusion of these "core group" samples in the baseline was confirmed by stepwise discriminant analysis. These findings suggest the ability to determine quarry of origin on the island of Tutuila, which can elucidate the importance of individual Tutuilan quarries in the export and exchange of fine-grained basalts.

Johnson, Phillip Ray, II

2005-12-01T23:59:59.000Z

139

Activated Corrosion Product Analysis. Analytical Approach.  

SciTech Connect

The presence of activated corrosion products (ACPs) in a water cooling system is a key factor in the licensing of ITER and affects nuclear classification, which governs design and operation. The objective of this study is to develop a method to accurately estimate radionuclide concentrations during ITER operation in support of nuclear classification. A brief overview of the PACTITER numerical code, which is currently used for ACP estimation, is presented. An alternative analytical approach for calculation of ACPs, which can also be used for validation of existing numerical codes, including PACTITER, has been proposed. A continuity equation describing the kinetics of accumulation of radioactive isotopes in a water cooling system in the form of a closed ring has been formulated, taking into account the following processes: production of radioactive elements and their decay, filtration, and ACP accumulation in filter system. Additional work is needed to more accurately assess the ACP inventory in the cooling water system, including more accurate simulation of the Tokamak cooling water system (TCWS) operating cycle and consideration of material corrosion, release, and deposition rates.

Golubov, Stanislav I [ORNL; Busby, Jeremy T [ORNL; Stoller, Roger E [ORNL

2010-01-01T23:59:59.000Z

140

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

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


141

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

142

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

143

Prompt gamma activation analysis (PGAA) and short-lived neutron activation analysis (NAA) applied to the characterization of legacy materials  

SciTech Connect

Without quality historical records that provide the composition of legacy materials, the elemental and/or chemical characterization of such materials requires a manual analytical strategy that may expose the analyst to unknown toxicological hazards. In addition, much of the existing legacy inventory also incorporates radioactivity, and, although radiological composition may be determined by various nuclear-analytical methods, most importantly, gamma-spectroscopy, current methods of chemical characterization still require direct sample manipulation, thereby presenting special problems with broad implications for both the analyst and the environment. Alternately, prompt gamma activation analysis (PGAA) provides a'single-shot' in-situ, non-destructive method that provides a complete assay of all major entrained elemental constituents.1-3. Additionally, neutron activation analysis (NAA) using short-lived activation products complements PGAA and is especially useful when NAA activation surpasses the PGAA in elemental sensitivity.

Firestone, Richard B; English, G.A.; Firestone, R.B.; Perry, D.L.; Reijonen, J.P.; Leung, Ka-Ngo; Garabedian, G.F.; Molnar, G.L.; Revay, Zs.

2008-02-13T23:59:59.000Z

144

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

145

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

146

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

147

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

148

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

149

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.

150

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

151

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.

152

Active cooling for downhole instrumentation: Preliminary analysis and system selection  

DOE Green Energy (OSTI)

A feasibility study and a series of preliminary designs and analyses were done to identify candidate processes or cycles for use in active cooling systems for downhole electronic instruments. A matrix of energy types and their possible combinations was developed and the energy conversion process for each pari was identified. The feasibility study revealed conventional as well as unconventional processes and possible refrigerants and identified parameters needing further clarifications. A conceptual design or series od oesigns for each system was formulated and a preliminary analysis of each design was completed. The resulting coefficient of performance for each system was compared with the Carnot COP and all systems were ranked by decreasing COP. The system showing the best combination of COP, exchangeability to other operating conditions, failure mode, and system serviceability is chosen for use as a downhole refrigerator. 85 refs., 48 figs., 33 tabs.

Bennett, G.A.

1988-03-01T23:59:59.000Z

153

Testing the quasi-absolute method in photon activation analysis  

SciTech Connect

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

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

2013-04-19T23:59:59.000Z

154

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

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

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

155

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

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

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

156

Carbon Dioxide Information Analysis Center: FY 1991 activities  

SciTech Connect

During the course of a fiscal year, Oak Ridge National Laboratory`s Carbon Dioxide Information Analysis Center (CDIAC) distributes thousands of specially publications-numeric data packages (NDPs), computer model packages (CMPs), technical reports, public communication publications, newsletters, article reprints, and reference books-in response to requests for information related to global environmental issues, primarily those pertaining to climate change. CDIAC`s staff also provides technical responses to specific inquiries related to carbon dioxide (CO{sub 2}), other trace gases, and climate. Hundreds of referrals to other researchers, policy analysts, information specialists, or organizations are also facilitated by CDIAC`s staff. This report provides an account of the activities accomplished by CDIAC during the period October 1, 1990 to September 30, 1991. An organizational overview of CDIAC and its staff is supplemented by a detailed description of inquiries received and CDIAC`s response to those inquiries. An analysis and description of the preparation and distribution of numeric data packages, computer model packages, technical reports, newsletters, factsheets, specially publications, and reprints is provided. Comments and descriptions of CDIAC`s information management systems, professional networking, and special bilateral agreements are also described.

Cushman, R.M.; Stoss, F.W.

1992-06-01T23:59:59.000Z

157

Prompt gamma activation analysis facility at MITR-II  

SciTech Connect

A relatively simple and inexpensive prompt gamma neutron activation analysis facility has been constructed at the 5-MW MITR-II research reactor. The analytical beam is obtained by diffraction using a multilayer graphite monochromator placed in the white beam of one of the MITR-II beam tubes. Use of a diffracted beam, with its concomitant reduction in sample flux compared to the direct beam from the reactor moderator, was initially dictated by the need to construct rapidly and inexpensively an analytical facility that could analyze {sup 10}B at the level of a few micrograms per gram in biological samples. By relatively simple modifications to an existing two-axis neutron spectrometer, we were able to produce a useful intensity on the sample. Furthermore, the inherent advantage of reduced background when using a Bragg diffracted beam permitted the use of short sample-to-detector distances, which compensated for the loss in slow neutron intensity in the diffraction process. The resultant facility has exceeded our initial minimum requirements for {sup 10}B analysis. In fact, the current facility provides significantly higher full-energy peak count rates than those reported for direct thermal beam facilities at reactors with twice the power of MITR-II.

Harling, O.K. [Massachusetts Institute of Technology, Cambridge, MA (United States)

1994-12-31T23:59:59.000Z

158

Carbon Dioxide Information Analysis Center: FY 1992 activities  

SciTech Connect

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

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

1993-03-01T23:59:59.000Z

159

Carbon Dioxide Information Analysis Center: FY 1991 activities  

SciTech Connect

During the course of a fiscal year, Oak Ridge National Laboratory's Carbon Dioxide Information Analysis Center (CDIAC) distributes thousands of specially publications-numeric data packages (NDPs), computer model packages (CMPs), technical reports, public communication publications, newsletters, article reprints, and reference books-in response to requests for information related to global environmental issues, primarily those pertaining to climate change. CDIAC's staff also provides technical responses to specific inquiries related to carbon dioxide (CO{sub 2}), other trace gases, and climate. Hundreds of referrals to other researchers, policy analysts, information specialists, or organizations are also facilitated by CDIAC's staff. This report provides an account of the activities accomplished by CDIAC during the period October 1, 1990 to September 30, 1991. An organizational overview of CDIAC and its staff is supplemented by a detailed description of inquiries received and CDIAC's response to those inquiries. An analysis and description of the preparation and distribution of numeric data packages, computer model packages, technical reports, newsletters, factsheets, specially publications, and reprints is provided. Comments and descriptions of CDIAC's information management systems, professional networking, and special bilateral agreements are also described.

Cushman, R.M.; Stoss, F.W.

1992-06-01T23:59:59.000Z

160

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 "activity core analysis" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

HINODE/EIS SPECTROSCOPIC VALIDATION OF VERY HOT PLASMA IMAGED WITH THE SOLAR DYNAMICS OBSERVATORY IN NON-FLARING ACTIVE REGION CORES  

Science Conference Proceedings (OSTI)

We use coronal imaging observations with the Solar Dynamics Observatory/Atmospheric Imaging Assembly (AIA), and Hinode/Extreme-ultraviolet Imaging Spectrometer (EIS) spectral data to explore the potential of narrowband EUV imaging data for diagnosing the presence of hot (T {approx}> 5 MK) coronal plasma in active regions. We analyze observations of two active regions (AR 11281, AR 11289) with simultaneous AIA imaging and EIS spectral data, including the Ca XVII line (at 192.8 A), which is one of the few lines in the EIS spectral bands sensitive to hot coronal plasma even outside flares. After careful co-alignment of the imaging and spectral data, we compare the morphology in a three-color image combining the 171, 335, and 94 A AIA spectral bands, with the image obtained for Ca XVII emission from the analysis of EIS spectra. We find that in the selected active regions the Ca XVII emission is strong only in very limited areas, showing striking similarities with the features bright in the 94 A (and 335 A) AIA channels and weak in the 171 A band. We conclude that AIA imaging observations of the solar corona can be used to track hot plasma (6-8 MK), and so to study its spatial variability and temporal evolution at high spatial and temporal resolution.

Testa, Paola [Smithsonian Astrophysical Observatory, 60 Garden street, MS 58, Cambridge, MA 02138 (United States); Reale, Fabio, E-mail: ptesta@cfa.harvard.edu [Dipartimento di Fisica, Universita di Palermo, Piazza del Parlamento 1, 90134 Palermo (Italy)

2012-05-01T23:59:59.000Z

162

Stability of Molten Core Materials  

SciTech Connect

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

Layne Pincock; Wendell Hintze

2013-01-01T23:59:59.000Z

163

Analysis of unknown materials with prompt gamma-ray activation analysis (PGAA)  

Science Conference Proceedings (OSTI)

To assay the degradation of high explosives (HE) by a material-loss mechanism, prompt gamma activation analysis (PGAA), using a miniature neutron accelerator developed at Lawrence Berkeley National Laboratory (LBNL) is proposed. Whereas the PGAA signatures from carbon and nitrogen in the chemical matrices are relatively low, fast neutrons may be used due to the higher cross sections for interaction. By using the upgraded PGAA database developed by the Isotope Projects Group at LBNL in collaboration with new PGAA data obtained at the Institute of Isotope and Surface Chemistry in Budapest, Hungary, it should be possible to observe and potentially to quantify a macroscopic loss of mass in HE.

English, Gerald; Firestone, Richard

2002-09-17T23:59:59.000Z

164

Analysis of Fuel Ethanol Transportation Activity and Potential Distribution Constraints  

SciTech Connect

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

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

2010-01-01T23:59:59.000Z

165

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)

166

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 Glänzel; Bart Thijs

2011-07-01T23:59:59.000Z

167

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

168

Graph of words embedding for molecular structure-activity relationship analysis  

Science Conference Proceedings (OSTI)

Structure-Activity relationship analysis aims at discovering chemical activity of molecular compounds based on their structure. In this article we make use of a particular graph representation of molecules and propose a new graph embedding procedure ...

Jaume Gibert; Ernest Valveny; Horst Bunke

2010-11-01T23:59:59.000Z

169

A Tracer Study with Oxygen-18 in Photosynthesis by Activation Analysis  

E-Print Network (OSTI)

r e e n algae. t e r m photosynthesis products containing 0WITH OXYGEN - I8 IN PHOTOSYNTHESIS BY ACTIVATION ANALYSISWITH OXYGEN-18 IN PHOTOSYNTHESIS BY ACTIVATION ANALYSIS I n

Fogelstrom-Fineman, Ingrid; Holm-Hansen, Osmund; Tolbert, Bert M.; Calvin, Melvin

1957-01-01T23:59:59.000Z

170

Empirical Tracking and Analysis of the Dynamics in Activity Scheduling and Schedule Execution  

E-Print Network (OSTI)

R. G. (2004) Real-time Tracking of Activity Scheduling/GIS) viii ABSTRACT Empirical Tracking and Analysis of theSanta Barbara Empirical Tracking and Analysis of the

Zhou, Jianyu Jack

2006-01-01T23:59:59.000Z

171

Over Core Stress At Gabbs Valley Area (DOE GTP) | Open Energy...  

Open Energy Info (EERE)

Over Core Stress At Gabbs Valley Area (DOE GTP) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Over Core Stress At Gabbs Valley Area (DOE GTP)...

172

Spectroscopical Analysis of Mechano-chemically Activated Surfaces  

E-Print Network (OSTI)

Mechano-chemical activation is fundamentally different than chemical activation in that energy is added to alter the state of bond energy instead of exciting electrons to produce a chemical reaction. Mechano-chemical activation has demonstrated to alter the chemical reaction and rates. There remains no development of a model to quantify the changes in reactions due to mechano-chemical activation. This research aims in expanding our understanding of the influence of mechanochemical activation methods. The dynamics and kinetics of mechano-chemically activated surfaces will be studied using x-ray spectroscopy methods. Mechano-chemical interactions can be quantified through the study of electron energies. X-ray spectroscopy is a useful method of analyzing and quantifying electron energy states. X-ray absorbance is used to study the valence state electron shells of iron undergone activation through sliding friction of naturally produced wax. In-situ x-ray photoemission spectroscopy is employed to instantaneously characterize single crystal tantalum samples of each principal crystallographic orientation during oxidation. Sliding friction of the naturally produced wax resulted in a reduction in the binding energy of the iron 2p electrons by approximately one electron-volt. This reduction in binding energy is attributed to ferrocene which is an organo-metallic alloy, Fe(C5H5)2. Mechanical strain of the crystal lattices of tantalum resulted in altered activation energies. Activation energy increased with the application of lattice strain. At increasing strain, oxide properties become more dependent on the lattice strain than the crystal orientation and temperature. A model system is developed incorporating mechanical strain into the prediction of activation energy and rates.

Cooper, Rodrigo

2011-08-01T23:59:59.000Z

173

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

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

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

174

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

Open Energy Info (EERE)

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

175

Comparison of Impurities in Charcoal Sorbents Found by Neutron Activation Analysis  

Science Conference Proceedings (OSTI)

Abstract: Neutron activation of gas samples in a reactor often requires a medium to retain sufficient amounts of the gas for analysis. Charcoal is commonly used to adsorb gas and hold it for activation; however, the amount of activated sodium in the charcoal after irradiation swamps most signals of interest. Neutron activation analysis (NAA) was performed on several commonly available charcoal samples in an effort to determine the activation background. The results for several elements, including the dominant sodium element, are reported. It was found that ECN charcoal had the lowest elemental background, containing sodium at 2.65 ± 0.05 ppm, as well as trace levels of copper and tungsten.

Doll, Charles G.; Finn, Erin C.; Cantaloub, Michael G.; Greenwood, Lawrence R.; Kephart, Jeremy; Kephart, Rosara F.

2013-01-01T23:59:59.000Z

176

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

177

Analysis Activities at Idaho National Engineering & Environmental Laboratory  

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

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

178

Oxygen Reduction Reaction on Dispersed and Core-Shell Metal Alloy Catalysts: Density Functional Theory Studies  

E-Print Network (OSTI)

Pt-based alloy surfaces are used to catalyze the electrochemical oxygen reduction reaction (ORR), where molecular oxygen is converted into water on fuel cell electrodes. In this work, we address challenges due to the cost of high Pt loadings in the cathode electrocatalyst, as well as those arising from catalyst durability. We aim to develop an increased understanding of the factors that determine ORR activity together with stability against surface segregation and dissolution of Pt-based alloys. We firstly focus on the problem of determining surface atomic distribution resulting from surface segregation phenomena. We use first-principles density functional theory (DFT) calculations on PtCo and Pt3Co overall compositions, as well as adsorption of water and atomic oxygen on PtCo(111) and Pt-skin structures. The bonding between water and surfaces of PtCo and Pt-skin monolayers are investigated in terms of orbital population. Also, on both surfaces, the surface reconstruction effect due to high oxygen coverage and water co-adsorption is investigated. Although the PtCo structures show good activity, a large dissolution of Co atoms tends to occur in acid medium. To tackle this problem, we examine core-shell structures which showed improved stability and activity compared to Pt(111), in particular, one consisting of a surface Pt-skin monolayer over an IrCo or Ir3Co core, with or without a Pd interlayer between the Pt surface and the Ir-Co core. DFT analysis of surface segregation, surface stability against dissolution, surface Pourbaix diagrams, and reaction mechanisms provide useful predictions on catalyst durability, onset potential for water oxidation, surface atomic distribution, coverage of oxygenated species, and activity. The roles of the Pd interlayer in the core-shell structures that influence higher ORR activity are clarified. Furthermore, the stability and activity enhancement of new shell-anchor-core structures of Pt/Fe-C/core, Pt/Co-C/core and Pt/Ni-C/core are demonstrated with core materials of Ir, Pd3Co, Ir3Co, IrCo and IrNi. Based on the analysis, Pt/Fe-C/Ir, Pt/Co-C/Ir, Pt/Ni-C/Ir, Pt/Co-C/Pd3Co, Pt/Fe-C/Pd3Co, Pt/Co- C/Ir3Co, Pt/Fe-C/Ir3Co, Pt/Co-C/IrCo, Pt/Co-C/IrNi, and Pt/Fe-C/IrNi structures show promise in terms of both improved durability and relatively high ORR activity.

Hirunsit, Pussana

2010-08-01T23:59:59.000Z

179

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 Glänzel; Bart Thijs

2012-05-01T23:59:59.000Z

180

Core Holes At Hot Sulphur Springs Area (Goranson, 2005) | Open...  

Open Energy Info (EERE)

Springs Area (Goranson, 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Core Holes At Hot Sulphur Springs Area (Goranson, 2005)...

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


181

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

182

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

183

Systems simulation and economic analysis for active solar cooling  

DOE Green Energy (OSTI)

A consistent methodology has been developed by which general solar cooling market capture goals have been translated into specific cost and performance goals for solar cooling systems and subsystems. Preliminary results indicate that realistic cost/performance goals can be established for active solar cooling systems and that, with aggressive development, these goals can be reached by the year 2000. As the technology develops, tax incentives will be required to bridge the gap between the actual costs and the cost goals, so that the scenario of an ever increasing share of market penetration can be maintained over the 1986 to 2000 time period.

Warren, M.; Wahlig, M.

1981-07-01T23:59:59.000Z

184

Transmittal of Immobilized Low Activity Waste (ILAW) Disposal Preliminary RAM Analysis Report (formerly PLG-1412)  

Science Conference Proceedings (OSTI)

This report presents the results of the preliminary reliability, availability, and maintainability analysis of operations at the ILAW Disposal Facility, Project W-520, to be performed during Phase I activities in support of the WTP

CALMUS, R.B.

2002-12-04T23:59:59.000Z

185

Management Assessment Quality Assurance Guidance in support of EM environmental sampling and analysis activities  

SciTech Connect

This document is one of several guidance documents developed by DOE EM pertaining to environmental restoration and waste management sampling and analysis activities. This guidance contains performance objectives and representative assessment criteria that can be used to conduct management assessments.

1994-05-01T23:59:59.000Z

186

Systems Studies Department FY 78 activity report. Volume 2. Systems analysis. [Sandia Laboratories, Livermore  

DOE Green Energy (OSTI)

The Systems Studies Department at Sandia Laboratories Livermore (SLL) has two primary responsibilities: to provide computational and mathematical services and to perform systems analysis studies. This document (Volume 2) describes the FY Systems Analysis highlights. The description is an unclassified overview of activities and is not complete or exhaustive. The objective of the systems analysis activities is to evaluate the relative value of alternative concepts and systems. SLL systems analysis activities reflect Sandia Laboratory programs and in 1978 consisted of study efforts in three areas: national security: evaluations of strategic, theater, and navy nuclear weapons issues; energy technology: particularly in support of Sandia's solar thermal programs; and nuclear fuel cycle physical security: a special project conducted for the Nuclear Regulatory Commission. Highlights of these activities are described in the following sections. 7 figures. (RWR)

Gold, T.S.

1979-02-01T23:59:59.000Z

187

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

188

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

189

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

190

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

191

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

192

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

193

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

194

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

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

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

195

The relevance of particle flux monitors in accelerator-based activation analysis  

SciTech Connect

One of the most critical parameters in activation analysis is the flux density of the activating radiation, its spatial distribution in particular. The validity of the basic equation for calculating the activity induced to the exposed item depends upon the fulfilment of several conditions, the most relevant of them being equal doses of incident activating radiation received by the unknown sample, the calibration material and the reference material, respectively. This requirement is most problematic if accelerator-produced radiation is used for activation. Whilst nuclear research reactors usually are equipped with exposure positions that provide fairly homogenous activation fields for thermal neutron activation analysis accelerator-generated particle beams (neutrons, photons, charged particles) usually exhibit axial and, in particular, sharp radial flux gradients. Different experimental procedures have been developed to fulfil the condition mentioned above. In this paper, three variants of the application of flux monitors in photon activation analysis are discussed (external monitor, additive and inherent internal monitor). Experiments have indicated that the latter technique yields highest quality of the analytical results.

Segebade, Chr.; Maimaitimin, M.; Sun Zaijing [Idaho Accelerator Centre, Idaho State University, 1500 Alvin Ricken Drive, Pocatello, ID 83201 (United States)

2013-04-19T23:59:59.000Z

196

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

197

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

198

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.

199

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,

200

Europium-152 depth profile of a stone bridge pillar exposed to the Hiroshima atomic bomb: /sup 152/Eu activities for analysis of the neutron spectrum  

Science Conference Proceedings (OSTI)

The /sup 152/Eu activity depth profile of a granite pillar of the Motoyasu bridge located 132 m from the Hiroshima atomic bomb hypocenter was assessed. The pillars each measured 82 cm in depth, 82 cm in width and 193 cm in height. One of the pillars was bored and 6.8-cm-diameter core samples were removed and cut into 2-cm-thick disks. Two gamma rays of /sup 152/Eu, 122 keV and 344 keV, in each disk were measured using a low background, gamma-ray spectrometer, and the activity distribution was determined as a function of depth in the granite. A concentration of stable Eu in the granite was determined by activation analysis. The specific radioactivity of /sup 152/Eu and /sup 154/Eu at the pillar surface was determined to have been 117 and 24 Bq per mg Eu, respectively, at the time of detonation. The value of /sup 152/Eu agrees within 20% of that calculated by Loewe. The depth profile of /sup 152/Eu in granite demonstrates a distinct difference from the estimates made only by thermal neutrons. Present data provide valuable information for the analysis of the neutron spectrum of the Hiroshima atomic bomb and its intensity.

Hasai, H.; Iwatani, K.; Shizuma, K.; Hoshi, M.; Yokoro, K.; Sawada, S.; Kosako, T.; Morishima, H.

1987-09-01T23:59:59.000Z

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


201

Sampling and analysis plan for RCRA closure activities at 218-E-8 Borrow Pit Demolition Site  

Science Conference Proceedings (OSTI)

Purpose of this document is to provide guidance for sampling and analysis activities associated with the proposed Resource Conservation and Recovery Act of 1976 (RCRA) clean closure of the 218-E-8 West Ash Pit Demolition Site. The borrow pit was used for demolition of discarded explosive chemicals, asbestos disposal, tumbleweed incineration, and storage of hazardous waste. Soil samples will be taken from around the blasting pit, to verify that the concentrations of all detonation activity contaminants are below action levels.

Lucas, J.G.

1994-06-02T23:59:59.000Z

202

Neutron activation analysis for reference determination of the implantation dose of cobalt ions  

Science Conference Proceedings (OSTI)

The authors prepared depth profilling reference materials by cobalt ion implantation at an ion energy of 300 keV into n-type silicon. The implanted Co dose was then determined by instrumental neutron activation analysis (INAA) giving an analytical dynamic range of almost 5 decades and uncertainty of 1.5%. This form of analysis allows sources of error (beam spreading, misalignment) to be corrected. 70 refs., 3 tabs.

Garten, R.P.H. [Max-Planck-Institut fuer Metallforschung, Dortmund (Germany); Bubert, H. [Institut fuer Spektrochemie und angewandte Spektrokopie, Dortmund (Germany); Palmetshofer, L. [Johannes-Kepler-Universitaet, Linz (Australia)

1992-05-15T23:59:59.000Z

203

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

204

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

205

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

206

Testing and forecasting the time series of the solar activity by singular spectrum analysis  

E-Print Network (OSTI)

To study and forecast the solar activity data a quite perspective method of singular spectrum analysis (SSA) is proposed. As known, data of the solar activity are usually presented via the Wolf numbers associated with the effective amount of the sunspots. The advantages and disadvantages of SSA are described by its application to the series of the Wolf numbers. It is shown that the SSA method provides a sufficiently high reliability in the description of the 11-year solar cycle. Moreover, this method is appropriate for revealing more long cycles and forecasting the further solar activity during one and a half of 11-year cycle.

A. Loskutov; I. A. Istomin; K. M. Kuzanyan; O. L. Kotlyarov

2000-10-13T23:59:59.000Z

207

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

208

A Synoptic Analysis of the Interannual Variability of Winter Cyclone Activity in the Aleutian Low Region  

Science Conference Proceedings (OSTI)

An analysis of cyclone activity in winter associated with years of strong and weak Aleutian low in the North Pacific is presented. From 1958 to 2004, 10 winters with a strong Aleutian low are defined as the strong years, while 8 winters with a ...

Xiaojie Zhu; Jilin Sun; Zhengyu Liu; Qinyu Liu; Jonathan E. Martin

2007-04-01T23:59:59.000Z

209

Xenon diffusion studies with prompt gamma activation analysis Carlos A. Rios Perez Justin D. Lowrey  

E-Print Network (OSTI)

rates of xenon and argon gases through a porous medium. The University of Texas at Austin maintains at thermal and sub-thermal neutron energies, prompt gamma activation analysis is a suitable technique is anticipated to be well suited for this purpose as the energy spectrum of every xenon isotope is unique

Deinert, Mark

210

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 ...

211

Stability analysis for the generalized Cohen-Grossberg neural networks with inverse Lipschitz neuron activations  

Science Conference Proceedings (OSTI)

In this paper, by using nonsmooth analysis approach, linear matrix inequality (LMI) technique, topological degree theory and Lyapunov-Krasovskii function method, the issue of global exponential stability is investigated for a class of generalized Cohen-Grossberg ... Keywords: Cohen-Grossberg neural networks, Global exponential stability, Inverse Lipschitz neuron activations, Linear matrix inequality, Nonsmooth behaved functions, Topological degree theory

Xiaobing Nie; Jinde Cao

2009-05-01T23:59:59.000Z

212

Nonlinear vibration analysis of actively loaded sandwich piezoelectric beams with geometric imperfections  

Science Conference Proceedings (OSTI)

Modal analysis is developed for linear and nonlinear vibrations of deformed sandwich piezoelectric beams with initial imperfections. The beam is subjected to axial displacement and active voltage generated by the top and the bottom piezoelectric layers. ... Keywords: Control, Nonlinear, Piezoelectric, Sandwich, Stability, Vibration

L. Azrar; S. Belouettar; J. Wauer

2008-12-01T23:59:59.000Z

213

Arsenic and antimony in laundry aids by instrumental neutron activation analysis  

SciTech Connect

>The measurement of trace amounts of arsenic and antimony in laundry aids by neutron activation analysis is described. The results for arsenic are compared with those obtained by other analytical techniques. The concentratlons ln the various laundry aids tested ranged from 5 to 51 ppM of arsenic and from 1 to 8 ppM of antimony. (auth)

Tanner, J.T.; Friedman, M.H.; Holloway, G.E.

1973-10-01T23:59:59.000Z

214

Mass burning rate of premixed stretched flames: integral analysis versus large activation energy asymptotics  

E-Print Network (OSTI)

Mass burning rate of premixed stretched flames: integral analysis versus large activation energy, The Netherlands Abstract. New expressions for the mass burning rate are derived from a recently introduced burning rate. The consequences for experimental and numerical studies are investigated. Keywords: premixed

Eindhoven, Technische Universiteit

215

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

216

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

217

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

218

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

219

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

220

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

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


221

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

222

Report on INL Activities for Uncertainty Reduction Analysis of FY12  

SciTech Connect

The work scope of this project related to the Work Packages of “Uncertainty Reduction Analyses” with the goal of reducing nuclear data uncertainties is to produce a set of improved nuclear data to be used both for a wide range of validated advanced fast reactor design calculations, and for providing guidelines for further improvements of the ENDF/B files (i.e. ENDF/B-VII, and future releases). Recent extensive sensitivity/uncertainty studies, performed within an international OECD-NEA initiative, have quantified for the first time the impact of current nuclear data uncertainties on design parameters of the major FCR&D and GEN-IV systems, and in particular on Na-cooled fast reactors with different fuels (oxide or metal), fuel composition (e.g. different Pu/TRU ratios) and different conversion ratios. These studies have pointed out that present uncertainties on the nuclear data should be significantly reduced, in order to get full benefit from the advanced modeling and simulation initiatives. Nuclear data plays a fundamental role in performance calculations of advanced reactor concepts. Uncertainties in the nuclear data propagate into uncertainties in calculated integral quantities, driving margins and costs in advanced system design, operation and safeguards. This package contributes to the resolution of technical, cost, safety, security and proliferation concerns in a multi-pronged, systematic, science-based R&D approach. The Nuclear Data effort identifies and develops small scale, phenomenon-specific experiments informed by theory and engineering to reduce the number of large, expensive integral experiments. The Nuclear Data activities are leveraged by effective collaborations between experiment and theory, between DOE programs and offices, at national laboratories and universities, both domestic and international. The primary objective is to develop reactor core sensitivity and uncertainty analyses that identify the improvement needs of key nuclear data which would facilitate fast spectrum system optimization and assure safety performance. The inclusion of fast spectrum integral experiment data is key to minimizing the impact of nuclear data uncertainties on reactor core performance calculations, thus providing the best nuclear data needs assessment. This report presents the status of activities performed at INL under the ARC Work Package previously mentioned. As major achievement this year a comprehensive adjustment, including 87 experiments, was carried out. The results of this adjustment provide useful insights and helpful feedback to both nuclear data evaluation and measurer communities. In the following, we will document first the theory that underlines the adjustment methodology, and then we will illustrate the sensitivity coefficient computation and the nuclear data and experiment selection. Subsequently, the adjustment results will be shown, and, finally, conclusions, including future work, will be provided.

G. Palmiotti; M. Salvatores

2012-09-01T23:59:59.000Z

223

Applying observations of work activity in designing prototype data analysis tools  

Science Conference Proceedings (OSTI)

Designers, implementers, and marketers of data analysis tools typically have different perspectives than users. Consequently, data analysis often find themselves using tools focused on graphics and programming concepts rather than concepts which reflect their own domain and the context of their work. Some user studies focus on usability tests late in development; others observe work activity, but fail to show how to apply that knowledge in design. This paper describes a methodology for applying observations of data analysis work activity in prototype tool design. The approach can be used both in designing improved data analysis tools, and customizing visualization environments to specific applications. We present an example of user-centered design for a prototype tool to cull large data sets. We revisit the typical graphical approach of animating a large data set from the point of view of an analysis who is culling data. Field evaluations using the prototype tool not only revealed valuable usability information, but initiated in-depth discussions about user`s work, tools, technology, and requirements.

Springmeyer, R.R.

1993-07-06T23:59:59.000Z

224

Sampling and analysis plan for RCRA closure activities at 200 West Ash Pit Demolition Site  

Science Conference Proceedings (OSTI)

This document provides guidance for sampling and analysis activities associated with the proposed Resource Conservation and Recovery Act of 1976 (RCRA) clean closure of the 200 West Ash Pit Demolition Site. Soil samples will be taken around the blasting pit, in order to verify that the concentrations of all detonation activity contaminants are below action levels. The borrow pit was used for demolition of discarded explosive chemicals, tumbleweed incineration, and as a source of soil for construction material. The demolition site was located apart from the others within the borrow pit.

Lucas, J.G.

1994-06-02T23:59:59.000Z

225

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

226

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

227

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

228

Second Research Coordination Meeting on Reference Database for Neutron Activation Analysis -- Summary Report  

SciTech Connect

The second meeting of the Co-ordinated Research Project on"Reference Database for Neutron Activation Analysis" was held at the IAEA, Vienna from 7-9 May, 2007. A summary of the presentations made by participants is given, along with reports on specifically assigned tasks and subsequent discussions. In order to meet the overall objectives of this CRP, the outputs have been reiterated and new task assignments made.

Firestone, Richard B.; Kellett, Mark A.

2008-03-19T23:59:59.000Z

229

Overestimation of physical activity level is associated with lower BMI: a cross-sectional analysis.  

E-Print Network (OSTI)

RESEARCH Open Access Overestimation of physical activity level is associated with lower BMI: a cross-sectional analysis Clare Watkinson1, Esther MF van Sluijs1, Stephen Sutton2, Wendy Hardeman2, Kirsten Corder1, Simon J Griffin1* Abstract Background... . 1996. 3. Craig R, Mindell J: Health Survey for England 2006: CVD and risk factors adults, obesity and risk factors children. The NHS Information Centre 2008. 4. Hillsdon M, Foster C, Cavill N, Crombie H, Naidoo B: The effectiveness of public health...

Watkinson, Clare; van Sluijs, Esther M F; Sutton, Stephen; Hardeman, Wendy; Corder, Kirsten; Griffin, Simon J

2010-09-20T23:59:59.000Z

230

Tank 241-AN-105, cores 152 and 153, analytical results for the 45 day report  

Science Conference Proceedings (OSTI)

This document is the 45-day laboratory report for tank 241-AN-105 push mode core segments collected between June 10, 1996 and June 28, 1996. The segments were subsampled and analyzed in accordance with the Tank 241-AN-105 Push Mode Core Sampling and analysis Plan (TSAP) and the Safety Screening Data Quality Objective (DQO). The analytical results are included in the data summary table. None of the samples submitted for Total Alpha Activity or Differential Scanning Calorimetry (DSC) analyses exceeded notification limits as stated in the Safety Screening DQO. Statistical evaluation on results by calculating the 95% upper confidence limit is not performed by the 222-S Laboratory and is not considered in this report. Primary safety screening results and the raw data from thermogravimetric analysis (TGA) and DSC analyses are included in this report.

Steen, F.H.

1996-09-20T23:59:59.000Z

231

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

Science Conference Proceedings (OSTI)

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

Steen, F.H.

1996-10-18T23:59:59.000Z

232

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

233

A laser-induced repetitive fast neutron source applied for gold activation analysis  

SciTech Connect

A laser-induced repetitively operated fast neutron source was developed for applications in laser-driven nuclear physics research. The developed neutron source, which has a neutron yield of approximately 4 Multiplication-Sign 10{sup 5} n/pulse and can be operated up to a pulse repetition rate of 10 Hz, was applied for a gold activation analysis. Relatively strong delayed gamma spectra of the activated gold were measured at 333 keV and 355 keV, and proved the possibility of the neutron source for activation analyses. In addition, the nuclear reactions responsible for the measured gamma spectra of gold were elucidated by the 14 MeV fast neutrons resulting from the D(t,n)He{sup 4} nuclear reaction, for which the required tritium originated from the primary fusion reaction, D(d,p)T{sup 3}.

Lee, Sungman; Park, Sangsoon; Lee, Kitae; Cha, Hyungki [Quantum Optics Division, Korea Atomic Energy Research Institute, Daejeon 305-600 (Korea, Republic of)

2012-12-15T23:59:59.000Z

234

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

SciTech Connect

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

ESCH, R.A.

1998-11-19T23:59:59.000Z

235

Geographically-Based Infrastructure Analysis  

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

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

236

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...

237

ANALYSIS ON CORRELATIONS BETWEEN SUBSURFACE KINETIC HELICITY AND PHOTOSPHERIC CURRENT HELICITY IN ACTIVE REGIONS  

Science Conference Proceedings (OSTI)

An investigation on correlations between photospheric current helicity and subsurface kinetic helicity is carried out by analyzing vector magnetograms and subsurface velocities for two rapidly developing active regions. The vector magnetograms are from the Solar Dynamics Observatory/Helioseismic and Magnetic Imager (SDO/HMI) observed Stokes parameters, and the subsurface velocity is from time-distance data-analysis pipeline using HMI Dopplergrams. Over a span of several days, the evolution of the weighted current helicity shows a tendency similar to that of the weighted subsurface kinetic helicity, attaining a correlation coefficient above 0.60 for both active regions. Additionally, there seems to be a phase lag between the evolutions of the unweighted current and subsurface kinetic helicities for one of the active regions. The good correlation between these two helicities indicates that there is some intrinsic connection between the interior dynamics and photospheric magnetic twistedness inside active regions, which may help to interpret the well-known hemispheric preponderance of current-helicity distribution.

Gao Yu; Zhang Hongqi [Key Laboratory of Solar Activity, National Astronomical Observatories of China, Chinese Academy of Sciences, Beijing (China); Zhao Junwei [W. W. Hansen Experimental Physics Laboratory, Stanford University, Stanford, CA 94305-4085 (United States)

2012-12-10T23:59:59.000Z

238

In vivo Prompt Gamma Neutron Activation Analysis Facility for Total Body Nitrogen and Cd  

SciTech Connect

A Prompt Gamma Neutron Activation Analysis (PGNAA) system has been designed and constructed to measure the total body nitrogen and Cd for in vivo studies. An aqueous solution of KNO{sub 3} was used as phantom for system calibration. The facility has been used to monitor total body nitrogen (TBN) of mice and found that is related to their diet. Some mice swallowed diluted water with Cl{sub 2}Cd, and the presence of Cd was detected in the animals. The minimum Cd concentration that the system can detect was 20 ppm.

Munive, Marco; Revilla, Angel [Instituto Peruano de Energia Nuclear, Av. Canada 1470, Lima 41 (Peru); Solis, Jose L. [Instituto Peruano de Energia Nuclear, Av. Canada 1470, Lima 41 (Peru); Facultad de Ciencias, Universidad Nacional de Ingenieria, Av. Tupac Amaru 210, Lima (Peru)

2007-10-26T23:59:59.000Z

239

Determination of contamination in rare earth materials by promptgamma activation analysis (PGAA)  

SciTech Connect

Prompt gamma activation analysis (PGAA) has been used to detect and quantify impurities in the analyses of rare earth (RE) oxides. The analytical results are discussed with respect to the importance of having a thorough identification and understanding of contaminant elements in these compounds regarding the function of the materials in their various applications. Also, the importance of using PGAA to analyze materials in support of other physico-chemical studies of the materials is discussed, including the study of extremely low concentrations of ions such as the rare earth ions themselves in bulk material matrices.

Perry, D.L.; English, G.A.; Firestone, R.B.; Molnar, G.L.; Revay,Zs.

2004-11-09T23:59:59.000Z

240

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

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


241

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

242

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

243

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

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

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

244

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

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

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

245

X-RAY FLUORESCENCE ANALYSIS OF HANFORD LOW ACTIVITY WASTE SIMULANTS  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) was requested to develop an x-ray fluorescence (XRF) spectrometry method for elemental characterization of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) pretreated low activity waste (LAW) stream to the LAW Vitrification Plant. The WTP is evaluating the potential for using XRF as a rapid turnaround technique to support LAW product compliance and glass former batching. The overall objective of this task was to develop XRF analytical methods that provide the rapid turnaround time (with the objective of optimizing the XRF methodology. Three XRF sample methods used for preparing the LAW sub-sample for XRF analysis were studied: direct liquid analysis, dried spot, and fused glass. The direct liquid method was selected because its major advantage is that the LAW can be analyzed directly without any sample alteration that could bias the method accuracy. It also is the fastest preparation technique--a typical XRF measurement could be completed in with percent relative standard deviations (%RSDs) % for most elements in filtered solution. There were some issues with a few elements precipitating out of solution over time affecting the long term precision of the method. Additional research will need to be performed to resolve this sample stability problem. Activities related to methodology optimization in the Phase 1b portion of the study were eliminated as a result of WTP request to discontinue remaining activities due to funding reduction. These preliminary studies demonstrate that developing an XRF method to support the LAW vitrification plant is feasible. When funding is restored for the WTP, it is recommended that optimization of this technology should be pursued.

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

2006-05-08T23:59:59.000Z

246

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

247

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 accident—the first full-scale accident for a BWR design—poses challenges to the current core model that must be addressed.The ...

2013-02-25T23:59:59.000Z

248

Core Support of the Board on Mathematical Sciences  

SciTech Connect

This proposal summarizes activities conducted by the Board on Mathematical Sciences (BMS) during the period August 1, 1994 to July 31, 1995 and describes future plans of the Board for the period August 1, 1995 to July 31, 1998. We are requesting core support in the amount of $105,000 ($35,000 each year) from the Department of Energy for the additional three-year period. The BMS activities supported exclusively by core funding are the annual Department Chairs Colloquia, the National Science and Technology Symposia, specific reports, the initiation of all projects, continuous oversight of all activities, and partial core support of the Committee on Applied and Theoretical Statistics (CATS). Other activities of the Board include giving recommendations on research directions to federal agencies, and reports on education in the mathematical sciences, interaction of mathematical sciences with other areas, health of the mathematical sciences, and emerging research directions.

1995-04-04T23:59:59.000Z

249

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

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

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

250

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

251

Determination of laser-evaporated uranium dioxide by neutron activation analysis  

SciTech Connect

Safety analyses of nuclear reactors require information about the loss of fuel which may occur at high temperatures. In this study, the surface of a uranium dioxide target was heated rapidly by a laser. The uranium surface was vaporized into a vacuum. The uranium bearing species condensed on a graphite disk placed in the pathway of the expanding uranium vapor. Scanning electron microscopy and X-ray analysis showed very little droplet ejection directly from the laser target surface. Neutron activation analysis was used to measure the amount of uranium deposited. The surface temperature was measured by a fast-response automatic optical pyrometer. The maximum surface temperature ranged from 2400 to 3700/sup 0/K. The Hertz-Langmuir formula, in conjunction with the measured surface temperature transient, was used to calculate the theoretical amount of uranium deposited. There was good agreement between theory and experiment above the melting point of 3120/sup 0/K. Below the melting point much more uranium was collected than was expected theoretically. This was attributed to oxidation of the surface. 29 refs., 16 figs., 7 tabs.

Allred, R.

1987-05-01T23:59:59.000Z

252

Consilience: Radiocarbon, Instrumental Neutron Activation Analysis, and Litigation in the Ancestral Caddo Region  

E-Print Network (OSTI)

Through the creation and analysis of databases for radiocarbon, instrumental neutron activation analysis (INAA), and law, macro-level trends are exposed that form the framework of a broader research program aimed at advancing ideas of craft specialization and archaeological theory in the ancestral Caddo region of Southwest Arkansas, Northwest Louisiana, Northeast Texas, and Southeast Oklahoma. The findings of this investigation illustrate the research potential that remains buried within the context of cultural resource management (CRM) reports and legal databases (Westlaw and LexisNexis) that is awaiting consumption within regional research designs aimed at exploring the nuances and trends that appear through synthetic research. While more can—and should—be done to exploit these resources, this endeavor represents the first logical step toward a more general comprehension of Woodland and Caddo occupations in the region. As a testament to those projects that generated these data, the findings herein are representative of decades of work by numerous academic institutions, archaeological firms, undergraduate as well as graduate students, and avocational archaeologists alike; all of which have and continue to contribute to a more synthetic and dynamic understanding of the things, peoples, and cultures that lie underfoot.

Selden, Robert Zachary

2013-08-01T23:59:59.000Z

253

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...

254

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...

255

COMPARISON OF FEDAL MONITOR READINGS WITH RADIOCHEMICAL SAMPLE DATA. CORE I, SEED 1. Test Results T-641305  

SciTech Connect

Tests were conducted to compare the specific isotopic fission product activities with those of delayed neutron emitters which are monitored by the FEDAL System, and to obtain irformation on the source of activity observed in the PWR coolant. The monitors detected definite activity bursts of delayed neutrons during load increases, which indicated a rupture of the core blanket element. A radiochemical analysis of the coolant data did not show any unusual activity bursts, thus indicating a fuel element failure. It was concluded that the discrepancy in measurements is caused by methods not specifying exactly the time for taking radiochemical samples. The data are tabulated as activity and power output, and given as a function of time. A comparison is given of the activities in the primary coolant for April, June, and July of 1958. (B.O.G.)

1960-10-24T23:59:59.000Z

256

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

257

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

258

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

259

A needs-based approach to activity generation for travel demand analysis/  

E-Print Network (OSTI)

This thesis develops a needs-based framework for behavioral enhancement of conventional activity-based travel demand models. Operational activity-based models specify activity generation models based on empirical considerations ...

Pattabhiraman, Varun R. (Varun Ramakrishna)

2012-01-01T23:59:59.000Z

260

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

E-Print Network (OSTI)

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

Ishutkina, Mariya A. (Mariya Aleksandrovna)

2009-01-01T23:59:59.000Z

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


261

Critical analysis of the Hanford spent nuclear fuel project activity based cost estimate  

Science Conference Proceedings (OSTI)

In 1997, the SNFP developed a baseline change request (BCR) and submitted it to DOE-RL for approval. The schedule was formally evaluated to have a 19% probability of success [Williams, 1998]. In December 1997, DOE-RL Manager John Wagoner approved the BCR contingent upon a subsequent independent review of the new baseline. The SNFP took several actions during the first quarter of 1998 to prepare for the independent review. The project developed the Estimating Requirements and Implementation Guide [DESH, 1998] and trained cost account managers (CAMS) and other personnel involved in the estimating process in activity-based cost (ABC) estimating techniques. The SNFP then applied ABC estimating techniques to develop the basis for the December Baseline (DB) and documented that basis in Basis of Estimate (BOE) books. These BOEs were provided to DOE in April 1998. DOE commissioned Professional Analysis, Inc. (PAI) to perform a critical analysis (CA) of the DB. PAI`s review formally began on April 13. PAI performed the CA, provided three sets of findings to the SNFP contractor, and initiated reconciliation meetings. During the course of PAI`s review, DOE directed the SNFP to develop a new baseline with a higher probability of success. The contractor transmitted the new baseline, which is referred to as the High Probability Baseline (HPB), to DOE on April 15, 1998 [Williams, 1998]. The HPB was estimated to approach a 90% confidence level on the start of fuel movement [Williams, 1998]. This high probability resulted in an increased cost and a schedule extension. To implement the new baseline, the contractor initiated 26 BCRs with supporting BOES. PAI`s scope was revised on April 28 to add reviewing the HPB and the associated BCRs and BOES.

Warren, R.N.

1998-09-29T23:59:59.000Z

262

Report on INL Activities for Uncertainty Reduction Analysis of FY11  

SciTech Connect

This report presents the status of activities performed at INL under the ARC Work Package on 'Uncertainty Reduction Analyses' that has a main goal the reduction of uncertainties associated with nuclear data on neutronic integral parameters of interest for the design of advanced fast reactors under consideration by the ARC program. First, an analysis of experiments was carried out. For both JOYO (the first Japanese fast reactor) and ZPPR-9 (a large size zero power plutonium fueled experiment performed at ANL-W in Idaho) the performance of ENDF/B-VII.0 is quite satisfying except for the sodium void configurations of ZPPR-9, but for which one has to take into account the approximation of the modeling. In fact, when one uses a more detailed model (calculations performed at ANL in a companion WP) more reasonable results are obtained. A large effort was devoted to the analysis of the irradiation experiments, PROFIL-1 and -2 and TRAPU, performed at the French fast reactor PHENIX. For these experiments a pre-release of the ENDF/B-VII.1 cross section files was also used, in order to provide validation feedback to the CSWEG nuclear data evaluation community. In the PROFIL experiments improvements can be observed for the ENDF/B-VII.1 capture data in 238Pu, 241Am, 244Cm, 97Mo, 151Sm, 153Eu, and for 240Pu(n,2n). On the other hand, 240,242Pu, 95Mo, 133Cs and 145Nd capture C/E results are worse. For the major actinides 235U and especially 239Pu capture C/E's are underestimated. For fission products, 105,106Pd, 143,144Nd and 147,149Sm are significantly underestimated, while 101Ru and 151Sm are overestimated. Other C/E deviations from unity are within the combined experimental and calculated statistical uncertainty. From the TRAPU analysis, the major improvement is in the predicted 243Cm build-up, presumably due to an improved 242Cm capture evaluation. The COSMO experiment was also analyzed in order to provide useful feedback on fission cross sections. It was found out that ENDF/B-VII.1 238,240Pu fission cross sections have improved with respect to VII.0 files while 242Pu's fission cross section has not.

G. Plamiotti; H. Hiruta; M. Salvatores

2011-09-01T23:59:59.000Z

263

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

264

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

265

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; Cláudio T. Silva; William J. Schroeder

1998-10-01T23:59:59.000Z

266

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

E-Print Network (OSTI)

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

Hansman, R. John

2009-03-30T23:59:59.000Z

267

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

E-Print Network (OSTI)

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

Ishutkina, Mariya A.

2011-10-14T23:59:59.000Z

268

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

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

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

269

Method for including operation and maintenance costs in the economic analysis of active solar energy systems  

DOE Green Energy (OSTI)

For a developing technology such as solar energy, the costs for operation and maintenance (O and M) can be substantial. In the past, most economic analyses included these costs by simply assuming that an annual cost will be incurred that is proportional to the initial cost of the system. However, in assessing the economics of new systems proposed for further research and development, such a simplification can obscure the issues. For example, when the typical method for including O and M costs in an economic analysis is used, the O and M costs associated with a newly developed, more reliable, and slightly more expensive controller will be assumed to increase - an obvious inconsistency. The method presented in this report replaces this simplistic approach with a representation of the O and M costs that explicitly accounts for the uncertainties and risks inherent in the operation of any equipment. A detailed description of the data inputs required by the method is included as well as a summary of data sources and an example of the method as applied to an active solar heating system.

Short, W.D.

1986-08-01T23:59:59.000Z

270

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

271

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

272

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

273

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

274

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

275

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

276

activities  

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

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

277

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

278

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

Science Conference Proceedings (OSTI)

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

Steen, F.H.

1997-08-05T23:59:59.000Z

279

BWRVIP-34-A: BWR Vessel and Internals Project, Technical Basis for Part Circumference Weld Overlay Repair of Vessel Internal Core Sp ray Piping  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. This report summarizes the results of the design and analysis activities and the testing programs conducted to provide BWR utilities with a contingency repair option for internal core spray piping for BWR2/6 plants. A previous version of this report was published as BWRVIP-34 (TR-108198). This report (BWRVIP-34...

2008-03-11T23:59:59.000Z

280

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

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


281

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

282

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, ...

283

Analysis of Microbial Activity Under a Supercritical CO{sub 2} Atmosphere  

SciTech Connect

Because the extent and impact of microbial activity in deep saline aquifers during geologic sequestration is unknown, the objectives of this proposal were to: (1) characterize the growth requirements and optima of a biofilm-producing supercritical CO{sub 2}-tolerant microbial consortium (labeled MIT0212) isolated from hydrocarbons recovered from the Frio Ridge, TX carbon sequestration site; (2) evaluate the ability of this consortium to grow under simulated reservoir conditions associated with supercritical CO{sub 2} injection; (3) isolate and characterize individual microbial strains from this consortium; and (4) investigate the mechanisms of supercritical CO{sub 2} tolerance in isolated strains and the consortium through genome-enabled studies. Molecular analysis of genetic diversity in the consortium MIT0212 revealed a predominance of sequences closely related to species of the spore-forming genus Bacillus. Strain MIT0214 was isolated from this consortium and characterized by physiological profiling and genomic analysis. We have shown that the strain MIT0214 is an aerobic spore-former and capable of facultative anaerobic growth under both reducing N{sub 2} and CO{sub 2} atmospheres by fermentation and possibly anaerobic respiration. Strain MIT0214 is best adapted to anaerobic growth at pressures of 1 atm but is able to growth at elevated pressures After 1 week growth was observed at pressures as high as 27 atm (N{sub 2}) or 9 atm (CO{sub 2}) and after 26-30 days growth can be observed under supercritical CO{sub 2}. In addition, we have determined that spores of strain B. cereus MIT0214 are tolerant of both direct and indirect exposure to supercritical CO{sub 2}. Additional physiological characterization under aerobic conditions have revealed MIT0214 is able to grow from temperature of 21 to 45 °C and salinities 0.01 to 40 g/L NaCl with optimal growth occurring at 30°C and from 1 - 5 g NaCl/L. The genome sequence of B. cereus MIT0214 shared 89 to 91% of genes with other genome-sequenced strains with 93.3 to 97.8% nucleotide identity among shared genes. Comparison of the sequence of MIT0214 or a B. cereus strain isolated from an oil well in China to B. cereus isolates from surface environments revealed a higher proportion of genes involved in Cell wall and capsule biosynthesis and metabolism, metabolism of aromatic compounds, and stress response. Since Bacillus species, including B. cereus strains, have commonly been recovered from other “extreme” environments including the deep subsurface – the scCO{sub 2} tolerance of spores and growth under high pCO{sub 2} conditions is consistent with persistence in a subsurface environment after CO{sub 2} injection.

Thompson, Janelle

2012-11-30T23:59:59.000Z

284

Molecular Analysis of Microglial Activation and Macrophage Recruitment in Murine Models of Neuroinflammation.  

E-Print Network (OSTI)

OF CALIFORNIA RIVERSIDE Molecular Analysis of Microglialof Philosophy in Cell, Molecular, and Developmental BiologyNMDA receptors : molecular mechanisms and therapeutic

Puntambekar, Shweta

2009-01-01T23:59:59.000Z

285

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

286

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....

287

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...

288

A cost-based analysis of intrusion detection system configuration under active or passive response  

Science Conference Proceedings (OSTI)

This paper studies the joint decisions of IDS configuration and alarm investigation capacity under active and passive responses. In active response, alarm events are blocked immediately, whereas alarm events are allowed to access the information assets ... Keywords: IDS configuration, Information security, Intrusion response, Investigation capacity

Wei T. Yue; Metin Çakany?ld?r?m

2010-12-01T23:59:59.000Z

289

Design and analysis of multi-level active queue management mechanisms for emergency traffic  

Science Conference Proceedings (OSTI)

Multiple average-multiple threshold (MAMT) active queue management (AQM) is proposed as a solution for providing available and dependable service to traffic from emergency users after disasters. MAMT is a simple but effective approach that can be applied ... Keywords: Active queue management, Emergency services, Quality of service

Manali Joshi; Ajay Mansata; Salil Talauliker; Cory Beard

2005-02-01T23:59:59.000Z

290

For more information about services available at the COBRE-PSF Core Laboratories contact  

E-Print Network (OSTI)

For more information about services available at the COBRE-PSF Core Laboratories contact: PROTEIN P20 GM103420-10) from the National Institutes of Health. THE UNIVERSITY OF KANSAS CORE LABORATORIES Associate: Na Zhang The laboratory offers the following services: Activities in the Protein Production Group

Peterson, Blake R.

291

Core capabilities and technical enhancement, FY-98 annual report  

Science Conference Proceedings (OSTI)

The Core Capability and Technical Enhancement (CCTE) Program, a part of the Verification, Validation, and Engineering Assessment Program, was implemented to enhance and augment the technical capabilities of the Idaho National Engineering and Environmental Laboratory (INEEL). The purpose for strengthening the technical capabilities of the INEEL is to provide the technical base to serve effectively as the Environmental Management Laboratory for the Department of Energy's Office of Environmental Management (EM). An analysis of EM's science and technology needs as well as the technology investments currently being made by EM across the complex was used to formulate a portfolio of research activities designed to address EM's needs without overlapping work being done elsewhere. An additional purpose is to enhance and maintain the technical capabilities and research infrastructure at the INEEL. This is a progress report for fiscal year 1998 for the five CCTE research investment areas: (a) transport aspects of selective mass transport agents, (b) chemistry of environmental surfaces, (c) materials dynamics, (d) characterization science, and (e) computational simulation of mechanical and chemical systems. In addition to the five purely technical research areas, this report deals with the science and technology foundations element of the CCTE from the standpoint of program management and complex-wide issues. This report also provides details of ongoing and future work in all six areas.

Miller, D.L.

1999-04-01T23:59:59.000Z

292

Core Capabilities and Technical Enhancement -- FY-98 Annual Report  

Science Conference Proceedings (OSTI)

The Core Capability and Technical Enhancement (CC&TE) Program, a part of the Verification, Validation, and Engineering Assessment Program, was implemented to enhance and augment the technical capabilities of the Idaho National Engineering and Environmental Laboratory (INEEL). The purpose for strengthening the technical capabilities of the INEEL is to provide the technical base to serve effectively as the Environmental Management Laboratory for the Office of Environmental Management (EM). An analysis of EM's science and technology needs as well as the technology investments currently being made by EM across the complex was used to formulate a portfolio of research activities designed to address EM's needs without overlapping work being done elsewhere. An additional purpose is to enhance and maintain the technical capabilities and research infrastructure at the INEEL. This is a progress report for fiscal year 1998 for the five CC&TE research investment areas: (a) transport aspects of selective mass transport agents, (b) chemistry of environmental surfaces, (c) materials dynamics, (d) characterization science, and (e) computational simulation of mechanical and chemical systems. In addition to the five purely technical research areas, this report deals with the science and technology foundations element of the CC&TE from the standpoint of program management and complex-wide issues. This report also provides details of ongoing and future work in all six areas.

Miller, David Lynn

1999-04-01T23:59:59.000Z

293

India-NREL Energy Activities | Open Energy Information  

Open Energy Info (EERE)

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

294

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

295

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

296

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

297

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

298

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

299

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

300

A comparative energetic analysis of active and passive emission control systems adopting standard emission test cycles  

Science Conference Proceedings (OSTI)

The present work aims at analysing and comparing the thermal performances of active and passive aftertreatment systems. A one-dimensional transient model has been developed in order to evaluate the heat exchange between the solid and the exhaust gas ...

Angelo Algieri, Mario Amelio, Pietropaolo Morrone

2012-01-01T23:59:59.000Z

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


301

Bayesian Change-Point Analysis of Tropical Cyclone Activity: The Central North Pacific Case  

Science Conference Proceedings (OSTI)

Bayesian analysis is applied to detect change points in the time series of annual tropical cyclone counts over the central North Pacific. Specifically, a hierarchical Bayesian approach involving three layers—data, parameter, and hypothesis—is ...

Pao-Shin Chu; Xin Zhao

2004-12-01T23:59:59.000Z

302

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

303

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...

304

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...

305

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...

306

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...

307

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...

308

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

309

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

310

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

311

Aerobic composting of waste activated sludge: Kinetic analysis for microbiological reaction and oxygen consumption  

SciTech Connect

In order to examine the optimal design and operating parameters, kinetics for microbiological reaction and oxygen consumption in composting of waste activated sludge were quantitatively examined. A series of experiments was conducted to discuss the optimal operating parameters for aerobic composting of waste activated sludge obtained from Kawagoe City Wastewater Treatment Plant (Saitama, Japan) using 4 and 20 L laboratory scale bioreactors. Aeration rate, compositions of compost mixture and height of compost pile were investigated as main design and operating parameters. The optimal aerobic composting of waste activated sludge was found at the aeration rate of 2.0 L/min/kg (initial composting mixture dry weight). A compost pile up to 0.5 m could be operated effectively. A simple model for composting of waste activated sludge in a composting reactor was developed by assuming that a solid phase of compost mixture is well mixed and the kinetics for microbiological reaction is represented by a Monod-type equation. The model predictions could fit the experimental data for decomposition of waste activated sludge with an average deviation of 2.14%. Oxygen consumption during composting was also examined using a simplified model in which the oxygen consumption was represented by a Monod-type equation and the axial distribution of oxygen concentration in the composting pile was described by a plug-flow model. The predictions could satisfactorily simulate the experiment results for the average maximum oxygen consumption rate during aerobic composting with an average deviation of 7.4%.

Yamada, Y. [Research Center for Biochemical and Environmental Engineering, Department of Applied Chemistry, Toyo University, Kawagoe, Saitama, 350-8585 (Japan); Kawase, Y. [Research Center for Biochemical and Environmental Engineering, Department of Applied Chemistry, Toyo University, Kawagoe, Saitama, 350-8585 (Japan)]. E-mail: bckawase@mail.eng.toyo.ac.jp

2006-07-01T23:59:59.000Z

312

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

313

TOWARD REALISTIC PROGENITORS OF CORE-COLLAPSE SUPERNOVAE  

SciTech Connect

Two-dimensional (2D) hydrodynamical simulations of progenitor evolution of a 23 M{sub sun} star, close to core collapse (in {approx}1 hr in one dimension (1D)), with simultaneously active C, Ne, O, and Si burning shells, are presented and contrasted to existing 1D models (which are forced to be quasi-static). Pronounced asymmetries and strong dynamical interactions between shells are seen in 2D. Although instigated by turbulence, the dynamic behavior proceeds to sufficiently large amplitudes that it couples to the nuclear burning. Dramatic growth of low-order modes is seen as well as large deviations from spherical symmetry in the burning shells. The vigorous dynamics is more violent than that seen in earlier burning stages in the three-dimensional (3D) simulations of a single cell in the oxygen burning shell, or in 2D simulations not including an active Si shell. Linear perturbative analysis does not capture the chaotic behavior of turbulence (e.g., strange attractors such as that discovered by Lorenz), and therefore badly underestimates the vigor of the instability. The limitations of 1D and 2D models are discussed in detail. The 2D models, although flawed geometrically, represent a more realistic treatment of the relevant dynamics than existing 1D models, and present a dramatically different view of the stages of evolution prior to collapse. Implications for interpretation of SN1987A, abundances in young supernova remnants, pre-collapse outbursts, progenitor structure, neutron star kicks, and fallback are outlined. While 2D simulations provide new qualitative insight, fully 3D simulations are needed for a quantitative understanding of this stage of stellar evolution. The necessary properties of such simulations are delineated.

David Arnett, W.; Meakin, Casey, E-mail: wdarnett@gmail.com, E-mail: casey.meakin@gmail.com [Steward Observatory, University of Arizona, 933 North Cherry Avenue, Tucson, AZ 85721 (United States)

2011-06-01T23:59:59.000Z

314

Dynamic Analysis and Control of an Energy Storage Flywheel Rotor with Active Magnetic Bearings  

Science Conference Proceedings (OSTI)

Flywheel energy storage is a promising technology for providing intermediate energy storage. An energy storage flywheel is supported by active magnetic bearings (AMBs) to achieve high speed running and increase energy efficiency of the energy storage ... Keywords: Flywheel, Energy Storage, Magnetic Bearing, Rotor Dynamics

Zhang Kai; Dai Xingjian; Zhang Xiaozhang

2010-12-01T23:59:59.000Z

315

iDiary : compression, analysis, and visualization of GPS data to predict user activities  

E-Print Network (OSTI)

"What did you do today?" When we hear this question, we try to think back to our day's activities and locations. When we end up drawing a blank on the details of our day, we reply with a simple, "not much." Remembering our ...

Sugaya, Andrew (Andrew Kiminari)

2012-01-01T23:59:59.000Z

316

Analysis and comparison of active solar desiccant and absorption cooling systems. Part 1; Model description  

DOE Green Energy (OSTI)

A comparative analysis has been performed to compare the cooling and dehumidification performance of future ventilation-mode desiccant systems, proposed advanced absorption systems, and conventional vapor compression systems. A common framework has been developed for direct comparison of these different cooling technologies; this method is described in this paper.

Warren, M.L. (ASI Controls, San Ramon, CA (US)); Wahlig, M. (Lawrence Berkeley Lab., CA (USA). Applied Science Div.)

1991-02-01T23:59:59.000Z

317

Analysis methods for solar heating and cooling applications: passive and active systems. 2nd edition  

DOE Green Energy (OSTI)

Brief descriptions of analysis methods and design tools which are valuable in performing parametric studies of candidate designs are presented in this brochure. The methods included range from rules-of-thumb for builders to the simulation packages used by researchers. (MHR)

None

1980-01-01T23:59:59.000Z

318

Simulation analysis of data processing activities in Compact Muon Solenoid physics  

Science Conference Proceedings (OSTI)

The scale, complexity and worldwide geographical spread of the Large Hadron Collider (LHC) computing and data analysis problems are unprecedented in scientific research. The complexity of processing and accessing this data is increased substantially ... Keywords: Compact Muon Solenoid, large-scale distributed systems, simulation model

Ciprian Dobre

2012-12-01T23:59:59.000Z

319

Time-Distance analysis of the Emerging Active Region NOAA 10790  

E-Print Network (OSTI)

We investigate the emergence of Active Region NOAA 10790 by means of time--distance helioseismology. Shallow regions of increased sound speed at the location of increased magnetic activity are observed, with regions becoming deeper at the locations of sunspot pores. We also see a long-lasting region of decreased sound speed located underneath the region of the flux emergence, possibly relating to a temperature perturbation due to magnetic quenching of eddy diffusivity, or to a dense flux tube. We detect and track an object in the subsurface layers of the Sun characterised by increased sound speed which could be related to emerging magnetic flux and thus obtain a provisional estimate of the speed of emergence of around $1 {\\rm km s^{-1}}$.

S. Zharkov; M. J. Thompson

2008-07-18T23:59:59.000Z

320

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

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


321

Analysis and comparison of active solar desiccant and absorption cooling systems. Part 2; Annual simulation results  

DOE Green Energy (OSTI)

A comparative analysis has been performed to compare the cooling and dehumidification performance of future ventilation mode desiccant systems, proposed advanced absorption systems, and conventional vapor compression systems. A common framework has been developed for direct comparison of these different cooling technologies; this method is described in a companion paper. This paper presents the application of this method to annual simulations of cooling system performance in five cities.

Warren, M.L. (ASI Controls, San Ramon, CA (US)); Wahlig, M. (Lawrence Berkeley Lab., CA (USA). Applied Science Div.)

1991-02-01T23:59:59.000Z

322

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:

323

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

324

Determination of hydrogen in niobium by cold neutron prompt gamma ray activation analysis and neutron incoherent scattering  

DOE Green Energy (OSTI)

The presence of trace amounts of hydrogen in niobium is believed to have a detrimental effect on the mechanical and superconducting properties. Unfortunately, few techniques are capable of measuring hydrogen at these levels. We have developed two techniques for measuring hydrogen in materials. Cold neutron prompt gamma-ray activation analysis (PGAA) has proven useful for the determination of hydrogen and other elements in a wide variety of materials. Neutron incoherent scattering (NIS), a complementary tool to PGAA, has been used to measure trace hydrogen in titanium. Both techniques were used to study the effects of vacuum heating and chemical polishing on the hydrogen content of superconducting niobium.

R.L. Paul; H.H. Cheu-Maya; G.R. Myneni

2002-11-01T23:59:59.000Z

325

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

326

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 ...

327

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

328

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...

329

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...

330

Modern Methods for Lipid AnalysisChapter 3 Electrospray Ionization with Low-Energy Collisionally Activated Dissociation Tandem Mass Spectrometry of Complex Lipids:  

Science Conference Proceedings (OSTI)

Modern Methods for Lipid Analysis Chapter 3 Electrospray Ionization with Low-Energy Collisionally Activated Dissociation Tandem Mass Spectrometry of Complex Lipids: Methods and Analyses eChapters Methods - Analyses Books AOCS Press ...

331

Crossing Active Faults on the Sakhalin II Onshore Pipeline Route: Pipeline Design and Risk Analysis  

SciTech Connect

Twin oil (20 and 24 inch) and gas (20 and 48 inch) pipeline systems stretching 800 km are being constructed to connect offshore hydrocarbon deposits from the Sakhalin II concession in the North to an LNG plant and oil export terminal in the South of Sakhalin island. The onshore pipeline route follows a regional fault zone and crosses individual active faults at 19 locations. Sakhalin Energy, Design and Construction companies took significant care to ensure the integrity of the pipelines, should large seismic induced ground movements occur during the Operational life of the facilities. Complex investigations including the identification of the active faults, their precise location, their particular displacement values and assessment of the fault kinematics were carried out to provide input data for unique design solutions. Lateral and reverse offset displacements of 5.5 and 4.5 m respectively were determined as the single-event values for the design level earthquake (DLE) - the 1000-year return period event. Within the constraints of a pipeline route largely fixed, the underground pipeline fault crossing design was developed to define the optimum routing which would minimize stresses and strain using linepipe materials which had been ordered prior to the completion of detailed design, and to specify requirements for pipe trenching shape, materials, drainage system, etc. Detailed Design was performed with due regard to actual topography and to avoid the possibility of the trenches freezing in winter, the implementation of specific drainage solutions and thermal protection measures.

Mattiozzi, Pierpaolo [Snamprogetti-Saipem, Via Toniolo, 1, 61032 Fano (Italy); Strom, Alexander [Institute of Geospheres Dynamics, Leninskiy Avenue, 38, Building 1, 119334, Moscow (Russian Federation)

2008-07-08T23:59:59.000Z

332

Crossing Active Faults on the Sakhalin II Onshore Pipeline Route: Analysis Methodology and Basic Design  

Science Conference Proceedings (OSTI)

Twin oil (20 and 24 inch) and gas (20 and 48 inch) pipeline systems stretching 800 km are being constructed to connect offshore hydrocarbon deposits from the Sakhalin II concession in the North to an LNG plant and oil export terminal in the South of Sakhalin island. The onshore pipeline route follows a regional fault zone and crosses individual active faults at 19 locations. Sakhalin Energy, Design and Construction companies took significant care to ensure the integrity of the pipelines, should large seismic induced ground movements occur during the Operational life of the facilities. Complex investigations including the identification of the active faults, their precise location, their particular displacement values and assessment of the fault kinematics were carried out to provide input data for unique design solutions. Lateral and reverse offset displacements of 5.5 and 4.5 m respectively were determined as the single-event values for the design level earthquake (DLE)--the 1000-year return period event. Within the constraints of a pipeline route largely fixed, the underground pipeline fault crossing design was developed to define the optimum routing which would minimize stresses and strain using linepipe materials which had been ordered prior to the completion of detailed design, and to specify requirements for pipe trenching shape, materials, drainage system, etc. This Paper describes the steps followed to formulate the concept of the special trenches and the analytical characteristics of the Model.

Vitali, Luigino [Snamprogetti-Saipem, Via Toniolo, 1, 61032 Fano, Luigino (Italy); Mattiozzi, Pierpaolo [Snamprogetti-Saipem, Via Toniolo, 1, 61032 Fano (Italy)

2008-07-08T23:59:59.000Z

333

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

334

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

335

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

336

Neutron formation temperature gauge and neutron activation analysis brine flow meter. Final report, October 1, 1976--March 31, 1978  

DOE Green Energy (OSTI)

Feasibility studies of nuclear techniques applicable to the determination of geothermal formation temperature and two-phase brine flow downhole have been performed. The formation temperature gauging technique involves injection of fast neutrons into the formation and analysis of the moderated slow neutron energy distribution by appropriately filtered neutron detectors. The scientific feasibility of the method has been demonstrated by analytical computational and experimental evaluation of the system response. A data analysis method has been developed to determine unambiguously the temperature, neutron absorption cross section and neutron moderating power of an arbitrary medium. The initial phase of a program to demonstrate the engineering feasibility of the technique has been performed. A sonde mockup was fabricated and measurements have been performed in a test stand designed to simulate a geothermal well. The results indicate that the formation temperature determined by this method is independent of differences between the temperature in the borehole fluid and the formation, borehole fluid density, and borehole fluid salinity. Estimates of performance specifications for a formation temperature sonde have been made on the basis of information obtained in this study and a conceptual design of a logging system has been developed. The technique for the determination of fluid flow in a well is based on neutron activation analysis of elements present in the brine. An analytical evaluation of the method has been performed. The results warrant further, experimental evaluation.

Vagelatos, N.; Steinman, D.K.; John, J.

1978-03-31T23:59:59.000Z

337

81.114- University Reactor Infrastructure and Education Support / Prompt Gamma-ray Activation Analysis of Lithioum Ion Battery Cathodes  

Science Conference Proceedings (OSTI)

This project focuses on the use of the Prompt Gamma-ray Activation Analysis (PGAA) technique available at the Nuclear Engineering Teaching Laboratory of the University of Texas at Austin to precisely determine the hydrogen (proton) contents in layered oxide cathode samples obtained by chemical lithium extraction in order to obtain a better understanding of the factors limiting the practical capacities and overall performance of lithium ion battery cathodes. The project takes careful precautionary experimental measures to avoid proton contamination both from solvents used in chemical delithiation and from ambient moisture. The results obtained from PGAA are complemented by the data obtained from other techniques such as thermogravimetric analysis, redox titration, atomic absorption spectroscopy, X-ray diffraction, and mass spectroscopic analysis of the evolved gas on heating. The research results broaden our understanding of the structure-property-performance relationships of lithium ion battery cathodes and could aid the design and development of new better performing lithium ion batteries for consumer (portable and electric vehicles), military, and space applications.

Manthiram, Arumugam; Landsberger, S.

2006-11-11T23:59:59.000Z

338

Wind Farm Power Fluctuations, Ancillary Services, and System Operating Impact Analysis Activities in the United States: Preprint  

SciTech Connect

With ever increasing penetration of wind capacity and growing interest in wind power by electric utilities and other power providers, questions about the impacts and costs associated with maintaining a stable grid is receiving lots of attention. These issues are important, both in competitive and regulated monopoly markets.To evaluate the range of ancillary service impact of wind power plants, wind power plant output fluctuations on the order of seconds to minutes must be known. However, the data required for a credible analysis has not been widely available. The National Renewable Energy Laboratory (NREL), through its own efforts, and in conjunction with a wide group of stakeholders including other national labs, consultants, developers, utilities, and the non-profit Utility Wind Interest Group, has initiated measurement and analysis activities. The efforts are ongoing. While final system-cost results are not available, this paper will describe the progress to date and present typical results and statistical analysis. In addition, methods will be explained with the aim of soliciting feedback from others looking at similar issues worldwide.

Parsons, B. K. (National Renewable Energy Laboratory); Wan, Y. (National Renewable Energy Laboratory); Kirby, B. (Oak Ridge National Laboratory)

2001-07-01T23:59:59.000Z

339

Modern Records of Atmospheric Methane (CH4) and a 2000-year Ice-core Record  

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

(CH4) » Ice Cores (CH4) » Ice Cores Modern Records of Atmospheric Methane (CH4) and a 2000-year Ice-core Record from Law Dome, Antarctica Introduction This page provides an introduction and links to records of atmospheric methane (CH4) over the last 2000 years, emphasizing large data bases each representing currently active stations. Records in recent decades (time period depending on location) have been obtained from samples of ambient-air at remote locations, which represent global atmospheric conditions rather than influences of local sources. The longer (2000-year) record is from the Law Dome ice core in Antarctica. The ice-core record has been merged with modern annual data from Cape Grim, Tasmania to provide a 2000-year record ending with the most recent data. A spline function has

340

Modern Records of Atmospheric Carbon Dioxide (CO2) and a 2000-year Ice-core  

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

Carbon Dioxide (CO2) » Ice Cores Carbon Dioxide (CO2) » Ice Cores Modern Records of Atmospheric Carbon Dioxide (CO2) and a 2000-year Ice-core Record from Law Dome, Antarctica Introduction This page provides an introduction and links to records of atmospheric carbon dioxide (CO2) concentrations over the last 2000 years, emphasizing large data bases each representing many currently active stations. Records since about 1960 (depending on location) have been obtained from samples of ambient-air at remote stations, which represent changing global atmospheric concentrations rather than influences of local sources. The longer (2000-year) record is from the Law Dome ice core in Antarctica. The ice-core record has been merged with modern annual data from Cape Grim, Tasmania to provide a 2000-year record ending with the most recent data. A

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


341

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

342

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

343

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

344

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

345

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

346

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.

347

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

348

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

349

Preferential CO Oxidation in Hydrogen: Reactivity of Core-Shell Nanoparticles  

Science Conference Proceedings (OSTI)

We report on the first-principles-guided design, synthesis, and characterization of core-shell nanoparticle (NP) catalysts made of a transition metal core (M ) Ru, Rh, Ir, Pd, or Au) covered with a ?1-2 monolayer thick shell of Pt atoms (i.e., a M@Pt core-shell NP). An array of experimental techniques, including X-ray diffraction, Fourier transform infrared spectroscopy, high resolution transmission electron microscopy, and temperature-programmed reaction, are employed to establish the composition of the synthesized NPs. Subsequent studies of these NPs’ catalytic properties for preferential CO oxidation in hydrogen-rich environments (PROX), combined with Density Functional Theory (DFT)-based mechanistic studies, elucidate important trends and provide fundamental understanding of the reactivity of Pt shells as a function of the core metal. Both the PROX activity and selectivity of several of these M@Pt core-shell NPs are significantly improved compared to monometallic and bulk nonsegregated bimetallic nanoalloys. Among the systems studied, Ru@Pt core-shell NPs exhibit the highest PROX activity, where the CO oxidation is complete by 30 °C (1000 ppm CO in H2). Therefore, despite their reduced Pt content, M@Pt core-shell NPs afford the design of more active PROX catalysts. DFT studies suggest that the relative differences in the catalytic activities for the various core-shell NPs originate from a combination of (i) the relative availability of CO-free Pt surface sites on the M@Pt NPs, which are necessary for O2 activation, and (ii) a hydrogen-mediated low-temperature CO oxidation process that is clearly distinct from the traditional bifunctional CO oxidation mechanism.

Nilekar, Anand U.; Alayoglu, Selim; Eichhorn, Bryan W.; Mavrikakis, Manos

2010-06-02T23:59:59.000Z

350

Policy and Analysis Team | Department of Energy  

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

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

351

The X-ray Crystallographic Structure and Activity Analysis of a Pseudomonas-Specific Subfamily of the HAD Enzyme Superfamily Evidences a Novel Biochemical Function  

Science Conference Proceedings (OSTI)

The haloacid dehalogenase (HAD) superfamily is a large family of proteins dominated by phosphotransferases. Thirty-three sequence families within the HAD superfamily (HADSF) have been identified to assist in function assignment. One such family includes the enzyme phosphoacetaldehyde hydrolase (phosphonatase). Phosphonatase possesses the conserved Rossmanniod core domain and a C1-type cap domain. Other members of this family do not possess a cap domain and because the cap domain of phosphonatase plays an important role in active site desolvation and catalysis, the function of the capless family members must be unique. A representative of the capless subfamily, PSPTO{_}2114, from the plant pathogen Pseudomonas syringae, was targeted for catalytic activity and structure analyses. The X-ray structure of PSPTO{_}2114 reveals a capless homodimer that conserves some but not all of the intersubunit contacts contributed by the core domains of the phosphonatase homodimer. The region of the PSPTO{_}2114 that corresponds to the catalytic scaffold of phosphonatase (and other HAD phosphotransfereases) positions amino acid residues that are ill suited for Mg+2 cofactor binding and mediation of phosphoryl group transfer between donor and acceptor substrates. The absence of phosphotransferase activity in PSPTO{_}2114 was confirmed by kinetic assays. To explore PSPTO{_}2114 function, the conservation of sequence motifs extending outside of the HADSF catalytic scaffold was examined. The stringently conserved residues among PSPTO{_}2114 homologs were mapped onto the PSPTO{_}2114 three-dimensional structure to identify a surface region unique to the family members that do not possess a cap domain. The hypothesis that this region is used in protein-protein recognition is explored to define, for the first time, HADSF proteins which have acquired a function other than that of a catalyst. Proteins 2008.

Peisach,E.; Wang, L.; Burroughs, A.; Aravind, L.; Dunaway-Mariano, D.; Allen, K.

2008-01-01T23:59:59.000Z

352

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

353

The nascent Coso metamorphic core complex, east-central California, brittle  

Open Energy Info (EERE)

nascent Coso metamorphic core complex, east-central California, brittle nascent Coso metamorphic core complex, east-central California, brittle upper plate structure revealed by reflection seismic data Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Journal Article: The nascent Coso metamorphic core complex, east-central California, brittle upper plate structure revealed by reflection seismic data Details Activities (1) Areas (1) Regions (0) Abstract: The relationships between upper crustal faults, the brittle-ductile transition zone, and underlying magmatic features imaged by multifold seismic reflection data are consistent with the hypothesis that the Coso geothermal field, which lies within an extensional step-over between dextral faults, is a young, actively developing metamorphic core complex. The reflection images were processed using a non-linear simulated

354

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

355

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

356

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

357

Carbon Dioxide Information Analysis Center and World Data Center-A for atmospheric trace gases: FY 1993 activities  

SciTech Connect

During the course of a fiscal year, Oak Ridge National Laboratory`s Carbon Dioxide Information Analysis Center (CDIAC) distributes thousands of specialty publications-numeric data packages (NDPs), computer model packages (CMPs), technical reports, public communication publications, newsletters, article reprints, and reference books-in response to requests for information related to global environmental issues, primarily those pertaining to climate change. CDIAC`s staff also provide technical responses to specific inquiries related to carbon dioxide (CO{sub 2}), other trace gases, and climate. Hundreds of referrals to other researchers, policy analysts, information specialists, or organizations are also facilitated by CDIAC`s staff. This report provides an account of the activities accomplished by CDIAC (including World Data Center-A for Atmospheric Trace Gases) during the period October 1, 1992, to September 30, 1993. An organizational overview of CDIAC and its staff is supplemented by a detailed description of inquiries received and CDIAC`s response to those inquiries. An analysis and description of the preparation and distribution of NDPS, CMPS, technical reports, newsletters, fact sheets, specialty publications, and reprints are provided. Comments and descriptions of CDIAC`s information management systems, professional networking, and special bilateral agreements are also presented.

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

1994-01-01T23:59:59.000Z

358

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

359

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

360

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

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


361

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":""}]}

362

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

363

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.)

364

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

365

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

366

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

367

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

368

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

369

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

370

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

371

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

372

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

373

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

374

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

375

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

376

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...

377

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...

378

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.

379

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

380

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

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


381

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

382

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....

383

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...

384

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...

385

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....

386

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, ...

387

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...

388

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...

389

{sup 152}Eu depths profiles granite and concrete cores exposed to the Hiroshima atomic bomb  

SciTech Connect

Two granite and two concrete core samples were obtained within 500 m from the hypocenter of the Hiroshima atomic bomb, and the depth profile of {sup 152}Eu was measured to evaluate the incident neutron spectrum. The granite cores were obtained from a pillar of the Motoyasu Bridge located 101 m from the hypocenter and from a granite rock in the Shirakami Shrine (379 m); the concrete cores were obtained from a gate in the Gokoku Shrine (398 m) and from top of the Hiroshima bank (250 m). The profiles of the specific activities of the cores were measured to a depth of 40 cm from the surface using low background germanium (Ge) spectrometers. According to the measured depth profiles, relaxation lengths of incident neutrons were derived as 13.6 cm for Motoyasu Bridge pillar (granite), 12.2 cm for Shirakami Shrine core (granite), and 9.6 cm for concrete cores of Gokoku Shrine and Hiroshima Bank. In addition, a comparison of the granite cores in Hiroshima showed good agreement with Nagasaki data. Present results indicates that the depth profile of {sup 152}Eu reflects incident neutrons not so high but in the epithermal region. 19 refs., 7 figs., 8 tabs.

Shizuma, Kiyoshi; Iwatani, Kazuo [Hiroshima Univ. (Japan); Oka, Takamitsu [Kure Univ. (Japan)] [and others

1997-06-01T23:59:59.000Z

390

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

391

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

392

DOE/NETL's phase II mercury control technology field testing program: preliminary economic analysis of activated carbon injection  

Science Conference Proceedings (OSTI)

Based on results of field testing conducted by the U.S. Department of Energy's National Energy Technology Laboratory (DOE/NETL), this article provides preliminary costs for mercury control via conventional activated carbon injection (ACI), brominated ACI, and conventional ACI coupled with the application of a sorbent enhancement additive (SEA) to coal prior to combustion. The economic analyses are reported on a plant-specific basis in terms of the cost required to achieve low (50%), mid (70%), and high (90%) levels of mercury removal 'above and beyond' the baseline mercury removal achieved by existing emission control equipment. In other words, the levels of mercury control are directly attributable to ACI. Mercury control costs via ACI have been amortized on a current dollar basis. Using a 20-year book life, levelized costs for the incremental increase in cost of electricity (COE), expressed in mills per kilowatt-hour (mills/kWh), and the incremental cost of mercury control, expressed in dollars per pound of mercury removed ($/lb Hg removed), have been calculated for each level of ACI mercury control. For this analysis, the increase in COE varied from 0.14 mills/kWh to 3.92 mills/kWh. Meanwhile, the incremental cost of mercury control ranged from $3810/lb Hg removed to $166 000/lb Hg removed. 13 refs., 4 figs., 3 tabs.

Andrew P. Jones; Jeffrey W. Hoffmann; Dennis N. Smith; Thomas J. Feeley III; James T. Murphy [National Energy Technology Laboratory, Pittsburgh, PA (United States)

2007-02-15T23:59:59.000Z

393

Modern Records of Atmospheric Nitrous Oxide (N2O) and a 2000-year Ice-core  

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

Modern Records of Atmospheric Nitrous Oxide (N2O) and a 2000-year Ice-core Modern Records of Atmospheric Nitrous Oxide (N2O) and a 2000-year Ice-core Record from Law Dome, Antarctica Introduction This page provides an introduction and links to records of atmospheric nitrous oxide (N2O) over the last 2000 years, emphasizing large data bases each representing currently active stations. Records in recent decades (time period depending on location) have been obtained from samples of ambient-air at remote locations, which represent changing global atmospheric conditions rather than influences of local sources. The longer (2000-year) record is from the Law Dome ice core in Antarctica. The ice-core record has been merged with modern annual data from Cape Grim, Tasmania to provide a 2000-year time series of annual values. A spline function has been fit to the data to provide a continuous time series of

394

Federal Assistance Program Quarterly Project Progress Report. Geothermal Energy Program: Information Dissemination, Public Outreach, and Technical Analysis Activities. Reporting Period: January 1 - March 31, 2001 [Final report  

SciTech Connect

The final report of the accomplishments of the geothermal energy program: information dissemination, public outreach and technical analysis activities by the project team consisting of the Geo-Heat Center, Geothermal Resources Council, Geothermal Education Office, Geothermal Energy Association and the Washington State University Energy Program.

Lund, John W.

2002-03-22T23:59:59.000Z

395

CA Core Competency Worksheet August 2010  

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

CA Core Competency Worksheet August 2010 CA Core Competency Worksheet August 2010 1 DOE CYBER SECURITY EBK: CORE COMPETENCY TRAINING REQUIREMENTS Key Cyber Security Role: Certification Agent (CA) (Also referred to as Security Control Assessor) Role Definition: The CA is the individual responsible for assessing the management, operational, assurance, and technical security controls implemented on an information system via security testing and evaluation (ST&E) methods. This individual must be independent of system development, operation, and deficiency mitigation. Competency Area: Data Security Functional Requirement: Design Competency Definition: Refers to the application of the principles, policies, and procedures necessary to ensure the confidentiality, integrity, availability, and privacy of data in all forms of media (i.e., electronic

396

NEUTRONIC REACTOR FUEL ELEMENT AND CORE SYSTEM  

DOE Patents (OSTI)

This patent relates to neutronic reactors and in particular to an improved fuel element and a novel reactor core system for facilitating removal of contaminating fission products, as they are fermed, from association with the flssionable fuel, so as to mitigate the interferent effects of such fission products during reactor operation. The fuel elements are comprised of tubular members impervious to fluid and contatning on their interior surfaces a thin layer of fissionable material providing a central void. The core structure is comprised of a plurality of the tubular fuel elements arranged in parallel and a closed manifold connected to their ends. In the reactor the core structure is dispersed in a water moderator and coolant within a pressure vessel, and a means connected to said manifuld is provided for withdrawing and disposing of mobile fission product contamination from the interior of the feel tubes and manifold.

Moore, W.T.

1958-09-01T23:59:59.000Z

397

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

398

ACOUSTIC SIGNATURES OF THE HELIUM CORE FLASH  

SciTech Connect

All evolved stars with masses M {approx}< 2 M{sub Sun} undergo an initiating off-center helium core flash in their M{sub c} Almost-Equal-To 0.48 M{sub Sun} He core as they ascend the red giant branch (RGB). This off-center flash is the first of a few successive helium shell subflashes that remove the core electron degeneracy over 2 Myr, converting the object into a He-burning star. Though characterized by Thomas over 40 years ago, this core flash phase has yet to be observationally probed. Using the Modules for Experiments in Stellar Astrophysics (MESA) code, we show that red giant asteroseismology enabled by space-based photometry (i.e., Kepler and CoRoT) can probe these stars during the flash. The rapid ({approx}< 10{sup 5} yr) contraction of the red giant envelope after the initiating flash dramatically improves the coupling of the p-modes to the core g-modes, making the detection of l = 1 mixed modes possible for these 2 Myr. This duration implies that 1 in 35 stars near the red clump in the H-R diagram will be in their core flash phase. During this time, the star has a g-mode period spacing of {Delta}P{sub g} Almost-Equal-To 70-100 s, lower than the {Delta}P{sub g} Almost-Equal-To 250 s of He-burning stars in the red clump, but higher than the RGB stars at the same luminosity. This places them in an underpopulated part of the large frequency spacing ({Delta}{nu}) versus {Delta}P{sub g} diagram that should ease their identification among the thousands of observed red giants.

Bildsten, Lars; Paxton, Bill; Moore, Kevin; Macias, Phillip J. [Kavli Institute for Theoretical Physics and Department of Physics Kohn Hall, University of California, Santa Barbara, CA 93106 (United States)

2012-01-15T23:59:59.000Z

399

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

400

SECA Core Technology Program Seal Workshop  

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

SECA Core Technology Program Seal Workshop Workshop held at Hyatt Regency, San Antonio August 10, 2007 Workshop organized by: Dr. Ayyakkannu Manivannan, National Energy technology Laboratory Morgantown, WV Dr. Prabhakar Singh Pacific Northwest National Laboratory Richland, WA 1 2 Table of Content * Executive Summary * Meeting Agenda * Presentations * List of Attendees 3 Executive Summary SECA Core Technology Program (SECA CTP) led workshop on the topical area titled "SOFC seal: Technology, Challenges and Future Directions" was held on August 10, 2007 at Hyatt Regency, San Antonio, TX. The workshop was attended by scientists and engineers presently involved in the development, engineering, fabrication, and testing of

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


401

Apparatus for controlling nuclear core debris  

DOE Patents (OSTI)

Nuclear reactor apparatus for containing, cooling, and dispersing reactor debris assumed to flow from the core area in the unlikely event of an accident causing core meltdown. The apparatus includes a plurality of horizontally disposed vertically spaced plates, having depressions to contain debris in controlled amounts, and a plurality of holes therein which provide natural circulation cooling and a path for debris to continue flowing downward to the plate beneath. The uppermost plates may also include generally vertical sections which form annular-like flow areas which assist the natural circulation cooling.

Jones, Robert D. (Irwin, PA)

1978-01-01T23:59:59.000Z

402

Basic criticality relations for gas core design  

DOE Green Energy (OSTI)

Minimum critical fissile concentrations are calculated for U-233, U-235, Pu-239, and Am-242m mixed homogeneously with hydrogen at temperatures to 15,000K. Minimum critical masses of the same mixtures in a 1000 liter sphere are also calculated. It is shown that propellent efficiencies of a gas core fizzler engine using Am-242m as fuel would exceed those in a solid core engine as small as 1000L operating at 100 atmospheres pressure. The same would be true for Pu-239 and possibly U-233 at pressures of 1000 atm. or at larger volumes.

Tanner, J.E.

1992-05-22T23:59:59.000Z

403

Analysis  

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

Analysis Analysis of Short-Bunch Production with the APS Booster and a Bunch Compressor Michael Borland, AOD/OAG ∗ August 8, 2003 1 Abstract There is significant interest among x-ray scientists in short-pulse x-rays. The x-rays from the APS ring, although very bright, are produced by an electron bunch with an rms length of more than 30 ps. Typically, it is only a linear accelerator that can produce a very short bunch. An idea was brought to my attention by Glenn Decker that might allow us to produce a short bunch using the APS booster. This idea involves extracting the beam from the booster at 3 to 4 GeV, while it is still relatively short, then compressing it with a magnetic bunch compressor. In this note, we present a preliminary analysis of this idea, along with the related idea of using a nonequilibrium beam from the APS photoinjector. 2 Background We will begin with an examination of the ideal result

404

Reactor Core Assembly - HFIR Technical Parameters | ORNL Neutron Sciences  

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

Home › Facilities › HFIR › Reactor Core Assembly Home › Facilities › HFIR › Reactor Core Assembly Reactor Core Assembly The reactor core assembly is contained in an 8-ft (2.44-m)-diameter pressure vessel located in a pool of water. The top of the pressure vessel is 17 ft (5.18 m) below the pool surface, and the reactor horizontal mid-plane is 27.5 ft (8.38 m) below the pool surface. The control plate drive mechanisms are located in a subpile room beneath the pressure vessel. These features provide the necessary shielding for working above the reactor core and greatly facilitate access to the pressure vessel, core, and reflector regions. In-core irradiation and experiment locations (cross section at horizontal midplane) Reactor core assembly Reactor core assembly: (1) in-core irradiation and experiment locations,

405

Computational Analysis of a Pylon-Chevron Core Nozzle Interaction  

Science Conference Proceedings (OSTI)

In typical engine installations, the pylon of an engine creates a flow disturbance that interacts with the engine exhaust flow. This interaction of the pylon with the exhaust flow from a dual stream nozzle was studied computationally. The dual stream ...

Thomas R. H.; Kinzie K. W.; Pao S. Paul

2001-05-01T23:59:59.000Z

406

Multiscale analysis of the core nanotube in a nanocomposite system  

Science Conference Proceedings (OSTI)

Carbon nanotube reinforced polymer composites have novel properties that make them useful in a wide variety of applications and there has been numerous studies to predict the overall bulk properties of these nanocomposites. Theoretical studies to understand ... Keywords: Carbon nanotube, Interphase, Molecular dynamics, Nanocomposite

Vinu Unnikrishnan; J. N. Reddy

2012-02-01T23:59:59.000Z

407

Transient analysis of hydride fueled pressurized water reactor cores  

E-Print Network (OSTI)

This thesis contributes to the hydride nuclear fuel project led by U. C. Berkeley for which MIT is to perform the thermal hydraulic and economic analyses. A parametric study has been performed to determine the optimum ...

Trant, Jarrod Michael

2004-01-01T23:59:59.000Z

408

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

Open Energy Info (EERE)

sections, and studied by petrographic microscope, cathodoluminescence and scanning electron microscope (SEM) . References Augustus K. Armstrong, Jacques R. Renault, Robert L....

409

An Analysis of Core Networks among First-Generation Immigrants  

E-Print Network (OSTI)

of the Commonwealth of Puerto Rico and the Massachusettslegal relationships to the U.S. Since Puerto Rico is a U.S.commonwealth, migrants from Puerto Rico are U.S. citizens,

Osuji, Chinyere K.

2006-01-01T23:59:59.000Z

410

Core Holes At Steamboat Springs Area (Warpinski, Et Al., 2002) | Open  

Open Energy Info (EERE)

2) 2) Exploration Activity Details Location Steamboat Springs Area Exploration Technique Core Holes Activity Date Usefulness not indicated DOE-funding Unknown Notes Stratigraphic slim hole 24-33 was drilled in a lease area south of current production during March 2001. The well was continuously cored from 235 m to the total depth of 610 m. Several fracture zones were encountered with noticeably large fracture apertures and the maximum recorded temperature was comparable to nearby productive wells. A second well, slim hole 12-33, was drilled to a total depth of 297 m during April 2001. Continuous core was taken from 152 m to total depth. Numerous open fractures were also observed in this well and the maximum recorded temperature was similar to the 24-33 well.

411

GIZ-Thailand-National energy efficiency plan as a core element for an  

Open Energy Info (EERE)

Thailand-National energy efficiency plan as a core element for an Thailand-National energy efficiency plan as a core element for an activity- and evidence-based mitigation strategy Jump to: navigation, search Name GIZ-Thailand-National energy efficiency plan as a core element for an activity- and evidence-based mitigation strategy Agency/Company /Organization Deutsche Gesellschaft für Internationale Zusammenarbeit (GIZ) GmbH Sector Climate Focus Area Renewable Energy, Energy Efficiency Topics Low emission development planning, -LEDS, -NAMA, Technology characterizations Website http://www.gtz.de/en/themen/28 Program End 2015 Country Thailand South-Eastern Asia References Deutsche Gesellschaft für Internationale Zusammenarbeit (GIZ) GmbH[1] Program Overview The project will support the formulation and implementation of a national

412

The Sinking of Warm-Core Rings  

Science Conference Proceedings (OSTI)

Intense cooling of a warm-core ring or warming of the fluids surrounding a ring can increase the density of that ring relative to the surrounding fluids. This increase in density can cause the ring to sink under the surrounding fluids. A simple ...

Rick Chapman; Doron Nof

1988-04-01T23:59:59.000Z

413

Alternative Transport Architecture for Core ATM Networks  

Science Conference Proceedings (OSTI)

In order to remain competitive in an increasingly aggressive market-place, it is essential that network operators deliver cost-effective, resilient bulk transport. This will enable the unit costs of circuit delivery in the core network to be reduced, ...

P. A. Veitch

1998-07-01T23:59:59.000Z

414

Configuration adjustment potential of the Very High Temperature Reactor prismatic cores with advanced actinide fuels  

E-Print Network (OSTI)

Minor actinides represent the long-term radiotoxicity of nuclear wastes. As one of their potential incineration options, partitioning and transmutation in fission reactors are seriously considered worldwide. If implemented, these technologies could also be a source of nuclear fuel materials required for sustainability of nuclear energy. The objective of this research was to evaluate performance characteristics of Very High Temperature Reactors (VHTRs) and their variations due to configuration adjustments targeting achievability of spectral variations. The development of realistic whole-core 3D VHTR models and their benchmarking against experimental data was an inherent part of the research effort. Although the performance analysis was primarily focused on prismatic core configurations, 3D pebble-bed core models were also created and analyzed. The whole-core 3D models representing the prismatic block and pebble-bed cores were created for use with the SCALE 5.0 code system. Each of the models required the Dancoff correction factor to be externally calculated. The code system DANCOFF-MCThe whole-core/system 3D models with multi-heterogeneity treatments were validated by the benchmark problems. Obtained results are in agreement with the available High Temperature Test Reactor data. Preliminary analyses of actinide-fueled VHTR configurations have indicated promising performance characteristics. Utilization of minor actinides as a fuel component would facilitate development of new fuel cycles and support sustainability of a fuel source for nuclear energy assuring future operation of Generation IV nuclear energy systems. was utilized to perform the Dancoff factor calculations.

Ames, David E, II

2006-08-01T23:59:59.000Z

415

Characteristics of the WWR-K test core and the LEU LTAS to be placed in the central experimental beryllium device.  

SciTech Connect

In 2010 life test of three LEU (19.7%) lead test assemblies (LTA) is expected in the existing WWR-K reactor core with regular WWR-C-type fuel assemblies and a smaller core with a beryllium insert. Preliminary analysis of test safety is to be carried out. It implies reconstruction of the reactor core history for last three years, including burnup calculation for each regular fuel assembly (FA), as well as calculation of characteristics of the test core. For the planned configuration of the test core a number of characteristics have been calculated. The obtained data will be used as input for calculations on LTA test core steady-state thermal hydraulics and on transient analysis.

Arinkin, F.; Chakrov, P.; Chekushina, L.; Gizatulin,, Sh.; Koltochnik, S.; Hanan, N.; Garner, P.; Nuclear Engineering Division; Kazakhstan Ministry of Energy and Mineral Resources

2010-03-01T23:59:59.000Z

416

An Enhanced In-Vessel Core Catcher for Improving In-Vessel Retention Margins  

SciTech Connect

In-vessel retention (IVR) of core melt that may relocate to the lower head of a reactor vessel is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for several advanced light water reactors. A U.S.-Korean International Nuclear Energy Research Initiative project has been initiated to explore design enhancements that could increase the margin for IVR for advanced reactors with higher power levels [up to 1500 MW(electric)]. As part of this effort, an enhanced in-vessel core catcher is being designed and evaluated. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary). The first is a base material that has the capability to support and contain the mass of core materials that may relocate during a severe accident; the second is an oxide coating on top of the base material, which resists interactions with high-temperature core materials; and the third is an optional coating on the bottom side of the base material to protect it from oxidation during the lifetime of the reactor. This paper summarizes results from the invessel core catcher design and evaluation efforts, focusing on recently obtained results from materials interaction tests and prototypic testing activities.

Joy L. Rempe

2005-11-01T23:59:59.000Z

417

Development of an Enhanced Core Catcher for Improving In-Vessel Retention Margins  

Science Conference Proceedings (OSTI)

In-vessel retention (IVR) of core melt that may relocate to the lower head of a reactor vessel is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for several advanced light water reactors. A U.S.-Korean International Nuclear Energy Research Initiative project has been initiated to explore design enhancements that could increase the margin for IVR for advanced reactors with higher power levels [up to 1500 MW(electric)]. As part of this effort, an enhanced in-vessel core catcher is being designed and evaluated. To reduce cost and simplify manufacture and installation, this new core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. If needed, the core catcher can be manufactured with holes to accommodate lower head penetrations. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary). The first is a base material that has the capability to support and contain the mass of core materials that may relocate during a severe accident; the second is an oxide coating on top of the base material, which resists interactions with high-temperature core materials; and the third is an optional coating on the bottom side of the base material to protect it from oxidation during the lifetime of the reactor. This paper summarizes results from the in-vessel core catcher design and evaluation efforts, focusing on recently obtained results from materials interaction tests and prototypic testing activities.

Rempe, J.L. [Idaho National Engineering and Environmental Laboratory (United States); Condie, K.G. [Idaho National Engineering and Environmental Laboratory (United States); Knudson, D.L. [Idaho National Engineering and Environmental Laboratory (United States); Suh, K.Y. [Seoul National University (Korea, Republic of); Cheung, F.B. [The Pennsylvania State University (United States); Kim, S.B. [Korea Atomic Energy Research Institute (Korea, Republic of)

2005-11-15T23:59:59.000Z

418

Neutron-induced prompt gamma activation analysis (PGAA) of metalsand non-metals in ocean floor geothermal vent-generated samples  

DOE Green Energy (OSTI)

Neutron-induced prompt gamma activation analysis (PGAA) hasbeen used to analyze ocean floor geothermal vent-generated samples thatare composed of mixed metal sulfides, silicates, and aluminosilicates.The modern application of the PGAA technique is discussed, and elementalanalytical results are given for 25 elements observed in the samples. Theelemental analysis of the samples is consistent with the expectedmineralogical compositions, and very consistent results are obtained forcomparable samples. Special sensitivity to trace quantities of hydrogen,boron, cadmium, dysprosium, gadolinium, and samarium isdiscussed.

Perry, D.L.; Firestone, R.B.; Molnar, G.L.; Revay, Zs.; Kasztovszky, Zs.; Gatti, R.C.; Wilde, P.

2002-12-05T23:59:59.000Z

419

Coring unconsolidated sands in the Gulf of Mexico  

SciTech Connect

Diamant Board Stratabit has achieved coring recovery rates in soft, unconsolidated formations as high as 99 percent. These rates are achieved using conventional coring equipment in a special configuration to minimize frictional resistance to the core as it passes through the bit and core catcher assembly and enters the inner barrel. This paper describes DBS's coring experience with its Maximum Core Protection System, which has been used at depths from 3000 ft to below 20,000 ft and in deviated holes up to 57 degrees. In the Gulf of Mexico, the system cored over 5800 ft from Matagorda Island to Charlotte Harbor, with an overall recovery rate of 93 percent. In most applications, the hole size dictates the core barrel and core size. Through 9 5/8-in. casing with an 8 1/2-in. by 4-in. core bit, the 6 3/4-in. by 4-in. by 30-ft conventional core barrel will be used with a Fibertube inner barrel to replace the steel inner barrel, allowing a full 4-in. core to be cut. In smaller hole sizes, other equipment with the Maximum Core Protection System will be used. With a top drive unit or long Kelly, a 45-ft or 60-ft barrel may be used. Many times an unconsolidated formation will not support more than 30 ft of core, therefore 30-ft barrels are normally used.

Wilcox, J.

1988-09-01T23:59:59.000Z

420

Heatup of the TMI-2 (Three Mile Island Unit 2) lower head during core relocation  

SciTech Connect

According to current perceptions of the Three Mile Island Unit 2 (TMI-2) accident, corium largely relocated into the reactor vessel lower head at {approximately}224 min into the accident. Defueling examinations have revealed that the corium relocated from the molten core region to the lower head predominantly by way of drainage through the core former region (CFR) located between the vertical baffle plates immediately surrounding the fuel assemblies and the core barrel. An analysis has been carried out to assess the heatup of the reactor vessel lower head during the core relocation event, particularly the potential for a melting attack on the lower head wall and the in-core instrument nozzle penetration weldments. The analysis employed the THIRMAL computer code developed at Argonne National Laboratory (ANL) to predict the breakup and quenching or corium jets under film boiling conditions as well as the size distributions and quenching of the resultant molten droplets. The transient heatup and ablation of the vessel wall and penetration weldments due to impinging corium jets was calculated using the MISTI computer code.

Wang, S.K.; Sienicki, J.J.; Spencer, B.W. (Argonne National Laboratory, IL (USA))

1989-11-01T23:59:59.000Z

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421

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

422

The MU Science Education Center (MUSEC) has at the core of its mission (see back  

E-Print Network (OSTI)

to be active participants in continuing the reform of K-16 science education. (GRADUATE EDUCATION) G O A L A RThe MU Science Education Center (MUSEC) has at the core of its mission (see back cover) to improve science teaching and learning for all. This annual report cele- brates the successes of the MU Science

Noble, James S.

423

Core-Protected Platinum Monolayer Shell High-Stability Electrocatalysts for Fuel-Cell Cathodes  

Science Conference Proceedings (OSTI)

Platinum monolayers can act as shells for palladium nanoparticles to lead to electrocatalysts with high activities and an ultralow platinum content, but high platinum utilization. The stability derives from the core protecting the shell from dissolution. In fuel-cell tests, no loss of platinum was observed in 200,000 potential cycles, whereas loss of palladium was significant.

K Sasaki; H Naohara; Y Cai; Y Choi; P Liu; M Vukmirovic; J Wang; R Adzic

2011-12-31T23:59:59.000Z

424

Design/Operations review of core sampling trucks and associated equipment  

SciTech Connect

A systematic review of the design and operations of the core sampling trucks was commissioned by Characterization Equipment Engineering of the Westinghouse Hanford Company in October 1995. The review team reviewed the design documents, specifications, operating procedure, training manuals and safety analysis reports. The review process, findings and corrective actions are summarized in this supporting document.

Shrivastava, H.P.

1996-03-11T23:59:59.000Z

425

Collapse and Fragmentation of Molecular Cloud Cores. X. Magnetic Braking of Prolate and Oblate Cores  

E-Print Network (OSTI)

The collapse and fragmentation of initially prolate and oblate, magnetic molecular clouds is calculated in three dimensions with a gravitational, radiative hydrodynamics code. The code includes magnetic field effects in an approximate manner: magnetic pressure, tension, braking, and ambipolar diffusion are all modelled. The parameters varied for both the initially prolate and oblate clouds are the initial degree of central concentration of the radial density profile, the initial angular velocity, and the efficiency of magnetic braking (represented by a factor $f_{mb} = 10^{-4}$ or $10^{-3}$). The oblate cores all collapse to form rings that might be susceptible to fragmentation into multiple systems. The outcome of the collapse of the prolate cores depends strongly on the initial density profile. Prolate cores with central densities 20 times higher than their boundary densities collapse and fragment into binary or quadruple systems, whereas cores with central densities 100 times higher collapse to form single...

Boss, Alan P

2009-01-01T23:59:59.000Z

426

Sandia Site Office Assessment of Activity-Levell Work Planning...  

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

Center (FMOC) and Technical Area (TA) V and review of work activities at the Auxiliary Hot Cell Facility (AHCF), the Annular Core Research Reactor (ACRR), and the Gamma...

427

Assessment of CRBR core disruptive accident energetics  

Science Conference Proceedings (OSTI)

The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly.

Theofanous, T.G.; Bell, C.R.

1984-03-01T23:59:59.000Z

428

Mox fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion. characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-05-15T23:59:59.000Z

429

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly. 38 figs.

Kantrowitz, M.L.; Rosenstein, R.G.

1998-10-13T23:59:59.000Z

430

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

1998-01-01T23:59:59.000Z

431

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-07-17T23:59:59.000Z

432

Next Generation CANDU Core Physics Innovations  

SciTech Connect

NG CANDU is the 'Next Generation' CANDU{sup R} reactor, aimed at producing electrical power at a capital cost significantly less than that of the current reactor designs. A key element of cost reduction is the use of H{sub 2}O as coolant and Slightly Enriched Uranium fuel in a tight D{sub 2}O-moderated lattice. The innovations in the CANDU core physics result in substantial improvements in economics as well as significant enhancements in reactor licensability, controllability, and waste reduction. The full-core coolant-void reactivity in NG CANDU is about -3 mk. Power coefficient is substantially negative. Fuel burnup is about three times the current natural-uranium burnup. (authors)

Chan, P.S.W.; Hopwood, J.M.; Love, J.W. [Atomic Energy of Canada Ltd., Ontario (Canada)

2002-07-01T23:59:59.000Z

433

Preservation under Substructures modulo Bounded Cores  

E-Print Network (OSTI)

We investigate a model-theoretic property that generalizes the classical notion of "preservation under substructures". We call this property \\emph{preservation under substructures modulo bounded cores}, and present a syntactic characterization via $\\Sigma_2^0$ sentences for properties of arbitrary structures definable by FO sentences. Towards a sharper characterization, we conjecture that the count of existential quantifiers in the $\\Sigma_2^0$ sentence equals the size of the smallest bounded core. While we do not have a proof of the conjecture yet, we show that it holds for special fragments of FO and also over special classes of structures. We present a (not FO-definable) class of finite structures for which the conjecture fails, but for which the classical {\\L}o\\'s-Tarski preservation theorem holds. As a fallout of our studies, we have obtained combinatorial proofs of the {\\L}o\\'s-Tarski theorem for some of the aforementioned cases.

Sankaran, Abhisekh; Madan, Vivek; Kamath, Pritish; Chakraborty, Supratik

2012-01-01T23:59:59.000Z

434

Improved cryogenic coring device for sampling wetland soils  

SciTech Connect

This paper is the third in a series on the design and construction (Knaus 1986) and improvements (Knaus and Cahoon 1990) of a cryogenic soil-coring device (cryocorer). Freezing wetland soils in place during sampling eliminates compaction, dewatering, and loss of flocculent material at the water-sediment interface. The cryocorer is suitable for sampling soils of emergent marsh and mangrove forests as well as shallow water bottoms, although it has been used primarily for the former. A small-diameter frozen soil core minimizes disruption of the surface, can be evaluated immediately for overall quality, and can be used to measure soil profiles and subsample for further analysis. The cryocorer continues to be used in studies of wetland accretion and soil bulk density throughout the US. Concomitant with the increased use of the device, improvements in cryocorer design and application have occurred. Reported here are improvements in design that have been made since 1992 with references to wetland research in which the cryocorer has been used extensively.

Cahoon, D.R.; Lynch, J.C. [National Biological Service, Lafayette, LA (United States); Knaus, R.M. [Louisiana State Univ., Baton Rouge, LA (United States)

1996-09-01T23:59:59.000Z

435

PRESSURIZED WATER REACTOR CORE WITH PLUTONIUM BURNUP  

DOE Patents (OSTI)

A pressurized water reactor is described having a core containing Pu/sup 240/ in which the effective microscopic neutronabsorption cross section of Pu/sup 240/ in unconverted condition decreases as the time of operation of the reactor increases, in order to compensate for loss of reactivity resulting from fission product buildup during reactor operation. This means serves to improve the efficiency of the reactor operation by reducing power losses resulting from control rods and burnable poisons. (AEC)

Puechl, K.H.

1963-09-24T23:59:59.000Z

436

Nuclear reactor core and fuel element therefor  

SciTech Connect

This patent describes a nuclear reactor core. This core consists of vertical columns of disengageable fuel elements stacked one atop another. These columns are arranged in side-by-side relationship to form a substantially continuous horizontal array. Each of the fuel elements include a block of refractory material having relatively good thermal conductivity and neutron moderating characteristics. The block has a pair of parallel flat top and bottom end faces and sides which are substantially prependicular to the end faces. The sides of each block is aligned vertically within a vertical column, with the sides of vertically adjacent blocks. Each of the blocks contains fuel chambers, including outer rows containing only fuel chambers along the sides of the block have nuclear fuel material disposed in them. The blocks also contain vertical coolant holes which are located inside the fuel chambers in the outer rows and the fuel chambers which are not located in the outer rows with the fuel chambers and which extend axially completely through from end face to end face and form continuous vertical intracolumn coolant passageways in the reactor core. The blocks have vertical grooves extending along the sides of the blocks form interblock channels which align in groups to form continuous vertical intercolumn coolant passsageways in the reactor core. The blocks are in the form of a regular hexagonal prism with each side of the block having vertical gooves defining one half of one of the coolant interblock channels, six corner edges on the blocks have vertical groves defining one-third of an interblock channel, the vertical sides of the blocks defining planar vertical surfaces.

Fortescue, P.

1986-02-11T23:59:59.000Z

437

Independent assessment of the natural-circulation capability of the heterogeneous-core CRBR  

SciTech Connect

This summary describes results of an independent assessment of the natural circulation capability of the heterogeneous core Clinch River Breeder Reactor Plant (CRBRP) following station blackout. The primary tool for this analysis is the Super System Code (SSC) which was developed at Brookhaven National Laboratory. Comparisons are made between SSC and the project's analysis, with emphasis on the effect of inter-assembly flow redistribution.

Guppy, J.G.; Horak, W.C.; Van Tuyle, G.J.

1983-01-01T23:59:59.000Z

438

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

DOE Patents (OSTI)

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

Day, Clifford K. (Richland, WA); Stringer, James L. (Richland, WA)

1977-01-01T23:59:59.000Z

439

Precursors to potential severe core damage accidents: 1992, A status report. Volume 17, Main report and Appendix A  

SciTech Connect

Twenty-seven operational events with conditional probabilities of subsequent severe core damage of 1.0 {times} 10E-06 or higher occurring at commercial light-water reactors during 1992 are considered to be precursors to potential core damage. These are described along with associated significance estimates, categorization, and subsequent analyses. The report discusses (1) the general rationale for this study, (2) the selection and documentation of events as precursors, (3) the estimation and use of conditional probabilities of subsequent severe core damage to rank precursor events, and (4) the plant models used in the analysis process.

Cox, D.F.; Cletcher, J.W.; Copinger, D.A.; Cross-Dial, A.E.; Morris, R.H.; Vanden Heuvel, L.N. [Oak Ridge National Lab., TN (United States); Dolan, B.W.; Jansen, J.M.; Minarick, J.W. [Science Applications International Corp., Oak Ridge, TN (United States); Lau, W.; Salyer, W.D. [Reliability and Performance Associates (United States)

1993-12-01T23:59:59.000Z

440

Comparison of a NuScale SMR conceptual core design using CASMO5/simulate5 and MCNP5  

Science Conference Proceedings (OSTI)

A key issue during the initial start-ups of new Small Modular Reactors (SMRs) is the lack of operational data for reactor model validation. To help better understand the accuracy of the reactor analysis codes CASMO5 and SIMULATE5, higher order comparisons to MCNP5 have been performed. These comparisons are for an initial core conceptual design of the NuScale reactor. The data have been evaluated at Hot Zero Power (HZP) conditions. Comparisons of core reactivity, fuel temperature coefficient (FTC), and moderator temperature coefficients (MTC) have been performed. Comparison results show good agreement between CASMO5/SIMULATE5 and MCNP5 for the conceptual initial core design. (authors)

Haugh, B. [Studsvik Scandpower Inc., 1015 Ashes Drive, Wilmington, NC 28405 (United States); Mohamed, A. [NuScale Power Inc., 1100 NE Circle Blvd, Corvallis, OR 97330 (United States)

2012-07-01T23:59:59.000Z

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