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


1

HTTF Core Stress Analysis  

SciTech Connect (OSTI)

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

2

Multi-core Performance Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource ProgramModification andinterface1JUN 2 5core Performance Analysis

3

Multi-core Performance Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource ProgramModification andinterface1JUN 2 5core Performance

4

Core analysis workstation development and verification  

SciTech Connect (OSTI)

An engineering workstation utilizing a three-dimensional reactor simulator along with a series of auxiliary programs has been developed for use in predicting core reactivity and power distributions. This workstation can be used by both core analysis and core operations personnel. Expected applications are power distribution analyses, technical specification limit verification, and various types of reactivity analyses. Reactor operations personnel can quickly simulate load follow or other reactor maneuvers and, through the interactive graphics capability of the personal computer, the reactor responses, such as power distribution and control rod position, can be displayed and understood by operations personnel.

Mays, C.W.; Kochendarfer, R.A.; Mays, B.E.

1987-01-01T23:59:59.000Z

5

Overview on Hydrate Coring, Handling and Analysis  

SciTech Connect (OSTI)

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

6

CFD Analysis of Core Bypass Phenomena  

SciTech Connect (OSTI)

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

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

2010-03-01T23:59:59.000Z

7

CFD Analysis of Core Bypass Phenomena  

SciTech Connect (OSTI)

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

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

2009-11-01T23:59:59.000Z

8

Category:Core Analysis | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin: EnergyBostonFacilityCascade SierraStatus Status ofCore Analysis page? For

9

Geologic analysis of Devonian Shale cores  

SciTech Connect (OSTI)

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

none,

1982-02-01T23:59:59.000Z

10

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

Open Energy Info (EERE)

Details Location Valles Caldera - Sulphur Springs Geothermal Area Exploration Technique Core Analysis Activity Date - 1995 Usefulness could be useful with more improvements...

11

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

Open Energy Info (EERE)

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

12

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

Open Energy Info (EERE)

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

13

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

Open Energy Info (EERE)

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

14

Rollover analysis of rotary mode core sampler truck No. 2  

SciTech Connect (OSTI)

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

Ziada, H.H.

1994-11-08T23:59:59.000Z

15

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

Open Energy Info (EERE)

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

16

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

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

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

17

Analysis of tru-fueled vhtr prismatic core performance domains  

E-Print Network [OSTI]

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

Lewis, Tom Goslee

2009-05-15T23:59:59.000Z

18

SAS4A LMFBR whole core accident analysis code  

SciTech Connect (OSTI)

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

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

1985-01-01T23:59:59.000Z

19

Neutronic analysis of pebble-bed cores with transuranics  

E-Print Network [OSTI]

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

Pritchard, Megan Leigh

2009-05-15T23:59:59.000Z

20

Design and analysis of PCRV core cavity closure  

SciTech Connect (OSTI)

Design requirements and considerations for a core cavity closure which led to the choice of a concrete closure with a toggle hold-down as the design for the Gas-Cooled Fast Breeder Reactor (GCFR) plant are discussed. A procedure for preliminary stress analysis of the closure by means of a three-dimensional finite element method is described. A limited parametric study using this procedure indicates the adequacy of the present closure design and the significance of radial compression developed as a result of inclined support reaction.

Lee, T.T.; Schwartz, A.A.; Koopman, D.C.A.

1980-05-01T23:59:59.000Z

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

Application of Covariances to Fast Reactor Core Analysis  

SciTech Connect (OSTI)

In the present paper, the current status of covariance applications to fast reactor analysis and design is summarized with actual examples. The covariance applications are classified into three fields. First, covariances are used to quantify the uncertainty of nuclear core parameters such as criticality, control rod worth, reaction rate ratio, power distribution, sodium void reactivity, etc. The special features of the Japanese case are to include both the burnup-related parameters such as burnup reactivity loss or fuel composition changes, and the temperature-related parameter, that is, the Doppler reactivity. Second, covariances are used to select the important nuclides, reactions and energy ranges which are dominant to the uncertainty of core parameters, and to give nuclear scientists recommendations to improve the accuracy of the data. Finally, covariances are used to improve the accuracy of core design values by adopting the integral data such as the critical experiments and the power reactor operation data. The way toward improvement is classified into the conventional E/C (Experiment/Calculation) bias method and the more comprehensive cross section adjustment based on the Bayesian theorem and the generalized least square method. In Japan, an adjusted group-constant set, ADJ2000R, is now being used in the design work for future fast reactors.

Ishikawa, M. [Japan Atomic Energy Agency (JAEA), O-arai, Ibaraki, 311-1393 (Japan)], E-mail: ishikawa.makoto@jaea.go.jp

2008-12-15T23:59:59.000Z

22

Criticality safety analysis on fissile materials in Fukushima reactor cores  

SciTech Connect (OSTI)

The present study focuses on the criticality analysis for geological disposal of damaged fuels from Fukushima reactor cores. Starting from the basic understanding of behaviors of plutonium and uranium, a scenario sequence for criticality event is considered. Due to the different mobility of plutonium and uranium in geological formations, the criticality safety is considered in two parts: (1) near-field plutonium system and (2) far-field low enriched uranium (LEU) system. For the near-field plutonium system, a mathematical analysis for pure-solute transport was given, assuming a particular buffer material and waste form configuration. With the transport and decay of plutonium accounted, the critical mass of plutonium was compared with the initial load of a single canister. Our calculation leads us to the conclusion that our system with the initial loading being the average mass of plutonium in an assembly just before the accident is very unlikely to become critical over time. For the far-field LEU system, due to the uncertainties in the geological and geochemical conditions, calculations were made in a parametric space that covers the variation of material compositions and different geometries. Results show that the LEU system could not remain sub-critical within the entire parameter space assumed, although in the iron-rich rock, the neutron multiplicity is significantly reduced.

Liu, Xudong; Lemaitre-Xavier, E.; Ahn, Joonhong [Department of Nuclear Engineering, University of California, Berkeley, Berkeley, CA 94720 (United States); Hirano, Fumio [Japan Atomic Energy Agency, Geological Isolation Research and Development Directorate, Tokai-mura, Ibaraki 319-1194 (Japan)

2013-07-01T23:59:59.000Z

23

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

Open Energy Info (EERE)

Blue Mountain Geothermal Area (U.S. Geological Survey, 2009) Exploration Activity Details Location Blue Mountain Geothermal Area Exploration Technique Core Analysis Activity Date...

24

100-KE REACTOR CORE REMOVAL PROJECT ALTERNATIVE ANALYSIS WORKSHOP REPORT  

SciTech Connect (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

25

ANALYSIS OF THE SALT FEED TANK CORE SAMPLE  

SciTech Connect (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

26

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

SciTech Connect (OSTI)

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

Sattler, A.R.

1989-04-01T23:59:59.000Z

27

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

SciTech Connect (OSTI)

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

28

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

E-Print Network [OSTI]

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

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

2003-01-01T23:59:59.000Z

29

CO2 & global temperature: Analysis of ice core and marine sediment data in  

E-Print Network [OSTI]

CO2 & global temperature: Analysis of ice core and marine sediment data in combination with modeling of marine reservoir ages Gerrit Lohmann & Martin Butzin #12;Deglaciation CO2 vs. global temperature Ice cores: Temperature leads CO2 People (mainly outside the scientific comunity) use

Sengun, Mehmet Haluk

30

Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake, Madagascar)  

E-Print Network [OSTI]

Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake, Université d'Orléans, BP 6759, 45067 Orléans Cedex 2, France Abstract Seven samples from a 1 m long peat core targets because of their dominant or even exclusive OM content, peat deposits have received relatively

Boyer, Edmond

31

Model for LMFBR core transient analysis in real time  

SciTech Connect (OSTI)

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

Tzanos, C.P.

1986-01-01T23:59:59.000Z

32

Model for LMFBR core transient analysis in real-time  

SciTech Connect (OSTI)

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

Tzanos, C.P.

1986-01-01T23:59:59.000Z

33

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

34

Application of an artificial neural network to reactor core analysis  

SciTech Connect (OSTI)

To analyze three-dimensional reactor core behaviors, the finite difference or the finite element method have generally been used. Nodal method is adopted as another tool for analyzing transient core characteristics. These methods, however, require much calculation time to solve very complicated iterations for better convergence. Especially when the transient states are to be predicted, none of these methods can meet the requirements within the time span in which the operator can react. To overcome these difficulties, a new analytic model based on the artificial neural networks (ANNs) is suggested. Because trained ANNs are capable of modeling the input/output relationships of a nonlinear system without complex analogy, they are able to map the power distributions and calculate the eigenvalue corresponding to the core conditions in a short time and utilize the previous results by updating the weights of inter-connection between input and output patterns. To confirm the accuracy and capability, daily load-follow operation in a pressurized water reactor (PWR) is simulated using the new analytic model.

Seung Hwan Seong; Un Chul Lee [Seoul National Univ. (Korea, Republic of)

1995-12-31T23:59:59.000Z

35

Experimental ferrite core circuit analysis and design applied to an analog/digital converter  

E-Print Network [OSTI]

EXPKRflIENTAL FERRITE CORE CIRCUIT ANALYSIS A/4i) CESIGN APPLI ED' TO AN ANALOG+I QITAL -CCWERTER I I 'O' Thaaka RCSERT, NI. LL'I AN HQQAKS:-. , ";, , '. . :. . '. -:. '"":, , ':-. ', . -' ". ' t, . I I I' I, ' . Sobalttad, ta tb ~ Qra... , Na'fir. Sabjaat& ' Eiaktr leal EnCInaaring . EXPERIIIENTAL FERRITE CORE CIRCUIT ANALYSIS AND DESIGN APPLIED TO 'AN AMALGG/DIGITAL CONVERTER f 1 A, . Thea I'a t ROBERT Wl LI. I Al'Jl. HUGHES (Goober, ) ' (Me@bar) ' A'yprived . a'o . . to a4...

Hughes, Robert William

1965-01-01T23:59:59.000Z

36

Core image analysis of matrix porosity in The Geysers reservoir  

SciTech Connect (OSTI)

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

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

1993-01-28T23:59:59.000Z

37

Stability analysis of a nonlinear coupled-core reactor control system  

SciTech Connect (OSTI)

In this paper, stability-equation method is applied to the analysis of a large coupled-core reactor control system having multiple nonlinearities and adjustable parameters. The characteristics of the limit-cycle and the asymptotically stable regions can be easily defined in a parameter plane. A numerical example is given and comparisons with other methods in current literature are made.

Tsay, T.S.; Han, K.W.

1987-12-01T23:59:59.000Z

38

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

SciTech Connect (OSTI)

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

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

1981-01-01T23:59:59.000Z

39

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

SciTech Connect (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

40

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

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

The Neutronics Design and Analysis of a 200-MW(electric) Simplified Boiling Water Reactor Core  

SciTech Connect (OSTI)

A 200-MW(electric) simplified boiling water reactor (SBWR) was designed and analyzed under sponsorship of the U.S. Department of Energy Nuclear Energy Research Initiative program. The compact size of a 200-MW(electric) reactor makes it attractive for countries with a less well developed engineering infrastructure, as well as for developed countries seeking to tailor generation capacity more closely to the growth of their electricity demand. The 200-MW(electric) core design reported here is based on the 600-MW(electric) General Electric SBWR core, which was first analyzed in the work performed here in order to qualify the computer codes used in the analysis. Cross sections for the 8 x 8 fuel assembly design were generated with the HELIOS lattice physics code, and core simulation was performed with the U.S. Nuclear Regulatory Commission codes RELAP5/PARCS. In order to predict the critical heat flux, the Hench-Gillis correlation was implemented in the RELAP5 code. An equilibrium cycle was designed for the 200-MW(electric) core, which provided a cycle length of more than 2 yr and satisfied the minimum critical power ratio throughout the core life.

Tinkler, Daniel R.; Downar, Thomas J. [Purdue University (United States)

2003-06-15T23:59:59.000Z

42

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

SciTech Connect (OSTI)

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

43

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

SciTech Connect (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

44

Safety analysis for operating the Annular Core Research Reactor with Cintichem-type targets installed in the central region of the core  

SciTech Connect (OSTI)

Production of the molybdenum-99 isotope at the Annular Core Research Reactor requires highly enriched, uranium oxide loaded targets to be irradiated for several days in the high neutron-flux region of the core. This report presents the safety analysis for the irradiation of up to seven Cintichem-type targets in the central region of the core and compares the results to the Annular Core Research Reactor Safety Analysis Report. A 19 target grid configuration is presented that allows one to seven targets to be irradiated, with the remainder of the grid locations filled with aluminum ''void'' targets. Analyses of reactor, neutronic, thermal hydraulics, and heat transfer calculations are presented. Steady-state operation and accident scenarios are analyzed with the conclusion that the reactor can be operated safely with seven targets in the grid, and no additional risk to the public.

PARMA JR.,EDWARD J.

2000-01-01T23:59:59.000Z

45

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

E-Print Network [OSTI]

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

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

2015-01-01T23:59:59.000Z

46

Analysis of volume distribution of power loss in ferrite cores M. LoBue, V. Loyau, and F. Mazaleyrat  

E-Print Network [OSTI]

Analysis of volume distribution of power loss in ferrite cores M. LoBue, V. Loyau, and F the section of ferrite cores under AC excitation. The technique is based on two distinct calorimetric methods the procedure to an industrial sample of Mn-Zn ferrite under controlled sinusoidal excitation with a peak

Boyer, Edmond

47

Determination of power distribution in the VVER-440 core on the basis of data from in-core monitors by means of a metric analysis  

SciTech Connect (OSTI)

Problems associated with determining the power distribution in the VVER-440 core on the basis of a neutron-physics calculation and data from in-core monitors are considered. A new mathematical scheme is proposed for this on the basis of a metric analysis. In relation to the existing mathematical schemes, the scheme in question improves the accuracy and reliability of the resulting power distribution.

Kryanev, A. V.; Udumyan, D. K. [National Research Nuclear University “MEPHI,” (Russian Federation); Kurchenkov, A. Yu., E-mail: s327@vver.kiae.ru; Gagarinskiy, A. A. [National Research Center Kurchatov Institute (Russian Federation)

2014-12-15T23:59:59.000Z

48

Analysis of MSE Cores Tuba City, Arizona, Site | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergy Cooperation |South42.2 (April 2012) 1 DocumentationAnalysis of Crossover PointsMSE Cores

49

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

50

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

SciTech Connect (OSTI)

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

51

Thermal hydraulic method for whole core design analysis of an HTGR  

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

52

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

SciTech Connect (OSTI)

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

CONNER, J.M.

1998-10-09T23:59:59.000Z

53

Near Real-time Data Analysis of Core-Collapse Supernova Simulations With Bellerophon  

SciTech Connect (OSTI)

We present an overview of a software system, Bellerophon, built to support a production-level HPC application called CHIMERA, which simulates core-collapse supernova events at the petascale. Developed over the last four years, Bellerophon enables CHIMERA s geographically dispersed team of collaborators to perform data analysis in near real-time. Its n-tier architecture provides an encapsulated, end-to-end software solution that enables the CHIMERA team to quickly and easily access highly customizable animated and static views of results from anywhere in the world via a web-deliverable, cross-platform desktop application. In addition, Bellerophon addresses software engineering tasks for the CHIMERA team by providing an automated mechanism for performing regression testing on a variety of supercomputing platforms. Elements of the team s workflow management needs are met with software tools that dynamically generate code repository statistics, access important online resources, and monitor the current status of several supercomputing resources.

Lingerfelt, Eric J [ORNL] [ORNL; Messer, Bronson [ORNL] [ORNL; Desai, Sharvari S [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK); Holt, Chastity A [Appalachian State University] [Appalachian State University; Lentz, Eric J [University of Tennessee, Knoxville (UTK)] [University of Tennessee, Knoxville (UTK)

2014-01-01T23:59:59.000Z

54

Analysis on fuel breeding capability of FBR core region based on minor actinide recycling doping  

SciTech Connect (OSTI)

Nuclear fuel breeding based on the capability of fuel conversion capability can be achieved by conversion ratio of some fertile materials into fissile materials during nuclear reaction processes such as main fissile materials of U-233, U-235, Pu-239 and Pu-241 and for fertile materials of Th-232, U-238, and Pu-240 as well as Pu-238. Minor actinide (MA) loading option which consists of neptunium, americium and curium will gives some additional contribution from converted MA into plutonium such as conversion Np-237 into Pu-238 and it's produced Pu-238 converts to Pu-239 via neutron capture. Increasing composition of Pu-238 can be used to produce fissile material of Pu-239 as additional contribution. Trans-uranium (TRU) fuel (Mixed fuel loading of MOX (U-Pu) and MA composition) and mixed oxide (MOX) fuel compositions are analyzed for comparative analysis in order to show the effect of MA to the plutonium productions in core in term of reactor criticality condition and fuel breeding capability. In the present study, neptunium (Np) nuclide is used as a representative of MAin trans-uranium (TRU) fuel composition as Np-MOX fuel type. It was loaded into the core region gives significant contribution to reduce the excess reactivity in comparing to mixed oxide (MOX) fuel and in the same time it contributes to increase nuclear fuel breeding capability of the reactor. Neptunium fuel loading scheme in FBR core region gives significant production of Pu-238 as fertile material to absorp neutrons for reducing excess reactivity and additional contribution for fuel breeding.

Permana, Sidik; Novitrian,; Waris, Abdul [Nuclear Physics and Biophysics Research Division, Physics Department, Institut Teknologi Bandung (Indonesia); Ismail [Center for Technical Assessment of Nuclear Installation and Materials, Indonesian Nuclear Energy Regulatory (Indonesia); Suzuki, Mitsutoshi [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA) (Japan); Saito, Masaki [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology (Japan)

2014-09-30T23:59:59.000Z

55

Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion  

SciTech Connect (OSTI)

The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The facility has been used in the past as one facet of a suite of reactor fuels and component examination facilities available to researchers at the INL and throughout the DOE complex. The facility has also served various commercial research activities in addition to the DOE research and development support. The reactor was initially constructed using Fuel Lifetime Improvement Program (FLIP)- type highly enriched uranium (HEU) fuel obtained from the dismantled Puerto Rico Nuclear Center (PRNC) reactor. In accordance with international non-proliferation agreements, the NRAD core will be converted to a low enriched uranium (LEU) fuel and will continue to utilize the PRNC control rods, control rod drives, startup source, and instrument console as was previously used with the HEU core. The existing NRAD Safety Analysis Report (SAR) was created and maintained in the preferred format of the day, combining sections of both DOE-STD-3009 and Nuclear Regulatory Commission Regulatory Guide 1.70. An addendum was developed to cover the refueling and reactor operation with the LEU core. This addendum follows the existing SAR format combining required formats from both the DOE and NRC. This paper discusses the project to successfully write a compliant and approved addendum to the existing safety basis documents.

Boyd D. Christensen

2009-05-01T23:59:59.000Z

56

Measurement and analysis of fractures in vertical, slant, and horizontal core, with examples from the Mesaverde formation  

SciTech Connect (OSTI)

Optimum analysis of natural fracture characteristics and distributions in reservoirs requires conscientious supervision of coring operations, on-site core processing, careful layout and marketing of the core, and detailed measurement of fracture characteristics. Natural fractures provide information on the in situ permeability system, and coring-induced fractures provide data on the in situ stresses. Fracture data derived from vertical core should include fracture height, type and location of fracture terminations with respect to lithologic heterogeneity, fracture planatary and roughness, and distribution with depth. Fractures in core from either a vertical or a deviated well will yield information on dip, dip azimuth, strike, mineralization, and the orientation of fractures relative to the in situ stresses. Only measurements of fractures in core from a deviated/horizontal well will provide estimates of fracture spacing and porosity. These data can be graphed and cross-plotted to yield semi-quantitative fracture characteristics for reservoir models. Data on the orientations of fractures relative to each other in unoriented core can be nearly as useful as the absolute orientations of fractures. A deviated pilot hole is recommended for fracture assessment prior to a drilling horizontal production well because it significantly enhances the chances of fracture intersection, and therefore of fracture characterization. 35 refs., 20 figs., 2 tabs.

Lorenz, J.C. (Sandia National Labs., Albuquerque, NM (United States)); Hill, R.E. (CER Corp., Las Vegas, NV (United States))

1991-01-01T23:59:59.000Z

57

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

SciTech Connect (OSTI)

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

58

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

SciTech Connect (OSTI)

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

59

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

SciTech Connect (OSTI)

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

60

Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake, Madagascar): diagenesis appraisal and consequences for palaeoenvironmental  

E-Print Network [OSTI]

1 Sequential fatty acid analysis of a peat core covering the last two millennia (Tritrivakely lake and petrographical work [2], we applied such an approach to the analysis of a peat core section to get additional (saturated and unsaturated n-FAs, plus i-C16) at the surface of the peat sequence and low amounts

Paris-Sud XI, Université de

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

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

SciTech Connect (OSTI)

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

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

1982-01-01T23:59:59.000Z

62

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

SciTech Connect (OSTI)

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

Ziada, H.H.

1995-02-28T23:59:59.000Z

63

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

SciTech Connect (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

64

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

SciTech Connect (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

65

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

SciTech Connect (OSTI)

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

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

2014-04-01T23:59:59.000Z

66

ESPP Functional Genomics and Imaging Core: Cell wide analysis of Metal-Reducing Bacteria  

E-Print Network [OSTI]

and Environmental Research, Genomics:GTL Program throughESPP Functional Genomics and Imaging Core: Cell widemetals. The Functional Genomics and Imaging Core (FGIC)

Mukhopadhyay, Aindrila

2014-01-01T23:59:59.000Z

67

Time-resolved characterization and energy balance analysis of implosion core in shock-ignition experiments at OMEGA  

SciTech Connect (OSTI)

Time-resolved temperature and density conditions in the core of shock-ignition implosions have been determined for the first time. The diagnostic method relies on the observation, with a streaked crystal spectrometer, of the signature of an Ar tracer added to the deuterium gas fill. The data analysis confirms the importance of the shell attenuation effect previously noted on time-integrated spectroscopic measurements of thick-wall targets [R. Florido et al., Phys. Rev. E 83, 066408 (2011)]. This effect must be taken into account in order to obtain reliable results. The extracted temperature and density time-histories are representative of the state of the core during the implosion deceleration and burning phases. As a consequence of the ignitor shock launched by the sharp intensity spike at the end of the laser pulse, observed average core electron temperature and mass density reach T???1100?eV and ????2?g/cm{sup 3}; then temperature drops to T???920?eV while density rises to ????3.4?g/cm{sup 3} about the time of peak compression. Compared to 1D hydrodynamic simulations, the experiment shows similar maximum temperatures and smaller densities. Simulations do not reproduce all observations. Differences are noted in the heating dynamics driven by the ignitor shock and the optical depth time-history of the compressed shell. Time-histories of core conditions extracted from spectroscopy show that the implosion can be interpreted as a two-stage polytropic process. Furthermore, an energy balance analysis of implosion core suggests an increase in total energy greater than what 1D hydrodynamic simulations predict. This new methodology can be implemented in other ICF experiments to look into implosion dynamics and help to understand the underlying physics.

Florido, R., E-mail: ricardo.florido@ulpgc.es; Mancini, R. C.; Nagayama, T. [Department of Physics, University of Nevada, Reno, Nevada 89557 (United States); Tommasini, R. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Delettrez, J. A.; Regan, S. P. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)

2014-10-15T23:59:59.000Z

68

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

SciTech Connect (OSTI)

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

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

1984-01-01T23:59:59.000Z

69

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

SciTech Connect (OSTI)

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

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

2013-03-01T23:59:59.000Z

70

Comparative analysis of core drilling and rotary drilling in volcanic terrane  

SciTech Connect (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

71

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

72

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

SciTech Connect (OSTI)

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

Tzanos, C.P.

1987-01-01T23:59:59.000Z

73

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

74

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

SciTech Connect (OSTI)

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

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

1982-01-01T23:59:59.000Z

75

Advanced BWR core component designs and the implications for SFD analysis  

SciTech Connect (OSTI)

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

Ott, L.J.

1997-02-01T23:59:59.000Z

76

Benchmark analysis of high temperature engineering test reactor core using McCARD code  

SciTech Connect (OSTI)

A benchmark calculation has been performed for a startup core physics test of Japan's High Temperature Engineering Test Reactor (HTTR). The calculation is carried out by the McCARD code, which adopts the Monte Carlo method. The cross section library is ENDF-B/VII.0. The fuel cell is modeled by the reactivity-equivalent physical transform (RPT) method. Effective multiplication factors with different numbers of fuel columns have been analyzed. The calculation shows that the HTTR becomes critical with 19 fuel columns with an excess reactivity of 0.84% ?k/k. The discrepancies between the measurements and Monte Carlo calculations are 2.2 and 1.4 % ?k/k for 24 and 30 columns, respectively. The reasons for the discrepancy are thought to be the current version of cross section library and the impurity in the graphite which is represented by the boron concentration. In the future, the depletion results will be proposed for further benchmark calculations. (authors)

Jeong, Chang Joon; Jo, Chang Keun; Lee, Hyun Chul; Noh, Jae Man [Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong, Daejeon, 305-353 (Korea, Republic of)

2013-07-01T23:59:59.000Z

77

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

SciTech Connect (OSTI)

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

Jean Ragusa; Karen Vierow

2011-09-01T23:59:59.000Z

78

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

SciTech Connect (OSTI)

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

79

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 (OSTI)

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

80

Formation and Collapse of Nonaxisymmetric Protostellar Cores in Planar Magnetic Interstellar Clouds: Formulation of the Problem and Linear Analysis  

E-Print Network [OSTI]

We formulate the problem of the formation and collapse of nonaxisymmetric protostellar cores in weakly ionized, self-gravitating, magnetic molecular clouds. In our formulation, molecular clouds are approximated as isothermal, thin (but with finite thickness) sheets. We present the governing dynamical equations for the multifluid system of neutral gas and ions, including ambipolar diffusion, and also a self-consistent treatment of thermal pressure, gravitational, and magnetic (pressure and tension) forces. The dimensionless free parameters characterizing model clouds are discussed. The response of cloud models to linear perturbations is also examined, with particular emphasis on length and time scales for the growth of gravitational instability in magnetically subcritical and supercritical clouds. We investigate their dependence on a cloud's initial mass-to-magnetic-flux ratio (normalized to the critical value for collapse), the dimensionless initial neutral-ion collision time, and also the relative external pressure exerted on a model cloud. Among our results, we find that nearly-critical model clouds have significantly larger characteristic instability lengthscales than do more distinctly sub- or supercritical models. Another result is that the effect of a greater external pressure is to reduce the critical lengthscale for instability. Numerical simulations showing the evolution of model clouds during the linear regime of evolution are also presented, and compared to the results of the dispersion analysis. They are found to be in agreement with the dispersion results, and confirm the dependence of the characteristic length and time scales on parameters such as the initial mass-to-flux ratio and relative external pressure.

Glenn E. Ciolek; Shantanu Basu

2006-07-27T23:59:59.000Z

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

Direct chemical analysis of frozen ice cores by UV-laser ablation ICPMS Wolfgang Muller,*a  

E-Print Network [OSTI]

mm long ice (b, c); its `tongue-like' extension through the cell door has a Peltier element clamped DOI: 10.1039/c1ja10242g Cryo-cell UV-LA-ICPMS is a new technique for direct chemical analysis analysis at cell UV-LA-ICPMS setup used

Royal Holloway, University of London

82

Please cite this article in press as: Shuffler, C., et al., Thermal hydraulic analysis for grid supported pressurized water reactor cores. Nucl. Eng. Des. (2009), doi:10.1016/j.nucengdes.2008.12.028  

E-Print Network [OSTI]

Please cite this article in press as: Shuffler, C., et al., Thermal hydraulic analysis for grid.elsevier.com/locate/nucengdes Thermal hydraulic analysis for grid supported pressurized water reactor cores C. Shuffler , J. Trant, J online xxx a b s t r a c t This paper presents the methodology and results for thermal hydraulic analysis

Malen, Jonathan A.

2009-01-01T23:59:59.000Z

83

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

SciTech Connect (OSTI)

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

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

2013-04-01T23:59:59.000Z

84

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

85

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

86

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

87

An investigation of the correlation of core analysis data with original core saturations in the Kelly-Snyder Field, Scurry County, Texas  

E-Print Network [OSTI]

" . . . . . . . ? . *. . . . ~ . . ~ 1$ III, Summary of Mud Propertiee ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ i ~ t ~ ~ ~ 4 ~ t ~ ~ Io 16 XV. Sample Permeability Caloulationsi ~ . . . ~ . ~ ~ ~ ~ ~ i ~ ~ i ~ 26 V. Basic Data on Canyon Reef Cores'. ~ . ". i ~ . ~ . i. . i. . 27 VI & Summary of Oi 1... kpparatus?~~ Capillary Pressure Curves on Carxyon Reef Cores Nos 1 end No ~ 2 ~ ~ ~ o ~ ~ ~ ~ ~ t o 1 e ~ ~ ~ ~ ~ ~ i ~ ~ ~ i ~ ~ ~ ~ ~ 11 4 ~ 17 i ~ 1$ ~ ~ 22 5. 10+ Sohematio Drawing of Cell Connected for Permeability Neasurementsoo...

Van Meter, Orville Everett, Jr

1952-01-01T23:59:59.000Z

88

Hydrogen Analysis  

Broader source: Energy.gov [DOE]

Presentation on Hydrogen Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

89

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

E-Print Network [OSTI]

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...

Wang, Huhu 1985-

2012-12-13T23:59:59.000Z

90

Development code for sensitivity and uncertainty analysis of input on the MCNPX for neutronic calculation in PWR core  

SciTech Connect (OSTI)

This research was carried out on the development of code for uncertainty analysis is based on a statistical approach for assessing the uncertainty input parameters. In the butn-up calculation of fuel, uncertainty analysis performed for input parameters fuel density, coolant density and fuel temperature. This calculation is performed during irradiation using Monte Carlo N-Particle Transport. The Uncertainty method based on the probabilities density function. Development code is made in python script to do coupling with MCNPX for criticality and burn-up calculations. Simulation is done by modeling the geometry of PWR terrace, with MCNPX on the power 54 MW with fuel type UO2 pellets. The calculation is done by using the data library continuous energy cross-sections ENDF / B-VI. MCNPX requires nuclear data in ACE format. Development of interfaces for obtaining nuclear data in the form of ACE format of ENDF through special process NJOY calculation to temperature changes in a certain range.

Hartini, Entin, E-mail: entin@batan.go.id; Andiwijayakusuma, Dinan, E-mail: entin@batan.go.id [Center for Development of Nuclear Informatics - National Nuclear Energy Agency, PUSPIPTEK, Serpong, Tangerang, Banten (Indonesia)

2014-09-30T23:59:59.000Z

91

Tank Vapor Sampling and Analysis Data Package for Tank 241-Z-361 Sampled 09/22/1999 and 09/271999 During Sludge Core Removal  

SciTech Connect (OSTI)

This data package presents sampling data and analytical results from the September 22 and 27, 1999, headspace vapor sampling of Hanford Site Tank 241-2-361 during sludge core removal. The Lockheed Martin Hanford Corporation (LMHC) sampling team collected the samples and Waste Management Laboratory (WML) analyzed the samples in accordance with the requirements specified in the 241-2361 Sludge Characterization Sampling and Analysis Plan, (SAP), HNF-4371, Rev. 1, (Babcock and Wilcox Hanford Corporation, 1999). Six SUMMA{trademark} canister samples were collected on each day (1 ambient field blank and 5 tank vapor samples collected when each core segment was removed). The samples were radiologically released on September 28 and October 4, 1999, and received at the laboratory on September 29 and October 6, 1999. Target analytes were not detected at concentrations greater than their notification limits as specified in the SAP. Analytical results for the target analytes and tentatively identified compounds (TICs) are presented in Section 2.2.2 starting on page 2B-7. Three compounds identified for analysis in the SAP were analyzed as TICs. The discussion of this modification is presented in Section 2.2.1.2.

VISWANATH, R.S.

1999-12-29T23:59:59.000Z

92

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

SciTech Connect (OSTI)

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

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

1995-09-01T23:59:59.000Z

93

Forces in bolted joints: analysis methods and test results utilized for nuclear core applications (LWBR Development Program)  

SciTech Connect (OSTI)

Analytical methods and test data employed in the core design of bolted joints for the LWBR core are presented. The effects of external working loads, thermal expansion, and material stress relaxation are considered in the formulation developed to analyze joint performance. Extensions of these methods are also provided for bolted joints having both axial and bending flexibilities, and for the effect of plastic deformation on internal forces developed in a bolted joint. Design applications are illustrated by examples.

Crescimanno, P.J.; Keller, K.L.

1981-03-01T23:59:59.000Z

94

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

E-Print Network [OSTI]

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

Roberts-Tompkins, Altramese L.

2010-07-14T23:59:59.000Z

95

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

SciTech Connect (OSTI)

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

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

1995-12-31T23:59:59.000Z

96

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 (OSTI)

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

97

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

SciTech Connect (OSTI)

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

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

2010-07-01T23:59:59.000Z

98

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

SciTech Connect (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

99

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

100

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

E-Print Network [OSTI]

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

M. Gemard; J. Aichelin

2014-02-02T23:59:59.000Z

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

Measurement and analysis of neutron flux distribution of STACY heterogeneous core by position sensitive proportional counter. Contract research  

E-Print Network [OSTI]

We have measured neutron flux distribution around the core tank of STACY heterogeneous core by position sensitive proportional counter (PSPC) to develop the method to measure reactivity for subcritical systems. The neutron flux distribution data in the position accuracy of +-13 mm have been obtained in the range of uranium concentration of 50g/L to 210g/L both in critical and in subcritical state. The prompt neutron decay constant, alpha, was evaluated from the measurement data of pulsed neutron source experiments. We also calculated distribution of neutron flux and sup 3 He reaction rates at the location of PSPC by using continuous energy Monte Carlo code MCNP. The measurement data was compared with the calculation results. As results of comparison, calculated values agreed generally with measurement data of PSPC with Cd cover in the region above half of solution height, but the difference between calculated value and measurement data was large in the region below half of solution height. On the other hand, ...

Murazaki, M; Uno, Y

2003-01-01T23:59:59.000Z

102

Environmental Analysis & Policy: Sample Pathway  

E-Print Network [OSTI]

Environmental Analysis & Policy: Sample Pathway Semester I Semester II Freshman Year CGS Core CGS Sustainable Development OR Spring GE 425 U.S. Environmental Policy (Senior) GE 309 Intermediate Env Analysis (Fall) EAP Elective Summer Environmental Internship Senior Year GE 420 Env Policy Analysis 4 th Semester

Goldberg, Bennett

103

Image Analysis  

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

Recognition Image Analysis and Recognition Snapshot1498121slicesqResedison Fibers permeating imaged material (Courtesy: Bale, Loring, Perciano and Ushizima) Imagery coming from...

104

OIL ANALYSIS LAB TRIVECTOR ANALYSIS  

E-Print Network [OSTI]

OIL ANALYSIS LAB TRIVECTOR ANALYSIS This test method is a good routine test for the overall condition of the oil, the cleanliness, and can indicate the presence of wear metals that could be coming of magnetic metal particles within the oil. This may represent metals being worn from components (i

105

Financial Analysis  

Broader source: Energy.gov [DOE]

The first step in financing a street lighting retrofit is a detailed financial analysis. Because street lighting systems are designed to last ten or twenty years, or even longer, all aspects of first costs, ongoing expenses, and long-term savings are important. While a preliminary or first-level analysis can be used to determine such things as simple payback, rate of return, and cost of light, the results may neglect a number of important economic considerations, such as the time value of money, additional savings and expenses and their relative timing, and future energy price escalations. Hence a first-level analysis does not typically provide the end user with sufficient details to make a fully informed decision. For this reason, the Illuminating Engineering Society (IES) recommends a full life cycle cost/benefit analysis (LCCBA).

106

Multi-core Performance Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment SurfacesResource ProgramModification andinterface1JUN 2 5

107

Core Analysis | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump to: navigation, search

108

Supply Chain Analysis Center for Transportation Analysis  

E-Print Network [OSTI]

Supply Chain Analysis Center for Transportation Analysis 2360 Cherahala Boulevard Knoxville, TN experience in supply chain analysis and automated support for supply chain systems. ORNL's Capabilities Optimization modeling for supply chain systems, including: Facility number and location analysis

109

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

SciTech Connect (OSTI)

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

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

1994-07-01T23:59:59.000Z

110

Economic analysis  

SciTech Connect (OSTI)

The Energy Policy and Conservation Act (EPCA) mandated that minimum energy efficiency standards be established for classes of refrigerators and refrigerator-freezers, freezers, clothes dryers, water heaters, room air conditioners, home heating equipment, kitchen ranges and ovens, central air conditioners, and furnaces. EPCA requires that standards be designed to achieve the maximum improvement in energy efficiency that is technologically feasible and economically justified. Following the introductory chapter, Chapter Two describes the methodology used in the economic analysis and its relationship to legislative criteria for consumer product efficiency assessment; details how the CPES Value Model systematically compared and evaluated the economic impacts of regulation on the consumer, manufacturer and Nation. Chapter Three briefly displays the results of the analysis and lists the proposed performance standards by product class. Chapter Four describes the reasons for developing a baseline forecast, characterizes the baseline scenario from which regulatory impacts were calculated and summarizes the primary models, data sources and assumptions used in the baseline formulations. Chapter Five summarizes the methodology used to calculate regulatory impacts; describes the impacts of energy performance standards relative to the baseline discussed in Chapter Four. Also discussed are regional standards and other program alternatives to performance standards. Chapter Six describes the procedure for balancing consumer, manufacturer, and national impacts to select standard levels. Details of models and data bases used in the analysis are included in Appendices A through K.

None

1980-06-01T23:59:59.000Z

111

Supplement Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystalline Gallium OxideSuminDeposition ofSupplement Analysis

112

Data Analysis  

SciTech Connect (OSTI)

Analysis of the material protection, control, and accountability (MPC&A) system is necessary to understand the limits and vulnerabilities of the system to internal threats. A self-appraisal helps the facility be prepared to respond to internal threats and reduce the risk of theft or diversion of nuclear material. The material control and accountability (MC&A) system effectiveness tool (MSET) fault tree was developed to depict the failure of the MPC&A system as a result of poor practices and random failures in the MC&A system. It can also be employed as a basis for assessing deliberate threats against a facility. MSET uses fault tree analysis, which is a top-down approach to examining system failure. The analysis starts with identifying a potential undesirable event called a 'top event' and then determining the ways it can occur (e.g., 'Fail To Maintain Nuclear Materials Under The Purview Of The MC&A System'). The analysis proceeds by determining how the top event can be caused by individual or combined lower level faults or failures. These faults, which are the causes of the top event, are 'connected' through logic gates. The MSET model uses AND-gates and OR-gates and propagates the effect of event failure using Boolean algebra. To enable the fault tree analysis calculations, the basic events in the fault tree are populated with probability risk values derived by conversion of questionnaire data to numeric values. The basic events are treated as independent variables. This assumption affects the Boolean algebraic calculations used to calculate results. All the necessary calculations are built into the fault tree codes, but it is often useful to estimate the probabilities manually as a check on code functioning. The probability of failure of a given basic event is the probability that the basic event primary question fails to meet the performance metric for that question. The failure probability is related to how well the facility performs the task identified in that basic event over time (not just one performance or exercise). Fault tree calculations provide a failure probability for the top event in the fault tree. The basic fault tree calculations establish a baseline relative risk value for the system. This probability depicts relative risk, not absolute risk. Subsequent calculations are made to evaluate the change in relative risk that would occur if system performance is improved or degraded. During the development effort of MSET, the fault tree analysis program used was SAPHIRE. SAPHIRE is an acronym for 'Systems Analysis Programs for Hands-on Integrated Reliability Evaluations.' Version 1 of the SAPHIRE code was sponsored by the Nuclear Regulatory Commission in 1987 as an innovative way to draw, edit, and analyze graphical fault trees primarily for safe operation of nuclear power reactors. When the fault tree calculations are performed, the fault tree analysis program will produce several reports that can be used to analyze the MPC&A system. SAPHIRE produces reports showing risk importance factors for all basic events in the operational MC&A system. The risk importance information is used to examine the potential impacts when performance of certain basic events increases or decreases. The initial results produced by the SAPHIRE program are considered relative risk values. None of the results can be interpreted as absolute risk values since the basic event probability values represent estimates of risk associated with the performance of MPC&A tasks throughout the material balance area (MBA). The RRR for a basic event represents the decrease in total system risk that would result from improvement of that one event to a perfect performance level. Improvement of the basic event with the greatest RRR value produces a greater decrease in total system risk than improvement of any other basic event. Basic events with the greatest potential for system risk reduction are assigned performance improvement values, and new fault tree calculations show the improvement in total system risk. The ope

Powell, Danny H [ORNL] [ORNL; Elwood Jr, Robert H [ORNL] [ORNL

2011-01-01T23:59:59.000Z

113

Strategic Analysis and Modeling  

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

analysis Conceptual Process Design Material and Energy Balance Capital and Project Cost Estimates Environmental Sustainability Analysis R&D DOE Goals Economic Analysis...

114

Economic Analysis of Policy Effects Analysis Platform  

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

Economic Analysis of Policy Effects Analysis Platform March 24, 2015 Jason Hansen, PhD Idaho National Laboratory This presentation does not contain any proprietary, confidential,...

115

NREL: Energy Analysis - Market Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions and Achievements ofLiz Torres Photo of Liz Torres LizMarket Analysis

116

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

E-Print Network [OSTI]

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

Connaway, Heather M. (Heather Moira)

2012-01-01T23:59:59.000Z

117

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 (OSTI)

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

118

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 (OSTI)

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

119

Research Associate Position Defense Analysis Department  

E-Print Network [OSTI]

in analyzing social network data as well as geospatial, temporal, and standard statistical analysis of largeResearch Associate Position Defense Analysis Department Naval Postgraduate School, Monterey, CA Research Associate The Department of Defense Analysis is home to the CORE (Common Operational Research

120

Hazard Analysis Database report  

SciTech Connect (OSTI)

This document describes and defines the Hazard Analysis Database for the Tank Waste Remediation System Final Safety Analysis Report.

Niemi, B.J.

1997-08-12T23:59:59.000Z

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

Hazard analysis results report  

SciTech Connect (OSTI)

This document describes and defines the Hazard Analysis Results for the Tank Waste Remediation System Final Safety Analysis Report.

Niemi, B.J., Westinghouse Hanford

1996-09-30T23:59:59.000Z

122

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 (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.; 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

123

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  

SciTech Connect (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

124

Uncertainty analysis  

SciTech Connect (OSTI)

An evaluation is made of the suitability of analytical and statistical sampling methods for making uncertainty analyses. The adjoint method is found to be well-suited for obtaining sensitivity coefficients for computer programs involving large numbers of equations and input parameters. For this purpose the Latin Hypercube Sampling method is found to be inferior to conventional experimental designs. The Latin hypercube method can be used to estimate output probability density functions, but requires supplementary rank transformations followed by stepwise regression to obtain uncertainty information on individual input parameters. A simple Cork and Bottle problem is used to illustrate the efficiency of the adjoint method relative to certain statistical sampling methods. For linear models of the form Ax=b it is shown that a complete adjoint sensitivity analysis can be made without formulating and solving the adjoint problem. This can be done either by using a special type of statistical sampling or by reformulating the primal problem and using suitable linear programming software.

Thomas, R.E.

1982-03-01T23:59:59.000Z

125

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

E-Print Network [OSTI]

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

Rezvyi, Aleksey

2012-06-07T23:59:59.000Z

126

Utilization Analysis Page 1 UTILIZATION ANALYSIS  

E-Print Network [OSTI]

Utilization Analysis Page 1 UTILIZATION ANALYSIS Section 46a-68-40 and HIRING/PROMOTION GOALS utilized in the Health Center's workforce, the numbers of protected classes in the workforce must conducted for each occupational category and position classification. The Utilization Analysis was performed

Oliver, Douglas L.

127

Robustness Analysis Michael Weisberg  

E-Print Network [OSTI]

Robustness Analysis Michael Weisberg University of Pennsylvania September 14, 2005 Abstract Modelers often rely on robustness analysis, the search for predic- tions common to several independent models. Robustness analysis has been characterized and championed by Richard Levins and William Wimsatt

Weisberg, Michael

128

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

E-Print Network [OSTI]

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

Conte, Thomas M.

129

chemical analysis | EMSL  

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

chemical analysis chemical analysis Leads No leads are available at this time. Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. Abstract: As a...

130

Laser Desorption Analysis | EMSL  

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

Laser Desorption Analysis Laser Desorption Analysis EMSL offers a suite of instrumentation dedicated to understanding photoreactivity in the condensed phase, on surfaces, and at...

131

Clean Energy Policy Analysis: Impact Analysis of Potential Clean...  

Energy Savers [EERE]

Clean Energy Policy Analysis: Impact Analysis of Potential Clean Energy Policy Options for the Hawaii Clean Energy Initiative Clean Energy Policy Analysis: Impact Analysis of...

132

Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel...  

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

Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel Cells Analysis Models and Tools: Systems Analysis of Hydrogen and Fuel Cells The Fuel Cell Technologies Office's...

133

Isotopic Analysis- Rock At Kilauea East Rift Geothermal Area...  

Open Energy Info (EERE)

Technique Isotopic Analysis- Rock Activity Date 1989 - 2000 Usefulness not indicated DOE-funding Unknown Exploration Basis The purpose of this study was to analyze deep core...

134

Petrography Analysis At Kilauea East Rift Geothermal Area (Quane...  

Open Energy Info (EERE)

Technique Petrography Analysis Activity Date 1989 - 2000 Usefulness not indicated DOE-funding Unknown Exploration Basis The purpose of this study was to analyze deep core...

135

analysis reveals permanent: Topics by E-print Network  

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

Index 21 Design and analysis aspects of radial flux air-cored permanent magnet wind generator system for direct battery charging applications. Open Access Theses and...

136

Analysis Of Macroscopic Fractures In Granite In The Hdr Geothermal...  

Open Energy Info (EERE)

between core and acoustic borehole imagery. Detailed structural analysis of the fracture population indicates that fractures are grouped in two principal fractures sets...

137

Reactor hot spot analysis  

SciTech Connect (OSTI)

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

Vilim, R.B.

1985-08-01T23:59:59.000Z

138

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 (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. 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

139

COBRA-IV PC: A personal computer version of COBRA-IV-I for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores  

SciTech Connect (OSTI)

COBRA-IV PC is a modified version of COBRA-IV-I, adapted for use with most IBM PC and PC-compatible desktop computers. Like COBRA-IV-I, COBRA-IV PC uses the subchannel analysis approach to determine the enthalpy and flow distribution in rod bundles for both steady-state and transient conditions. The steady-state and transient solution schemes used in COBRA-IIIC are still available in COBRA-IV PC as the implicit solution scheme option. An explicit solution scheme is also available, allowing the calculation of severe transients involving flow reversals, recirculations, expulsions, and reentry flows, with a pressure or flow boundary condition specified. In addition, several modifications have been incorporated into COBRA-IV PC to allow the code to run on the PC. These include a reduction in the array dimensions, the removal of the dump and restart options, and the inclusion of several code modifications by Oregon State University, most notably, a critical heat flux correlation for boiling water reactor fuel and a new solution scheme for cross-flow distribution calculations. 7 refs., 8 figs., 1 tab.

Webb, B.J.

1988-01-01T23:59:59.000Z

140

Statistical Analysis and Geologic Evaluation of Laboratory-Derived Physical Property Data for Selected Nevada Test Site Core Samples of Non-Zeolitized Tuffs  

SciTech Connect (OSTI)

A statistical analysis and geologic evaluation of recently acquired laboratory-derived physical property data are being performed to better understand and more precisely correlate physical properties with specific geologic parameters associated with non-zeolitized tuffs at the Nevada Test Site. Physical property data include wet and dry bulk density, grain density (i.e., specific gravity), total porosity, and effective porosity. Geologic parameters utilized include degree of welding, lithology, stratigraphy, geographic area, and matrix mineralogy (i.e., vitric versus devitrified). Initial results indicate a very good correlation between physical properties and geologic parameters such as degree of welding, lithology, and matrix mineralogy. However, physical properties appear to be independent of stratigraphy and geographic area, suggesting that the data are transferrable with regards to these two geologic parameters. Statistical analyses also indicate that the assumed grain density of 2.65 grams per cubic centimeter used to calculate porosity in some samples is too high. This results in corresponding calculated porosity values approximately 5 percent too high (e.g., 45 percent versus 40 percent), which can be significant in the lower porosity rocks. Similar analyses and evaluations of zeolitic tuffs and carbonate rock physical properties data are ongoing as well as comparisons to geophysical log values.

NSTec Environmental Restoration

2009-04-20T23:59:59.000Z

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

K Basins Hazard Analysis  

SciTech Connect (OSTI)

This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Safety Analysis Report (HNF-SD-WM-SAR-062, Rev.4). This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

WEBB, R.H.

1999-12-29T23:59:59.000Z

142

K Basin Hazard Analysis  

SciTech Connect (OSTI)

This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Final Safety Analysis Report. This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

PECH, S.H.

2000-08-23T23:59:59.000Z

143

Comparative Analysis of the 15.5kD Box C/D snoRNP Core Protein in the Primitive Eukaryote Giardia lamblia Reveals Unique Structural and Functional Features  

SciTech Connect (OSTI)

Box C/D ribonucleoproteins (RNP) guide the 2'-O-methylation of targeted nucleotides in archaeal and eukaryotic rRNAs. The archaeal L7Ae and eukaryotic 15.5kD box C/D RNP core protein homologues initiate RNP assembly by recognizing kink-turn (K-turn) motifs. The crystal structure of the 15.5kD core protein from the primitive eukaryote Giardia lamblia is described here to a resolution of 1.8 {angstrom}. The Giardia 15.5kD protein exhibits the typical {alpha}-{beta}-{alpha} sandwich fold exhibited by both archaeal L7Ae and eukaryotic 15.5kD proteins. Characteristic of eukaryotic homologues, the Giardia 15.5kD protein binds the K-turn motif but not the variant K-loop motif. The highly conserved residues of loop 9, critical for RNA binding, also exhibit conformations similar to those of the human 15.5kD protein when bound to the K-turn motif. However, comparative sequence analysis indicated a distinct evolutionary position between Archaea and Eukarya. Indeed, assessment of the Giardia 15.5kD protein in denaturing experiments demonstrated an intermediate stability in protein structure when compared with that of the eukaryotic mouse 15.5kD and archaeal Methanocaldococcus jannaschii L7Ae proteins. Most notable was the ability of the Giardia 15.5kD protein to assemble in vitro a catalytically active chimeric box C/D RNP utilizing the archaeal M. jannaschii Nop56/58 and fibrillarin core proteins. In contrast, a catalytically competent chimeric RNP could not be assembled using the mouse 15.5kD protein. Collectively, these analyses suggest that the G. lamblia 15.5kD protein occupies a unique position in the evolution of this box C/D RNP core protein retaining structural and functional features characteristic of both archaeal L7Ae and higher eukaryotic 15.5kD homologues.

Biswas, Shyamasri; Buhrman, Greg; Gagnon, Keith; Mattos, Carla; Brown, II, Bernard A.; Maxwell, E. Stuart (NCSU); (UTSMC)

2012-07-11T23:59:59.000Z

144

Analysis of a rod withdrawal in a PWR core with the neutronic- thermalhydraulic coupled code RELAP/PARCS and RELAP/VALKIN  

SciTech Connect (OSTI)

The Reactor Ejection Accident (REA) belongs to the Reactor Initiated Accidents (RIA) category of accidents and it is part of the licensing basis accident analyses required for pressure water reactors (PWR). The REA at hot zero power (HZP) is characterized by a single rod ejection from a core position with a very low power level. The evolution consists basically of a continuous reactivity insertion. The main feature limiting the consequences of the accident in a PWR is the Doppler Effect. To check the performance of the coupled code RELAP5/PARCS2.5 and RELAP5/VALKIN a REA in Trillo NPP is simulated. These analyses will allow knowing more accurately the PWR real plant phenomenology in the RIA most limiting conditions. (authors)

Miro, R.; Maggini, F.; Barrachina, T.; Verdu, G. [Departamento de Ingenieria Quimica y Nuclear, Universidad Politecnica de Valencia, Camino de Vera, 14, 46022, Valencia (Spain); Gomez, A.; Ortego, A. [IBERINCO, Avenida de Burgos, Madrid (Spain); Murillo, J. C. [CNAT, Av. Manoteras, Madrid (Spain)

2006-07-01T23:59:59.000Z

145

Tree Fertilization Soil Analysis  

E-Print Network [OSTI]

, increase root density, maintain tree health #12;#12;pH ­ effects nutrient availability · Symptoms of high pHTree Fertilization #12;Soil Analysis vs. Foliar Analysis #12;Macronutrients N P K Mg S Ca

146

Photovoltaics Life Cycle Analysis  

E-Print Network [OSTI]

1 Photovoltaics Life Cycle Analysis Vasilis Fthenakis Center of Life Cycle Analysis Earth & Environmental Engineering Department Columbia University and National Photovoltaic (PV) EHS Research Center (air, water, solid) M, Q E PV array Photovoltaic modules Balance of System (BOS) (Inverters

147

Hydrogen Analysis Group  

SciTech Connect (OSTI)

NREL factsheet that describes the general activites of the Hydrogen Analysis Group within NREL's Hydrogen Technologies and Systems Center.

Not Available

2008-03-01T23:59:59.000Z

148

REAL ANALYSIS: DRIPPED VERSION  

E-Print Network [OSTI]

i ELEMENTARY REAL ANALYSIS: DRIPPED VERSION -------------------------- thomson·bruckner2 -------------------------- Brian S. Thomson Judith B. Bruckner Andrew M. Bruckner www.classicalrealanalysis.com (2008) ClassicalRealAnalysis.com [TBB-Dripped] Elementary Real Analysis - Dripped Version Thomson*Bruckner*Bruckner #12;ii D

California at Santa Cruz, University of

149

The Tariff Analysis Project: A Database and Analysis Platform...  

Open Energy Info (EERE)

Tariff Analysis Project: A Database and Analysis Platform for Electricity Tariffs Jump to: navigation, search Tool Summary LAUNCH TOOL Name: The Tariff Analysis Project: A Database...

150

Transportation Analysis | Clean Energy | ORNL  

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

Transportation Analysis SHARE Transportation Analysis Transportation Analysis efforts at Oak Ridge National Laboratory contribute to the efficient, safe, and free movement of...

151

Fusion neutronics experiments and analysis  

SciTech Connect (OSTI)

This report discusses the following topics: Tritium breeding measurements and analysis; induced radioactivity measurements and analysis; and nuclear heating measurements and analysis. (LSP)

Abdou, M.A.

1991-06-01T23:59:59.000Z

152

Systems-level analysis of age-related macular degeneration reveals global biomarkers and phenotype-specific functional networks  

E-Print Network [OSTI]

derived from Homo sapiens, an IPA Core Analysis was run forin the RPE-choroid interactome, we restricted IPA results tothe highest scoring IPA network for a given Core Analysis.

2012-01-01T23:59:59.000Z

153

LULU analysis program  

SciTech Connect (OSTI)

Our analysis program LULU has proven very useful in all stages of experiment analysis, from prerun detector debugging through final data reduction. It has solved our problem of having arbitrary word length events and is easy enough to use that many separate experimenters are now analyzing with LULU. The ability to use the same software for all stages of experiment analysis greatly eases the programming burden. We may even get around to making the graphics elegant someday.

Crawford, H.J.; Lindstrom, P.J.

1983-06-01T23:59:59.000Z

154

PROCESS ANALYSIS What is it?  

E-Print Network [OSTI]

PROCESS ANALYSIS What is it? Process analysis answers the question: "How?" Process analysis of events occurred. There are two kinds of process analysis: directional and informational. Directional, or prescriptive, process analysis asks: How do you do it? This kind of analysis examines how to do something

Boonstra, Rudy

155

Hazard Analysis Database Report  

SciTech Connect (OSTI)

The Hazard Analysis Database was developed in conjunction with the hazard analysis activities conducted in accordance with DOE-STD-3009-94, Preparation Guide for U S . Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, for HNF-SD-WM-SAR-067, Tank Farms Final Safety Analysis Report (FSAR). The FSAR is part of the approved Authorization Basis (AB) for the River Protection Project (RPP). This document describes, identifies, and defines the contents and structure of the Tank Farms FSAR Hazard Analysis Database and documents the configuration control changes made to the database. The Hazard Analysis Database contains the collection of information generated during the initial hazard evaluations and the subsequent hazard and accident analysis activities. The Hazard Analysis Database supports the preparation of Chapters 3 ,4 , and 5 of the Tank Farms FSAR and the Unreviewed Safety Question (USQ) process and consists of two major, interrelated data sets: (1) Hazard Analysis Database: Data from the results of the hazard evaluations, and (2) Hazard Topography Database: Data from the system familiarization and hazard identification.

GRAMS, W.H.

2000-12-28T23:59:59.000Z

156

Asset Protection Analysis Guide  

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

The Guide provides examples of the application of as set protection analysis to several common problems. Canceled by DOE N 251.80.

2008-08-21T23:59:59.000Z

157

Data Collection and Analysis  

Energy Savers [EERE]

DataCollecGon&Analysis MarloweKulley PortlandBureauofPlanning&Sustainability DOEConference|May20,2011|Arlington,VA 2...

158

EMSL - chemical analysis  

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

chemical-analysis en Magnesium behavior and structural defects in Mg+ ion implanted silicon carbide. http:www.emsl.pnl.govemslwebpublicationsmagnesium-behavior-and-structural-...

159

harmonic analysis and geometry  

E-Print Network [OSTI]

Faculty listing for "harmonic analysis and geometry". vCard of Nicola Garofalo Garofalo, Nicola [bio] [homepage] Adjunct Professor of Mathematics

160

Modeling and Analysis  

Broader source: Energy.gov [DOE]

DOE modeling and analysis activities focus on reducing uncertainties and improving transparency in photovoltaics (PV) and concentrating solar power (CSP) performance modeling. The overall goal of...

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

Analysis of Hydrologic Properties Data  

SciTech Connect (OSTI)

This analysis report describes the methods used to determine hydrologic properties based on the available field data from the unsaturated zone (UZ) at Yucca Mountain, Nevada. The technical scope, content, and management of this analysis report are described in the planning document ''Technical Work Plan for: Unsaturated Zone Flow Analysis and Model Report Integration'' (BSC 2004 [DIRS 169654], Sections 2, 4, and 8). Fracture and matrix properties are developed by analyzing available survey data from the Exploratory Studies Facility (ESF), the Enhanced Characterization of Repository Block (ECRB) Cross-Drift, and/or boreholes; air-injection testing data from surface boreholes and from boreholes in the ESF; and data from laboratory testing of core samples. In addition, the report ''Geologic Framework Model'' (GFM2000) (BSC 2004 [DIRS 170029]) also serves as a source report by providing the geological framework model of the site. This report is a revision of the model report under the same title (BSC 2003 [DIRS 161773]), which in turn superceded the analysis report under the same title. The principal purpose of this work is to provide representative uncalibrated estimates of fracture and matrix properties for use in the model report Calibrated Properties Model. The term ''uncalibrated'' is used to distinguish the properties or parameters estimated in this report from those obtained from the inversion modeling used in ''Calibrated Properties Model''. The present work also provides fracture geometry properties for generating dual-permeability grids as documented in the scientific analyses report, ''Development of Numerical Grids for UZ Flow and Transport Modeling''.

L. Pan

2004-10-04T23:59:59.000Z

162

K Basin safety analysis  

SciTech Connect (OSTI)

The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

Porten, D.R.; Crowe, R.D.

1994-12-16T23:59:59.000Z

163

Modern Real Analysis William P. Ziemer  

E-Print Network [OSTI]

the fact that the theory of functions of one real variable is the core of the subject. ... equalized and they will be prepared to pursue the main thrust of the book. The text ... A chapter on elementary functional analysis is followed by one on the Daniell ...... methods discussed so far, namely, by cardinality, topological density, or.

2013-08-09T23:59:59.000Z

164

The Bitcoin Backbone Protocol: Analysis and Applications  

E-Print Network [OSTI]

The Bitcoin Backbone Protocol: Analysis and Applications Juan A. Garay Yahoo Labs garay.leonardos@gmail.com November 16, 2014 Abstract Bitcoin is the first and most popular decentralized cryptocurrency to date. In this work, we extract and analyze the core of the Bitcoin protocol, which we term the Bitcoin backbone

165

Decision Support:Decision Support: Decision AnalysisDecision Analysis  

E-Print Network [OSTI]

-Making under Risk · Expected Value · Sensitivity Analysis Decision Analysis Decision Analysis: Applied Decision Decision-Making Process Source: Decision Analysis ­ A Tool to Deal with Uncertainty, http Succeed Fail Decision Trees OR/MS · Multi-Criteria Optimisation · Risk Analysis and Simulation · Bayesian

Bohanec, Marko

166

Attached sunspace design analysis  

SciTech Connect (OSTI)

An introduction to new design analysis information for attached sunspaces is presented. The 28 sunspace reference designs are described. Note is taken of those designs (the semi-enclosed geometries) analyzed more recently than the previously published reports. The role of sensitivity studies is discussed, and some sample plots of sunspace performance sensitivity to key design parameters are presented. The monthly solar load ratio (SLR) correlations are reviewed with emphasis on the modified SLR used in the sunspace analysis. The application of the sunspace SLR correlations to monthly design analysis is outlined.

Jones, R.W.; McFarland, R.D.

1981-01-01T23:59:59.000Z

167

Supplementary Figure 1 SHAPE-MaP data analysis pipeline.  

E-Print Network [OSTI]

Supplementary Figure 1 SHAPE-MaP data analysis pipeline. Outline of software pipeline that fully.1 GHz Intel Core i7 and 16 GB RAM). This strategy is implemented in the SHAPE-MaP Folding Pipeline

Cai, Long

168

Energy Sector Market Analysis  

SciTech Connect (OSTI)

This paper presents the results of energy market analysis sponsored by the Department of Energy's (DOE) Weatherization and International Program (WIP) within the Office of Energy Efficiency and Renewable Energy (EERE). The analysis was conducted by a team of DOE laboratory experts from the National Renewable Energy Laboratory (NREL), Oak Ridge National Laboratory (ORNL), and Pacific Northwest National Laboratory (PNNL), with additional input from Lawrence Berkeley National Laboratory (LBNL). The analysis was structured to identify those markets and niches where government can create the biggest impact by informing management decisions in the private and public sectors. The analysis identifies those markets and niches where opportunities exist for increasing energy efficiency and renewable energy use.

Arent, D.; Benioff, R.; Mosey, G.; Bird, L.; Brown, J.; Brown, E.; Vimmerstedt, L.; Aabakken, J.; Parks, K.; Lapsa, M.; Davis, S.; Olszewski, M.; Cox, D.; McElhaney, K.; Hadley, S.; Hostick, D.; Nicholls, A.; McDonald, S.; Holloman, B.

2006-10-01T23:59:59.000Z

169

On Field Constraint Analysis  

E-Print Network [OSTI]

We introduce field constraint analysis, a new technique for verifying data structure invariants. A field constraint for a field is a formula specifying a set of objects to which the field can point. Field constraints ...

Wies, Thomas

2005-11-03T23:59:59.000Z

170

Fluid Inclusion Gas Analysis  

SciTech Connect (OSTI)

Fluid inclusion gas analysis for wells in various geothermal areas. Analyses used in developing fluid inclusion stratigraphy for wells and defining fluids across the geothermal fields. Each sample has mass spectrum counts for 180 chemical species.

Dilley, Lorie

2013-01-01T23:59:59.000Z

171

Uncertainty Analysis Economic Evaluations  

E-Print Network [OSTI]

uncertainties in typical oil and gas projects: 1. The oil price, 2. The investments (capex) and operating 4.1 Oil Prices...............................................................................................14 4.1.1 Analysis of historical oil prices........................................................15

Bhulai, Sandjai

172

Fluid Inclusion Gas Analysis  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

Fluid inclusion gas analysis for wells in various geothermal areas. Analyses used in developing fluid inclusion stratigraphy for wells and defining fluids across the geothermal fields. Each sample has mass spectrum counts for 180 chemical species.

Dilley, Lorie

173

K Basin Hazard Analysis  

SciTech Connect (OSTI)

The K East (KE)/K West (KW) Basins in the 100 K Area of the Hanford Site have been used for storage of irradiated N Reactor and single-pass reactor fuel. Remaining spent fuel is continuing to be stored underwater in racks and canisters in the basins while fuel retrieval activities proceed to remove the fuel from the basins. The Spent Nuclear Fuel (SNF) Project is adding equipment to the facility in preparation for removing the fuel and sludge from the basins In preparing this hazard analysis, a variety of hazard analysis techniques were used by the K Basins hazard analysis team, including hazard and operability studies, preliminary hazard analyses, and ''what if'' analyses (WHC-SD-SNF-PHA-001, HNF-2032, HNF-2456, and HNF-SD-SNF-SAD-002). This document summarizes the hazard analyses performed as part of the safety evaluations for the various modification projects and combines them with the original hazard analyses to create a living hazard analysis document. As additional operational activities and modifications are developed, this document will be updated as needed to ensure it covers all the hazards at the K Basins in a summary form and to ensure the subsequent safety analysis is bounding. This hazard analysis also identifies the preliminary set of design features and controls that the facility could rely on to prevent or reduce the frequency or mitigate consequences of identified accident conditions based on their importance and significance to safety. The operational controls and institutional programs relied on for prevention or mitigation of an uncontrolled release are identified as potential technical safety requirements. All operational activities and energy sources at the K Basins are evaluated in this hazard analysis. Using a systematic approach, this document identifies hazards created by abnormal operating conditions and external events (e.g., earthquakes) that have the potential for causing undesirable consequences to the facility worker, the onsite individual, or the public. This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Final Safety Analysis Report. This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and complies with the requirements of 10 CFR 830.

SEMMENS, L.S.

2001-04-20T23:59:59.000Z

174

Environmental Cost Analysis  

E-Print Network [OSTI]

Environmental Cost Analysis David Edge Texas Natural Resource Conservation Commission 131 ESL-IE-00-04-21 Proceedings from the Twenty-second National Industrial Energy Technology Conference, Houston, TX, April 5-6, 2000 Tuas Natural... Resource Conservation CorDDliuion Environmental Cost Analysis Presented By David Edge Determine the Costs c> Input co Output c> Hidden c> Capital (non recurring) Envirormenlal Cost Analy.;is "There has to be a measurable result...

Edge, D.

175

Distributed analysis in ATLAS  

E-Print Network [OSTI]

The ATLAS experiment accumulated more than 140 PB of data during the first run of the Large Hadron Collider (LHC) at CERN. The analysis of such an amount of data for the distributed physics community is a challenging task. The Distributed Analysis (DA) system of the ATLAS experiment is an established and stable component of the ATLAS distributed computing operations. About half a million user jobs are daily running on DA resources, submitted by more than 1500 ATLAS physicists. The reliability of the DA system during the first run of the LHC and the following shutdown period has been high thanks to the continuous automatic validation of the distributed analysis sites and the user support provided by a dedicated team of expert shifters. During the LHC shutdown, the ATLAS computing model has undergone several changes to improve the analysis workflows, including the re-design of the production system, a new analysis data format and event model, and the development of common reduction and analysis frameworks. We r...

Dewhurst, Alastair; The ATLAS collaboration

2015-01-01T23:59:59.000Z

176

Chernobyl Deconstruction ALARA Analysis  

SciTech Connect (OSTI)

The Bechtel/EDF/Battelle Consortium has recently completed the conceptual design for the Chernobyl New Safe Confinement (NSC). Battelle has the scope of work related to environment and safety of the design. As part of the safety analysis, an ALARA analysis was performed for deconstruction of the major, unstable elements of the Shelter Object over the destroyed Unit 4 of the reactor complex. The major elements addressed in the analysis included the current roof sections and the major beams supporting the roof sections. The analysis was based on the existing configuration of the Shelter Object, the developing conceptual design of the NSC arch structure, the developing conceptual design of the facilities within and associated with the NSC (including handling and processing of deconstructed elements, and waste management), and existing Ukranian regulations and working processes and procedures. KSK (a Ukranian Consortium) is a subcontractor to the Bechtel/EDF/Battelle Consortium and performed much of the dose analysis. The analysis concluded that ALARA could be achieved with appropriate implementation of existing Ukrainian regulations and procedures, and developing conceptual design criteria and features.

Shipler, Dillard B.; Batiy, Valeriy; Povlovsky, Leonid; Schmidt, John P.; Schmieman, Eric A.

2004-03-24T23:59:59.000Z

177

CORCON-MOD1 preliminary evaluation and application to safety analysis of a large LMFBR plant  

SciTech Connect (OSTI)

The CORCON-MOD1 core material-concrete interaction code, developed at the Sandia Laboratories for LWR safety analysis, was adapted for analyzing a postulated LMFBR core melt accident.

Chen, K.H.; Ray, K.S.

1981-06-30T23:59:59.000Z

178

Inception report and Gap analysis  

E-Print Network [OSTI]

Inception report and Gap analysis Boiler inspection Riga, June 2004 #12;Inception report and gap analysis ­ boiler inspection Table of Content 1 INTRODUCTION ................................................................................................................................. 3 2 BOILER INSTALLATIONS ­ GAP ANALYSIS

179

Production, Storage, and FC Analysis  

Broader source: Energy.gov [DOE]

Presentation on Production, Storage, and FC Analysis to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

180

Statistical Hot Channel Analysis for the NBSR  

SciTech Connect (OSTI)

A statistical analysis of thermal limits has been carried out for the research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The objective of this analysis was to update the uncertainties of the hot channel factors with respect to previous analysis for both high-enriched uranium (HEU) and low-enriched uranium (LEU) fuels. Although uncertainties in key parameters which enter into the analysis are not yet known for the LEU core, the current analysis uses reasonable approximations instead of conservative estimates based on HEU values. Cumulative distribution functions (CDFs) were obtained for critical heat flux ratio (CHFR), and onset of flow instability ratio (OFIR). As was done previously, the Sudo-Kaminaga correlation was used for CHF and the Saha-Zuber correlation was used for OFI. Results were obtained for probability levels of 90%, 95%, and 99.9%. As an example of the analysis, the results for both the existing reactor with HEU fuel and the LEU core show that CHFR would have to be above 1.39 to assure with 95% probability that there is no CHF. For the OFIR, the results show that the ratio should be above 1.40 to assure with a 95% probability that OFI is not reached.

Cuadra A.; Baek J.

2014-05-27T23:59:59.000Z

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

Sandia National Laboratories: Modeling & Analysis  

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

Sandia Study Shows Large LNG Fires Hotter but Smaller Than Expected On December 6, 2011, in Analysis, Energy Assurance, Infrastructure Security, Modeling, Modeling & Analysis,...

182

PORTFOLIO ANALYSIS AND ITS POTENTIAL  

E-Print Network [OSTI]

Vidaver Electricity Analysis Office Electricity Supply Analysis Division California Energy Commission ............................................................................................................................. 5 Gas Price Risk.................................................................................................................................. 9 Discount Rates ­ The Present Cost of Future Gas Prices

183

Requirements Identification, Analysis and Measurement  

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

Analysis, and Management adds detail and rigor to the Mission Analysis output by: Refining the initial customer input into formal Customer Requirements Identifying any...

184

ORISE: Media Analysis and Monitoring  

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

Media Analysis and Monitoring The Oak Ridge Institute for Science and Education (ORISE) uses comprehensive media analysis and monitoring tools to define media interest and the...

185

E-Print Network 3.0 - air system analysis Sample Search Results  

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

Quality Publications Assignment 4 5 Oct. 13 Combustion... ; Pollution Meteorology Air Pollution Topics 3 CORE Network Data Analysis 5 6 Oct. 20 Trajectories... and Trends...

186

E-Print Network 3.0 - analysis full genome Sample Search Results  

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

Markers: 2996 cores from 211 patients; Analysis by 12 Laboratories 12;UCSC Cancer Genomics Browser... Stephen Benz Cancer Cytogenomics Microarray Consortium August 5th, 2010...

187

Figure 2 Analysis Tool Interface Level-1 / PBBT Analysis Tool  

E-Print Network [OSTI]

Figure 2 ­ Analysis Tool Interface Level-1 / PBBT Analysis Tool Introduction The Level-1/PBBT Analysis Tool (LPAT) was designed to assist in the analysis of North American Standard Level-1 Inspection. The data incorporated into the tool includes the results of Level-1 inspections with accompanying PBBT test

188

Statistical Analysis of CCD Data: Error Analysis/Noise Theorem  

E-Print Network [OSTI]

Statistical Analysis of CCD Data: Error Analysis/Noise Theorem Why Statistical Approach? Systematic Errors Random Errors (= Statistical Errors) Accuracy and Precision Best Estimator: Mean, Median Distribution Statistical CCD Data Analysis #12;Why do we need statistical analysis? (= Why do we need to worry

Peletier, Reynier

189

Power electronics reliability analysis.  

SciTech Connect (OSTI)

This report provides the DOE and industry with a general process for analyzing power electronics reliability. The analysis can help with understanding the main causes of failures, downtime, and cost and how to reduce them. One approach is to collect field maintenance data and use it directly to calculate reliability metrics related to each cause. Another approach is to model the functional structure of the equipment using a fault tree to derive system reliability from component reliability. Analysis of a fictitious device demonstrates the latter process. Optimization can use the resulting baseline model to decide how to improve reliability and/or lower costs. It is recommended that both electric utilities and equipment manufacturers make provisions to collect and share data in order to lay the groundwork for improving reliability into the future. Reliability analysis helps guide reliability improvements in hardware and software technology including condition monitoring and prognostics and health management.

Smith, Mark A.; Atcitty, Stanley

2009-12-01T23:59:59.000Z

190

Contamination analysis unit  

DOE Patents [OSTI]

The portable Contamination Analysis Unit (CAU) measures trace quantifies of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surface by measuring residual hazardous surface contamination, such as tritium and trace organics It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings.

Gregg, Hugh R. (Livermore, CA); Meltzer, Michael P. (Livermore, CA)

1996-01-01T23:59:59.000Z

191

Contamination analysis unit  

DOE Patents [OSTI]

The portable Contamination Analysis Unit (CAU) measures trace quantities of surface contamination in real time. The detector head of the portable contamination analysis unit has an opening with an O-ring seal, one or more vacuum valves and a small mass spectrometer. With the valve closed, the mass spectrometer is evacuated with one or more pumps. The O-ring seal is placed against a surface to be tested and the vacuum valve is opened. Data is collected from the mass spectrometer and a portable computer provides contamination analysis. The CAU can be used to decontaminate and decommission hazardous and radioactive surfaces by measuring residual hazardous surface contamination, such as tritium and trace organics. It provides surface contamination data for research and development applications as well as real-time process control feedback for industrial cleaning operations and can be used to determine the readiness of a surface to accept bonding or coatings. 1 fig.

Gregg, H.R.; Meltzer, M.P.

1996-05-28T23:59:59.000Z

192

Advanced application of the discrete generalized multigroup method and recondensation to reactor analysis  

E-Print Network [OSTI]

Fine-group whole-core reactor analysis remains one of the long sought goals of the reactor physics community. Such a detailed analysis is typically too computationally expensive to be realized on anything except the largest ...

Everson, Matthew S

2014-01-01T23:59:59.000Z

193

Cost analysis guidelines  

SciTech Connect (OSTI)

The first phase of the Depleted Uranium Hexafluoride Management Program (Program)--management strategy selection--consists of several program elements: Technology Assessment, Engineering Analysis, Cost Analysis, and preparation of an Environmental Impact Statement (EIS). Cost Analysis will estimate the life-cycle costs associated with each of the long-term management strategy alternatives for depleted uranium hexafluoride (UF6). The scope of Cost Analysis will include all major expenditures, from the planning and design stages through decontamination and decommissioning. The costs will be estimated at a scoping or preconceptual design level and are intended to assist decision makers in comparing alternatives for further consideration. They will not be absolute costs or bid-document costs. The purpose of the Cost Analysis Guidelines is to establish a consistent approach to analyzing of cost alternatives for managing Department of Energy`s (DOE`s) stocks of depleted uranium hexafluoride (DUF6). The component modules that make up the DUF6 management program differ substantially in operational maintenance, process-options, requirements for R and D, equipment, facilities, regulatory compliance, (O and M), and operations risk. To facilitate a consistent and equitable comparison of costs, the guidelines offer common definitions, assumptions or basis, and limitations integrated with a standard approach to the analysis. Further, the goal is to evaluate total net life-cycle costs and display them in a way that gives DOE the capability to evaluate a variety of overall DUF6 management strategies, including commercial potential. The cost estimates reflect the preconceptual level of the designs. They will be appropriate for distinguishing among management strategies.

Strait, R.S.

1996-01-10T23:59:59.000Z

194

UCF WP TIPOVER ANALYSIS  

SciTech Connect (OSTI)

The purpose of this analysis is to determine the structural response of the 21 pressurized water reactor (PWR) uncanistered fuel (UCF) waste package (WP) to a tipover design basis event (DBE) dynamic load; the results will be reported in terms of stress magnitudes. Finite-element solution was performed by making use of the commercially available ANSYS finite-element code. A finite-element model of the waste package was developed and analyzed for a tipover DBE dynamic load. The results of this analysis were provided in tables and were also plotted in terms of the maximum stress contours to determine their locations.

Z. Ceylan

1998-04-28T23:59:59.000Z

195

Analysis Preservation in ATLAS  

E-Print Network [OSTI]

Long before data taking ATLAS established a policy that all analyses need to be preserved. In the initial data-taking period, this has been achieved by various tools and techniques. ATLAS is now reviewing the analysis preservation with the aim to bring coherence and robustness to the process and with a clearer view of the level of reproducibility that is reasonably achievable. The secondary aim is to reduce the load on the analysts. Once complete, this will serve for our internal preservation needs but also provide a basis for any subsequent sharing of analysis results with external parties.

Heinrich, Lukas; The ATLAS collaboration; Jones, Roger; Cranmer, Kyle

2015-01-01T23:59:59.000Z

196

Numerical Analysis Gordon K. Smyth  

E-Print Network [OSTI]

Numerical Analysis Gordon K. Smyth May 1997 Numerical analysis is concerned with the accurate discipline of numer­ ical analysis is almost entirely a product of the period since 1950 during which biostatisticians can benefit from familiarity with numerical analysis. An understanding of the numerical methods

Smyth, Gordon K.

197

STEP Utility Bill Analysis Report  

Broader source: Energy.gov [DOE]

STEP Utility Bill Analysis Report, from the Tool Kit Framework: Small Town University Energy Program (STEP).

198

Image texture analysis of elastograms  

E-Print Network [OSTI]

generated elastograms to obtain effective texture features. Four image analysis techniques, co-occurrence statistics, wavelet decomposition, fractal analysis and granulomeay are used to extract a number of features from each image. The inclusions...-RESOLUTION FRACTAL ANALYSIS . . . . . . E. GRANULOMETRIC FEATURES . . F. DATA NORMALIZATION . G. SEPARABILITY MEASURE 13 13 . . . . . 14 . . . . . 20 . . . . . 29 33 36 36 IV TEXTURE ANALYSIS OF SIMULATED ELASTOGRAMS. . . . . . . . . . . 38 A. SIMULATION...

Hussain, Fasahat

1999-01-01T23:59:59.000Z

199

Toward Models for Forensic Analysis  

E-Print Network [OSTI]

Toward Models for Forensic Analysis Sean Peisert (UC San Diego) Matt Bishop (UC Davis) Sid Karin is Forensic Analysis? Forensic analysis is the process of answering the questions: How did an event take place? What was the nature of the event? What were the effects of the event? Forensic analysis applies

Peisert, Sean

200

Pest Risk Analysis for Hymenoscyphus  

E-Print Network [OSTI]

Pest Risk Analysis for Hymenoscyphus pseudoalbidus for the UK and the Republic of Ireland #12;2 PRA for Hymenoscyphus pseudoalbidus C.E. Sansford 23rd May 2013 Pest Risk Analysis Pest Risk Analysis for Hymenoscyphus (Kowalski and Holdenrieder, 2009). 1 Please cite this document as: Sansford, CE (2013). Pest Risk Analysis

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

Environmental analysis & Re-  

E-Print Network [OSTI]

Environmental analysis & Re- sources Manage- ment includes a range of careers. Environmental, and managers of land, water, and atmos- pheric resources. Their job titles include those listed in the bulleted to make you an attractive and competitive environmental management professional. The package is based

de Doncker, Elise

202

Radiative Flux Analysis  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

The Radiative Flux Analysis is a technique for using surface broadband radiation measurements for detecting periods of clear (i.e. cloudless) skies, and using the detected clear-sky data to fit functions which are then used to produce continuous clear-sky estimates. The clear-sky estimates and measurements are then used in various ways to infer cloud macrophysical properties.

Long, Chuck [NOAA

203

Electronic Mail Analysis Capability  

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

Establishes the pilot program to test the Department of Energy (DOE) Electronic Mail Analysis Capability (EMAC), which will be used to monitor and analyze outgoing and incoming electronic mail (e-mail) from the National Nuclear Security Administration (NNSA) and DOE laboratories that are engaged in nuclear weapons design or work involving special nuclear material. No cancellation.

2001-01-08T23:59:59.000Z

204

Fourier Analysis Tom Leinster  

E-Print Network [OSTI]

functions. (For recall that every power series is infinitely differen- tiable inside its disk of convergence . . . . . . . . . . . . . . . . 66 D2 The dual of a finite abelian group . . . . . . . . . . . . . . . . . . 70 D3 Fourier transforms The algebraist thinks: `Analysis is hard. Can we reduce it to algebra?' Idea Use power series. 1 Many functions f

205

Regional Analysis Briefs  

Reports and Publications (EIA)

Regional Analysis Briefs (RABs) provide an overview of specific regions that play an important role in world energy markets, either directly or indirectly. These briefs cover areas that are currently major producers (Caspian Sea), have geopolitical importance (South China Sea), or may have future potential as producers or transit areas (East Africa, Eastern Mediterranean).

2028-01-01T23:59:59.000Z

206

Country Analysis Briefs  

Reports and Publications (EIA)

An ongoing compilation of country energy profiles. The Energy Information Administration (EIA) maintains Country Analysis Briefs (CABs) for specific countries that are important to world energy markets, including members of the Organization of the Petroleum Exporting Countries (OPEC), major non-OPEC oil producers, major energy transit countries, major energy consumers, and other areas of current interest to energy analysts and policy makers.

2028-01-01T23:59:59.000Z

207

Coal systems analysis  

SciTech Connect (OSTI)

This collection of papers provides an introduction to the concept of coal systems analysis and contains examples of how coal systems analysis can be used to understand, characterize, and evaluate coal and coal gas resources. Chapter are: Coal systems analysis: A new approach to the understanding of coal formation, coal quality and environmental considerations, and coal as a source rock for hydrocarbons by Peter D. Warwick. Appalachian coal assessment: Defining the coal systems of the Appalachian Basin by Robert C. Milici. Subtle structural influences on coal thickness and distribution: Examples from the Lower Broas-Stockton coal (Middle Pennsylvanian), Eastern Kentucky Coal Field, USA by Stephen F. Greb, Cortland F. Eble, and J.C. Hower. Palynology in coal systems analysis The key to floras, climate, and stratigraphy of coal-forming environments by Douglas J. Nichols. A comparison of late Paleocene and late Eocene lignite depositional systems using palynology, upper Wilcox and upper Jackson Groups, east-central Texas by Jennifer M.K. O'Keefe, Recep H. Sancay, Anne L. Raymond, and Thomas E. Yancey. New insights on the hydrocarbon system of the Fruitland Formation coal beds, northern San Juan Basin, Colorado and New Mexico, USA by W.C. Riese, William L. Pelzmann, and Glen T. Snyder.

Warwick, P.D. (ed.)

2005-07-01T23:59:59.000Z

208

Zeta Functional Analysis  

E-Print Network [OSTI]

We intimate deeper connections between the Riemann zeta and gamma functions than often reported and further derive a new formula for expressing the value of $\\zeta(2n+1)$ in terms of zeta at other fractional points. This paper also establishes and presents new expository notes and perspectives on zeta function theory and functional analysis. In addition, a new fundamental result, in form of a new function called omega $\\Omega(s)$, is introduced to analytic number theory for the first time. This new function together with some of its most fundamental properties and other related identities are here disclosed and presented as a new approach to the analysis of sums of generalised harmonic series, related alternating series and polygamma functions associated with Riemann zeta function.

Michael A. Idowu

2014-10-15T23:59:59.000Z

209

SAMPLING AND ANALYSIS PROTOCOLS  

SciTech Connect (OSTI)

Radiological sampling and analyses are performed to collect data for a variety of specific reasons covering a wide range of projects. These activities include: Effluent monitoring; Environmental surveillance; Emergency response; Routine ambient monitoring; Background assessments; Nuclear license termination; Remediation; Deactivation and decommissioning (D&D); and Waste management. In this chapter, effluent monitoring and environmental surveillance programs at nuclear operating facilities and radiological sampling and analysis plans for remediation and D&D activities will be discussed.

Jannik, T; P Fledderman, P

2007-02-09T23:59:59.000Z

210

Automated Job Hazards Analysis  

Broader source: Energy.gov [DOE]

AJHA Program - The Automated Job Hazard Analysis (AJHA) computer program is part of an enhanced work planning process employed at the Department of Energy's Hanford worksite. The AJHA system is routinely used to performed evaluations for medium and high risk work, and in the development of corrective maintenance work packages at the site. The tool is designed to ensure that workers are fully involved in identifying the hazards, requirements, and controls associated with tasks.

211

Residual gas analysis device  

DOE Patents [OSTI]

A system is provided for testing the hermeticity of a package, such as a microelectromechanical systems package containing a sealed gas volume, with a sampling device that has the capability to isolate the package and breach the gas seal connected to a pulse valve that can controllably transmit small volumes down to 2 nanoliters to a gas chamber for analysis using gas chromatography/mass spectroscopy diagnostics.

Thornberg, Steven M. (Peralta, NM)

2012-07-31T23:59:59.000Z

212

Benchmarking and Data Analysis  

E-Print Network [OSTI]

? Meetings ? Focused on individual knowledge ESL-KT-14-11-14 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Personalization ? Relationship building ? Increase informal interactions ? Share experiences and brainstorm ? Data...Benchmarking and Data Analysis Kellie Williams | Houston ISD ESL-KT-14-11-14 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Benchmarking ? Process of comparing data sets ? Baselines, Goals, KPIs ? Energy Star...

Williams, K.

2014-01-01T23:59:59.000Z

213

Independent Statistics & Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningto FuelIndependent Statistics & Analysis

214

Text analysis methods, text analysis apparatuses, and articles of manufacture  

DOE Patents [OSTI]

Text analysis methods, text analysis apparatuses, and articles of manufacture are described according to some aspects. In one aspect, a text analysis method includes accessing information indicative of data content of a collection of text comprising a plurality of different topics, using a computing device, analyzing the information indicative of the data content, and using results of the analysis, identifying a presence of a new topic in the collection of text.

Whitney, Paul D; Willse, Alan R; Lopresti, Charles A; White, Amanda M

2014-10-28T23:59:59.000Z

215

Optical Filter Design: Gain Analysis and Tolerance Analysis  

E-Print Network [OSTI]

OPTICAL FILTER DESIGN: GAIN ANALYSIS AND TOLERANCE ANALYSIS A Thesis by VIVEK VANDRASI Submitted to the O ce of Graduate Studies of Texas A&M University in partial ful llment of the requirements for the degree of MASTER OF SCIENCE August... 2010 Major Subject: Electrical Engineering OPTICAL FILTER DESIGN: GAIN ANALYSIS AND TOLERANCE ANALYSIS A Thesis by VIVEK VANDRASI Submitted to the O ce of Graduate Studies of Texas A&M University in partial ful llment of the requirements...

Vandrasi, Vivek

2011-10-21T23:59:59.000Z

216

Generalized Multicoincidence Analysis Methods  

SciTech Connect (OSTI)

The ability to conduct automated trace radionuclide analysis at or near the sample collection point would provide a valuable tool for emergency response, nuclear forensics and environmental monitoring. Pacific Northwest National Laboratory is developing systems for this purpose based on dual gamma-ray spectrometers, e.g. NaI(TI) or HPGe, combined with thin organic scintillator sensors to detect light charged particles. Translating the coincident signatures recorded by these systems, which include , and , into the concentration of detectable radionuclides in the sample requires generalized multicoincidence analysis tools. The development and validation of the Coincidence Lookup Library, which currently contains the probabilities of single and coincidence signatures from more than 420 isotopes, is described. Also discussed is a method to calculate the probability of observing a coincidence signature which incorporates true coincidence summing effects. These effects are particularly important for high-geometric-efficiency detection systems. Finally, a process for validating the integrated analysis software package is demonstrated using GEANT 4 simulations of the prototype detector systems.

Warren, Glen A.; Smith, Leon E.; Aalseth, Craig E.; Ellis, J. E.; Valsan, Andrei B.; Mengesha, Wondwosen

2005-10-01T23:59:59.000Z

217

(Intrusion Path Analysis)  

SciTech Connect (OSTI)

The design and implementation of an Intrusion Path Analysis (IPA) function came about as a result of the upgrades to the security systems at the Savannah River Site (SRS), near Aiken, South Carolina. The stated requirements for IPA were broad, leaving opportunity for creative freedom during design and development. The essential elements were that it: be based on alarm and sensor state data; consider insider as well as outsider threats; be flexible and easily enabled or disabled; not be processor intensive; and provide information to the operator in the event the analysis reveals possible path openings. The final design resulted from many and varied conceptual inputs, and will be implemented in selected test areas at SRS. It fulfils the requirements and: allows selective inclusion of sensors in the analysis; permits the formation of concentric rings of protection around assets; permits the defining of the number of rings which must be breached before issuing an alert; evaluates current sensor states as well as a recent, configurable history of sensor states; considers the sensors' physical location, with respect to the concentric rings; and enables changes for maintenance without software recompilation. 3 figs.

Hardwick, R D

1989-01-01T23:59:59.000Z

218

Data& Error Analysis 1 DATA and ERROR ANALYSIS  

E-Print Network [OSTI]

Data& Error Analysis 1 DATA and ERROR ANALYSIS Performing the experiment and collecting data learned, you might get a better grade.) Data analysis should NOT be delayed until all of the data. This will help one avoid the problem of spending an entire class collecting bad data because of a mistake

Mukasyan, Alexander

219

Petroleum County Secondary Data Analysis  

E-Print Network [OSTI]

Petroleum County Secondary Data Analysis July 23, 2012 1 Community Health Data, MT Dept American Diabetes Association (2012) Region 3 (South Central) ­ Judith Basin, Fergus, Petroleum* #12; Petroleum County Secondary Data Analysis July 23, 2012 2 Socioeconomic Measures1

Maxwell, Bruce D.

220

PORTAL Aggregation Analysis and Documentation  

E-Print Network [OSTI]

PORTAL Aggregation Analysis and Documentation Kristin A. Tufte Portland State University Introduction This document describes the aggregation procedures for PORTAL . Analysis of different aggregation system. Details on the status values and their descriptions can be found in the SWARM documentation

Bertini, Robert L.

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

Scalable Performance Measurement and Analysis  

SciTech Connect (OSTI)

Concurrency levels in large-scale, distributed-memory supercomputers are rising exponentially. Modern machines may contain 100,000 or more microprocessor cores, and the largest of these, IBM's Blue Gene/L, contains over 200,000 cores. Future systems are expected to support millions of concurrent tasks. In this dissertation, we focus on efficient techniques for measuring and analyzing the performance of applications running on very large parallel machines. Tuning the performance of large-scale applications can be a subtle and time-consuming task because application developers must measure and interpret data from many independent processes. While the volume of the raw data scales linearly with the number of tasks in the running system, the number of tasks is growing exponentially, and data for even small systems quickly becomes unmanageable. Transporting performance data from so many processes over a network can perturb application performance and make measurements inaccurate, and storing such data would require a prohibitive amount of space. Moreover, even if it were stored, analyzing the data would be extremely time-consuming. In this dissertation, we present novel methods for reducing performance data volume. The first draws on multi-scale wavelet techniques from signal processing to compress systemwide, time-varying load-balance data. The second uses statistical sampling to select a small subset of running processes to generate low-volume traces. A third approach combines sampling and wavelet compression to stratify performance data adaptively at run-time and to reduce further the cost of sampled tracing. We have integrated these approaches into Libra, a toolset for scalable load-balance analysis. We present Libra and show how it can be used to analyze data from large scientific applications scalably.

Gamblin, T

2009-10-27T23:59:59.000Z

222

Sandia National Laboratories: Modeling & Analysis  

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

On September 19, 2013, in Computational Modeling & Simulation, Distribution Grid Integration, Energy, Facilities, Grid Integration, Modeling, Modeling & Analysis, News, News &...

223

Ontological Analysis P. B. Ladkin  

E-Print Network [OSTI]

such as HAZOP or FMEA cannot answer CQ. Ontological Analysis, OA, is a method for developing safety requirements

Ladkin, Peter B.

224

Numerical Analysis Gordon K. Smyth  

E-Print Network [OSTI]

Numerical Analysis Gordon K. Smyth in Encyclopedia of Biostatistics (ISBN 0471 975761) Edited by Peter Armitage and Theodore Colton John Wiley & Sons, Ltd, Chichester, 1998 #12;Numerical Analysis Numerical analysis is concerned with the accurate and efficient evalua- tion of mathematical expressions

Smyth, Gordon K.

225

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Daniel D. Huppert, Chair Lon L. Peters, Vice-Chair Joel R and Guidance for Economic Analysis in Subbasin Planning Independent Economic Analysis Board January 2003, document IEAB 2003-2 Summary Subbasin planning may need to consider two types of economic issues; 1

226

Beowulf Analysis Symbolic INterface BASIN: Interactive Parallel Data Analysis for Everyone  

E-Print Network [OSTI]

The advent of affordable parallel computers such as Beowulf PC clusters and, more recently, of multi-core PCs has been highly beneficial for a large number of scientists and smaller institutions that might not otherwise have access to substantial computing facilities. However, there has not been an analogous progress in the development and dissemination of parallel software: scientists need the expertise to develop parallel codes and have to invest a significant amount of time in the development of tools even for the most common data analysis tasks. We describe the Beowulf Analysis Symbolic INterface (BASIN) a multi-user parallel data analysis and visualization framework. BASIN is aimed at providing scientists with a suite of parallel libraries for astrophysical data analysis along with general tools for data distribution and parallel operations on distributed data to allow them to easily develop new parallel libraries for their specific tasks.

Enrico Vesperini; David M. Goldberg; Stephen L. W. McMillan; James Dura; Douglas Jones

2008-04-29T23:59:59.000Z

227

SMACS. Probabilistic Seismic Analysis System  

SciTech Connect (OSTI)

The SMACS (Seismic Methodology Analysis Chain with Statistics) system of computer programs is one of the major computational tools of the U.S. NRC Seismic Safety Margins Research Program (SSMRP). SMACS is comprised of the core program SMAX, which performs the SSI response analyses, five preprocessing programs, and two postprocessors. The preprocessing programs include: GLAY and CLAN, which generate the nominal impedance matrices and wave scattering vectors for surface-founded structures; INSSIN, which projects the dynamic properties of structures to the foundation in the form of modal participation factors and mass matrices; SAPPAC, which projects the dynamic and pseudostatic properties of multiply-supported piping systems to the support locations, and LNGEN, which can be used to generate the multiplication factors to be applied to the nominal soil, structural, and subsystem properties for each of the response calculations in accounting for random variations of these properties. The postprocessors are: PRESTO, which performs statistical operations on the raw data from the response vectors that SMAX produces to calculate best fit lognormal distributions for each response location, and CHANGO, which manipulates the data produced by PRESTO to produce other results of interest to the user. Also included is the computer program SAP4 (a modified version of the University of California, Berkeley SAPIV program), a general linear structural analysis program used for eigenvalue extractions and pseudostatic mode calculations of the models of major structures and subsystems. SAP4 is used to prepare input to the INSSIN and SAPPAC preprocessing programs. The GLAY and CLAN programs were originally developed by J.E. Luco (UCSD) and H.L. Wong (USC).

Johnson, J.J.; Maslenikov, O.R.; Tiong, L.W.; Mraz, M.J. [EQE Incorporated, San Ramon, CA (United States); Bumpus, S.; Gerhard, M.A. [Lawrence Livermore National Lab., CA (United States)

1992-01-14T23:59:59.000Z

228

Arundo Donax Analysis Report  

SciTech Connect (OSTI)

This is a summary report of preliminary analysis conducted on Arundo Donax. Arundo Donax was received from Greenwood Resources via Portland General Electric. PGE plans to transition a coal-fired boiler to 100% biomass by 2020, and has partnered with EPRI and INL to conduct the necessary testing and development to understand what needs to take place to make this transition. Arundo Donax is a promising energy crop for biopower, and is as yet relatively untested and uncharacterized. The INL has begun initial characterization of this material, and this summary report presents the initial findings.

Corrie I. Nichol, Ph.D.; Tyler L. Westover, Ph.D.

2012-01-01T23:59:59.000Z

229

Bus transfer analysis  

SciTech Connect (OSTI)

This paper discusses bus transfer schemes and the methodology used in modeling and analysis. Due to the unavailability of generic acceptance criteria, simulations were performed to analyze the actual fast bus transfer operations at four operating nuclear power generating stations. Sample simulation results illustrating the transient variations in motors currents and torques are included. The analyses were performed to ensure that motors and other rotating parts are not subjected to excessive or accumulated stresses caused by bus transfer operations. A summary of the experience gained in the process of performing this work and suggested bus transfer acceptance criteria are also presented.

Weronick, R.; Hassan, I.D. [Raytheon Engineers and Constructors, Lyndhurst, NJ (United States)

1996-11-01T23:59:59.000Z

230

Chemical exchange program analysis.  

SciTech Connect (OSTI)

As part of its EMS, Sandia performs an annual environmental aspects/impacts analysis. The purpose of this analysis is to identify the environmental aspects associated with Sandia's activities, products, and services and the potential environmental impacts associated with those aspects. Division and environmental programs established objectives and targets based on the environmental aspects associated with their operations. In 2007 the most significant aspect identified was Hazardous Materials (Use and Storage). The objective for Hazardous Materials (Use and Storage) was to improve chemical handling, storage, and on-site movement of hazardous materials. One of the targets supporting this objective was to develop an effective chemical exchange program, making a business case for it in FY07, and fully implementing a comprehensive chemical exchange program in FY08. A Chemical Exchange Program (CEP) team was formed to implement this target. The team consists of representatives from the Chemical Information System (CIS), Pollution Prevention (P2), the HWMF, Procurement and the Environmental Management System (EMS). The CEP Team performed benchmarking and conducted a life-cycle analysis of the current management of chemicals at SNL/NM and compared it to Chemical Exchange alternatives. Those alternatives are as follows: (1) Revive the 'Virtual' Chemical Exchange Program; (2) Re-implement a 'Physical' Chemical Exchange Program using a Chemical Information System; and (3) Transition to a Chemical Management Services System. The analysis and benchmarking study shows that the present management of chemicals at SNL/NM is significantly disjointed and a life-cycle or 'Cradle-to-Grave' approach to chemical management is needed. This approach must consider the purchasing and maintenance costs as well as the cost of ultimate disposal of the chemicals and materials. A chemical exchange is needed as a mechanism to re-apply chemicals on site. This will not only reduce the quantity of unneeded chemicals and the amount spent on new purchases, but will also avoid disposal costs. If SNL/NM were to realize a 5 percent reduction in chemical inventory and a 10 percent reduction in disposal of unused chemicals the total savings would be $189, 200 per year.

Waffelaert, Pascale

2007-09-01T23:59:59.000Z

231

Sandia National Laboratories: Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive SolarEducation Programs: CroSSlinksHuman ResourcesFacebookAnalysis Sandia

232

Risk Analysis and Simulation  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 Resource Program September DepartmentRio Grande ProjectAnalysis

233

Regulatory Analysis on Criteria  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298,NIST3 AÇORIANONewsRegulatory Analysis on Criteria for

234

Drift Degradation Analysis  

SciTech Connect (OSTI)

Degradation of underground openings as a function of time is a natural and expected occurrence for any subsurface excavation. Over time, changes occur to both the stress condition and the strength of the rock mass due to several interacting factors. Once the factors contributing to degradation are characterized, the effects of drift degradation can typically be mitigated through appropriate design and maintenance of the ground support system. However, for the emplacement drifts of the geologic repository at Yucca Mountain, it is necessary to characterize drift degradation over a 10,000-year period, which is well beyond the functional period of the ground support system. This document provides an analysis of the amount of drift degradation anticipated in repository emplacement drifts for discrete events and time increments extending throughout the 10,000-year regulatory period for postclosure performance. This revision of the drift degradation analysis was developed to support the license application and fulfill specific agreement items between the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Department of Energy (DOE). The earlier versions of ''Drift Degradation Analysis'' (BSC 2001 [DIRS 156304]) relied primarily on the DRKBA numerical code, which provides for a probabilistic key-block assessment based on realistic fracture patterns determined from field mapping in the Exploratory Studies Facility (ESF) at Yucca Mountain. A key block is defined as a critical block in the surrounding rock mass of an excavation, which is removable and oriented in an unsafe manner such that it is likely to move into an opening unless support is provided. However, the use of the DRKBA code to determine potential rockfall data at the repository horizon during the postclosure period has several limitations: (1) The DRKBA code cannot explicitly apply dynamic loads due to seismic ground motion. (2) The DRKBA code cannot explicitly apply loads due to thermal stress. (3) The DRKBA code, which determines structurally controlled key-block failure, is not applicable for stress-controlled failure in the lithophysal units. To address these limitations, additional numerical codes have been included that can explicitly apply seismic and thermal loads, providing significant improvements to the analysis of drift degradation and extending the validity of drift degradation models.

D. Kicker

2004-09-16T23:59:59.000Z

235

Alternatives Analysis for the Resumption of Transient Testing Program  

SciTech Connect (OSTI)

An alternatives analysis was performed for resumption of transient testing. The analysis considered eleven alternatives – including both US international facilities. A screening process was used to identify two viable alternatives from the original eleven. In addition, the alternatives analysis includes a no action alternative as required by the National Environmental Policy Act (NEPA). The alternatives considered in this analysis included: 1. Restart the Transient Reactor Test Facility (TREAT) 2. Modify the Annular Core Research Reactor (ACRR) which includes construction of a new hot cell and installation of a new hodoscope. 3. No Action

Lee Nelson

2013-11-01T23:59:59.000Z

236

Climate Analysis The central theme of the Climate Analysis Division is the analysis and  

E-Print Network [OSTI]

Climate Analysis The central theme of the Climate Analysis Division is the analysis and diagnosis of the climate and its variability on the basis of observations and models. The objective of this research of climate change scenarios for impact studies using downscaling techniques. The research can be summarised

Haak, Hein

237

Crude Oil Analysis Database  

DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

The composition and physical properties of crude oil vary widely from one reservoir to another within an oil field, as well as from one field or region to another. Although all oils consist of hydrocarbons and their derivatives, the proportions of various types of compounds differ greatly. This makes some oils more suitable than others for specific refining processes and uses. To take advantage of this diversity, one needs access to information in a large database of crude oil analyses. The Crude Oil Analysis Database (COADB) currently satisfies this need by offering 9,056 crude oil analyses. Of these, 8,500 are United States domestic oils. The database contains results of analysis of the general properties and chemical composition, as well as the field, formation, and geographic location of the crude oil sample. [Taken from the Introduction to COAMDATA_DESC.pdf, part of the zipped software and database file at http://www.netl.doe.gov/technologies/oil-gas/Software/database.html] Save the zipped file to your PC. When opened, it will contain PDF documents and a large Excel spreadsheet. It will also contain the database in Microsoft Access 2002.

Shay, Johanna Y.

238

Decision Analysis for EGS | Department of Energy  

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

Decision Analysis for EGS Decision Analysis for EGS Project objectives: DEVELOPMENT OF ANALYSIS TOOLS TO ASSESS: Uncertainties associated with exploration for EGS; Uncertainties...

239

Final Report - Hydrogen Delivery Infrastructure Options Analysis...  

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

- Hydrogen Delivery Infrastructure Options Analysis Final Report - Hydrogen Delivery Infrastructure Options Analysis This report, by the Nexant team, documents an in-depth analysis...

240

Analysis of Geothermal Reservoir Stimulation using Geomechanics...  

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

Analysis of Geothermal Reservoir Stimulation using Geomechanics-Based Stochastic Analysis of Injection-Induced Seismicity Analysis of Geothermal Reservoir Stimulation using...

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

Geographically Based Hydrogen Demand and Infrastructure Analysis...  

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

Analysis Geographically Based Hydrogen Demand and Infrastructure Analysis Presentation by NREL's Margo Melendez at the 2010 - 2025 Scenario Analysis for Hydrogen Fuel Cell Vehicles...

242

Suggestions for Functional Analysis Basics (FAB) Seminar  

E-Print Network [OSTI]

Aug 14, 2014 ... Page 1 ... Functional analysis is a central topic in analysis at an advanced level and is at the foundation of many parts of analysis, including ...

2014-08-14T23:59:59.000Z

243

LOFA and LOCA analysis on CGNPC SCWR  

SciTech Connect (OSTI)

Safety analysis is one of the chief difficulties during the research and design of SCWRs. At present, the development of SCWR safety analysis code is still in the initial stage all around the world, and very few computer codes could carry out trans-critical calculations where significant changes in water properties would take place. In this paper, a safety analysis code SCTRAN for SCWRs, has been developed based on RETRAN-02. The ability of SCTRAN code to simulate the transient where both supercritical and subcritical regimes are encountered has been verified by comparing with APROS code and RELAP5-3D code, respectively. With SCTRAN code, the preliminary LOFA and LOCA analysis of the SCWR design proposed by CGNPC, have been analyzed. The characteristics and performance of the passive safety systems applied to CGNPC-SCWR are evaluated. The results show that: 1) The SCTRAN computer code developed in this study is capable to carry out safety analysis for SCWRs, and its results are reliable; 2) During LOFA and LOCA accidents, very complex flow regime might take place in the double-pass core design, but the passive safety systems would greatly mitigate the consequences of these transients and increase the inherent safety. (authors)

Wu, P.; Gou, J.; Shan, J.; Jiang, Y.; Zhang, B. [Xi'an Jiaotong Univ., No.28, Xianning West Road, Xi'an, Shaanxi Province (China); Yang, J. [China Nuclear Power Technology Research Inst., Jiangsu Building, Yitian road, Shenzhen, Guangdong Province (China)

2012-07-01T23:59:59.000Z

244

Hypothesis analysis methods, hypothesis analysis devices, and articles of manufacture  

DOE Patents [OSTI]

Hypothesis analysis methods, hypothesis analysis devices, and articles of manufacture are described according to some aspects. In one aspect, a hypothesis analysis method includes providing a hypothesis, providing an indicator which at least one of supports and refutes the hypothesis, using the indicator, associating evidence with the hypothesis, weighting the association of the evidence with the hypothesis, and using the weighting, providing information regarding the accuracy of the hypothesis.

Sanfilippo, Antonio P. (Richland, WA); Cowell, Andrew J. (Kennewick, WA); Gregory, Michelle L. (Richland, WA); Baddeley, Robert L. (Richland, WA); Paulson, Patrick R. (Pasco, WA); Tratz, Stephen C. (Richland, WA); Hohimer, Ryan E. (West Richland, WA)

2012-03-20T23:59:59.000Z

245

Certification/enforcement analysis  

SciTech Connect (OSTI)

Industry compliance with minimum energy efficiency standards will be assured through a two-part program approach of certification and enforcement activities. The technical support document (TSD) presents the analyses upon which the proposed rule for assuring that consumer product comply with applicable energy efficiency standards is based. Much of the TSD is based upon support provided DOE by Vitro Laboratories. The OAO Corporation provided additional support in the development of the sampling plan incorporated in the proposed rule. Vitro's recommended approach to appliance certification and enforcement, developed after consideration of various program options, benefits, and impacts, establishes the C/E program framework, general criteria, and procedures for assuring a specified level of energy efficiency performance of covered consumer products. The results of the OAO analysis are given in Volume II of the TSD.

None

1980-06-01T23:59:59.000Z

246

Ultrasound Analysis of Slurries  

DOE Patents [OSTI]

An autoclave reactor allows for the ultrasonic analysis of slurry concentration and particle size distribution at elevated temperatures and pressures while maintaining the temperature- and pressure-sensitive ultrasonic transducers under ambient conditions. The reactor vessel is a hollow stainless steel cylinder containing the slurry which includes a stirrer and a N, gas source for directing gas bubbles through the slurry. Input and output transducers are connected to opposed lateral portions of the hollow cylinder for respectively directing sound waves through the slurry and receiving these sound waves after transmission through the slurry, where changes in sound wave velocity and amplitude can be used to measure slurry parameters. Ultrasonic adapters connect the transducers to the reactor vessel in a sealed manner and isolate the transducers from the hostile conditions within the vessel without ultrasonic signal distortion or losses.

Soong, Yee and Blackwell, Arthur G.

2005-11-01T23:59:59.000Z

247

Capacitor discharge pulse analysis.  

SciTech Connect (OSTI)

Capacitors used in firing sets and other high discharge current applications are discharge tested to verify performance of the capacitor against the application requirements. Parameters such as capacitance, inductance, rise time, pulse width, peak current and current reversal must be verified to ensure that the capacitor will meet the application needs. This report summarizes an analysis performed on the discharge current data to extract these parameters by fitting a second-order system model to the discharge data and using this fit to determine the resulting performance metrics. Details of the theory and implementation are presented. Using the best-fit second-order system model to extract these metrics results in less sensitivity to noise in the measured data and allows for direct extraction of the total series resistance, inductance, and capacitance.

Baker, Michael Sean; Griffiths, Stewart K.; Tanner, Danelle Mary

2013-08-01T23:59:59.000Z

248

Ultrasound Analysis Of Slurries  

DOE Patents [OSTI]

An autoclave reactor allows for the ultrasonic analysis of slurry concentration and particle size distribution at elevated temperatures and pressures while maintaining the temperature- and pressure-sensitive ultrasonic transducers under ambient conditions. The reactor vessel is a hollow stainless steel cylinder containing the slurry which includes a stirrer and a N.sub.2 gas source for directing gas bubbles through the slurry. Input and output transducers are connected to opposed lateral portions of the hollow cylinder for respectively directing sound waves through the slurry and receiving these sound waves after transmission through the slurry, where changes in sound wave velocity and amplitude can be used to measure slurry parameters. Ultrasonic adapters connect the transducers to the reactor vessel in a sealed manner and isolate the transducers from the hostile conditions within the vessel without ultrasonic signal distortion or losses.

Soong, Yee (Monroeville, PA); Blackwell, Arthur G. (Duquesne, PA)

2005-11-01T23:59:59.000Z

249

ACCIDENT TOLERANT FUEL ANALYSIS  

SciTech Connect (OSTI)

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

Smith, Curtis [Idaho National Laboratory; Chichester, Heather [Idaho National Laboratory; Johns, Jesse [Texas A& M University; Teague, Melissa [Idaho National Laboratory; Tonks, Michael Idaho National Laboratory; Youngblood, Robert [Idaho National Laboratory

2014-09-01T23:59:59.000Z

250

Chemical process hazards analysis  

SciTech Connect (OSTI)

The Office of Worker Health and Safety (EH-5) under the Assistant Secretary for the Environment, Safety and Health of the US Department (DOE) has published two handbooks for use by DOE contractors managing facilities and processes covered by the Occupational Safety and Health Administration (OSHA) Rule for Process Safety Management of Highly Hazardous Chemicals (29 CFR 1910.119), herein referred to as the PSM Rule. The PSM Rule contains an integrated set of chemical process safety management elements designed to prevent chemical releases that can lead to catastrophic fires, explosions, or toxic exposures. The purpose of the two handbooks, ``Process Safety Management for Highly Hazardous Chemicals`` and ``Chemical Process Hazards Analysis,`` is to facilitate implementation of the provisions of the PSM Rule within the DOE. The purpose of this handbook ``Chemical Process Hazards Analysis,`` is to facilitate, within the DOE, the performance of chemical process hazards analyses (PrHAs) as required under the PSM Rule. It provides basic information for the performance of PrHAs, and should not be considered a complete resource on PrHA methods. Likewise, to determine if a facility is covered by the PSM rule, the reader should refer to the handbook, ``Process Safety Management for Highly Hazardous Chemicals`` (DOE- HDBK-1101-96). Promulgation of the PSM Rule has heightened the awareness of chemical safety management issues within the DOE. This handbook is intended for use by DOE facilities and processes covered by the PSM rule to facilitate contractor implementation of the PrHA element of the PSM Rule. However, contractors whose facilities and processes not covered by the PSM Rule may also use this handbook as a basis for conducting process hazards analyses as part of their good management practices. This handbook explains the minimum requirements for PrHAs outlined in the PSM Rule. Nowhere have requirements been added beyond what is specifically required by the rule.

NONE

1996-02-01T23:59:59.000Z

251

Accident Tolerant Fuel Analysis  

SciTech Connect (OSTI)

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for risk-informed margins management by improving economics and reliability, and sustaining safety, of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. In order to carry out the R&D needed for the Pathway, the Idaho National Laboratory is performing a series of case studies that will explore methods- and tools-development issues, in addition to being of current interest in their own right. One such study is a comparative analysis of safety margins of plants using different fuel cladding types: specifically, a comparison between current-technology Zircaloy cladding and a notional “accident-tolerant” (e.g., SiC-based) cladding. The present report begins the process of applying capabilities that are still under development to the problem of assessing new fuel designs. The approach and lessons learned from this case study will be included in future Technical Basis Guides produced by the RISMC Pathway. These guides will be the mechanism for developing the specifications for RISMC tools and for defining how plant decision makers should propose and evaluate margin recovery strategies.

Curtis Smith; Heather Chichester; Jesse Johns; Melissa Teague; Michael Tonks; Robert Youngblood

2014-09-01T23:59:59.000Z

252

Abductive Analysis of Modular Logic Programs  

E-Print Network [OSTI]

Abductive Analysis of Modular Logic Programs Roberto Giacobazzi LIX, Laboratoire d introduce a practical method for abductive analysis of modular logic programs. This is obtained of abductive reasoning in dataflow analysis of logic programs. 1 Introduction Dataflow analysis

Giacobazzi, Roberto

253

Proteogenomic Analysis of a Thermophilic Bacterial Consortium...  

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

Analysis of a Thermophilic Bacterial Consortium Adapted to Deconstruct Switchgrass. Proteogenomic Analysis of a Thermophilic Bacterial Consortium Adapted to Deconstruct...

254

Transcriptional analysis of the unicellular, diazotrophic cyanobacteri...  

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

analysis of the unicellular, diazotrophic cyanobacterium Cyanothece sp. ATCC 51142 grown under short daynight Transcriptional analysis of the unicellular, diazotrophic...

255

Technoeconomic Analysis of Photoelectrochemical (PEC) Hydrogen...  

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

Analysis of Photoelectrochemical (PEC) Hydrogen Production Technoeconomic Analysis of Photoelectrochemical (PEC) Hydrogen Production This report documents the engineering and cost...

256

Analysis Activities at Idaho National Engineering & Environmental...  

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

Analysis Activities at Idaho National Engineering & Environmental Laboratory Analysis Activities at Idaho National Engineering & Environmental Laboratory Presentation on INEENL's...

257

Stretch Efficiency - Thermodynamic Analysis of New Combustion...  

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

Stretch Efficiency - Thermodynamic Analysis of New Combustion Regimes (Agreement 10037) Stretch Efficiency - Thermodynamic Analysis of New Combustion Regimes (Agreement 10037)...

258

Semi-classical signal analysis  

E-Print Network [OSTI]

This study introduces a new signal analysis method called SCSA, based on a semi-classical approach. The main idea in the SCSA is to interpret a pulse-shaped signal as a potential of a Schr\\"odinger operator and then to use the discrete spectrum of this operator for the analysis of the signal. We present some numerical examples and the first results obtained with this method on the analysis of arterial blood pressure waveforms.

Taous-Meriem Laleg-Kirati; Emmanuelle Crépeau; Michel Sorine

2010-07-06T23:59:59.000Z

259

Category:Cuttings Analysis | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin: EnergyBostonFacilityCascade SierraStatus Status ofCore AnalysisCuttings

260

Biomass Rapid Analysis Network (BRAN)  

SciTech Connect (OSTI)

Helping the emerging biotechnology industry develop new tools and methods for real-time analysis of biomass feedstocks, process intermediates and The Biomass Rapid Analysis Network is designed to fast track the development of modern tools and methods for biomass analysis to accelerate the development of the emerging industry. The network will be led by industry and organized and coordinated through the National Renewable Energy Lab. The network will provide training and other activities of interest to BRAN members. BRAN members will share the cost and work of rapid analysis method development, validate the new methods, and work together to develop the training for the future biomass conversion workforce.

Not Available

2003-10-01T23:59:59.000Z

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

Virtual data in CMS analysis  

SciTech Connect (OSTI)

The use of virtual data for enhancing the collaboration between large groups of scientists is explored in several ways: by defining ''virtual'' parameter spaces which can be searched and shared in an organized way by a collaboration of scientists in the course of their analysis; by providing a mechanism to log the provenance of results and the ability to trace them back to the various stages in the analysis of real or simulated data; by creating ''check points'' in the course of an analysis to permit collaborators to explore their own analysis branches by refining selections, improving the signal to background ratio, varying the estimation of parameters, etc.; by facilitating the audit of an analysis and the reproduction of its results by a different group, or in a peer review context. We describe a prototype for the analysis of data from the CMS experiment based on the virtual data system Chimera and the object-oriented data analysis framework ROOT. The Chimera system is used to chain together several steps in the analysis process including the Monte Carlo generation of data, the simulation of detector response, the reconstruction of physics objects and their subsequent analysis, histogramming and visualization using the ROOT framework.

A. Arbree et al.

2003-10-01T23:59:59.000Z

262

GenII Gap Analysis  

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

generally recognized and acceptable approaches for modeling source and consequence phenomenology, and can be applied as appropriate to support accident analysis in term ocumented...

263

Chapter 16: Environmental Impact Analysis  

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

or gases a . This analysis also considers carbon dioxide (CO 2 ). a More information on air pollution characteristics and regulations is available on the U.S. Environment...

264

Power network analysis and optimization  

E-Print Network [OSTI]

chip power supply network optimization using multigrid-basedchip decoupling capacitor optimization for high- performanceSapatnekar, “Analysis and optimization of structured power/

Zhang, Wanping

2009-01-01T23:59:59.000Z

265

"Charter and Code" Gap Analysis ANALYSIS FOR NORWAY  

E-Print Network [OSTI]

"Charter and Code" ­ Gap Analysis ANALYSIS FOR NORWAY The European Charter for Researchers: Acceptable. The principle of research freedom is well-established in Norway. The committee refers for Research Ethics in Norway. #12;In recent years, issues of research ethics have received increasing

Johansen, Tom Henning

266

Text analysis devices, articles of manufacture, and text analysis methods  

DOE Patents [OSTI]

Text analysis devices, articles of manufacture, and text analysis methods are described according to some aspects. In one aspect, a text analysis device includes processing circuitry configured to analyze initial text to generate a measurement basis usable in analysis of subsequent text, wherein the measurement basis comprises a plurality of measurement features from the initial text, a plurality of dimension anchors from the initial text and a plurality of associations of the measurement features with the dimension anchors, and wherein the processing circuitry is configured to access a viewpoint indicative of a perspective of interest of a user with respect to the analysis of the subsequent text, and wherein the processing circuitry is configured to use the viewpoint to generate the measurement basis.

Turner, Alan E; Hetzler, Elizabeth G; Nakamura, Grant C

2013-05-28T23:59:59.000Z

267

DNDO Analysis Cell Concept  

SciTech Connect (OSTI)

The Domestic Nuclear Detection Office (DNDO) has a mission of implementing rad/nuc interdiction capabilities for a managed and coordinated response to threats, integration of federal nuclear forensics programs, and coordinating the development of the global nuclear detection and reporting architecture. In the process of executing this mission, DNDO has generated substantial information, data, technical results, operational workflows and analytical tools. The effective utilization of these resources is an overarching goal of the organization. After nearly a decade of performing work, DNDO faces a challenge in capitalizing on the large amount of data, reports, processes, tools, and people. As new work is being planned, managers and researchers need to have an understating of what information has been collected, what tools are available, the collaborations which can be utilized to propel the work forward, processes to plan and execute, and how to present conclusions and results that can assist the government in making decisions. This type of challenge can be met through the use of a series of organized and connected elements which form a broader structure (cell) that promotes cross utilization of elements such that they can be tailored (analyzed) to fit the context of the problem to be solved. The development of an analysis cell for DNDO will address the challenges of utilizing existing elements, identifying gaps, annually reporting the performance of rad/nuc interdiction instrumentation, and planning the execution of future work.

Pagh, Richard T.; Dimmerling, Paul J.; Guillen, Zoe C.; Hoyt, Joel R.; Jarman, Kenneth D.; Kernan, Warnick J.; Reichmuth, Barbara A.; Rohlfing, Kerrie S.; Schweppe, John E.; Sego, Landon H.; Shergur, Jason M.; Siciliano, Edward R.; Woodring, Mitchell L.

2014-03-12T23:59:59.000Z

268

Cygnus Diverter Switch Analysis  

SciTech Connect (OSTI)

The Cygnus Dual Beam Radiographic Facility consists of two 2.25-MV, 60-kA, 50-ns x-ray sources fielded in an underground laboratory at the Nevada Test Site. The tests performed in this laboratory involve study of the dynamic properties of plutonium and are called subcritical experiments. From end-to-end, the Cygnus machines utilize the following components: Marx generator, water-filled pulse-forming line (PFL), waterfilled coaxial transmission line (WTL), 3-cell inductive voltage adder (IVA), and rod-pinch diode. The upstream WTL interface to the PFL is via a radial insulator with coaxial geometry. The downstream WTL terminates in a manifold where the center conductor splits into three lines which individually connect to each of the IVA cell inputs. There is an impedance mismatch at this juncture. It is a concern that a reflected pulse due to anomalous behavior in the IVA or diode might initiate breakdown upon arrival at the upstream PFL/WTL insulator. Therefore near the beginning of the WTL a radial diverter switch is installed to protect the insulator from over voltage and breakdown. The diverter has adjustable gap spacing, and an in-line aqueous-solution (sodium thiosulfate) resistor array for energy dissipation. There are capacitive voltage probes at both ends of the WTL and on the diverter switch. These voltage signals will be analyzed to determine diverter performance. Using this analysis the usefulness of the diverter switch will be evaluated.

G. Corrow, M. Hansen, D. Henderson, C. Mitton et al.

2008-02-01T23:59:59.000Z

269

Frequency Response Analysis Tool  

SciTech Connect (OSTI)

Frequency response has received a lot of attention in recent years at the national level, which culminated in the development and approval of North American Electricity Reliability Corporation (NERC) BAL-003-1 Frequency Response and Frequency Bias Setting Reliability Standard. This report is prepared to describe the details of the work conducted by Pacific Northwest National Laboratory (PNNL) in collaboration with the Bonneville Power Administration and Western Electricity Coordinating Council (WECC) Joint Synchronized Information Subcommittee (JSIS) to develop a frequency response analysis tool (FRAT). The document provides the details on the methodology and main features of the FRAT. The tool manages the database of under-frequency events and calculates the frequency response baseline. Frequency response calculations are consistent with frequency response measure (FRM) in NERC BAL-003-1 for an interconnection and balancing authority. The FRAT can use both phasor measurement unit (PMU) data, where available, and supervisory control and data acquisition (SCADA) data. The tool is also capable of automatically generating NERC Frequency Response Survey (FRS) forms required by BAL-003-1 Standard.

Etingov, Pavel V.; Kosterev, Dmitry; Dai, T.

2014-12-31T23:59:59.000Z

270

An Open Infrastructure for Scalable, Reconfigurable Analysis  

SciTech Connect (OSTI)

Petascale systems will have hundreds of thousands of processor cores so their applications must be massively parallel. Effective use of petascale systems will require efficient interprocess communication through memory hierarchies and complex network topologies. Tools to collect and analyze detailed data about this communication would facilitate its optimization. However, several factors complicate tool design. First, large-scale runs on petascale systems will be a precious commodity, so scalable tools must have almost no overhead. Second, the volume of performance data from petascale runs could easily overwhelm hand analysis and, thus, tools must collect only data that is relevant to diagnosing performance problems. Analysis must be done in-situ, when available processing power is proportional to the data. We describe a tool framework that overcomes these complications. Our approach allows application developers to combine existing techniques for measurement, analysis, and data aggregation to develop application-specific tools quickly. Dynamic configuration enables application developers to select exactly the measurements needed and generic components support scalable aggregation and analysis of this data with little additional effort.

de Supinski, B R; Fowler, R; Gamblin, T; Mueller, F; Ratn, P; Schulz, M

2008-05-15T23:59:59.000Z

271

ENVIRONMENTAL DATA ANALYSIS WITH MATLAB  

E-Print Network [OSTI]

ENVIRONMENTAL DATA ANALYSIS WITH MATLAB WILLIAM MENKE PROFESSOR OF EARTH AND ENVIRONMENTAL SCIENCE RIGHTS RESERVED. #12;CONTENTS CHAPTER 1: DATA ANALYSIS WITH MATLAB SECTION 1.1 WHY MATLAB? SECTION 1.2 GETTING STARTED WITH MATLAB. SECTION 1.3 GETTING ORGANIZED. SECTION 1.4 NAVIGATING FOLDERS. SECTION 1

Menke, William

272

Canonical Analysis of Unimodular Gravity  

E-Print Network [OSTI]

This short note is devoted to the Hamiltonian analysis of the Unimodular Gravity.We treat the unimodular gravity as General Relativity action with the unimodular constraint imposed with the help of Lagrange multiplier. We perform the canonical analysis of the resulting theory and determine its constraint structure.

J. Kluson

2014-10-07T23:59:59.000Z

273

Passive solar heating and analysis  

SciTech Connect (OSTI)

Passive solar heating experience and analysis techniques are reviewed with emphasis on annual auxiliary heat requirement. The role of analysis in the design of passive solar buildings is discussed. Selected results for existing systems are presented for locations in Saudi Arabia and climatically similar locations in the US. Advanced systems in the research stage are described.

Jones, R.W.

1984-01-01T23:59:59.000Z

274

VCAT: Visual Crosswalk Analysis Tool  

SciTech Connect (OSTI)

VCAT is a knowledge modeling and analysis tool. It was synthesized from ideas in functional analysis, business process modeling, and complex network science. VCAT discovers synergies by analyzing natural language descriptions. Specifically, it creates visual analytic perspectives that capture intended organization structures, then overlays the serendipitous relationships that point to potential synergies within an organization or across multiple organizations.

Cleland, Timothy J. [Los Alamos National Laboratory; Forslund, David W. [Los Alamos National Laboratory; Cleland, Catherine A. [Los Alamos National Laboratory

2012-08-31T23:59:59.000Z

275

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Kenneth L. Casavant, Chair Roger Mann, Vice-Chair Joel R of Independent Economic Analysis Board's Activities and Contributions to NPPC Fish and Wildlife Planning document of achieving the same sound biological objective exist, the alternative with the minimum economic cost

276

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Daniel D. Huppert, Chair Lon L. Peters, Vice-Chair Joel R. Hamilton Kenneth L. Casavant Jack A. Richards Roger Mann Paul C. Sorensen Hans Radtke Economic Review of Instream Water Supply Components of the Salmon Creek Project Independent Economic Analysis Board Northwest

277

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Roger Mann, Chair Noelwah R. Netusil, Vice-Chair Kenneth L. Casavant Daniel D. Huppert Joel R. Hamilton Lon L. Peters Susan S. Hanna Hans Radtke A I - 1 Economic Effects From Columbia River Basin Anadromous Salmonid Fish Production Independent Economic Analysis Board

278

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Hans Radtke, Chair Roger Mann, Vice-Chair Daniel D. Huppert Joel R. Hamilton Susan S. Hanna John Duffield Noelwah R. Netusil Independent Economic Analysis Board Task Number 139 Integrated Hatchery Operations: Fish and Wildlife Program Costs and Other Economic

279

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

IEAB Independent Economic Analysis Board Kenneth L. Casavant, Chair Roger Mann, Vice-Chair Joel R Application of the IEAB's Recommendations and Guidance for Economic Analysis in Subbasin Planning improvements related to economic content of the draft Clearwater Subbasin Management Plan (the draft Clearwater

280

Structural Analysis of Combustion Models  

E-Print Network [OSTI]

Using ReactionKinetics, a Mathematica based package a few dozen detailed models for combustion of hydrogen, carbon monoxide and methanol are investigated. Essential structural characteristics are pulled out, and similarities and differences of the mechanisms are highlighted. These investigations can be used before or parallel with usual numerical investigations, such as pathway analysis, sensitivity analysis, parameter estimation, or simulation.

Tóth, J; Zsély, I

2013-01-01T23:59:59.000Z

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

Thyristor converter simulation and analysis  

SciTech Connect (OSTI)

In this paper we present a simulation on thyristor converters. The simulation features nonlinearity, non-uniform firing, and the commutations. Several applications such as a current regulation, a converter frequency characteristics analysis, and a power line disturbance analysis will be presented. 4 refs., 4 figs.

Zhang, S.Y.

1991-01-01T23:59:59.000Z

282

Energy, Environmental & Economic Systems Analysis  

E-Print Network [OSTI]

Energy, Environmental & Economic Systems Analysis ENPEP-BALANCE: A Tool for Long-term Nuclear Power, Environmental & Economic Systems Analysis A resurgence of interest in nuclear energy is taking place Market Simulations Opportunity Decision and Information Sciences Division Center for Energy

283

SPECTRAL ANALYSIS OF RADIOXENON  

SciTech Connect (OSTI)

Monitoring changes in atmospheric radioxenon concentrations is a major tool in the detection of an underground nuclear explosion. Ground based systems like the Automated Radioxenon Sampler /Analyzer (ARSA), the Swedish Unattended Noble gas Analyzer (SAUNA) and the Automatic portable radiometer of isotopes Xe (ARIX), can collect and detect several radioxenon isotopes by processing and transferring samples into a high efficiency beta-gamma coincidence detector. The high efficiency beta-gamma coincidence detector makes these systems highly sensitive to the radioxenon isotopes 133Xe, 131mXe, 133mXe and 135Xe. The standard analysis uses regions of interest (ROI) to determine the amount of a particular radioxenon isotope present. The ROI method relies on the peaks of interest falling within energy limits of the ROI. Some potential problems inherent in this method are the reliance on stable detector gains and a fixed resolution for each energy peak. In addition, when a high activity sample is measured there will be more interference among the ROI, in particular within the 133Xe, 133mXe, and 131mXe regions. A solution to some of these problems can be obtained through spectral fitting of the data. Spectral fitting is simply the fitting of the peaks using known functions to determine the number and relative peak positions and widths. By knowing this information it is possible to determine which isotopes are present. Area under each peak can then be used to determine an overall concentration for each isotope. Using the areas of the peaks several key detector characteristics can be determined: efficiency, energy calibration, energy resolution and ratios between interfering isotopes (Radon daughters).

Cooper, Matthew W.; Bowyer, Ted W.; Hayes, James C.; Heimbigner, Tom R.; Hubbard, Charles W.; McIntyre, Justin I.; Schrom, Brian T.

2008-09-23T23:59:59.000Z

284

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

SciTech Connect (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

285

ARIES-CS MAINTENANCE SYSTEM DEFINITION AND ANALYSIS  

E-Print Network [OSTI]

ARIES-CS MAINTENANCE SYSTEM DEFINITION AND ANALYSIS LESTER M. WAGANER* and RICHARD J. PEIPERT, Jr in the electronic version. I. INTRODUCTION The ARIES studies, sponsored by the U.S. Depart- ment of Energy and led how the physics and coil definition determine and influence the power core elements. Especially

286

Infrastructure Analysis Tools: A Focus on Cash Flow Analysis (Presentation)  

SciTech Connect (OSTI)

NREL has developed and maintains a variety of infrastructure analysis models for the U.S. Department of Energy. Business case analysis has recently been added to this tool set. This presentation focuses on cash flow analysis. Cash flows depend upon infrastructure costs, optimized spatially and temporally, and assumptions about financing and revenue. NREL has incorporated detailed metrics on financing and incentives into the models. Next steps in modeling include continuing to collect feedback on regional/local infrastructure development activities and 'roadmap' dynamics, and incorporating consumer preference assumptions on infrastructure to provide direct feedback between vehicles and station rollout.

Melaina, M.; Penev, M.

2012-09-01T23:59:59.000Z

287

SYNTHESIS OF SAFETY ANALYSIS AND FIRE HAZARD ANALYSIS METHODOLOGIES  

SciTech Connect (OSTI)

Successful implementation of both the nuclear safety program and fire protection program is best accomplished using a coordinated process that relies on sound technical approaches. When systematically prepared, the documented safety analysis (DSA) and fire hazard analysis (FHA) can present a consistent technical basis that streamlines implementation. If not coordinated, the DSA and FHA can present inconsistent conclusions, which can create unnecessary confusion and can promulgate a negative safety perception. This paper will compare the scope, purpose, and analysis techniques for DSAs and FHAs. It will also consolidate several lessons-learned papers on this topic, which were prepared in the 1990s.

Coutts, D

2007-04-17T23:59:59.000Z

288

Scalable analysis tools for sensitivity analysis and UQ (3160) results.  

SciTech Connect (OSTI)

The 9/30/2009 ASC Level 2 Scalable Analysis Tools for Sensitivity Analysis and UQ (Milestone 3160) contains feature recognition capability required by the user community for certain verification and validation tasks focused around sensitivity analysis and uncertainty quantification (UQ). These feature recognition capabilities include crater detection, characterization, and analysis from CTH simulation data; the ability to call fragment and crater identification code from within a CTH simulation; and the ability to output fragments in a geometric format that includes data values over the fragments. The feature recognition capabilities were tested extensively on sample and actual simulations. In addition, a number of stretch criteria were met including the ability to visualize CTH tracer particles and the ability to visualize output from within an S3D simulation.

Karelitz, David B.; Ice, Lisa G.; Thompson, David C.; Bennett, Janine C.; Fabian, Nathan; Scott, W. Alan; Moreland, Kenneth D.

2009-09-01T23:59:59.000Z

289

Radiation analysis devices, radiation analysis methods, and articles of manufacture  

DOE Patents [OSTI]

Radiation analysis devices include circuitry configured to determine respective radiation count data for a plurality of sections of an area of interest and combine the radiation count data of individual of sections to determine whether a selected radioactive material is present in the area of interest. An amount of the radiation count data for an individual section is insufficient to determine whether the selected radioactive material is present in the individual section. An article of manufacture includes media comprising programming configured to cause processing circuitry to perform processing comprising determining one or more correction factors based on a calibration of a radiation analysis device, measuring radiation received by the radiation analysis device using the one or more correction factors, and presenting information relating to an amount of radiation measured by the radiation analysis device having one of a plurality of specified radiation energy levels of a range of interest.

Roybal, Lyle Gene

2010-06-08T23:59:59.000Z

290

Introduction to Network Analysis 1 Introduction to Network Analysis  

E-Print Network [OSTI]

of movie actors Transportation and logistics network of nuclear power plant Actors, Reactors and More #12). Points Grade 92 A 80 B 60 C 0 F #12;Introduction to Network Analysis 2 Recommended Books (optional

Safro, Ilya

291

The MARTE VNIR Imaging Spectrometer Experiment: Design and Analysis  

E-Print Network [OSTI]

We report on the design, operation, and data analysis methods employed on the VNIR imaging spectrometer instrument that was part of the Mars Astrobiology Research and Technology Experiment (MARTE). The imaging spectrometer is a hyperspectral scanning pushbroom device sensitive to VNIR wavelengths from 400-1000 nm. During the MARTE project, the spectrometer was deployed to the Rio Tinto region of Spain. We analyzed subsets of 3 cores from Rio Tinto using a new band modeling technique. We found most of the MARTE drill cores to contain predominantly goethite, though spatially coherent areas of hematite were identified in Core 23. We also distinguished non Fe-bearing minerals that were subsequently analyzed by X-ray diffraction (XRD) and found to be primarily muscovite. We present drill core maps that include spectra of goethite, hematite, and non Fe-bearing minerals.

Brown, Adrian J; Dunagan, Stephen

2014-01-01T23:59:59.000Z

292

22.351 Systems Analysis of the Nuclear Fuel Cycle, Spring 2003  

E-Print Network [OSTI]

In-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, thorium and other fuel types, ...

Kazimi, Mujid S.

293

22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005  

E-Print Network [OSTI]

This course provides an in-depth technical and policy analysis of various options for the nuclear fuel cycle. Topics include uranium supply, enrichment fuel fabrication, in-core physics and fuel management of uranium, ...

Kazimi, Mujid S.

294

Eigenmode analysis for turbomachinery applications  

E-Print Network [OSTI]

Eigenmode analysis for turbomachinery applications Pierre Moinier , Michael B. Giles Oxford-processing and for the construction of non-reflecting boundary conditions. Introduction Turbomachinery flows are approximately time

Giles, Mike

295

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

and restoration funded by the FWP may create opportunities to develop carbon credits which might be used to offset the carbon footprint of thermal power supplies. Interactions that may not need analysis but should

296

Process Cooling Pumping Systems Analysis  

E-Print Network [OSTI]

An analysis of the mill water pumping systems at a North American manufacturing facility was conducted late las year and the following issues were observed: 1. Overpumping – Both systems were overpumped to a significant degree against...

Sherman, C.

2008-01-01T23:59:59.000Z

297

Protein Structure Analysis Iosif Vaisman  

E-Print Network [OSTI]

Protein Structure Analysis Iosif Vaisman 2012 BINF 731 Protein Engineering Protein Engineering Increase catalytic activity Change substrate binding site to increase specificity Change the thermal stability Increase proteins resistance to proteases Change codon composition Protein Engineering

Vaisman, Iosif

298

Nonstandard Tools for Nonsmooth Analysis  

E-Print Network [OSTI]

This is an overview of the basic tools of nonsmooth analysis which are grounded on nonstandard models of set theory. By way of illustration we give a criterion for an infinitesimally optimal path of a general discrete dynamic system.

S. S. Kutateladze

2012-06-11T23:59:59.000Z

299

Geometric Analysis and General Relativity  

E-Print Network [OSTI]

This article discusses methods of geometric analysis in general relativity, with special focus on the role of "critical surfaces" such as minimal surfaces, marginal surface, maximal surfaces and null surfaces.

Lars Andersson

2005-12-23T23:59:59.000Z

300

Thermal analysis of vascular reactivity  

E-Print Network [OSTI]

dysfunction. Given the promising nature of thermal monitoring to study VR, this thesis focuses on the analysis of the underlying physics affecting fingertip temperature during vascular occlusion and subsequent hyperemia. I will quantify the contribution...

Deshpande, Chinmay Vishwas

2009-05-15T23:59:59.000Z

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

NREL: Energy Analysis - Marissa Hummon  

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

Marissa Hummon is a member of the Energy Forecasting and Modeling Group in the Strategic Energy Analysis Center. Engineer On staff since January 2010 Phone number: 303-275-3269...

302

Mandatory Photovoltaic System Cost Analysis  

Broader source: Energy.gov [DOE]

The Arizona Corporation Commission requires electric utilities to conduct a cost/benefit analysis to compare the cost of line extension with the cost of installing a stand-alone photovoltaic (PV)...

303

Equilibrium analysis of masonry domes  

E-Print Network [OSTI]

This thesis developed a new method to analyze the structural behavior of masonry domes: the modified thrust line analysis. This graphical-based method offers several advantages to existing methods. It is the first to account ...

Lau, Wanda W

2006-01-01T23:59:59.000Z

304

Hydrogen Delivery Infrastructure Options Analysis  

Fuel Cell Technologies Publication and Product Library (EERE)

This report, by the Nexant team, documents an in-depth analysis of seven hydrogen delivery options to identify the most cost-effective hydrogen infrastructure for the transition and long term. The pro

305

Intrinsic Shapes of Molecular Cloud Cores  

E-Print Network [OSTI]

We conduct an analysis of the shapes of molecular cloud cores using recently compiled catalogs of observed axis ratios of individual cores mapped in ammonia or through optical selection. We apply both analytical and statistical techniques to deproject the observed axis ratios in order to determine the true distribution of cloud core shapes. We find that neither pure oblate nor pure prolate cores can account for the observed distribution of core shapes. Intrinsically triaxial cores produce distributions which agree with observations. The best-fit triaxial distribution contains cores which are more nearly oblate than prolate.

C. E. Jones; Shantanu Basu; John Dubinski

2001-01-08T23:59:59.000Z

306

Pollen analysis of Patschke bog  

E-Print Network [OSTI]

POLLEN ANALYSIS OF PATSCHKE BOG A Thesis by HOPE ARMSTRONG CAMPER Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 1991 Major Subject...: Botany POLLEN ANALYSIS OF PATSCHKE BOG A Thesis by HOPE ARMSTRONG CAMPER Approved as to style and content by: Merrill Sweet (Co-Chair of Committee) Vaughn Bryant (Co-Chair of Committee) Elenor Cox (Member) Timothy Hall (Head of Department) May...

Camper, Hope Armstrong

1991-01-01T23:59:59.000Z

307

Thermodynamic Analysis for Energy Conservation  

E-Print Network [OSTI]

THERMODYNAMIC ANALYSIS FOR ENERGY CONSERVATION William F. Kenney Exxon Chemical Company Florham Park, New Jersey , ,,~ This paper describes a methodology for per forming a thermodynamic analysis of a process, and it demonstrates how... fired. In a cracking furnace it can reduce lost work in combustion and in the convec tion section at the cost of more surface area in the convection section, reduced steam make, and slightly higher radiative temperature differences. Preheating air...

Kenney, W. F.

1981-01-01T23:59:59.000Z

308

Multi-Metric Sustainability Analysis  

SciTech Connect (OSTI)

A readily accessible framework that allows for evaluating impacts and comparing tradeoffs among factors in energy policy, expansion planning, and investment decision making is lacking. Recognizing this, the Joint Institute for Strategic Energy Analysis (JISEA) funded an exploration of multi-metric sustainability analysis (MMSA) to provide energy decision makers with a means to make more comprehensive comparisons of energy technologies. The resulting MMSA tool lets decision makers simultaneously compare technologies and potential deployment locations.

Cowlin, S.; Heimiller, D.; Macknick, J.; Mann, M.; Pless, J.; Munoz, D.

2014-12-01T23:59:59.000Z

309

Analysis Paralysis: when to stop?  

E-Print Network [OSTI]

Analysis of a system constitutes the most important aspect of the systems development life cycle.But it is also the most confusing and time consuming of all the stages.The critical question always remains: How much and till when to analyse? Ed Yourdon has called this phenomenon as Analysis Paralysis. In this paper, I suggest a model which can actually help in arriving at a satisfactory answer to this problem.

Bhardwaj, Er Akshay

2009-01-01T23:59:59.000Z

310

Moment Analysis and Zipf Law  

E-Print Network [OSTI]

The moment analysis method and nuclear Zipf's law of fragment size distributions are reviewed to study nuclear disassembly. In this report, we present a compilation of both theoretical and experimental studies on moment analysis and Zipf law performed so far. The relationship of both methods to a possible critical behavior or phase transition of nuclear disassembly is discussed. In addition, scaled factorial moments and intermittency are reviewed.

Y. G. Ma

2006-11-30T23:59:59.000Z

311

UNL Core for Applied Genomics and Ecology  

E-Print Network [OSTI]

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

Farritor, Shane

312

Bismuth-based electrochemical stripping analysis  

DOE Patents [OSTI]

Method and apparatus for trace metal detection and analysis using bismuth-coated electrodes and electrochemical stripping analysis. Both anodic stripping voltammetry and adsorptive stripping analysis may be employed.

Wang, Joseph

2004-01-27T23:59:59.000Z

313

Geospatial Analysis School of Forest Resources &  

E-Print Network [OSTI]

Geospatial Analysis GIS 4121 School of Forest Resources & Conservation Geomatics Program _______________________________________________________________________________________ 1 GIS 4121 Geospatial Analysis INSTRUCTORS: Dr. Hartwig Henry Hochmair (FLREC Fort Lauderdale) Dr MATERIALS: de Smith, MJ, Goodchild, MF, & Longley, PA (2010). Geospatial Analysis (3rd ed.). Leicester

Watson, Craig A.

314

Valliappa Lakshmanan Automating the Analysis of  

E-Print Network [OSTI]

Geospatial Images January 5, 2012 Springer #12;Contents 1 Automated Analysis of Spatial Grids: MotivationValliappa Lakshmanan Automating the Analysis of Spatial Grids A Practitioner's Guide to Data Mining . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.5 Challenges in Automated Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1

Lakshmanan, Valliappa

315

Corporate Analysis of DOE Safety Performance  

Broader source: Energy.gov [DOE]

The Office of Environment, Health, Safety and Security (EHSS), Office of Analysis develops analysis tools and performance dashboards, and conducts analysis of DOE safety performance corporately and on a variety of specific environment, safety and health topics.

316

ANALYSIS OF THE CALIFORNIA SOLAR RESOURCE  

E-Print Network [OSTI]

SECTION ANALYSIS OF THE CALIFORNIA SOLAR RESOURCE' Volume 1:Analysis of the California Solar Resource is a three-volumeUC-62 ANALYSIS OF THE CALIFORNIA SOLAR RESOURCE VOLUME 1:

Berdahl, P.

2011-01-01T23:59:59.000Z

317

Function Analysis and Decomposistion using Function Analysis Systems Technique  

SciTech Connect (OSTI)

The "Father of Value Analysis", Lawrence D. Miles, was a design engineer for General Electric in Schenectady, New York. Miles developed the concept of function analysis to address difficulties in satisfying the requirements to fill shortages of high demand manufactured parts and electrical components during World War II. His concept of function analysis was further developed in the 1960s by Charles W. Bytheway, a design engineer at Sperry Univac in Salt Lake City, Utah. Charles Bytheway extended Mile's function analysis concepts and introduced the methodology called Function Analysis Systems Technique (FAST) to the Society of American Value Engineers (SAVE) at their International Convention in 1965 (Bytheway 1965). FAST uses intuitive logic to decompose a high level, or objective function into secondary and lower level functions that are displayed in a logic diagram called a FAST model. Other techniques can then be applied to allocate functions to components, individuals, processes, or other entities that accomplish the functions. FAST is best applied in a team setting and proves to be an effective methodology for functional decomposition, allocation, and alternative development.

Wixson, James Robert

1999-06-01T23:59:59.000Z

318

Function Analysis and Decomposistion using Function Analysis Systems Technique  

SciTech Connect (OSTI)

The "Father of Value Analysis", Lawrence D. Miles, was a design engineer for General Electric in Schenectady, New York. Miles developed the concept of function analysis to address difficulties in satisfying the requirements to fill shortages of high demand manufactured parts and electrical components during World War II. His concept of function analysis was further developed in the 1960s by Charles W. Bytheway, a design engineer at Sperry Univac in Salt Lake City, Utah. Charles Bytheway extended Mile's function analysis concepts and introduced the methodology called Function Analysis Systems Techniques (FAST) to the Society of American Value Engineers (SAVE) at their International Convention in 1965 (Bytheway 1965). FAST uses intuitive logic to decompose a high level, or objective function into secondary and lower level functions that are displayed in a logic diagram called a FAST model. Other techniques can then be applied to allocate functions to components, individuals, processes, or other entities that accomplish the functions. FAST is best applied in a team setting and proves to be an effective methodology for functional decomposition, allocation, and alternative development.

J. R. Wixson

1999-06-01T23:59:59.000Z

319

Analysis Activities at National Renewable Energy Laboratory  

Broader source: Energy.gov [DOE]

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

320

Advanced Vehicle Technology Analysis & Evaluation Team  

Broader source: Energy.gov [DOE]

Presentation on Advanced Vehicle Technology Analysis & Evaluation Team to the DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004.

Note: This page contains sample records for the topic "analysis 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 Activities at Sandia National Laboratory  

Broader source: Energy.gov [DOE]

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

322

Analysis Activities at Pacific Northwest National Laboratory  

Broader source: Energy.gov [DOE]

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

323

Safety System Oversight Staffing Analysis (Instructions, Blank...  

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

Safety System Oversight Staffing Analysis (Instructions, Blank Sheet and Example Sheet) Safety System Oversight Staffing Analysis (Instructions, Blank Sheet and Example Sheet) This...

324

Integrated External Aerodynamic and Underhood Thermal Analysis...  

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

External Aerodynamic and Underhood Thermal Analysis for Heavy Vehicles Integrated External Aerodynamic and Underhood Thermal Analysis for Heavy Vehicles 2012 DOE Hydrogen and Fuel...

325

Comparative Analysis of Proteome and Transcriptome Variation...  

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

Comparative Analysis of Proteome and Transcriptome Variation in Mouse. Comparative Analysis of Proteome and Transcriptome Variation in Mouse. Abstract: The relationships between...

326

Quantitative proteomics analysis of adsorbed plasma proteins...  

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

proteomics analysis of adsorbed plasma proteins classifies nanoparticles with different surface properties and size Quantitative proteomics analysis of adsorbed plasma proteins...

327

Analysis Activities at Lawrence Livermore National Laboratory  

Broader source: Energy.gov [DOE]

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

328

Innovative Corridors Initiative: Business Model Analysis  

E-Print Network [OSTI]

Wenger, Joyce. Business Models for Vehicle InfrastructureCorridors Initiative: Business Model Analysis Rachel S.Corridors Initiative: Business Model Analysis Task Order

Shaheen, Susan; Lingham, Viginia; Finson, Rachel S.

2007-01-01T23:59:59.000Z

329

Hydrogen Delivery Infrastructure Analysis, Options and Trade...  

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

Analysis, Options and Trade-offs, Transition and Long-term Hydrogen Delivery Infrastructure Analysis, Options and Trade-offs, Transition and Long-term Presentation on Hydrogen...

330

Analysis Activities at Oak Ridge National Laboratory  

Broader source: Energy.gov [DOE]

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

331

UCSF Sustainability Baseline Assessment: Carbon Footprint Analysis  

E-Print Network [OSTI]

UCSF Sustainability Baseline Assessment: Carbon Footprint Analysis Final Issue Date: March 21, 2010 #12;Carbon Footprint Analysis Background This chapter of the Sustainability Assessment focuses on UCSF

Yamamoto, Keith

332

Computational prediction and analysis of protein structure  

E-Print Network [OSTI]

I, and Bowie JU. Kink prediction in membrane proteins.Los Angeles Computational prediction and analysis of proteinOF THE DISSERTATION Computational prediction and analysis of

Meruelo, Alejandro Daniel

2012-01-01T23:59:59.000Z

333

Building Energy Optimization Analysis Method (BEopt) - Building...  

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

Energy Optimization Analysis Method (BEopt) - Building America Top Innovation Building Energy Optimization Analysis Method (BEopt) - Building America Top Innovation House graphic...

334

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

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

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

335

Analysis Activities at Argonne National Laboratory  

Broader source: Energy.gov [DOE]

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

336

Power System Transient Stability Analysis through a Homotopy Analysis Method  

SciTech Connect (OSTI)

As an important function of energy management systems (EMSs), online contingency analysis plays an important role in providing power system security warnings of instability. At present, N-1 contingency analysis still relies on time-consuming numerical integration. To save computational cost, the paper proposes a quasi-analytical method to evaluate transient stability through time domain periodic solutions’ frequency sensitivities against initial values. First, dynamic systems described in classical models are modified into damping free systems whose solutions are either periodic or expanded (non-convergent). Second, because the sensitivities experience sharp changes when periodic solutions vanish and turn into expanded solutions, transient stability is assessed using the sensitivity. Third, homotopy analysis is introduced to extract frequency information and evaluate the sensitivities only from initial values so that time consuming numerical integration is avoided. Finally, a simple case is presented to demonstrate application of the proposed method, and simulation results show that the proposed method is promising.

Wang, Shaobu; Du, Pengwei; Zhou, Ning

2014-04-01T23:59:59.000Z

337

Timing analysis of PWR fuel pin failures  

SciTech Connect (OSTI)

This report discusses research conducted to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calculations were performed for a Babcock and Wilcox (B W) design (Oconee) and a Westinghouse (W) four-loop design (Seabrook). Sensitivity studies were performed to assess the impacts of fuel pin burnup, axial peaking factor, break size, emergency core cooling system availability, and main coolant pump trip on these times. The analysis was performed using the following codes: FRAPCON-2, for the calculation of steady-state fuel behavior; SCDAP/RELAP5/MOD3 and TRACPF1/MOD1, for the calculation of the transient thermal-hydraulic conditions in the reactor system; and FRAP-T6, for the calculation of transient fuel behavior. In addition to the calculation of fuel pin failure timing, this analysis provides a comparison of the predicted results of SCDAP/RELAP5/MOD3 and TRAC-PF1/MOD1 for large-break LOCA analysis. Using SCDAP/RELAP5/MOD3 thermal-hydraulic data, the shortest time intervals calculated between initiation of containment isolation and fuel pin failure are 10.4 seconds and 19.1 seconds for the B W and W plants, respectively. Using data generated by TRAC-PF1/MOD1, the shortest intervals are 10.3 seconds and 29.1 seconds for the B W and W plants, respectively. These intervals are for a double-ended, offset-shear, cold leg break, using the technical specification maximum peaking factor and applied to fuel with maximum design burnup. Using peaking factors commensurate with actual burnups would result in longer intervals for both reactor designs. This document provides appendices K and L of this report which provide plots for the timing analysis of PWR fuel pin failures for Oconee and Seabrook respectively.

Jones, K.R.; Wade, N.L.; Katsma, K.R.; Siefken, L.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Straka, M. (Halliburton NUS, Idaho Falls, ID (United States))

1992-09-01T23:59:59.000Z

338

Method of photon spectral analysis  

DOE Patents [OSTI]

A spectroscopic method to rapidly measure the presence of plutonium in soils, filters, smears, and glass waste forms by measuring the uranium L-shell x-ray emissions associated with the decay of plutonium. In addition, the technique can simultaneously acquire spectra of samples and automatically analyze them for the amount of americium and [gamma]-ray emitting activation and fission products present. The samples are counted with a large area, thin-window, n-type germanium spectrometer which is equally efficient for the detection of low-energy x-rays (10-2,000 keV), as well as high-energy [gamma] rays (>1 MeV). A 8,192- or 16,384 channel analyzer is used to acquire the entire photon spectrum at one time. A dual-energy, time-tagged pulser, that is injected into the test input of the preamplifier to monitor the energy scale, and detector resolution. The L x-ray portion of each spectrum is analyzed by a linear-least-squares spectral fitting technique. The [gamma]-ray portion of each spectrum is analyzed by a standard Ge [gamma]-ray analysis program. This method can be applied to any analysis involving x- and [gamma]-ray analysis in one spectrum and is especially useful when interferences in the x-ray region can be identified from the [gamma]-ray analysis and accommodated during the x-ray analysis.

Gehrke, R.J.; Putnam, M.H.; Killian, E.W.; Helmer, R.G.; Kynaston, R.L.; Goodwin, S.G.; Johnson, L.O.

1993-04-27T23:59:59.000Z

339

The ALICE analysis train system  

E-Print Network [OSTI]

In the ALICE experiment hundreds of users are analyzing big datasets on a Grid system. High throughput and short turn-around times are achieved by a centralized system called the LEGO trains. This system combines analysis from different users in so-called analysis trains which are then executed within the same Grid jobs thereby reducing the number of times the data needs to be read from the storage systems. The centralized trains improve the performance, the usability for users and the bookkeeping in comparison to single user analysis. The train system builds upon the already existing ALICE tools, i.e. the analysis framework as well as the Grid submission and monitoring infrastructure. The entry point to the train system is a web interface which is used to configure the analysis and the desired datasets as well as to test and submit the train. Several measures have been implemented to reduce the time a train needs to finish and to increase the CPU efficiency.

Markus Zimmermann; for the ALICE collaboration

2015-02-23T23:59:59.000Z

340

Method of photon spectral analysis  

DOE Patents [OSTI]

A spectroscopic method to rapidly measure the presence of plutonium in soils, filters, smears, and glass waste forms by measuring the uranium L-shell x-ray emissions associated with the decay of plutonium. In addition, the technique can simultaneously acquire spectra of samples and automatically analyze them for the amount of americium and .gamma.-ray emitting activation and fission products present. The samples are counted with a large area, thin-window, n-type germanium spectrometer which is equally efficient for the detection of low-energy x-rays (10-2000 keV), as well as high-energy .gamma. rays (>1 MeV). A 8192- or 16,384 channel analyzer is used to acquire the entire photon spectrum at one time. A dual-energy, time-tagged pulser, that is injected into the test input of the preamplifier to monitor the energy scale, and detector resolution. The L x-ray portion of each spectrum is analyzed by a linear-least-squares spectral fitting technique. The .gamma.-ray portion of each spectrum is analyzed by a standard Ge .gamma.-ray analysis program. This method can be applied to any analysis involving x- and .gamma.-ray analysis in one spectrum and is especially useful when interferences in the x-ray region can be identified from the .gamma.-ray analysis and accommodated during the x-ray analysis.

Gehrke, Robert J. (Idaho Falls, ID); Putnam, Marie H. (Idaho Falls, ID); Killian, E. Wayne (Idaho Falls, ID); Helmer, Richard G. (Idaho Falls, ID); Kynaston, Ronnie L. (Blackfoot, ID); Goodwin, Scott G. (Idaho Falls, ID); Johnson, Larry O. (Pocatello, ID)

1993-01-01T23:59:59.000Z

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

Development of Tritium Permeation Analysis Code (TPAC)  

SciTech Connect (OSTI)

Idaho National Laboratory developed the Tritium Permeation Analysis Code (TPAC) for tritium permeation in the Very High Temperature Gas Cooled Reactor (VHTR). All the component models in the VHTR were developed and were embedded into the MATHLAB SIMULINK package with a Graphic User Interface. The governing equations of the nuclear ternary reaction and thermal neutron capture reactions from impurities in helium and graphite core, reflector, and control rods were implemented. The TPAC code was verified using analytical solutions for the tritium birth rate from the ternary fission, the birth rate from 3He, and the birth rate from 10B. This paper also provides comparisons of the TPAC with the existing other codes. A VHTR reference design was selected for tritium permeation study from the reference design to the nuclear-assisted hydrogen production plant and some sensitivity study results are presented based on the HTGR outlet temperature of 750 degrees C.

Eung S. Kim; Chang H. Oh; Mike Patterson

2010-10-01T23:59:59.000Z

342

Visual analysis of code security  

SciTech Connect (OSTI)

To help increase the confidence that software is secure, researchers and vendors have developed different kinds of automated software security analysis tools. These tools analyze software for weaknesses and vulnerabilities, but the individual tools catch different vulnerabilities and produce voluminous data with many false positives. This paper describes a system that brings together the results of disparate software analysis tools into a visual environment to support the triage and exploration of code vulnerabilities. Our system allows software developers to explore vulnerability results to uncover hidden trends, triage the most important code weaknesses, and show who is responsible for introducing software vulnerabilities. By correlating and normalizing multiple software analysis tools' data, the overall vulnerability detection coverage of software is increased. A visual overview and powerful interaction allows the user to focus attention on the most pressing vulnerabilities within huge volumes of data, and streamlines the secure software development workflow through integration with development tools.

Goodall, John R [ORNL] [ORNL; Radwan, Hassan [Applied Visions, Inc.] [Applied Visions, Inc.; Halseth, Lenny [Applied Visions, Inc.] [Applied Visions, Inc.

2010-01-01T23:59:59.000Z

343

Traversal, Case Analysis, and Lowering for C++ Program Analysis  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . . 11 II TUTORIAL : : : : : : : : : : : : : : : : : : : : : : : : : : : : : 13 A. Motivation . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 B. Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 C. \\Hello, Unit... are and leaves the why for the discussion in Chapter III. Also, these goals are introduced by metaphor and example, saving their realization in the Filter library for the tutorial in Chapter II. 1. Traversal and case analysis The rst functional goal...

Wagner, Luke A.

2010-01-14T23:59:59.000Z

344

analysis energy analysis: Topics by E-print Network  

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

energy analysis First Page Previous Page 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 Next Page Last Page Topic Index 1 Energy, Environmental, and Economic...

345

Relative trajectory data reduction analysis  

E-Print Network [OSTI]

REDATIVE TRAJECTORY DATA RFDUCTION ANA1. YS1S A Thesis KENNE'Ill Vi. GRANT Subrnitl ed to the Gratluate College of 'J exas ASM University in pa) &ial full'illment of the reouir ament for the degree of MASTER OF SCIENCE August 1969 Major... Trajectory Data Reduction Analysis. (August 1969) Kenneth W. Grant, B. A. , University of California at Riverside Directed by: Dr. Rudolph Freund Knowledge of missile/drone intercept parameters is extremely important in the analysis of ordnance system...

Grant, Kenneth William

1969-01-01T23:59:59.000Z

346

Initial Decision and Risk Analysis  

SciTech Connect (OSTI)

Decision and Risk Analysis capabilities will be developed for industry consideration and possible adoption within Year 1. These tools will provide a methodology for merging qualitative ranking of technology maturity and acknowledged risk contributors with quantitative metrics that drive investment decision processes. Methods and tools will be initially introduced as applications to the A650.1 case study, but modular spreadsheets and analysis routines will be offered to industry collaborators as soon as possible to stimulate user feedback and co-development opportunities.

Engel, David W.

2012-02-29T23:59:59.000Z

347

GUM Analysis for TIMS Isotopic Ratios in BEP0 Graphite Qualification Samples, Round 2  

SciTech Connect (OSTI)

In May 2007, one set of three samples from NBL were addressed to Steve Petersen for TIMS analysis, and included BEP0 samples numbered 27008, 30986, and 50846. All cores were trimmed by tooling, and lightly cleaned by CO2 pellet blasting. Small discs were cut from the second set of samples for SIMS analysis, with the remainder of each used for TIMS preparation.

Gerlach, David C.; Heasler, Patrick G.; Reid, Bruce D.

2009-01-01T23:59:59.000Z

348

Controlled Hydrogen Fleet and Infrastructure Analysis (Presentation)  

SciTech Connect (OSTI)

This presentation summarizes controlled hydrogen fleet & infrastructure analysis undertaken for the DOE Fuel Cell Technologies Program.

Wipke, K.; Sprik, S.; Kurtz, J.; Ramsden, T.

2010-06-10T23:59:59.000Z

349

Multilinear (Tensor) Image Synthesis, Analysis, and Recognition  

E-Print Network [OSTI]

and a col- umn space. In a factor analysis of D, the SVD orthogonalizes these two spaces and decomposesMultilinear (Tensor) Image Synthesis, Analysis, and Recognition [exploratory DSP] M. Alex O analysis (PCA) and its refinement known as independ- ent components analysis (ICA) model single

Terzopoulos, Demetri

350

Freight Analysis Framework version 3 (FAF3)  

E-Print Network [OSTI]

Freight Analysis Framework version 3 (FAF3) Oak Ridge National Laboratory managed by UT Technologies Research Brief T he Freight Analysis Framework version 3 (FAF3) database is a Federal Highway data to enable users to perform train analysis. FAF3 Geography Figure 1 shows the analysis regions

351

Systems Analysis Department Annual Report 2001  

E-Print Network [OSTI]

benchmarking analysis to the Danish district heating sector Technology Scenarios 17 Sensor Technology Foresight

352

Change impact analysis -what, why, how ?  

E-Print Network [OSTI]

analysis How to perform the change impact analysis Future direction of research Q&A 2 KAIST SE LAB 2008 have unpredictable consequences that often delay their implementation 3 KAIST SE LAB 2008 #12 Implement change #12;What is the change impact analysis (3/3) Results of the change impact analysis 8 KAIST

Bae, Doo-Hwan

353

Canister storage building hazard analysis report  

SciTech Connect (OSTI)

This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the CSB final safety analysis report (FSAR) and documents the results. The hazard analysis was performed in accordance with the DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', and meets the intent of HNF-PRO-704, ''Hazard and Accident Analysis Process''. This hazard analysis implements the requirements of DOE Order 5480.23, ''Nuclear Safety Analysis Reports''.

POWERS, T.B.

1999-05-11T23:59:59.000Z

354

Canister storage building hazard analysis report  

SciTech Connect (OSTI)

This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the final CSB safety analysis report (SAR) and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Report, and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

Krahn, D.E.; Garvin, L.J.

1997-07-01T23:59:59.000Z

355

Cold Vacuum Drying Facility hazard analysis report  

SciTech Connect (OSTI)

This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.

Krahn, D.E.

1998-02-23T23:59:59.000Z

356

Feasibility of a Monte Carlo-deterministic hybrid method for fast reactor analysis  

SciTech Connect (OSTI)

A Monte Carlo and deterministic hybrid method is investigated for the analysis of fast reactors in this paper. Effective multi-group cross sections data are generated using a collision estimator in the MCNP5. A high order Legendre scattering cross section data generation module was added into the MCNP5 code. Both cross section data generated from MCNP5 and TRANSX/TWODANT using the homogeneous core model were compared, and were applied to DIF3D code for fast reactor core analysis of a 300 MWe SFR TRU burner core. For this analysis, 9 groups macroscopic-wise data was used. In this paper, a hybrid calculation MCNP5/DIF3D was used to analyze the core model. The cross section data was generated using MCNP5. The k{sub eff} and core power distribution were calculated using the 54 triangle FDM code DIF3D. A whole core calculation of the heterogeneous core model using the MCNP5 was selected as a reference. In terms of the k{sub eff}, 9-group MCNP5/DIF3D has a discrepancy of -154 pcm from the reference solution, 9-group TRANSX/TWODANT/DIF3D analysis gives -1070 pcm discrepancy. (authors)

Heo, W.; Kim, W.; Kim, Y. [Korea Advanced Institute of Science and Technology - KAIST, 291 Daehak-ro, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of); Yun, S. [Korea Atomic Energy Research Institute - KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2013-07-01T23:59:59.000Z

357

Garfield County Secondary Data Analysis  

E-Print Network [OSTI]

prevalence (Heart Attack) 5.5% 4.1% 6.0% All Sites Cancer 472.3 455.5 543.2 1 Community Health Data, MT. Cancer 2. Heart Disease 3. Pneumonia, CLRD*, Unintentional Injuries** 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Garfield County Secondary Data Analysis July 23

Maxwell, Bruce D.

358

Prairie County Secondary Data Analysis  

E-Print Network [OSTI]

prevalence (Heart Attack) 5.5% 4.1% 6.0% All Sites Cancer 472.3 455.5 543.2 1 Community Health Data, MT. Heart Disease, Cancer 2. CLRD* 3. Unintentional Injuries** 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Prairie County Secondary Data Analysis July 23, 2012 2

Maxwell, Bruce D.

359

Valley County Secondary Data Analysis  

E-Print Network [OSTI]

Infarction prevalence (Heart Attack) 5.5% 4.1% 6.0% All Sites Cancer 472.3 455.5 543.2 1 Community Montana1,2 Nation2 1. Heart Disease 2. Cancer 3. Diabetes 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Valley County Secondary Data Analysis July 23, 2012 2

Maxwell, Bruce D.

360

Rosebud County Secondary Data Analysis  

E-Print Network [OSTI]

prevalence (Heart Attack) 4.6% 4.1% 6.0% All Sites Cancer 472.3 (Region 1) 455.5 543.2 1 Community County1 Montana1,2 Nation2 1. Cancer 2. Heart Disease 3. Unintentional Injuries** 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Rosebud County Secondary Data Analysis

Maxwell, Bruce D.

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

Strategic Energy Analysis (Fact Sheet)  

SciTech Connect (OSTI)

NREL complements its scientific research with high-quality, credible, technology-neutral, objective analysis that informs policy and investment decisions as renewable energy and energy efficiency technologies move from innovation through integration. This sheet highlights NREL's analytical capabilities and achievements.

Not Available

2014-02-01T23:59:59.000Z

362

WHC fire hazards analysis policy  

SciTech Connect (OSTI)

The purpose of this document is to establish the fire protection policy for Westinghouse Hanford Company (WHC) relative to US Department of Energy (DOE) directives for Fire Hazards Analyses (FHAs) and their relationship to facility Safety Analysis Reports (SARs) as promulgated by the DOE Richland Operations Office.

Evans, C.B.

1994-04-01T23:59:59.000Z

363

Protein Structure Analysis Iosif Vaisman  

E-Print Network [OSTI]

Protein Structure Analysis Iosif Vaisman 2009 BINF 731 Protein Engineering Protein Engineering Increase catalytic activity Change substrate binding site to increase specificity Change the thermal152S -1.08 1goj S152T 1.12 Protein Engineering Protein Engineering #12;Protein Engineering Protein

Vaisman, Iosif

364

Fourier Analysis of Ghost Imaging  

E-Print Network [OSTI]

Fourier analysis of ghost imaging (FAGI) is proposed in this paper to analyze the properties of ghost imaging with thermal light sources. This new theory is compatible with the general correlation theory of intensity fluctuation and could explain some amazed phenomena. Furthermore we design a series of experiments to verify the new theory and investigate the inherent properties of ghost imaging.

Honglin Liu; Jing Cheng; Yanfeng Bai; Shensheng Han

2006-09-28T23:59:59.000Z

365

Regression analysis with missing data  

E-Print Network [OSTI]

: Statistios REGRESSION ANALYSIS WITH MISS1NG DATA A Thesis FRANK ANTHONY MICHELLI Approved as to style and content by: hairman of o ttee Member Head of Department Member Member Zanuary 196B ACZNOWLED ONE NT S I can only begin to express my sincere...

Michelli, Frank Anthony

1968-01-01T23:59:59.000Z

366

IEAB Independent Economic Analysis Board  

E-Print Network [OSTI]

. Huppert Noelwah R. Netusil JunJie Wu Cost-Effectiveness of Fish Tagging Technologies and Programs in the Columbia River Basin1 Independent Economic Analysis Board Fish and Wildlife Program Northwest Power and Conservation Council June 2, 2013 1 This report benefitted from the meetings of the Fish Tagging Forum

367

Microlocal Analysis : a short introduction  

E-Print Network [OSTI]

One of the fundamental ideas of classical analysis is a thorough study of functions near a point, ... study is the wave front set WF(f ) ? T?Rn \\ 0 that we define below. Definition. The basic .... asymptotic expansion of the form p(x,?) ?. ?. ? j=0.

Plamen Stefanov

2012-07-18T23:59:59.000Z

368

ADVANCED DECISION ANALYSIS Winter 2011  

E-Print Network [OSTI]

ADVANCED DECISION ANALYSIS PH 444 Winter 2011 Course Instructor: Gordon Hazen, Ph.D. Professor a factored cost-effectiveness model · Construct a stochastic tree transition diagram for a medical treatment problem. · Convert a stochastic tree diagram to a discrete-time Markov chain transition diagram

Chisholm, Rex L.

369

Reactor Cost Analysis Brian James  

E-Print Network [OSTI]

Reactor Cost Analysis Brian James Directed Technologies, Inc. 6-7 November 2007 This presentation specification & optimization · Capital cost estimation · Projected hydrogen $/kg #12;Directed Technologies, Inc/WGS Membrane Reactor OTM/ Water-Splitting ANL With WGS #12;Directed Technologies, Inc. 6-7 November 2007 BILIWG

370

Sodium loop framework structural analysis  

SciTech Connect (OSTI)

This document provides the structural analysis of the Sodium Loop framework in a drop condition. The drop is similar to the US Department of Transportation non-bulk, performance-oriented packaging (Packaging Group I) drop test. The drop height evaluated for the Sodium Loop framework is 5.9 ft.

Nguyen, P.M.

1995-06-06T23:59:59.000Z

371

Supplementary Figure 1 Analysis Modalities  

E-Print Network [OSTI]

of the dataset being analyzed is depicted by the dark color. Global Analysis. The entire dataset is analyzed wide user base. First, users can access the web application from our own web servers, which are running.IOBIO uses the MIT License. Implementation Details BAM.IOBIO is a Javascript and HTML web application using

Cai, Long

372

AGR-1 Thermocouple Data Analysis  

SciTech Connect (OSTI)

This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas Reactor (AGR) fuel irradiation test program conducted in the INL's Advanced Test Reactor (ATR) to support the Next Generation Nuclear Plant (NGNP) R&D program. The work follows up on a previous study (Pham and Einerson, 2010), in which statistical analysis methods were applied for AGR-1 thermocouple data qualification. The present work exercises the idea that, while recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, results of the numerical simulations can be used in combination with the statistical analysis methods to further improve qualification of measured data. Additionally, the combined analysis of measured and simulation data can generate insights about simulation model uncertainty that can be useful for model improvement. This report also describes an experimental control procedure to maintain fuel target temperature in the future AGR tests using regression relationships that include simulation results. The report is organized into four chapters. Chapter 1 introduces the AGR Fuel Development and Qualification program, AGR-1 test configuration and test procedure, overview of AGR-1 measured data, and overview of physics and thermal simulation, including modeling assumptions and uncertainties. A brief summary of statistical analysis methods developed in (Pham and Einerson 2010) for AGR-1 measured data qualification within NGNP Data Management and Analysis System (NDMAS) is also included for completeness. Chapters 2-3 describe and discuss cases, in which the combined use of experimental and simulation data is realized. A set of issues associated with measurement and modeling uncertainties resulted from the combined analysis are identified. This includes demonstration that such a combined analysis led to important insights for reducing uncertainty in presentation of AGR-1 measured data (Chapter 2) and interpretation of simulation results (Chapter 3). The statistics-based simulation-aided experimental control procedure described for the future AGR tests is developed and demonstrated in Chapter 4. The procedure for controlling the target fuel temperature (capsule peak or average) is based on regression functions of thermocouple readings and other relevant parameters and accounting for possible changes in both physical and thermal conditions and in instrument performance.

Jeff Einerson

2012-05-01T23:59:59.000Z

373

Preliminary hazards analysis -- vitrification process  

SciTech Connect (OSTI)

This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.

Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P. [Science Applications International Corp., Pleasanton, CA (United States)] [Science Applications International Corp., Pleasanton, CA (United States)

1994-06-01T23:59:59.000Z

374

B PLANT DOCUMENTED SAFETY ANALYSIS  

SciTech Connect (OSTI)

This document provides the documented safety analysis (DSA) and Central Plateau Remediation Project (CP) requirements that apply to surveillance and maintenance (S&M) activities at the 221-B Canyon Building and ancillary support structures (B Plant). The document replaces BHI-010582, Documented Safety Analysis for the B-Plant Facility. The B Plant is non-operational, deactivated and undergoing long term S&M prior to decontamination and decommissioning (D&D). This DSA is compliant with 10 CFR 830, Nuclear Safety Management, Subpart B, ''Safety Basis Requirements.'' The DSA was developed in accordance with U.S. Department of Energy (DOE) standard DOE-STD-1120-98, Integration of Environment, Safety, and Health into Facility Disposition Activities (DOE 1998) per Table 2 of 10 CFR 830 Appendix A, DOE Richland Operation Office (RL) direction (02-ABD-0053, Fluor Hanford Nuclear Safety Basis Strategy and Criteria) for facilities in long term S&M, and RL Direction (02-ABD-0091, ''FHI Nuclear Safety Expectations for Nuclear Facilities in Surveillance and Maintenance''). A crosswalk was prepared to identify potential inconsistencies between the previous B Plant safety analysis and DOE-STD-1120-98 guidance. In general, the safety analysis met the criteria of DOE-STD-1120-98. Some format and content changes have been made, including incorporating recent facility modifications and updating the evaluation guidelines and control selection criteria in accordance with RL direction (02-ABD-0053). The facility fire hazard analysis (FHA) and Technical Safety Requirements (TSR) are appended to this DSA as an aid to the users, to minimize editorial redundancy, and to provide an efficient basis for update.

DODD, E.N.; KERR, N.R.

2003-08-01T23:59:59.000Z

375

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

Open Energy Info (EERE)

and thermal conductivities were measured at a mean temperature of 25C with a line source in either the needle-probe or half-space configuration. Rock thermal conductivities...

376

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

Open Energy Info (EERE)

a fundamental understanding of the geophysical properties of reservoir rocks and fracture systems. Even in the best of circumstances, spatial variability in porosity, fracture...

377

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

378

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump to: navigation,

379

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump to: navigation,2009)

380

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump to: navigation,2009)the

Note: This page contains sample records for the topic "analysis 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 Analysis At Dunes Geothermal Area (1976) | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump to:

382

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump to:1983)

383

Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump to:1983)Laney,

384

Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc Jump

385

Core Analysis At Valles Caldera - Sulphur Springs Geothermal Area (Morgan,  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) |Cordova Electric Coop, Inc JumpTanaka, 1995) | OpenEt

386

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump to: Exploration

387

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump| Open Energy

388

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump| Open EnergyOpen

389

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump| Open EnergyOpenOpen

390

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump|2003) |Information

391

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

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC Jump to:Information NewAdvisors Jump|2003)

392

Comparative Bacterial Proteomics: Analysis of the Core Genome Concept. |  

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

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

393

Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout theOFFICEAmes Laboratory Site| Department ofAn| Princeton Plasmaheavy

394

Analysis  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout theOFFICEAmes Laboratory Site| Department ofAn| Princeton

395

3D neutronic/thermal-hydraulic coupled analysis of MYRRHA  

SciTech Connect (OSTI)

The current tendency in multiphysics calculations applied to reactor physics is the use of already validated computer codes, coupled by means of an iterative approach. In this paper such an approach is explained concerning neutronics and thermal-hydraulics coupled analysis with MCNPX and COBRA-IV codes using a driver program and file exchange between codes. MCNPX provides the neutronic analysis of heterogeneous nuclear systems, both in critical and subcritical states, while COBRA-IV is a subchannel code that can be used for rod bundles or core thermal-hydraulics analysis. In our model, the MCNP temperature dependence of nuclear data is handled via pseudo-material approach, mixing pre-generated cross section data set to obtain the material with the desired cross section temperature. On the other hand, COBRA-IV has been updated to allow for the simulation of liquid metal cooled reactors. The coupled computational tool can be applied to any geometry and coolant, as it is the case of single fuel assembly, at pin-by-pin level, or full core simulation with the average pin of each fuel-assembly. The coupling tool has been applied to the critical core layout of the SCK-CEN MYRRHA concept, an experimental LBE cooled fast reactor presently in engineering design stage. (authors)

Vazquez, M.; Martin-Fuertes, F. [CIEMAT, Avda. Complutense 40, 28040 Madrid (Spain)

2012-07-01T23:59:59.000Z

396

Analysis reveals potential rangeland impacts if Williamson Act eliminated  

E-Print Network [OSTI]

Act, using a geospatial analysis and a mail question- naireelimination scenario. The geospatial analysis revealed that

Wetzel, William C; Lacher, Iara L; Swezey, Daniel s; Moffitt, Sarah E; Manning, Dale T

2012-01-01T23:59:59.000Z

397

SAFETY ANALYSIS AND INTEGRATION FOR ROBOTIC SYSTEMS -APPLICATION TO A  

E-Print Network [OSTI]

Analysis (FMEA) and Fault Tree Analysis (FTA) which identify potential unit errors resulting in hazards

Guiochet, Jérémie

398

Extending and automating a systems-theoretic hazard analysis for requirements generation and analysis  

E-Print Network [OSTI]

Systems Theoretic Process Analysis (STPA) is a powerful new hazard analysis method designed to go beyond traditional safety techniques-such as Fault Tree Analysis (FTA)-that overlook important causes of accidents like ...

Thomas, John P., IV

2013-01-01T23:59:59.000Z

399

Experiment Design and Analysis Guide - Neutronics & Physics  

SciTech Connect (OSTI)

The purpose of this guide is to provide a consistent, standardized approach to performing neutronics/physics analysis for experiments inserted into the Advanced Test Reactor (ATR). This document provides neutronics/physics analysis guidance to support experiment design and analysis needs for experiments irradiated in the ATR. This guide addresses neutronics/physics analysis in support of experiment design, experiment safety, and experiment program objectives and goals. The intent of this guide is to provide a standardized approach for performing typical neutronics/physics analyses. Deviation from this guide is allowed provided that neutronics/physics analysis details are properly documented in an analysis report.

Misti A Lillo

2014-06-01T23:59:59.000Z

400

Voltammetric analysis apparatus and method  

DOE Patents [OSTI]

An apparatus and method is described for electrochemical analysis of elements in solution. An auxiliary electrode, a reference electrode, and five working electrodes are positioned in a container containing a sample solution. The working electrodes are spaced apart evenly from each other and the auxiliary electrode to minimize any inter-electrode interference that may occur during analysis. An electric potential is applied between the auxiliary electrode and each of the working electrodes. Simultaneous measurements taken of the current flow through each of the working electrodes for each given potential in a potential range are used for identifying chemical elements present in the sample solution and their respective concentrations. Multiple working electrodes enable a more positive identification to be made by providing unique data characteristic of chemical elements present in the sample solution.

Almon, A.C.

1993-06-08T23:59:59.000Z

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

Residential solar home resale analysis  

SciTech Connect (OSTI)

One of the determinants of the market acceptance of solar technologies in the residential housing sector is the value placed upon the solar property at the time of resale. The resale factor is shown to be an important economic parameter when net benefits of the solar design are considered over a typical ownership cycle rather than the life cycle of the system. Although a study of solar resale in Davis, Ca, indicates that those particular homes have been appreciating in value faster than nonsolar market comparables, no study has been made that would confirm this conclusion for markets in other geograhical locations with supporting tests of statistical significance. The data to undertake such an analysis is available through numerous local sources; however, case by case data collection is prohibitively expensive. A recommended alternative approach is to make use of real estate market data firms who compile large data bases and provide multi-variate statistical analysis packages.

Noll, S.A.

1980-01-01T23:59:59.000Z

402

Ion mobility analysis of lipoproteins  

DOE Patents [OSTI]

A medical diagnostic method and instrumentation system for analyzing noncovalently bonded agglomerated biological particles is described. The method and system comprises: a method of preparation for the biological particles; an electrospray generator; an alpha particle radiation source; a differential mobility analyzer; a particle counter; and data acquisition and analysis means. The medical device is useful for the assessment of human diseases, such as cardiac disease risk and hyperlipidemia, by rapid quantitative analysis of lipoprotein fraction densities. Initially, purification procedures are described to reduce an initial blood sample to an analytical input to the instrument. The measured sizes from the analytical sample are correlated with densities, resulting in a spectrum of lipoprotein densities. The lipoprotein density distribution can then be used to characterize cardiac and other lipid-related health risks.

Benner, W. Henry (Danville, CA); Krauss, Ronald M. (Berkeley, CA); Blanche, Patricia J. (Berkeley, CA)

2007-08-21T23:59:59.000Z

403

Needs Analysis for Dimethyl Mercury  

SciTech Connect (OSTI)

For this needs analysis, a total of 131 DMHg analytical results were collected and reviewed from the Hanford Tank Farms from 2004 to 2007. Sampling data from the Site Wide Industrial Hygiene Database (SWIHO), the Tank waste inventory System (TWINs), and prior sampling campaigns by CH2M Hill Hanford that were not available in the SWIHD database, were aggregated for analysis. Technical literature used by the Savannah River Site (SRS). Bechtel RPP·WTP, and CH2M Hill Hanford from 2003-2007, were also reviewed to identify potential DMHg exposure concerns applicable to the tank farms. After analyzing the adequacy of lhe data, information gaps were identified and recommendations for corrective actions items were developed.

Schmoldt, Michael J.

2013-02-13T23:59:59.000Z

404

Building Energy Monitoring and Analysis  

SciTech Connect (OSTI)

This project aimed to develop a standard methodology for building energy data definition, collection, presentation, and analysis; apply the developed methods to a standardized energy monitoring platform, including hardware and software, to collect and analyze building energy use data; and compile offline statistical data and online real-time data in both countries for fully understanding the current status of building energy use. This helps decode the driving forces behind the discrepancy of building energy use between the two countries; identify gaps and deficiencies of current building energy monitoring, data collection, and analysis; and create knowledge and tools to collect and analyze good building energy data to provide valuable and actionable information for key stakeholders.

Hong, Tianzhen; Feng, Wei; Lu, Alison; Xia, Jianjun; Yang, Le; Shen, Qi; Im, Piljae; Bhandari, Mahabir

2013-06-01T23:59:59.000Z

405

Wibaux County Secondary Data Analysis  

E-Print Network [OSTI]

Infarction prevalence (Heart Attack) 5.5% 4.1% 6.0% All Sites Cancer 472.3 455.5 543.2 1 Community County1 Montana1,2 Nation2 1. Heart Disease 2. Cancer 3. CLRD* 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Wibaux County Secondary Data Analysis July 23, 2012 2

Maxwell, Bruce D.

406

Pondera County Secondary Data Analysis  

E-Print Network [OSTI]

prevalence (Heart Attack) 4.4% 4.1% 6.0% All Sites Cancer 461.9 455.5 543.2 1 Community Health Data, MT County1 Montana1,2 Nation2 1. Cancer 2. Heart Disease 3. Unintentional Injuries** 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Pondera County Secondary Data Analysis

Maxwell, Bruce D.

407

Dawson County Secondary Data Analysis  

E-Print Network [OSTI]

Infarction prevalence (Heart Attack) 5.5% 4.1% 6.0% All Sites Cancer 472.3 455.5 543.2 1 Community of Death County1 Montana1,2 Nation2 1. Cancer 2. Heart Disease 3. CLRD* 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Dawson County Secondary Data Analysis July 23

Maxwell, Bruce D.

408

Phillips County Secondary Data Analysis  

E-Print Network [OSTI]

Myocardial Infarction prevalence (Heart Attack) 5.5% 4.1% 6.0% All Sites Cancer 472.3 455.5 543.2 1 of Death County1 Montana1,2 Nation2 1. Cancer 2. Heart Disease 3. CLRD* 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Phillips County Secondary Data Analysis July 23

Maxwell, Bruce D.

409

Lincoln County Secondary Data Analysis  

E-Print Network [OSTI]

prevalence (Heart Attack) 5.0% 4.1% 6.0% All Sites Cancer 466.5 (Region 5) 455.5 543.2 1 Community of Death County1 Montana1,2 Nation2 1. Cancer 2. Heart Disease 3. CLRD* 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Lincoln County Secondary Data Analysis July 23

Maxwell, Bruce D.

410

Teton County Secondary Data Analysis  

E-Print Network [OSTI]

prevalence (Heart Attack) 4.4% 4.1% 6.0% All Sites Cancer 461.9 455.5 543.2 1 Community Health Data, MT County1 Montana1,2 Nation2 1. Heart Disease 2. Cancer 3. CLRD* 1. Cancer 2. Heart Disease 3.CLRD* 1. Heart Disease 2. Cancer 3. CLRD* #12; Teton County Secondary Data Analysis July 23, 2012 2

Maxwell, Bruce D.

411

The VERITAS standard data analysis  

E-Print Network [OSTI]

VERITAS is an array of Imaging Atmospheric Cherenkov Telescopes designed for very high energy gamma ray (E>100,GeV) observations of astrophysical sources. The experiment began its scientific observation program in the 2006/2007 observing season. We describe here the analysis chain for reducing the data, reconstructing the direction and energy of incident gamma rays and the rejection of background cosmic rays.

M. K. Daniel; for the VERITAS collaboration

2007-09-25T23:59:59.000Z

412

Agricultural capital project analysis system  

E-Print Network [OSTI]

analysis. Three specific objectives were established: (1) To select the most suitable procedures for economic and finan- cial evaluation of agricultural projects in developing countries, in- cluding the incorporation of an appropriate sensitivity..., Mercedes and Segismundo Lopez. TABLE OF CONTENTS INTRODUCTION General Objectives Procedure Page 1 1 3 4 LITERATURE REVIEW Evaluation Financial Evaluation Payback Period Accounting Rate of Return Net Present Value Internal Rate of Return...

Lopez, Ramon Antonio

2012-06-07T23:59:59.000Z

413

Analysis of hydrogen isotope mixtures  

DOE Patents [OSTI]

An apparatus and method for determining the concentrations of hydrogen isotopes in a sample. Hydrogen in the sample is separated from other elements using a filter selectively permeable to hydrogen. Then the hydrogen is condensed onto a cold finger or cryopump. The cold finger is rotated as pulsed laser energy vaporizes a portion of the condensed hydrogen, forming a packet of molecular hydrogen. The desorbed hydrogen is ionized and admitted into a mass spectrometer for analysis.

Villa-Aleman, Eliel (Aiken, SC)

1994-01-01T23:59:59.000Z

414

Analysis Patterns for Oil Refineries  

E-Print Network [OSTI]

We present analysis patterns to describe the structure of oil refineries. The Refinery Produc tion Unit Pattern describes the structure of units and unit groups. The Oil Storage Pattern describes the structure of tanks and tank groups. The Oil Delivery Pattern describes the structure of stations for import and export of oil. The Production Process Pattern describes the productionprocess. The audience for this paper includes analysts, designers, and programmers who are involved in developing Refinery Information Systems.

Lei Zhen; Guangzhen Shao

415

Petrography Analysis | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy ResourcesLoadingPenobscot County, Maine: Energy Resources2003) | Open EnergyInformationAnalysis Jump

416

Fuel-Coolant-Interaction modeling and analysis work for the High Flux Isotope Reactor Safety Analysis Report  

SciTech Connect (OSTI)

A brief historical background and a description of short- and long-term task plan development for effective closure of this important safety issue for the HFIR are given. Short-term aspects deal with Fuel-Coolant-Interaction (FCI) issues experimentation, modeling, and analysis for the flow-blockage-induced steam explosion events in direct support of the SAR. Long-term aspects deal with addressing FCI issues resulting from other accidents in conjunction with issues dealing with aluminum ignition, which can result in an order of magnitude increase in overall energetics. Problem formulation, modeling, and computer code simulation for the various phases of steam explosions are described. The evaluation of core melt initiation propagation, and melt superheat are described. Core melt initiation and propagation have been studied using simple conservative models as well as from modeling and analysis using RELAP5. Core debris coolability, heatup, and melting/freezing aspects have been studied by use of the two-dimensional melting/freezing analysis code 2DKO, which was also benchmarked with MELCOR code predictions. Descriptions are provided for the HM, BH, FCIMOD, and CTH computer codes that have been implemented for studying steam explosion energetics from the standpoint of evaluating bounding loads by thermodynamic models or best-estimate loads from one- and two-dimensional simulations of steam explosion energetics. Vessel failure modeling and analysis was conducted using the principles of probabilistic fracture mechanics in conjunction with ADINA code calculations. Top head bolts failure modeling has also been conducted where the failure criterion was based upon stresses in the bolts exceeding the material yield stress for a given time duration. Missile transport modeling and analysis was conducted by setting up a one-dimensional mathematical model that accounts for viscous dissipation, virtual mass effects, and material inertia.

Taleyarkhan, R.P.; Georgevich, V.; Nestor, C.W.; Chang, S.J.; Freels, J.; Gat, U.; Lepard, B.L.; Gwaltney, R.C.; Luttrell, C.; Kirkpatrick, J.

1993-07-01T23:59:59.000Z

417

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

418

Model building techniques for analysis.  

SciTech Connect (OSTI)

The practice of mechanical engineering for product development has evolved into a complex activity that requires a team of specialists for success. Sandia National Laboratories (SNL) has product engineers, mechanical designers, design engineers, manufacturing engineers, mechanical analysts and experimentalists, qualification engineers, and others that contribute through product realization teams to develop new mechanical hardware. The goal of SNL's Design Group is to change product development by enabling design teams to collaborate within a virtual model-based environment whereby analysis is used to guide design decisions. Computer-aided design (CAD) models using PTC's Pro/ENGINEER software tools are heavily relied upon in the product definition stage of parts and assemblies at SNL. The three-dimensional CAD solid model acts as the design solid model that is filled with all of the detailed design definition needed to manufacture the parts. Analysis is an important part of the product development process. The CAD design solid model (DSM) is the foundation for the creation of the analysis solid model (ASM). Creating an ASM from the DSM currently is a time-consuming effort; the turnaround time for results of a design needs to be decreased to have an impact on the overall product development. This effort can be decreased immensely through simple Pro/ENGINEER modeling techniques that summarize to the method features are created in a part model. This document contains recommended modeling techniques that increase the efficiency of the creation of the ASM from the DSM.

Walther, Howard P.; McDaniel, Karen Lynn; Keener, Donald; Cordova, Theresa Elena; Henry, Ronald C.; Brooks, Sean; Martin, Wilbur D.

2009-09-01T23:59:59.000Z

419

Emplacement Gantry Gap Analysis Study  

SciTech Connect (OSTI)

To date, the project has established important to safety (ITS) performance requirements for structures, systems, and components (SSCs) based on the identification and categorization of event sequences that may result in a radiological release. These performance requirements are defined within the ''Nuclear Safety Design Bases for License Application'' (NSDB) (BSC 2005 [DIRS 171512], Table A-11). Further, SSCs credited with performing safety functions are classified as ITS. In turn, assurance that these SSCs will perform as required is sought through the use of consensus codes and standards. This gap analysis is based on the design completed for license application only. Accordingly, identification of ITS SSCs beyond those defined within the NSDB are based on designs that may be subject to further development during detail design. Furthermore, several design alternatives may still be under consideration to satisfy certain safety functions, and final selection will not be determined until further design development has occurred. Therefore, for completeness, alternative designs currently under consideration will be discussed throughout this study. This gap analysis will evaluate each code and standard identified within the ''Emplacement Gantry ITS Standards Identification Study'' (BSC 2005 [DIRS 173586]) to ensure each ITS performance requirement is fully satisfied. When a performance requirement is not fully satisfied, a gap is highlighted. This study will identify requirements to supplement or augment the code or standard to meet performance requirements. Further, this gap analysis will identify nonstandard areas of the design that will be subject to a design development plan. Nonstandard components and nonstandard design configurations are defined as areas of the design that do not follow standard industry practices or codes and standards. Whereby, assurance that an SSC will perform as required may not be readily sought though the use of consensus standards. This gap analysis is prepared by the Emplacement and Retrieval (E&R) project team and is intended for the sole use of the Engineering department in work regarding the emplacement gantry. Yucca Mountain Project personnel from the E&R project team should be consulted before use of this gap analysis for purposes other than those stated herein or by individuals other than authorized by the Engineering department.

R. Thornley

2005-05-27T23:59:59.000Z

420

SUBSURFACE VISUAL ALARM SYSTEM ANALYSIS  

SciTech Connect (OSTI)

The ''Subsurface Fire Hazard Analysis'' (CRWMS M&O 1998, page 61), and the document, ''Title III Evaluation Report for the Surface and Subsurface Communication System'', (CRWMS M&O 1999a, pages 21 and 23), both indicate the installed communication system is adequate to support Exploratory Studies Facility (ESF) activities with the exception of the mine phone system for emergency notification purposes. They recommend the installation of a visual alarm system to supplement the page/party phone system The purpose of this analysis is to identify data communication highway design approaches, and provide justification for the selected or recommended alternatives for the data communication of the subsurface visual alarm system. This analysis is being prepared to document a basis for the design selection of the data communication method. This analysis will briefly describe existing data or voice communication or monitoring systems within the ESF, and look at how these may be revised or adapted to support the needed data highway of the subsurface visual alarm. system. The existing PLC communication system installed in subsurface is providing data communication for alcove No.5 ventilation fans, south portal ventilation fans, bulkhead doors and generator monitoring system. It is given that the data communication of the subsurface visual alarm system will be a digital based system. It is also given that it is most feasible to take advantage of existing systems and equipment and not consider an entirely new data communication system design and installation. The scope and primary objectives of this analysis are to: (1) Briefly review and describe existing available data communication highways or systems within the ESF. (2) Examine technical characteristics of an existing system to disqualify a design alternative is paramount in minimizing the number of and depth of a system review. (3) Apply general engineering design practices or criteria such as relative cost, and degree of difficulty and complexity in determining requirements in adapting existing data communication highways to support the subsurface visual alarm system. These requirements would include such things as added or new communication cables, added Programmable Logic Controller (PLC), Inputs and Outputs (I/O), and communication hardware components, and human machine interfaces and their software operating system. (4) Select the best data communication highway system based on this review of adapting or integrating with existing data communication systems.

D.W. Markman

2001-08-06T23:59:59.000Z

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


421

Energy Engineering and Systems Analysis  

E-Print Network [OSTI]

electricity grid, backup diesel generators in the event that offsite power is lost, and standby backup.5% of the previous core power if the reactor has had a long and steady power history. About 1 hour after shutdown, the decay heat will be about 1.5% of the previous core power. After a day, the decay heat falls to 0

Kemner, Ken

422

Transportation Analysis, Modeling, and Simulation (TAMS) Application  

E-Print Network [OSTI]

Transportation Analysis, Modeling, and Simulation (TAMS) Application Center for Transportation Passenger Flows Supply Chain Efficiency Transportation: Energy Environment Safety Security Vehicle Technologies T he Center for Transportation Analysis (CTA) TAMS application is a web-based tool that supports

423

Transportation Routing Analysis Geographic Information System (TRAGIS)  

E-Print Network [OSTI]

Transportation Routing Analysis Geographic Information System (TRAGIS) Model and Network Databases The Transportation Routing Analysis Geographic Information System (TRAGIS) model is a geographic information system tool for modeling transportation routing. TRAGIS offers numerous options for route calculation

424

EnergyPlus Run Time Analysis  

E-Print Network [OSTI]

Tree Lawrence Berkeley National Laboratory  Page 37  California EnergyEnergy Commission EnergyPlus Run Time Analysis Plant Supply Calling Tree (Energy Commission EnergyPlus Run Time Analysis Appendix A – EnergyPlus Call Tree

Hong, Tianzhen

2009-01-01T23:59:59.000Z

425

Energy Analysis of the Texas Capitol Restoration  

E-Print Network [OSTI]

This paper presents the methodology and results of a detailed energy analysis of the Texas Capitol Restoration. The purpose of this analysis was two-fold: 1) to determine the projected energy cost savings of a series of design alternatives...

Hunn, B. D.; Banks, J. A.; Reddy, S. N.

426

Contributions to the analysis of proteins  

E-Print Network [OSTI]

Proteins are essential to organisms and play a central role in almost every biological process. The analysis of the conformational dynamics and mechanics of proteins using numerical methods, such as normal mode analysis ...

Sharifi Sedeh, Reza

2011-01-01T23:59:59.000Z

427

System architecture analysis and selection under uncertainty  

E-Print Network [OSTI]

A system architecture analysis and selection methodology is presented that builds on the Multidisciplinary Analysis and Optimization framework. It addresses a need and opportunity to extend the MAO techniques to include a ...

Smaling, Rudolf M

2005-01-01T23:59:59.000Z

428

Data Analysis and Mining at NERSC  

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

Mining Data Analysis and Mining microCTdani.jpg Data analysis techniques include post-processing (e.g., data statistics) of experimental datasets andor simulation output, as well...

429

Transportation Routing Analysis Geographic Information System...  

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

Analysis Geographic Information System (TRAGIS) to Spent Fuel Routing Analysis P. E. Johnson R.R. Rawl Oak Ridge National Laboratory TRAGIS is being used by OCRWM to identify...

430

Eugene Solid Waste Management Market Analysis  

E-Print Network [OSTI]

Eugene Solid Waste Management Market Analysis Prepared By: Mitchell Johnson Alex Sonnichsen #12;Eugene Solid Waste Management Market Analysis May 2012 Page 1 Summary This study examines the economic impact of the solid waste management system

Oregon, University of

431

Systems Analysis Workshop List of Attendees  

Broader source: Energy.gov [DOE]

List of Attendees from DOE Systems Analysis Workshop held in Washington, D.C. July 28-29, 2004 to discuss and define role of systems analysis in DOE Hydrogen Program.

432

2012 U.S. Vehicle Analysis  

E-Print Network [OSTI]

and Air Quality. Green Vehicle Guide. Web. May 2012. 2. "Los Angeles 2012 U.S. Vehicle Analysis A thesis submitted inOF THE THESIS 2012 U.S. Vehicle Analysis by Ho Yeung Michael

Lam, Ho Yeung Michael

2012-01-01T23:59:59.000Z

433

Energy analysis program. 1994 annual report  

SciTech Connect (OSTI)

This report provides an energy analysis overview. The following topics are described: building energy analysis; urban and energy environmental issues; appliance energy efficiency standards; utility planning and policy; energy efficiency, economics, and policy issues; and international energy and environmental issues.

Levine, M.D.

1995-04-01T23:59:59.000Z

434

The conservation planning analysis model. Final report  

SciTech Connect (OSTI)

This paper contains the source code for a program on conservation planning analysis for residential, commercial and industrial customers.

Not Available

1993-12-31T23:59:59.000Z

435

DATA MONITORING AND ANALYSIS PROGRAM MANUAL  

E-Print Network [OSTI]

charts and analysis guidelines can be found in common textbooks and guidebooks on Statistical Process Control (SPC).

Gravois, Melanie

2007-01-01T23:59:59.000Z

436

Optimization Online - Analysis of mixed integer programming ...  

E-Print Network [OSTI]

Jul 15, 2014 ... Analysis of mixed integer programming formulations for single machine scheduling problems with sequence dependent setup times and ...

Thiago Henrique Nogueira

2014-07-15T23:59:59.000Z

437

Biomass Compositional Analysis Laboratory (Fact Sheet)  

SciTech Connect (OSTI)

This fact sheet provides information about Biomass Compositional Analysis Laboratory (BCAL) capabilities and applications at NREL's National Bioenergy Center.

Not Available

2011-07-01T23:59:59.000Z

438

Tensor Principal Component Analysis via Convex Optimization  

E-Print Network [OSTI]

Dec 11, 2012 ... Keywords: Tensor; Principal Component Analysis; Low Rank; Nuclear Norm; Semidefinite Programming Relaxation. Category 1: Convex and ...

Bo Jiang

2012-12-11T23:59:59.000Z

439

Cuttings Analysis At International Geothermal Area, Indonesia...  

Open Energy Info (EERE)

Indonesia (Laney, 2005) Exploration Activity Details Location International Geothermal Area Indonesia Exploration Technique Cuttings Analysis Activity Date Usefulness not indicated...

440

Microlocal Analysis of Thermoacoustic (or ... - Purdue University  

E-Print Network [OSTI]

Microlocal Analysis of Thermoacoustic (or Multiwave). Tomography, III. Plamen Stefanov. Purdue University. TAT of brain imaging (discontinuous wave speed).

Plamen Stefanov

2012-07-20T23:59:59.000Z

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


441

Cuttings Analysis At International Geothermal Area, Philippines...  

Open Energy Info (EERE)

Cuttings Analysis At International Geothermal Area, Philippines (Laney, 2005) Exploration Activity Details Location International Geothermal Area Philippines Exploration Technique...

442

Analysis of accidents during flashing operations  

E-Print Network [OSTI]

University, 1976 Federal Highway Administration Study, 1980 San Francisco Study National Study Portland, Oregon Study Summary of Literature Review Studies 13 14 16 17 20 CHAPTER Page III. ACCIDENT ANALYSIS METHODOLOGY . 22 Study Site Location... V. SUMMARY AND FINDINGS 44 REFERENCES 48 VITA 50 LIST OF TABLES TABLE 1. Groupings for Marson's Accident Analysis 2. Groupings for San Francisco Accident Analysis 3. Groupings for Portland Accident Analysis 4. Sample Sizes by Volume Ratio 5...

Obermeyer, Michael Edward

1993-01-01T23:59:59.000Z

443

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

DOE Patents [OSTI]

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

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

2013-10-29T23:59:59.000Z

444

INEEL Greenhouse Gas Inventory and Trend Analysis  

SciTech Connect (OSTI)

The objective of the INEEL GHG Inventory and Trend Analysis is to establish INEEL expertise in carbon management decision making and policy analysis. This FY-99 effort is the first step toward placing the INEEL in a leadership role within the DOE laboratories to support carbon management systems and analysis.

Shropshire, David Earl; Teel, Dale Milton

2000-02-01T23:59:59.000Z

445

GIS Analysis GIS 6116 -Spring 2015  

E-Print Network [OSTI]

). Geospatial Analysis (4th ed.). Leicester: Matador. Available online at httpGIS Analysis GIS 6116 - Spring 2015 School of Forest Resources and Conservation Geomatics Program _______________________________________________________________________________________ 1 GIS 6116 (GIS Analysis) INSTRUCTORS: Dr. Hartwig Henry Hochmair (FLREC Fort Lauderdale) Dr. Amr

Watson, Craig A.

446

Hierarchical Linear Discriminant Analysis for Beamforming  

E-Print Network [OSTI]

model of h-LDA by relating it to the two-way multivariate analysis of variance (MANOVA), which fits well dimension reduction, hierarchical linear discriminant analysis (h-LDA) to a well-known spatial localization1 Hierarchical Linear Discriminant Analysis for Beamforming Jaegul Choo , Barry L. Drake

Park, Haesun

447

1. Integrated Database 2. Boundary Analysis  

E-Print Network [OSTI]

1. Integrated Database 2. Boundary Analysis Melinda Laituri Colorado State University June 2011 #12 data Model package/ Analysis technique #12;Establishing a Database What are our scales? What are our units of analysis? What commonality do we have? What is the nature of our data? What

448

Analysis methods for Atmospheric Cerenkov Telescopes  

E-Print Network [OSTI]

Three different analysis techniques for Atmospheric Imaging System are presented. The classical Hillas parameters based technique is shown to be robust and efficient, but more elaborate techniques can improve the sensitivity of the analysis. A comparison of the different analysis techniques shows that they use different information for gamma-hadron separation, and that it is possible to combine their qualities.

Mathieu de Naurois

2006-07-12T23:59:59.000Z

449

Analysis of Water Modeling of Air Entrainment  

E-Print Network [OSTI]

Analysis of Water Modeling of Air Entrainment S.C. Jain Professor and Research Engineer Dept. Civil, C., "Analysis of Water Modeling of Air Entrainment," in Proceedings of the 48th SFSA Technical An analysis is reported of the water modeling experiments of Bates et al. (1994) to study air entrainment

Beckermann, Christoph

450

Automated Eye-Movement Protocol Analysis  

E-Print Network [OSTI]

Automated Eye-Movement Protocol Analysis Dario D. Salvucci and John R. Anderson Carnegie Mellon analysis of eye-movement protocols. Although eye movements have be- come increasingly popular as a tool an ap- proach to automating eye-movement protocol analysis by means of tracing--re- lating observed eye

Salvucci, Dario D.

451

Addressing Climate Change in Environmental Impact Analysis  

E-Print Network [OSTI]

Addressing Climate Change in Environmental Impact Analysis 2010 CTS Research Conference Carissa ­! Environmental impact analysis methods and content ·! Next steps #12;Purpose ·! Explore the use of environmental ·! Federal and state policies govern environmental impact analysis ­!National Environmental Policy Act (NEPA

Minnesota, University of

452

Compiler Construction Lecture 3: Lexical Analysis II  

E-Print Network [OSTI]

Compiler Construction Lecture 3: Lexical Analysis II (Extended Matching Problem) Thomas Noll-Longest-Match Analysis 5 Implementation of FLM Analysis Compiler Construction Summer Semester 2012 3.2 #12;Lexical Construction Summer Semester 2012 3.3 #12;The DFA Method I Known from Formal Systems, Automata and Processes

Ábrahám, Erika

453

MODAL ENERGY ANALYSIS Nicolas Totaro1*  

E-Print Network [OSTI]

MODAL ENERGY ANALYSIS Nicolas Totaro1* , Jean-Louis Guyader1 1 Laboratoire Vibrations Acoustique.totaro@insa-lyon.fr Keywords: Energy methods, non resonant, pure tone, Statistical Energy Analysis, MODENA. ABSTRACT The Modal Energy Analysis presented in this paper is a method to predict energy exchanges between vibro

Paris-Sud XI, Université de

454

Principal Components Analysis for Binary Data  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ix CHAPTER I INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Formulations of Principal Components Analysis . . . . . . . . 2 1.2 Generalization of Sparse Principal Components Analysis to Binary Variables... . . . . . . . . . . . . . . . . . . . . . . . . 8 1.3 Review of Estimation Procedures . . . . . . . . . . . . . . . . 11 1.4 Overview of Dissertation . . . . . . . . . . . . . . . . . . . . . 18 II SPARSE PRINCIPAL COMPONENTS ANALYSIS FOR BI- NARY DATA...

Lee, Seokho

2010-07-14T23:59:59.000Z

455

Image patch analysis of sunspots and active regions. I. Intrinsic dimension and correlation analysis  

E-Print Network [OSTI]

Complexity of an active region is related to its flare-productivity. Mount Wilson or McIntosh sunspot classifications measure such complexity but in a categorical way, and may therefore not use all the information present in the observations. Moreover, such categorical schemes hinder a systematic study of an active region's evolution for example. We propose fine-scale quantitative descriptors for an active region's complexity and relate them to the Mount Wilson classification. We analyze the local correlation structure within continuum and magnetogram data, as well as the cross-correlation between continuum and magnetogram data. We compute the intrinsic dimension, partial correlation, and canonical correlation analysis (CCA) of image patches of continuum and magnetogram active region images taken from the SOHO-MDI instrument. We use masks of sunspots derived from continuum as well as larger masks of magnetic active regions derived from the magnetogram to analyze separately the core part of an active region fr...

Moon, Kevin R; Delouille, Veronique; De Visscher, Ruben; Watson, Fraser; Hero, Alfred O

2015-01-01T23:59:59.000Z

456

Discrete analysis of stochastic NMR  

SciTech Connect (OSTI)

Stochastic NMR is an efficient technique for high field in vivo imaging and spectroscopic studies in cases where the peak rf power required may be prohibitively high for conventional pulsed NMR techniques. This dissertation presents a theoretical analysis of a stochastic NMR method of acquiring spectroscopy data. The spin system is excited with rf pulses where the flip angles or the phases of the pulses are samples of a discrete stochastic process. The method is formulated as a stochastic difference equation which is then converted to ordinary deterministic difference equations describing the input-output cross-correlation, average signal power and signal power spectrum. The solutions of these equations are used to evaluate the stochastic, technique in terms of peak rf power requirement, spectral distortions and signal-to-noise ratio. Experimental results are also presented which verify the results of the discrete analysis. The analysis shows that the maximum signal-to-noise ratio is achieved when the RMS flip angle is approximately the Ernst angle. When the RMS flip angle is below the Ernst angle, the input-output cross-correlation is a good estimate of the FID. Increase of excitation power causes line broadening. In addition, the use of random flip angle, fixed phase excitation causes a notch artifact and non-uniform response across the spectrum both of which are not found in two new types of excitation, the random phase excitation and the random quadrature excitation. The signal power spectrum is also a good estimate of the real spectrum. The approximation of the cross-correlation by a time average causes systematic noise. The amount of systematic noise is found to be significantly reduced when an entire maximum length sequence (MLS) is used for excitation. Noise-like distortion at high power MLS excitation is discovered to be related to the number of feedback paths in the MLS generator. 29 refs., 58 figs.

Wong, Sam Tak-Sum

1988-12-01T23:59:59.000Z

457

MPQC: Performance Analysis and Optimization  

SciTech Connect (OSTI)

MPQC (Massively Parallel Quantum Chemistry) is a widely used computational quantum chemistry code. It is capable of performing a number of computations commonly occurring in quantum chemistry. In order to achieve better performance of MPQC, in this report we present a detailed performance analysis of this code. We then perform loop and memory access optimizations, and measure performance improvements by comparing the performance of the optimized code with that of the original MPQC code. We observe that the optimized MPQC code achieves a significant improvement in the performance through a better utilization of vector processing and memory hierarchies.

Sarje, Abhinav; Williams, Samuel; Bailey, David

2012-11-30T23:59:59.000Z

458

Economic analysis of fusion breeders  

SciTech Connect (OSTI)

This paper presents a study of the economic performance of Fission/Fusion Hybrid devices. This work takes fusion breeder cost estimates and applies methodology and cost factors used in the fission reactor programs to compare fusion breeders with Liquid Metal Fast Breeder Reactors (LMFBR). The results of the analysis indicate that the Hybrid will be in the same competitive range as proposed LMFBRs and have the potential to provide economically competitive power in a future of rising uranium prices. The sensitivity of the results to variations in key parameters is included.

Delene, J.G.

1985-01-01T23:59:59.000Z

459

Cost Estimating, Analysis, and Standardization  

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

To establish policy and responsibilities for: (a) developing and reviewing project cost estimates; (b) preparing independent cost estimates and analysis; (c) standardizing cost estimating procedures; and (d) improving overall cost estimating and analytical techniques, cost data bases, cost and economic escalation models, and cost estimating systems. Cancels DOE O 5700.2B, dated 8-5-1983; DOE O 5700.8, dated 5-27-1981; and HQ 1130.1A, dated 12-30-1981. Canceled by DOE O 5700.2D, dated 6-12-1992

1984-11-02T23:59:59.000Z

460

Nanoelectrode array for electrochemical analysis  

DOE Patents [OSTI]

A nanoelectrode array comprises a plurality of nanoelectrodes wherein the geometric dimensions of the electrode controls the electrochemical response, and the current density is independent of time. By combining a massive array of nanoelectrodes in parallel, the current signal can be amplified while still retaining the beneficial geometric advantages of nanoelectrodes. Such nanoelectrode arrays can be used in a sensor system for rapid, non-contaminating field analysis. For example, an array of suitably functionalized nanoelectrodes can be incorporated into a small, integrated sensor system that can identify many species rapidly and simultaneously under field conditions in high-resistivity water, without the need for chemical addition to increase conductivity.

Yelton, William G. (Sandia Park, NM); Siegal, Michael P. (Albuquerque, NM)

2009-12-01T23:59:59.000Z

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


461

SNL/CA Supplement Analysis  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of Energy fromCommentsRevolving LoanDepartment of422-SA-01 Supplement Analysis

462

The Independent Technical Analysis Process  

SciTech Connect (OSTI)

The Bonneville Power Administration (BPA) contracted with the Pacific Northwest National Laboratory (PNNL) to provide technical analytical support for system-wide fish passage information (BPA Project No. 2006-010-00). The goal of this project was to produce rigorous technical analysis products using independent analysts and anonymous peer reviewers. In the past, regional parties have interacted with a single entity, the Fish Passage Center to access the data, analyses, and coordination related to fish passage. This project provided an independent technical source for non-routine fish passage analyses while allowing routine support functions to be performed by other well-qualified entities.

Duberstein, Corey A.; Ham, Kenneth D.; Dauble, Dennis D.; Johnson, Gary E.

2007-04-13T23:59:59.000Z

463

Cuttings Analysis | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentratingRenewable Solutions LLC JumpCrow Lake Wind JumpCuttings Analysis At NewInformation

464

Energy Analysis | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-UpHeat PumpRecord ofESPC ENABLE:2009 DOE Hydrogen ProgramEnergize| Department ofAnalysis

465

Global Pathways Analysis Tool (GPAT)  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdf Flash2006-53.pdf0.pdfCostAnalysis GeothermalEnergyDepartment of Energy

466

Sandia National Laboratories: Systems Analysis  

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

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

467

Transportation Analysis | Clean Energy | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layered NbS2Topo II: AnTrainingTransportation Analysis SHARE

468

Chemical substructure analysis in toxicology  

SciTech Connect (OSTI)

A preliminary examination of chemical-substructure analysis (CSA) demonstrates the effective use of the Chemical Abstracts compound connectivity file in conjunction with the bibliographic file for relating chemical structures to biological activity. The importance of considering the role of metabolic intermediates under a variety of conditions is illustrated, suggesting structures that should be examined that may exhibit potential activity. This CSA technique, which utilizes existing large files accessible with online personal computers, is recommended for use as another tool in examining chemicals in drugs. 2 refs., 4 figs.

Beauchamp, R.O. Jr. [Center for Information on Toxicology and Environment, Raleigh, NC (United States)

1990-12-31T23:59:59.000Z

469

Canister Storage Building (CSB) Hazard Analysis Report  

SciTech Connect (OSTI)

This report describes the methodology used in conducting the Canister Storage Building (CSB) Hazard Analysis to support the final CSB Safety Analysis Report and documents the results. This report describes the methodology used in conducting the Canister Storage Building (CSB) hazard analysis to support the CSB final safety analysis report (FSAR) and documents the results. The hazard analysis process identified hazardous conditions and material-at-risk, determined causes for potential accidents, identified preventive and mitigative features, and qualitatively estimated the frequencies and consequences of specific occurrences. The hazard analysis was performed by a team of cognizant CSB operations and design personnel, safety analysts familiar with the CSB, and technical experts in specialty areas. The material included in this report documents the final state of a nearly two-year long process. Attachment A provides two lists of hazard analysis team members and describes the background and experience of each. The first list is a complete list of the hazard analysis team members that have been involved over the two-year long process. The second list is a subset of the first list and consists of those hazard analysis team members that reviewed and agreed to the final hazard analysis documentation. The material included in this report documents the final state of a nearly two-year long process involving formal facilitated group sessions and independent hazard and accident analysis work. The hazard analysis process led to the selection of candidate accidents for further quantitative analysis. New information relative to the hazards, discovered during the accident analysis, was incorporated into the hazard analysis data in order to compile a complete profile of facility hazards. Through this process, the results of the hazard and accident analyses led directly to the identification of safety structures, systems, and components, technical safety requirements, and other controls required to protect the public, workers, and environment.

POWERS, T.B.

2000-03-16T23:59:59.000Z

470

Chemical analysis of biomass fast pyrolysis oils  

SciTech Connect (OSTI)

This paper reviews the development of the field of chemical analysis of biomass fast pyrolysis oils. The techniques applied to pyrolysis oil analysis are reviewed including proximate and ultimate analysis, water (moisture) analysis, and chemical component analysis by various forms of chromatography, solvent separations, and spectrophotometric analyses, like infrared and ultraviolet. Advanced analytical techniques such as nuclear magnetic resonance and molecular beam -- mass spectrometry are also discussed. This paper reviews and compares the methods and the results of the analyses. The advantages and shortcomings of the various methods applied are identified. Comparisons derived from the IEA Round Robin are incorporated.

Elliott, D.C.

1994-09-01T23:59:59.000Z

471

Asset-based poverty analysis in rural Bangladesh: A comparison of principal component analysis and  

E-Print Network [OSTI]

1 Asset-based poverty analysis in rural Bangladesh: A comparison of principal component analysis not be regarded as the views of SRI or The University of Leeds. #12;3 Asset-based poverty analysis in rural The trend towards multi-dimensional poverty assessment ..................... 5 Principal component analysis

Mound, Jon

472

Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture  

DOE Patents [OSTI]

Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture are described. According to one embodiment, an earth analysis method includes engaging a device with the earth, analyzing the earth in a single substantially lineal direction using the device during the engaging, and providing information regarding a subsurface feature of the earth using the analysis.

West, Phillip B. (Idaho Falls, ID); Novascone, Stephen R. (Idaho Falls, ID); Wright, Jerry P. (Idaho Falls, ID)

2012-05-29T23:59:59.000Z

473

Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture  

DOE Patents [OSTI]

Earth analysis methods, subsurface feature detection methods, earth analysis devices, and articles of manufacture are described. According to one embodiment, an earth analysis method includes engaging a device with the earth, analyzing the earth in a single substantially lineal direction using the device during the engaging, and providing information regarding a subsurface feature of the earth using the analysis.

West, Phillip B. (Idaho Falls, ID); Novascone, Stephen R. (Idaho Falls, ID); Wright, Jerry P. (Idaho Falls, ID)

2011-09-27T23:59:59.000Z

474

Cameco UO3 Materials Analysis  

SciTech Connect (OSTI)

Uranium trioxide (UO{sub 3}) was characterized using a variety of techniques to better understand its physical properties. Scanning electron microscope (SEM) images were collected to examine particle morphology, which consisted of semi-spherical particles that tended to agglomerate before sonication. Particle size analysis revealed a singular mode distribution with a mean particle size of 43.0 {micro}m. After sonication a bimodal distribution was produced with peak particle sizes at 0.226 {micro}m and 9.43 {micro}m. The O/U ratio was measured to be 3.09 by Cameco in 2009, by gravimetric analysis. X-ray diffraction (XRD) showed that the sample was mostly {gamma}-UO{sub 3} (87.1%) with a small amount of UO{sub 3} {center_dot} 0.80 H{sub 2}O (12.9%). Bulk and tap densities were determined to be 3.678 {+-} 0.2 and 4.81 {+-} 0.2 g/cm{sup 3}, respectively (crystalline density is 7.3 g/cm{sup 3}). The stoichiometry was measured to be 2.99 in 2012.

Hill, Mary Ann [Los Alamos National Laboratory; Nolen, Blake Penfield [Los Alamos National Laboratory; Wermer, Joseph R. [Los Alamos National Laboratory; Wilkerson, Marianne P. [Los Alamos National Laboratory; Fredenburg, David A. [Los Alamos National Laboratory; Wagner, Gregory L. [Los Alamos National Laboratory; Papin, Pallas A. [Los Alamos National Laboratory; Scott, Brian L. [Los Alamos National Laboratory; Guidry, Dennis Ray [Los Alamos National Laboratory

2012-07-12T23:59:59.000Z

475

Technical Analysis of Hydrogen Production  

SciTech Connect (OSTI)

The aim of this work was to assess issues of cost, and performance associated with the production and storage of hydrogen via following three feedstocks: sub-quality natural gas (SQNG), ammonia (NH{sub 3}), and water. Three technology areas were considered: (1) Hydrogen production utilizing SQNG resources, (2) Hydrogen storage in ammonia and amine-borane complexes for fuel cell applications, and (3) Hydrogen from solar thermochemical cycles for splitting water. This report summarizes our findings with the following objectives: Technoeconomic analysis of the feasibility of the technology areas 1-3; Evaluation of the hydrogen production cost by technology areas 1; and Feasibility of ammonia and/or amine-borane complexes (technology areas 2) as a means of hydrogen storage on-board fuel cell powered vehicles. For each technology area, we reviewed the open literature with respect to the following criteria: process efficiency, cost, safety, and ease of implementation and impact of the latest materials innovations, if any. We employed various process analysis platforms including FactSage chemical equilibrium software and Aspen Technologies AspenPlus and HYSYS chemical process simulation programs for determining the performance of the prospective hydrogen production processes.

Ali T-Raissi

2005-01-14T23:59:59.000Z

476

HCCl Combustion: Analysis and Experiments  

SciTech Connect (OSTI)

Homogeneous charge compression ignition (HCCI) is a new combustion technology that may develop as an alternative to diesel engines with high efficiency and low NOx and particulate matter emissions. This paper describes the HCCI research activities being currently pursued at Lawrence Livermore National Laboratory and at the University of California Berkeley. Current activities include analysis as well as experimental work. On analysis, we have developed two powerful tools: a single zone model and a multi-zone model. The single zone model has proven very successful in predicting start of combustion and providing reasonable estimates for peak cylinder pressure, indicated efficiency and NOX emissions. This model is being applied to develop detailed engine performance maps and control strategies, and to analyze the problem of engine startability. The multi-zone model is capable of very accurate predictions of the combustion process, including HC and CO emissions. The multi-zone model has applicability to the optimization of combustion chamber geometry and operating conditions to achieve controlled combustion at high efficiency and low emissions. On experimental work, we have done a thorough evaluation of operating conditions in a 4-cylinder Volkswagen TDI engine. The engine has been operated over a wide range of conditions by adjusting the intake temperature and the fuel flow rate. Satisfactory operation has been obtained over a wide range of operating conditions. Cylinder-to-cylinder variations play an important role in limiting maximum power, and should be controlled to achieve satisfactory performance.

Aceves, S M; Flowers, D L; Martinez-Frias, J; Smith, J R; Dibble, R; Au, M; Girard, J

2001-05-04T23:59:59.000Z

477

HCCI Combustion: Analysis and Experiments  

SciTech Connect (OSTI)

Homogeneous charge compression ignition (HCCI) is a new combustion technology that may develop as an alternative to diesel engines with high efficiency and low NOx and particulate matter emissions. This paper describes the HCCI research activities being currently pursued at Lawrence Livermore National Laboratory and at the University of California Berkeley. Current activities include analysis as well as experimental work. On analysis, we have developed two powerful tools: a single zone model and a multi-zone model. The single zone model has proven very successful in predicting start of combustion and providing reasonable estimates for peak cylinder pressure, indicated efficiency and NOX emissions. This model is being applied to develop detailed engine performance maps and control strategies, and to analyze the problem of engine startability. The multi-zone model is capable of very accurate predictions of the combustion process, including HC and CO emissions. The multi-zone model h as applicability to the optimization of combustion chamber geometry and operating conditions to achieve controlled combustion at high efficiency and low emissions. On experimental work, we have done a thorough evaluation of operating conditions in a 4-cylinder Volkswagen TDI engine. The engine has been operated over a wide range of conditions by adjusting the intake temperature and the fuel flow rate. Satisfactory operation has been obtained over a wide range of operating conditions. Cylinder-to-cylinder variations play an important role in limiting maximum power, and should be controlled to achieve satisfactory performance.

Salvador M. Aceves; Daniel L. Flowers; Joel Martinez-Frias; J. Ray Smith; Robert Dibble; Michael Au; James Girard

2001-05-14T23:59:59.000Z

478

New likelihoods for shape analysis  

E-Print Network [OSTI]

We introduce a new kind of likelihood function based on the sequence of moments of the data distribution. Both binned and unbinned data samples are discussed, and the multivariate case is also derived. Building on this approach we lay out the formalism of shape analysis for signal searches. In addition to moment-based likelihoods, standard likelihoods and approximate statistical tests are provided. Enough material is included to make the paper self-contained from the perspective of shape analysis. We argue that the moment-based likelihoods can advantageously replace unbinned standard likelihoods for the search of non-local signals, by avoiding the step of fitting Monte-Carlo generated distributions. This benefit increases with the number of variables simultaneously analyzed. The moment-based signal search is exemplified and tested in various 1D toy models mimicking typical high-energy signal--background configurations. Moment-based techniques should be particularly appropriate for the searches for effective operators at the LHC.

Sylvain Fichet

2014-07-03T23:59:59.000Z

479

Analysis Efforts Supporting NSTX Upgrades  

SciTech Connect (OSTI)

The National Spherical Torus Experiment (NSTX) is a low aspect ratio, spherical torus (ST) configuration device which is located at Princeton Plasma Physics Laboratory (PPPL) This device is presently being updated to enhance its physics by doubling the TF field to 1 Tesla and increasing the plasma current to 2 Mega-amperes. The upgrades include a replacement of the centerstack and addition of a second neutral beam. The upgrade analyses have two missions. The first is to support design of new components, principally the centerstack, the second is to qualify existing NSTX components for higher loads, which will increase by a factor of four. Cost efficiency was a design goal for new equipment qualification, and reanalysis of the existing components. Showing that older components can sustain the increased loads has been a challenging effort in which designs had to be developed that would limit loading on weaker components, and would minimize the extent of modifications needed. Two areas representing this effort have been chosen to describe in more details: analysis of the current distribution in the new TF inner legs, and, second, analysis of the out-of-plane support of the existing TF outer legs.

H.Zhang, P. Titus, P. Rogoff, A.Zolfaghari, D. Mangra, M. Smith

2010-11-29T23:59:59.000Z

480

Analysis on a Fractal Set  

E-Print Network [OSTI]

The formulation of a new analysis on a zero measure Cantor set $C (\\subset I=[0,1])$ is presented. A non-archimedean absolute value is introduced in $C$ exploiting the concept of {\\em relative} infinitesimals and a scale invariant ultrametric valuation of the form $\\log_{\\varepsilon^{-1}} (\\varepsilon/x) $ for a given scale $\\varepsilon>0$ and infinitesimals $0analysis is also outlined, when the singleton $\\{0\\}$ of the real line $R$ is replaced by a zero measure Cantor set. The Cantor function is realised as a locally constant function in this setting. The ordinary derivative $dx/dt$ in $R$ is replaced by the scale invariant logarithmic derivative $d\\log x/d\\log t$ on the set of valued infinitesimals. As a result, the ordinary real valued functions are expected to enjoy some novel asymptotic properties, which might have important applications in number theory and in other areas of mathematics.

Santanu Raut; Dhurjati Prasad Datta

2010-01-10T23:59:59.000Z

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


481

Building Energy Monitoring and Analysis  

SciTech Connect (OSTI)

U.S. and China are the world’s top two economics. Together they consumed one-third of the world’s primary energy. It is an unprecedented opportunity and challenge for governments, researchers and industries in both countries to join together to address energy issues and global climate change. Such joint collaboration has huge potential in creating new jobs in energy technologies and services. Buildings in the US and China consumed about 40% and 25% of the primary energy in both countries in 2010 respectively. Worldwide, the building sector is the largest contributor to the greenhouse gas emission. Better understanding and improving the energy performance of buildings is a critical step towards sustainable development and mitigation of global climate change. This project aimed to develop a standard methodology for building energy data definition, collection, presentation, and analysis; apply the developed methods to a standardized energy monitoring platform, including hardware and software, to collect and analyze building energy use data; and compile offline statistical data and online real-time data in both countries for fully understanding the current status of building energy use. This helps decode the driving forces behind the discrepancy of building energy use between the two countries; identify gaps and deficiencies of current building energy monitoring, data collection, and analysis; and create knowledge and tools to collect and analyze good building energy data to provide valuable and actionable information for key stakeholders.

Hong, Tianzhen; Feng, Wei; Lu, Alison; Xia, Jianjun; Yang, Le; Shen, Qi; Im, Piljae; Bhandari, Mahabir

2013-06-01T23:59:59.000Z

482

Current work in energy analysis  

SciTech Connect (OSTI)

This report describes the work performed at Berkeley Lab most recently. One of the Labs accomplishments is the publication of Scenarios of US Carbon Reductions, an analysis of the potential of energy technologies to reduce carbon emissions in the US. This analysis is described and played a key role in shaping the US position on climate change in the Kyoto Protocol negotiations. The Labs participation in the fundamental characterization of the climate change issue by the IPCC is described. Described also is a study of leaking electricity, which is stimulating an international campaign for a one-watt ceiling for standby electricity losses from appliances. This ceiling has the potential to save two-thirds of the 5% of US residential electricity currently expended on standby losses. The 54 vignettes contained in the report summarize results of research activities ranging in scale from calculating the efficacy of individual lamp ballasts to estimating the cost-effectiveness of the national Energy Star{reg_sign} labeling program, and ranging in location from a scoping study of energy-efficiency market transformation in California to development of an energy-efficiency project in the auto parts industry in Shandong Province, China.

NONE

1998-03-01T23:59:59.000Z

483

Comparative Analysis of Urban Atmospheric Aerosol by Particle...  

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

Analysis of Urban Atmospheric Aerosol by Particle-Induced X-ray Emission (PIXE), Proton Elastic Scattering Analysis Comparative Analysis of Urban Atmospheric Aerosol by...

484

EIS-0218-SA-02: Supplement Analysis | Department of Energy  

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

Supplement Analysis EIS-0218-SA-02: Supplement Analysis Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program The objective of this analysis was to...

485

Events Beyond Design Safety Basis Analysis | Department of Energy  

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

Events Beyond Design Safety Basis Analysis Events Beyond Design Safety Basis Analysis March 23, 2011 Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis This Safety...

486

annihilation factor analysis: Topics by E-print Network  

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

16 Correlated Bayesian Factor Analysis CiteSeer Summary: Factor analysis is a method in multivariate statistical analysis that can help scientists determine which variables to...

487

acid sequence analysis: Topics by E-print Network  

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

sequences. The starting Radicioni, Daniele 26 A Method for Sequence Analysis Using Multivariate Analysis CiteSeer Summary: We developed a computational sequence analysis...

488

Atmospheric Solids Analysis Probe Mass Spectrometry: A New Approach...  

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

Atmospheric Solids Analysis Probe Mass Spectrometry: A New Approach for Airborne Particle Analysis. Atmospheric Solids Analysis Probe Mass Spectrometry: A New Approach for Airborne...

489

analysis naa applied: Topics by E-print Network  

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

Websites Summary: barrier (SBA), fault tree (FTA) and failure mode and effect analysis (FMEA) into one method. Our approach Analysis (FTA), Failure Mode and Effect Analysis (FMEA),...

490

assortment structure analysis: Topics by E-print Network  

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

Websites Summary: barrier (SBA), fault tree (FTA) and failure mode and effect analysis (FMEA) into one method. Our approach Analysis (FTA), Failure Mode and Effect Analysis...

491

Analysis of Low-Temperature Utilization of Geothermal Resources...  

Open Energy Info (EERE)

Analysis Project Type Topic 2 Geothermal Analysis Project Description In this proposal West Virginia University (WVU) outline a project which will perform an in-depth analysis...

492

Employee Job Task Analysis (EJTA) PIA, Richland Operations Office...  

Office of Environmental Management (EM)

Job Task Analysis (EJTA) PIA, Richland Operations Office Employee Job Task Analysis (EJTA) PIA, Richland Operations Office Employee Job Task Analysis (EJTA) PIA, Richland...

493

H2A Hydrogen Delivery Infrastructure Analysis Models and Conventional...  

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

H2A Hydrogen Delivery Infrastructure Analysis Models and Conventional Pathway Options Analysis Results - Interim Report H2A Hydrogen Delivery Infrastructure Analysis Models and...

494

The analysis of the OECD/NEA/NSC PBMR-400 benchmark problem using PARCS-DIREKT  

SciTech Connect (OSTI)

The OECD/NEA/NSC PBMR-400 benchmark problem was developed to support the validation and verification efforts for the PBMR design. This paper describes the analysis of this problem using the PARCS-DIREKT coupled code system. The benchmark problem involved the use of two different cross-section libraries, one which was generated from a VSOP equilibrium core calculation and has no dependence on core conditions. The second library provides for dependence on five state parameters and was designed for transient analysis. The paper here reports the steady-state cases using the VSOP set of cross-sections. The results are shown to be in good agreement with those of VSOP. Also reported here are the results of the steady-state thermal-hydraulic DIRECKT solution with a given power profile obtained from VSOP equilibrium core calculation. This analysis provides some insight as to the most important parameters in the design of PBMR-400. (authors)

Seker, V.; Downar, T. J. [Purdue Univ., 400 Central Drive, West Lafayette, IN 47907 (United States)

2006-07-01T23:59:59.000Z

495

NUCLEAR FORENSICS ANALYSIS CENTER FORENSIC ANALYSIS TO DATA INTERPRETATION  

SciTech Connect (OSTI)

The Nuclear Forensics Analysis Center (NFAC) is part of Savannah River National Laboratory (SRNL) and is one of only two USG National Laboratories accredited to perform nuclear forensic analyses to the requirements of ISO 17025. SRNL NFAC is capable of analyzing nuclear and radiological samples from bulk material to ultra-trace samples. NFAC provides analytical support to the FBI's Radiological Evidence Examination Facility (REEF), which is located within SRNL. REEF gives the FBI the capability to perform traditional forensics on material that is radiological and/or is contaminated. SRNL is engaged in research and development efforts to improve the USG technical nuclear forensics capabilities. Research includes improving predictive signatures and developing a database containing comparative samples.

Nichols, T.

2011-02-07T23:59:59.000Z

496

Trace Assessment for BWR ATWS Analysis  

SciTech Connect (OSTI)

A TRACE/PARCS input model has been developed in order to be able to analyze anticipated transients without scram (ATWS) in a boiling water reactor. The model is based on one developed previously for the Browns Ferry reactor for doing loss-of-coolant accident analysis. This model was updated by adding the control systems needed for ATWS and a core model using PARCS. The control systems were based on models previously developed for the TRAC-B code. The PARCS model is based on information (e.g., exposure and moderator density (void) history distributions) obtained from General Electric Hitachi and cross sections for GE14 fuel obtained from an independent source. The model is able to calculate an ATWS, initiated by the closure of main steam isolation valves, with recirculation pump trip, water level control, injection of borated water from the standby liquid control system and actuation of the automatic depres-surization system. The model is not considered complete and recommendations are made on how it should be improved.

Cheng, L.Y.; Diamond, D.; Arantxa Cuadra, Gilad Raitses, Arnold Aronson

2010-04-22T23:59:59.000Z

497

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1. Volume 2, Part 1C: Analysis of core damage frequency from internal events for plant operational State 5 during a refueling outage, Main report (Sections 11--14)  

SciTech Connect (OSTI)

This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power analyses performed on Grand Gulf.

Whitehead, D. [Sandia National Labs., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Yakle, J. [Science Applications International Corp., Albuquerque, NM (United States)] [and others

1994-06-01T23:59:59.000Z

498

Analysis of closed-pool boilup using the TRANSIT-HYDRO code. [LMFBR  

SciTech Connect (OSTI)

The benign termination of the transition phase of a hypothetical LMFBR accident rests on the avoidance of highly energetic recriticalities prior to escape of bottled molten core materials from the active core region. In scenarios where molten fuel is trapped due to axial blockages, the maintenance of subcritical configurations until radial flow paths develop requires stable boil-up of the molten fuel/steel mixture. This paper describes the analysis of an experiment investigating the behavior of closed boiling pools using the two-fluid hydrodynamics module of TRANSIT-HYDRO, a deterministic transition-phase analysis code.

Graff, D.L.

1983-01-04T23:59:59.000Z

499

A Geospatial Analysis on Empirical Distribution with Applications to Atmospheric Infrared Sounder Level 3 Data  

E-Print Network [OSTI]

3 Geospatial Analysis . . . . . . . . .5 Geospatial Lattice Analysis byof California Los Angeles A Geospatial Analysis on Empirical

Liu, Xian

2012-01-01T23:59:59.000Z

500

ROOT CAUSE ANALYSIS PROGRAM MANUAL  

SciTech Connect (OSTI)

Root Cause Analysis (RCA) identifies the cause of an adverse condition that, if corrected, will preclude recurrence or greatly reduce the probability of recurrence of the same or similar adverse conditions and thereby protect the health and safety of the public, the workers, and the environment. This procedure sets forth the requirements for management determination and the selection of RCA methods and implementation of RCAs that are a result of significant findings from Price-Anderson Amendments Act (PAAA) violations, occurrences/events, Significant Adverse Conditions, and external oversight Corrective Action Requests (CARs) generated by the Office of Enforcement (PAAA headquarters), the U.S. Environmental Protection Agency, and other oversight entities against Lawrence Berkeley National Laboratory (LBNL). Performance of an RCA may result in the identification of issues that should be reported in accordance with the Issues Management Program Manual.

Gravois, Melanie C.

2007-05-02T23:59:59.000Z