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Note: This page contains sample records for the topic "integrated iterative solution" from the National Library of EnergyBeta (NLEBeta).
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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

Accelerated Iterative Method for Solving Steady Solutions of Linearized Atmospheric Models  

E-Print Network [OSTI]

Accelerated Iterative Method for Solving Steady Solutions of Linearized Atmospheric Models Masahiro approach, referred to as the accelerated iterative method (AIM), is developed for solving steady state, respectively. For ensuring the accelerated asymptotic convergence of iterative procedure

Watanabe, Masahiro

2

Error Control of Iterative Linear Solvers for Integrated Groundwater Models  

E-Print Network [OSTI]

and presentation of GMRES performance benchmarking results. Introduction As the groundwater model infrastructureError Control of Iterative Linear Solvers for Integrated Groundwater Models by Matthew F. Dixon1 for integrated groundwater models, which are implicitly coupled to another model, such as surface water models

Bai, Zhaojun

3

Iterative solution of ordinary differential equations with polynomial coefficients  

E-Print Network [OSTI]

ITERATIVE SOLUTION OF ORDINARY DIFFERENTIAL EQUATIONS WITH POLYNOMIAL COEFFICIENTS A Thesis By JIMMIE CHARLES RHEA FOREHAND Submitted to the Graduate College of the Texas A&M University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE August 1965 Major Subject Mathematics FAMILIES OF FIFTH ORDER RUNGE-KUTTA FORMULAS A Thesis By HARRY PAUL KONEN 4 0 0 IXI v 0 Approved as to style and content by: (Chairman of Committee) (Head of Departmen...

Forehand, Jimmie Charles Rhea

1965-01-01T23:59:59.000Z

4

Volkov solution for two laser beams and ITER  

E-Print Network [OSTI]

We find the solution of the Dirac equation for two plane waves (laser beams) and we determine the modified Compton formula for the scattering of two photons on an alectron. The practical meaning of the two laser beams is, that two laser beams impinging on a targed which is constituted from material in the form of a foam, can replace 100-200 laser beams impinging on a normal targed. It means that the nuclear fusion with two laser beams is realistic in combination with the nuclear reactor such as ITER.

Miroslav Pardy

2005-07-12T23:59:59.000Z

5

Improved parallel solution techniques for the integral transport matrix method  

SciTech Connect (OSTI)

Alternative solution strategies to the parallel block Jacobi (PBJ) method for the solution of the global problem with the integral transport matrix method operators have been designed and tested. The most straightforward improvement to the Jacobi iterative method is the Gauss-Seidel alternative. The parallel red-black Gauss-Seidel (PGS) algorithm can improve on the number of iterations and reduce work per iteration by applying an alternating red-black color-set to the subdomains and assigning multiple sub-domains per processor. A parallel GMRES(m) method was implemented as an alternative to stationary iterations. Computational results show that the PGS method can improve on the PBJ method execution by up to {approx}50% when eight sub-domains per processor are used. However, compared to traditional source iterations with diffusion synthetic acceleration, it is still approximately an order of magnitude slower. The best-performing case are opticaUy thick because sub-domains decouple, yielding faster convergence. Further tests revealed that 64 sub-domains per processor was the best performing level of sub-domain division. An acceleration technique that improves the convergence rate would greatly improve the ITMM. The GMRES(m) method with a diagonal block preconditioner consumes approximately the same time as the PBJ solver but could be improved by an as yet undeveloped, more efficient preconditioner.

Zerr, Robert J [Los Alamos National Laboratory; Azmy, Yousry Y [NORTH CAROLINA STATE UNIV.

2010-11-23T23:59:59.000Z

6

ITER  

SciTech Connect (OSTI)

This year six international partners have signed up to construct the first burning plasma experiment -- ITER -- in the South of France.It is over 50 years since the beginning of national programs to produce controlled fusion energy. The challenge of fusion energy has proven harder than was first anticipated. In this Colloquium Steve Cowley from UCLA will explain the scientific issues and how the difficulties have been overcome.

Cowley, Steve

2005-10-10T23:59:59.000Z

7

Templates for the Solution of Linear Systems: Building Blocks for Iterative Methods 1  

E-Print Network [OSTI]

Templates for the Solution of Linear Systems: Building Blocks for Iterative Methods 1 Richard of the Office of Energy Research, U.S. Department of Energy, under Contract DE­AC05­84OR21400, and the Stichting This book is also available in Postscript from over the Internet. To retrieve the postscript file you can

Mignotte, Max

8

Solution characters of iterative coupling between energy simulation and CFD programs  

E-Print Network [OSTI]

third of the primary energy consumption and two thirds of the electricity. Designing an energy/heating loads, coil loads, and energy consumption can be obtained on an hourly or sub-hourly basis for a period1 Solution characters of iterative coupling between energy simulation and CFD programs Zhiqiang

Chen, Qingyan "Yan"

9

Nested (inverse) binomial sums and new iterated integrals for massive Feynman diagrams  

E-Print Network [OSTI]

Nested sums containing binomial coefficients occur in the computation of massive operator matrix elements. Their associated iterated integrals lead to alphabets including radicals, for which we determined a suitable basis. We discuss algorithms for converting between sum and integral representations, mainly relying on the Mellin transform. To aid the conversion we worked out dedicated rewrite rules, based on which also some general patterns emerging in the process can be obtained.

Jakob Ablinger; Johannes Blmlein; Clemens G. Raab; Carsten Schneider

2014-07-17T23:59:59.000Z

10

Momentum space iterative solution of the time-dependent Schrdinger equation  

SciTech Connect (OSTI)

We present a novel approach, the iterative solution of the time-dependent Schrdinger equation (iTDSE model), for the investigation of atomic systems interacting with external laser fields. This model is the extension of the momentum-space strong-field approximation (MSSFA) [1], in which the Coulomb potential was considered only as a first order perturbation. In the iTDSE approach higher order terms were gradually introduced until convergence was achieved. Benchmark calculations were done on the hydrogen atom, and the obtained results were compared to the direct numerical solution [2].

Kiss, G. Zs.; Borbly, S.; Nagy, L. [Faculty of Physics, Babe?-Bolyai University, str. Kog?lniceanu nr. 1, 400084 Cluj (Romania)

2013-11-13T23:59:59.000Z

11

Integrating Variable Renewable Energy: Challenges and Solutions  

SciTech Connect (OSTI)

In the U.S., a number of utilities are adopting higher penetrations of renewables, driven in part by state policies. While power systems have been designed to handle the variable nature of loads, the additional supply-side variability and uncertainty can pose new challenges for utilities and system operators. However, a variety of operational and technical solutions exist to help integrate higher penetrations of wind and solar generation. This paper explores renewable energy integration challenges and mitigation strategies that have been implemented in the U.S. and internationally, including forecasting, demand response, flexible generation, larger balancing areas or balancing area cooperation, and operational practices such as fast scheduling and dispatch.

Bird, L.; Milligan, M.; Lew, D.

2013-09-01T23:59:59.000Z

12

Remote power -- Integrated, customer oriented solutions  

SciTech Connect (OSTI)

Throughout its history, BP Solar has focused strongly on the production of integrated power solutions to it`s customers, using photovoltaics as the central, but not unique, technology. This paper discusses the customer driven development of two new generation hybrid power systems, one AC the other DC. Both involve the combination of renewable energy with a conventional power source in a fully integrated system, as well as providing remote electronic system access, advanced data and event logging, and comprehensive computer graphic analysis software. The first is a DC system providing power to telecommunication authorities in the Asian-Pacific region, the second is generating abundant high quality AC power for Australian domestic users.

Jordan, D.; Twidell, M.; Patel, J.; Teofilo, F.; Soin, R. [BP Solar Australia, Brookvale, New South Wales (Australia)

1994-12-31T23:59:59.000Z

13

Iterative Krylov solution methods for geophysical electromagnetic simulations on throughput-oriented processing units  

E-Print Network [OSTI]

R. , 1992. Conjugate gradient type methods for linearand bi-conjugate gradient iterative methods to solve complexcase, the conjugate gradient (CG) method of Hestenes and

Commer, M.

2012-01-01T23:59:59.000Z

14

Iterative methods for the solution of very large complex symmetric linear systems of equations in electrodynamics  

SciTech Connect (OSTI)

In the field of computational electrodynamics the discretization of Maxwell`s equations using the Finite Integration Theory (FIT) yields very large, sparse, complex symmetric linear systems of equations. For this class of complex non-Hermitian systems a number of conjugate gradient-type algorithms is considered. The complex version of the biconjugate gradient (BiCG) method by Jacobs can be extended to a whole class of methods for complex-symmetric algorithms SCBiCG(T, n), which only require one matrix vector multiplication per iteration step. In this class the well-known conjugate orthogonal conjugate gradient (COCG) method for complex-symmetric systems corresponds to the case n = 0. The case n = 1 yields the BiCGCR method which corresponds to the conjugate residual algorithm for the real-valued case. These methods in combination with a minimal residual smoothing process are applied separately to practical 3D electro-quasistatical and eddy-current problems in electrodynamics. The practical performance of the SCBiCG methods is compared with other methods such as QMR and TFQMR.

Clemens, M.; Weiland, T. [Technische Hochschule Darmstadt (Germany)

1996-12-31T23:59:59.000Z

15

Iterative Modellerstellung mit Siemens IDATG Das Siemens IDATG (Integrating Design and Automated Testcase Generation) Tool erlaubt eine  

E-Print Network [OSTI]

Iterative Modellerstellung mit Siemens IDATG Das Siemens IDATG (Integrating Design:http://www.ist.tugraz.at/staff/peischl Dipl.Ing. Armin Beer Support Center Test Siemens PSE Gudrunstrasse 11 1100 Wien Tel.: +43 51707 43 342 mailto: armin.beer@siemens.com web: http://www.siemens.com #12;

16

Safety Science & Solutions Integrating Human Factors in Healthcare  

E-Print Network [OSTI]

Safety Science & Solutions Integrating Human Factors in Healthcare Tuesday 2nd December 2014 safety, quality and productivity in healthcare. Showcasing enduring solutions to patient safety recognised speakers in patient safety including: Martin Bromiley, Founder, Clinical Human Factors Group Dr

Levi, Ran

17

Approximate solutions of a time-fractional diffusion equation with a source term using the variational iteration method  

E-Print Network [OSTI]

We consider a time fractional differential equation of order $\\alpha$, $0 0, t > 0, \\quad c(x,0)=f(x). $$ where ${}^C_0\\mathcal{D}_t^{\\alpha}$ is the Caputo fractional derivative of order $\\alpha$, $A$ is a linear differential operator, $q(x,t)$ is a source term, and $f(x)$ is the inital condition. Approximate (truncated) series solutions are obtained by means of the Variational Iteration Method (VIM). We find the series solutions for different cases of the source term, in a form that is readily implementable on the computer where symbolic computation platform is available. The error in truncated solution $c_n$ diminishes exponentially fast for a given $\\alpha$ as the number of terms in the series increases. VIM has several advantages over other methods that produce solutions in the series form. The truncated VIM solutions often converge rapidly requiring only a few terms for fast and accurate approximations.

Iftikhar Ali; Bilal Chanane; Nadeem A. Malik

2014-07-31T23:59:59.000Z

18

The IBM Health Integration Framework: Accelerating solutions for smarter healthcare  

E-Print Network [OSTI]

in improving health- care access, cost, quality of care and patient satisfaction. But progress can take many Integration Framework is a unified software platform for implementing comprehensive solutions for health- careThe IBM Health Integration Framework: Accelerating solutions for smarter healthcare Healthcare

19

Development and Integration Issues and Solutions  

E-Print Network [OSTI]

to RES integration: Transmission: 400 and 220 kV substations and lines. 400/220 kV transformers. All Load demand: Special events Demonstration against terrorist attack of 11th March: 15' #12;11 World Cup

20

Modified Chebyshev-Picard Iteration Methods for Solution of Initial Value and Boundary Value Problems  

E-Print Network [OSTI]

of y (final value problem) . . . . . . . . . . . . . . 68 32 Integration errors of y? (final value problem) . . . . . . . . . . . . . . 69 33 Integration errors of y (y(-1) and y(1)) are known) . . . . . . . . . . 72 34 Integration errors of y? (y(-1...) and y(1) are known) . . . . . . . . . . . 72 35 Integration errors of y (y?(?1) and y?(1) are known) . . . . . . . . . . 73 36 Integration errors of y? (y?(?1) and y?(1) are known) . . . . . . . . . . 74 37 Integration errors of y (y(-1) and yd(1...

Bai, Xiaoli

2011-10-21T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

CIB White Paper on IDDS Integrated Design & Delivery Solutions  

E-Print Network [OSTI]

CIB White Paper on IDDS Integrated Design & Delivery Solutions Publication 328 ISBN 978-90-6363-060-7 #12;CIB White Paper on IDDS Page 1 of 15 CIB White Paper on IDDS Integrated Design & Delivery White Paper on IDDS Page 2 of 15 Table of Contents Introduction and Use of this White Paper

Amor, Robert

22

Integrating Variable Renewable Energy: Challenges and Solutions  

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 ProposedUsingFunInfrared Land SurfaceVirus-Infected Macaques throughBiomassIntegrating

23

Integrating Mobile Agent Technology into an e-Marketplace Solution  

E-Print Network [OSTI]

Integrating Mobile Agent Technology into an e-Marketplace Solution - The InterMarket Marketplace. The mobile agent technology might take e-commerce trading to the next phase. Mobile agents are intelligent technology. A feasibility study, made for two existing software applications, the mobile-agent system Tracy

24

Implementation of an iterative technique for a solution of the Thomas-Fermi equation  

E-Print Network [OSTI]

to Nonlinear Differential and Integral Equations, Dover, New York, 1962. 6. E. Fermi, Un metodo statistico par la determinazione de alcume proprieta dell' atome, Rend. Accad. Naz. del Lincei. cl. sci, fis. , mat. e nat. , 6 (1927), 602-607. 7. F...

Flagg, Raymond Calvert

1978-01-01T23:59:59.000Z

25

Total integrals of global solutions to Painleve II  

E-Print Network [OSTI]

We evaluate the total integral from negative infinity to positive infinity of all global solutions to the Painleve II equation on the real line. The method is based on the interplay between one of the equations of the associated Lax pair and the corresponding Riemann-Hilbert problem. In addition, we evaluate the total integral of a function related to a special solution to the Painleve V equation. As a corollary, we obtain short proofs of the computation of the constant terms of the limiting gap probabilities in the edge and the bulk of the Gaussian Orthogonal and Gaussian Symplectic Ensembles that were obtained recently in [4] and [18]. We also evaluate the total integrals of certain polynomials of the Painleve functions and their derivatives. These polynomials are the densities of the first integrals of the modified Korteweg-de Vries equation. We discuss the relations of the formulae we have obtained to the classical trace formulae for the Dirac operator on the line.

Jinho Baik; Robert Buckingham; Jeffery DiFranco; Alexander Its

2008-10-15T23:59:59.000Z

26

A Programmable MicroFluidic Processor: Integrated and Hybrid Solutions  

SciTech Connect (OSTI)

The Programmable Fluidic Processor (PFP), a device conceived of by researchers at MD Anderson Cancer Center, is a reconfigurable and programmable bio-chemical analysis system designed for handheld operation in a variety of applications. Unlike most microfluidic systems which utilize channels to control fluids, the PFP device is a droplet-based system. The device is based on dielectrophoresis; a fluid transport phenomenon that utilizes mismatched polarizability between a droplet and its medium to induce droplet mobility. In the device, sample carrying droplets are polarized by an array of electrodes, individually addressable by subsurface microelectronics. My research focused on the development of a polymer-based microfluidic injection system for injecting these droplets onto the electrode array. The first of two device generations fabricated at LLNL was designed using extensive research and modeling performed by MD Anderson and Coventor. Fabricating the first generation required several iterations and design changes in order to generate an acceptable device for testing. Difficulties in planar fabrication of the fluidic system and a narrow channel design necessitated these changes. The second generation device incorporated modifications of the previous generation and improved on deficiencies discovered during experimentation with the initial device. Extensive modeling of the injection channels and fluid storage chamber also aided in redesigning the device's microfluidic system. A micromolding technique with interlocking features enabled precise alignments and dimensional control, critical requirements for device optimization. Fabrication of a final device will be fully integrated with the polymer-based microfluidics bonded directly to the silicon-based microelectronics. The optimized design and process flow developed in the trial generations will readily transfer to this approach.

Rose, K A

2002-05-10T23:59:59.000Z

27

DCLL TBM Safety Assessment A key objective for ITER includes integrated testing of blanket concepts suitable for demonstrating fusion  

E-Print Network [OSTI]

prototypical blanket modules into designated ports. Because ITER will be a licensed nuclear facility, occupation radiation exposure (ORE) analyzed, and decommissioning and waste disposal analysis performed

28

Local and global solutions of well-posed integrated Cauchy problems  

E-Print Network [OSTI]

Local and global solutions of well-posed integrated Cauchy problems Pedro J. Miana Departamento de, Spain Abstract In this paper we study the local well-posed integrated Cauchy problem, v (t) = Av large way. 2 #12;2 Extending solutions of well-posed local integrated Cauchy prob- lems Let X

Miana, Pedro J.

29

A domain decomposition method of stochastic PDEs: An iterative solution techniques using a two-level scalable preconditioner  

SciTech Connect (OSTI)

Recent advances in high performance computing systems and sensing technologies motivate computational simulations with extremely high resolution models with capabilities to quantify uncertainties for credible numerical predictions. A two-level domain decomposition method is reported in this investigation to devise a linear solver for the large-scale system in the Galerkin spectral stochastic finite element method (SSFEM). In particular, a two-level scalable preconditioner is introduced in order to iteratively solve the large-scale linear system in the intrusive SSFEM using an iterative substructuring based domain decomposition solver. The implementation of the algorithm involves solving a local problem on each subdomain that constructs the local part of the preconditioner and a coarse problem that propagates information globally among the subdomains. The numerical and parallel scalabilities of the two-level preconditioner are contrasted with the previously developed one-level preconditioner for two-dimensional flow through porous media and elasticity problems with spatially varying non-Gaussian material properties. A distributed implementation of the parallel algorithm is carried out using MPI and PETSc parallel libraries. The scalabilities of the algorithm are investigated in a Linux cluster.

Subber, Waad, E-mail: wsubber@connect.carleton.ca; Sarkar, Abhijit, E-mail: abhijit_sarkar@carleton.ca

2014-01-15T23:59:59.000Z

30

Use of the iterative solution method for coupled finite element and boundary element modeling; Yucca Mountain Site Characterization Project  

SciTech Connect (OSTI)

Tunnels buried deep within the earth constitute an important class geomechanics problems. Two numerical techniques used for the analysis of geomechanics problems, the finite element method and the boundary element method, have complementary characteristics for applications to problems of this type. The usefulness of combining these two methods for use as a geomechanics analysis tool has been recognized for some time, and a number of coupling techniques have been proposed. However, not all of them lend themselves to efficient computational implementations for large-scale problems. This report examines a coupling technique that can form the basis for an efficient analysis tool for large scale geomechanics problems through the use of an iterative equation solver.

Koteras, J.R.

1993-07-01T23:59:59.000Z

31

A Holistic Solution for Duplicate Entity Identification in Deep Web Data Integration  

E-Print Network [OSTI]

A Holistic Solution for Duplicate Entity Identification in Deep Web Data Integration Wei Liu 1 in deep Web data integration, the goal of duplicate entity identification is to discover the duplicate to deep Web data integration systems. That is, one duplicate entity matcher trained over two specific Web

32

Numerical solutions to integral equations of the Fredholm type  

E-Print Network [OSTI]

of the principal founders of the theory of integral equations are Vito Volterra (1860-1940), Ivar Fredholm (1866-1927), David Hilbert (1862-1943), and Erhard Schmidt (b. 1876). It was Volterra who recognised the importance of the theory, but Fredholm...

Pullin, John Henry

1966-01-01T23:59:59.000Z

33

Policy Iteration / Optimistic Policy Iteration Least-Squares Policy Iteration Experiments Least Squares Policy Iteration  

E-Print Network [OSTI]

Policy Iteration / Optimistic Policy Iteration Least-Squares Policy Iteration Experiments Least Squares Policy Iteration Bias-Variance Trade-o in Control Problems Christophe Thiéry and Bruno Scherrer/27 #12; Policy Iteration / Optimistic Policy Iteration Least-Squares Policy Iteration Experiments Markov

Scherrer, Bruno

34

Iterative solutions of simultaneous equations  

E-Print Network [OSTI]

functions. (See Ayyendixf pages 29 $6 and 42, for results. ) Also, the sufficient condition for convergence is not satisfied. . Xf the f functions are defined by the method prescribed. on page 14, then 1 2 P = -2 -8 -20 27. g 20 &n' 0. 20128 -0. 0$1...$$ -0. 01661 0. 00&6$ -0. 0/128 9. 00967 9. 1/626 9 ~ 9'$$$6 0. 02008 0, 29128 fl ? 0. 0$1$$ f2 ? 0. 01661 0, 09/6/ fl ? 0, 0/128 f2 + 0. 90967 fy Q ~ 1/626 fl + 0. 09/$6 f2 + 0. 02908 f~ The Jacobi and. Gauss-Seidel methods convexged...

Laycock, Guyron Brantley

2012-06-07T23:59:59.000Z

35

Levy path integral approach to the solution of the fractional Schrdinger equation with infinite square well  

E-Print Network [OSTI]

The solution to the fractional Schr\\"odinger equation with infinite square well is obtained in this paper, by use of the L\\'evy path integral approach. We obtain the even and odd parity wave functions of this problem, which are in accordance with those given by Laskin in [Chaos 10 (2000), 780--790].

Dong Jianping

2013-01-14T23:59:59.000Z

36

Two worlds, one smart card An integrated solution for physical access and logical security  

E-Print Network [OSTI]

issued, controlling access to over 1500 buildings, fitted with in total more than 6000 smart card readers to office buildings and plants, companies these days issue their employees a (smart) card that is bothTwo worlds, one smart card An integrated solution for physical access and logical security using

Hoepman, Jaap-Henk

37

Two worlds, one smart card # An integrated solution for physical access and logical security  

E-Print Network [OSTI]

issued, controlling access to over 1500 buildings, fitted with in total more than 6000 smart card readers#ce buildings and plants, companies these days issue their employees a (smart) card that is both an identityTwo worlds, one smart card # An integrated solution for physical access and logical security using

Hoepman, Jaap-Henk

38

Iterative Least-Squares Solution of the Combined-Field Integral Equation zgr Ergl and Levent Grel*  

E-Print Network [OSTI]

Gürel* Department of Electrical and Electronics Engineering Bilkent University, TR-06800, Bilkent was supported by the Turkish Academy of Sciences in the framework of the Young Scientist Award Program (LG

Gürel, Levent

39

Efficient solution of multiple cracks in great number using eigen COD boundary integral equations with iteration procedure  

E-Print Network [OSTI]

as the fibre-reinforced brittle materials after certain extent of tensile damage. The prediction of crack in an infinite domain under fictitious traction acting on the crack surface. With the concept of eigen COD

Liu, Yijun

40

ITER Project  

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-SeriesFlickr FlickrGuidedCH2MLLCBasicsScience at ALCFPhysicsQuality AssuranceITER

Note: This page contains sample records for the topic "integrated iterative solution" 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

To learn more about AT&T Network Integration Solutions, visit www.att.com/network-integration or have us contact you.  

E-Print Network [OSTI]

/ ITP Transformation services Help desk / User support Transformation support Multi-carrier solutions designed to help customers connect and integrate best-of-breed service offerings and capabilities and manage the process of service and capabilities integration. With the benefit of a well-established Iaa

Fisher, Kathleen

42

An Integrated Water Treatment Technology Solution for Sustainable Water Resource Management in the Marcellus Shale  

SciTech Connect (OSTI)

This Final Scientific/ Technical Report submitted with respect to Project DE-FE0000833 titled 'An Integrated Water Treatment Technology Solution for Sustainable Water Resource Management in the Marcellus Shale' in support of final reporting requirements. This final report contains a compilation of previous reports with the most current data in order to produce one final complete document. The goal of this research was to provide an integrated approach aimed at addressing the increasing water resource challenges between natural gas production and other water stakeholders in shale gas basins. The objective was to demonstrate that the AltelaRain{reg_sign} technology could be successfully deployed in the Marcellus Shale Basin to treat frac flow-back water. That objective has been successfully met.

Matthew Bruff; Ned Godshall; Karen Evans

2011-04-30T23:59:59.000Z

43

Integrated PEV Charging Solutions and Reduced Energy for Occupant Comfort (Brochure)  

SciTech Connect (OSTI)

Brochure on Vehicle Testing and Integration Facility, featuring the Vehicle Modification Facility, Vehicle Test Pad and ReCharge Integrated Demonstration System. Plug-in electric vehicles (PEVs) offer the opportunity to shift transportation energy demands from petroleum to electricity, but broad adoption will require integration with other systems. While automotive experts work to reduce the cost of PEVs, fossil fueled cars and trucks continue to burn hundreds of billions of gallons of petroleum each year - not only to get from point A to point B, but also to keep passengers comfortable with air conditioning and heat. At the National Renewable Energy Laboratory (NREL), three installations form a research laboratory known as the Vehicle Testing and Integration Facility (VTIF). At the VTIF, engineers are developing strategies to address two separate but equally crucial areas of research: meeting the demands of electric vehicle-grid integration and minimizing fuel consumption related to vehicle climate control. Part of NREL's Center for Transportation Technologies and Systems (CTTS), the VTIF is dedicated to renewable and energy efficient solutions. This facility showcases technology and systems designed to increase the viability of sustainably powered vehicles. NREL researchers instrument every class of on-road vehicle, conduct hardware and software validation for electric vehicle (EV) components and accessories, and develop analysis tools and technology for the Department of Energy, other government agencies and industry partners. Research conducted at the VTIF examines the interaction of building energy systems, utility grids, renewable energy sources and PEVs, integrating energy management solutions, and maximizing potential greenhouse gas (GHG) reduction, while smoothing the transition and reducing costs for EV owners. NREL's collaboration with automakers, charging station manufacturers, utilities and fleet operators to assess technologies using VTIF resources is designed to enable PEV communication with the smart grid and create opportunities for vehicles to play an active role in building and grid management. Ultimately, this creates value for the vehicle owner and will help renewables be deployed faster and more economically, making the U.S. transportation sector more flexible and sustainable.

Not Available

2012-01-01T23:59:59.000Z

44

US ITER Moving Forward  

ScienceCinema (OSTI)

US ITER Project Manager Ned Sauthoff, joined by Wayne Reiersen, Team Leader Magnet Systems, and Jan Berry, Team Leader Tokamak Cooling System, discuss the U.S.'s role in the ITER international collaboration.

US ITER / ORNL

2012-03-16T23:59:59.000Z

45

Innovation is Key from ITER to DEMO M. Porkolab, L. Bromberg, M. Greenwald, A. Hubbard,  

E-Print Network [OSTI]

PMI in tokamak SS current drive & heating Divertor solution compatible with core Porkolab_FPA_2013 #12;For PMI, the step from ITER to DEMO will be enormous. ITER ARIES- ACT1 ARIES- ACT2 R(m) 6.2 6.25 9/R than ITER Factor of 105 increase in pulse length Innovative solutions to critical PMI challenges

46

Nested off-diagonal Bethe ansatz and exact solutions of the su(n) spin chain with generic integrable boundaries  

E-Print Network [OSTI]

The nested off-diagonal Bethe ansatz method is proposed to diagonalize multi-component integrable models with generic integrable boundaries. As an example, the exact solutions of the su(n)-invariant spin chain model with both periodic and non-diagonal boundaries are derived by constructing the nested T-Q relations based on the operator product identities among the fused transfer matrices and the asymptotic behavior of the transfer matrices.

Junpeng Cao; Wen-Li Yang; Kangjie Shi; Yupeng Wang

2014-05-11T23:59:59.000Z

47

Iterated maps for clarinet-like systems  

E-Print Network [OSTI]

The dynamical equations of clarinet-like systems are known to be reducible to a non-linear iterated map within reasonable approximations. This leads to time oscillations that are represented by square signals, analogous to the Raman regime for string instruments. In this article, we study in more detail the properties of the corresponding non-linear iterations, with emphasis on the geometrical constructions that can be used to classify the various solutions (for instance with or without reed beating) as well as on the periodicity windows that occur within the chaotic region. In particular, we find a regime where period tripling occurs and examine the conditions for intermittency. We also show that, while the direct observation of the iteration function does not reveal much on the oscillation regime of the instrument, the graph of the high order iterates directly gives visible information on the oscillation regime (characterization of the number of period doubligs, chaotic behaviour, etc.).

Pierre-Andr Taillard; Jean Kergomard; Franck Lalo

2010-05-31T23:59:59.000Z

48

Path-integral solution for a two-dimensional model with axial-vector-current--pseudoscalar derivative interaction  

SciTech Connect (OSTI)

We study a two-dimensional quantum field model with axial-vector-current--pseudoscalar derivative interaction using path-integral methods. We construct an effective Lagrangian by performing a chiral change in the fermionic variables leading to an exact solution of the model.

Botelho, L.C.L.

1985-03-15T23:59:59.000Z

49

ITER convertible blanket evaluation  

SciTech Connect (OSTI)

Proposed International Thermonuclear Experimental Reactor (ITER) convertible blankets were reviewed. Key design difficulties were identified. A new particle filter concept is introduced and key performance parameters estimated. Results show that this particle filter concept can satisfy all of the convertible blanket design requirements except the generic issue of Be blanket lifetime. If the convertible blanket is an acceptable approach for ITER operation, this particle filter option should be a strong candidate.

Wong, C.P.C.; Cheng, E.

1995-09-01T23:59:59.000Z

50

Sensitivity and uncertainty analyses applied to one-dimensional radionuclide transport in a layered fractured rock: MULTFRAC --Analytic solutions and local sensitivities; Phase 2, Iterative performance assessment: Volume 1  

SciTech Connect (OSTI)

Exact analytical solutions based on the Laplace transforms are derived for describing the one-dimensional space-time-dependent, advective transport of a decaying species in a layered, saturated rock system intersected by a planar fracture of varying aperture. These solutions, which account for advection in fracture, molecular diffusion into the rock matrix, adsorption in both fracture and matrix, and radioactive decay, predict the concentrations in both fracture and rock matrix and the cumulative mass in the fracture. The solute migration domain in both fracture and rock is assumed to be semi-infinite with non-zero initial conditions. The concentration of each nuclide at the source is allowed to decay either continuously or according to some periodical fluctuations where both are subjected to either a step or band release mode. Two numerical examples related to the transport of Np-237 and Cm-245 in a five-layered system of fractured rock were used to verify these solutions with several well established evaluation methods of Laplace inversion integrals in the real and complex domain. In addition, with respect to the model parameters, a comparison of the analytically derived local sensitivities for the concentration and cumulative mass of Np-237 in the fracture with the ones obtained through a finite-difference method of approximation is also reported.

Gureghian, A.B.; Wu, Y.T.; Sagar, B. [Southwest Research Inst., San Antonio, TX (United States). Center for Nuclear Waste Regulatory Analyses; Codell, R.A. [Nuclear Regulatory Commission, Washington, DC (United States)

1992-12-01T23:59:59.000Z

51

Plans for US Contributions to ITER U.S. ITER Plans for US Contributions to ITER  

E-Print Network [OSTI]

windings 75% cooling for divertor, vacuum vessel, ... 20% blanket/shield pellet injector tokamak exhaust supplies #12;Plans for US Contributions to ITER U.S. ITER Plans for US Contributions to ITER December 4 Exploring: - Seam-less tube conduit - Perforated central cooling tube #12;Plans for US Contributions to ITER

52

The Status of ITER; the ITER Design Review -G. Janeschitz -November 2007 Town Hall Meeting onTown Hall Meeting on ITERITER APS ConferenceAPS Conference  

E-Print Network [OSTI]

Temporary ITER Offices Building 519: occupied by ~ 150 (designed for 140 ­ 150) Extension Bureau: completed !Planning / Design !Integration / QA / Safety / Licensing / Schedule !Installation !Testing + Commissioning Design Review - G. Janeschitz - November 2007 7 Integrated Project Schedule (IPS) Basis - official10

53

Integrated environmental degradation model for Fe-Ni-Cr alloys in irradiated aqueous solutions  

E-Print Network [OSTI]

An integrated model has been developed to evaluate the effect of reactor flux, fluence, and other operating conditions on crack growth rates in austenitic stainless steels in boiling water reactor (BWR) environments. The ...

Pleune, Thomas Todd, 1974-

1999-01-01T23:59:59.000Z

54

US ITER | Media Corner  

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

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55

US ITER | Media Corner  

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

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56

US ITER | Media Corner  

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

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57

US ITER | Media Corner  

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

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58

US ITER | Media Corner  

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59

US ITER | Media Corner  

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60

US ITER | Media Corner  

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61

US ITER | Media Corner  

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

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62

Co-simulation for performance prediction of integrated building and HVAC systems -An analysis of solution  

E-Print Network [OSTI]

Co-simulation for performance prediction of integrated building and HVAC systems - An analysis performance simulation of buildings and heating, ventilation and air- conditioning (HVAC) systems can help, heating, ventilation and air-conditioning (HVAC) systems are responsible for 10%-60% of the total building

63

Integrated Chemical Complex and Cogeneration Analysis System: Energy Conservation and Greenhouse Gas Management Solutions  

E-Print Network [OSTI]

19f Integrated Chemical Complex and Cogeneration Analysis System: Energy Conservation and Cogeneration Analysis System is an advanced technology for energy conservation and pollution prevention, Beaumont, TX 77710, hopperjr@hal.lamar.edu, yawscl@hal.lamar.edu Key words; Energy Conservation, Greenhouse

Pike, Ralph W.

64

ITER Fusion Energy  

ScienceCinema (OSTI)

ITER (in Latin ?the way?) is designed to demonstrate the scientific and technological feasibility of fusion energy. Fusion is the process by which two light atomic nuclei combine to form a heavier over one and thus release energy. In the fusion process two isotopes of hydrogen ? deuterium and tritium ? fuse together to form a helium atom and a neutron. Thus fusion could provide large scale energy production without greenhouse effects; essentially limitless fuel would be available all over the world. The principal goals of ITER are to generate 500 megawatts of fusion power for periods of 300 to 500 seconds with a fusion power multiplication factor, Q, of at least 10. Q ? 10 (input power 50 MW / output power 500 MW). The ITER Organization was officially established in Cadarache, France, on 24 October 2007. The seven members engaged in the project ? China, the European Union, India, Japan, Korea, Russia and the United States ? represent more than half the world?s population. The costs for ITER are shared by the seven members. The cost for the construction will be approximately 5.5 billion Euros, a similar amount is foreseen for the twenty-year phase of operation and the subsequent decommissioning.

Dr. Norbert Holtkamp

2010-01-08T23:59:59.000Z

65

ITER Physics and Exploring Magnetically-Confined  

E-Print Network [OSTI]

the Scientific and Technological Feasibility of Fusion Energy for Peaceful Purposes #12;Special ITER Features???Flow/rotation Port-based coils?RWM Stab. x~1.9, 95%~1.7 x~0.5, 95%~0.33 Shaping J(0)Jefficient (r>a/2)J (R)J(0) ­ pedestal characteristics ­ core-edge integration ­ ITB-access at low- * with weak rotation · Demands

66

ITER breeding blanket design  

SciTech Connect (OSTI)

A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine design of the Basic Performance Phase. Lithium zirconate and lithium oxide am the selected ceramic breeders based on the current data base. Enriched lithium and beryllium neutron multiplier are used for both breeders. Both forms of beryllium material, blocks and pebbles are used at different blanket locations based on thermo-mechanical considerations and beryllium thickness requirements. Type 316LN austenitic steel is used as structural material similar to the shielding blanket. Design issues and required R&D data are identified during the development of the design.

Gohar, Y.; Cardella, A.; Ioki, K.; Lousteau, D.; Mohri, K.; Raffray, R.; Zolti, E. [ITER Joint Central Team, Garching (Germany)] [and others

1995-12-31T23:59:59.000Z

67

Variational Iteration Method for Image Restoration  

E-Print Network [OSTI]

The famous Perona-Malik (P-M) equation which was at first introduced for image restoration has been solved via various numerical methods. In this paper we will solve it for the first time via applying a new numerical method called the Variational Iteration Method (VIM) and the correspondent approximated solutions will be obtained for the P-M equation with regards to relevant error analysis. Through implementation of our algorithm we will access some effective results which are deserved to be considered as worthy as the other solutions issued by the other methods.

Yahya, Keyvan; Azari, Hossein; Fard, Pouyan Rafiei

2010-01-01T23:59:59.000Z

68

US ITER | Media Corner  

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69

US ITER | Media Corner  

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70

US ITER | Media Corner  

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 JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central

71

US ITER | Media Corner  

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

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72

The Fourier integral and its use in the solution of certain boundary value problems  

E-Print Network [OSTI]

) cos u(x-t) dt 0 J' dt f f (t) cos u(x-t) du, . a Proof: j f(t) cos u(x-t) dt exists s1nce If (t) ccs u(x-t) [ & if (t) i. i'v ow J f ('t) cos u(x ? 't) dt [f +/ tf tf + )fltl t t) dt- I 7- 'I&is ssr1es converges uniformly with respect to u (o.... Then for a sufficiently large positive v, P (t) 1s L-integrable. turthermore, if x is a number such that f(t) is of bounced var1ation in some segment 16 (x ? J; x+f), ti, en C f(x+o) f f(xm) ] = ~ l1m f ~& es ds f f(t)e dt. Ef s is a number suci. that f...

McNutt, Wayne Eugene

1952-01-01T23:59:59.000Z

73

ITER blanket designs  

SciTech Connect (OSTI)

The ITER first wall, blanket, and shield system is being designed to handle 1.5{plus_minus}0.3 GW of fusion power and 3 MWa/m{sup 2} average neutron fluence. The reference shielding blanket (non breeding) uses austenitic steel structural material and water coolant with a copper first wall coated with beryllium. The first wall is protected by beryllium bumper limiters. The choice of copper first wall is dictated by the surface heat flux values anticipated during ITER operation. The water coolant is used at low pressure and low temperature. Liquid lithium is used as tritium breeder and coolant to alleviate issues of coolant breeder compatibility and reactivity. A layer of beryllium is incorporated in the blanket to improve the shielding performance and to insure tritium self-sufficiency. In addition, a shielding zone is incorporated at the back of the blanket to allow rewelding the vacuum vessel material during the ITER lifetime. The lithium coolant velocity required to remove the nuclear heating and the surface heat flux is 2 m/s, which produces a pressure drop of 0.6 MPa. Vanadium alloy (V-5Cr-5Ti) is being considered as the structural material because it can accommodate high heat loads and has good mechanical properties at high temperatures, high neutron fluence capability, low degradation under irradiation, good compatibility with liquid lithium, low decay heat, low waste disposal rating, and adequate strength to accommodate the electromagnetic loads during plasma disruption events.

Gohar, J.; Parker, R.; Rebut, P.H. [ITER Garching Joint Work Site, Garching bei Munchen (Germany)

1994-12-31T23:59:59.000Z

74

Information Technology Systems for Fusion Industry and ITER Project  

SciTech Connect (OSTI)

The industrial developments in the fusion industry will have to overcome numerous technical challenges and will have a strong need for modern information technology (IT) systems.The fusion industry has manifested itself with an unprecedented international collaboration, the International Thermonuclear Experimental Reactor (ITER). Data accumulated in ITER will be the major output of the project and will create the knowledge base for a future fusion power plant. A modern and effective information infrastructure will be critical to the success of the ITER project.To accumulate and maintain the knowledge base at all stages of the project, we propose to build an integrated information system for ITER: ITER Information Plant (IIP). IIP will minimize lost experiment time and accelerate the understanding, interpretation, and planning of fusion experiments. IIP will allow to reap maximum benefits from the project's scientific and technological achievements, make the ITER results accessible to hundreds of researchers worldwide. This will facilitate collaboration, dramatically increasing the pace of scientific and technological discovery and the rate at which practical use is made of these discoveries.As the first of its kind, the ITER Information Plant could be used in the future as a prototype IT system for national and international fusion projects, in which multicountry collaboration, distributed work sites and operations are catalysts for success.

Putvinskaya, N.; Bulasheva, N.; Cole, G.; Dillon, T.; Frieman, E.; Sabado, M.; Schissel, D. (and others)

2005-04-15T23:59:59.000Z

75

U.S. Plans and Strategy for ITER Blanket Testing  

SciTech Connect (OSTI)

Testing blanket concepts in the integrated fusion environment is one of the principal objectives of ITER. Blanket test modules will be inserted in ITER from Day 1 of its operation and will provide the first experimental data on the feasibility of the D-T cycle for fusion. With the US rejoining ITER, the US community has decided to have strong participation in the ITER Test Blanket Module (TBM) Program. A US strategy for ITER-TBM has evolved that emphasizes international collaboration. A study was initiated to select the two blanket options for the US ITER-TBM in light of new R and D results from the US and world programs over the past decade. The study is led by the Plasma Chamber community in partnership with the Materials, PFC, Safety, and physics communities. The study focuses on assessment of the critical feasibility issues for candidate blanket concepts and it is strongly coupled to R and D of modeling and experiments. Examples of issues are MHD insulators, SiC insert viability and compatibility with PbLi, tritium permeation, MHD effects on heat transfer, solid breeder 'temperature window' and thermomechanics, and chemistry control of molten salts. A dual coolant liquid breeder and a helium-cooled solid breeder blanket concept have been selected for the US ITER-TBM.

Abdou, M. [UCLA Fusion Engineering Sciences (United States); Sze, D. [UCSD Advanced Energy Technology Group (United States); Wong, C. [General Atomics (United States); Sawan, M. [University of Wisconsin Fusion Technology Institute, Madison (United States); Ying, A. [UCLA Fusion Engineering Sciences (United States); Morley, N.B. [UCLA Fusion Engineering Sciences (United States); Malang, S

2005-04-15T23:59:59.000Z

76

Design Analysis and Manufacturing Studies for ITER In-Vessel Coils  

SciTech Connect (OSTI)

ITER is incorporating two types of In Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Modes and VS Coils to provide Vertical Stabilization of the plasma. Strong coupling with the plasma is required so that the ELM and VS Coils can meet their performance requirements. Accordingly, the IVCs are in close proximity to the plasma, mounted just behind the Blanket Shield Modules. This location results in a radiation and temperature environment that is severe necessitating new solutions for material selection as well as challenging analysis and design solutions. Fitting the coil systems in between the blanket shield modules and the vacuum vessel leads to difficult integration with diagnostic cabling and cooling water manifolds.

Kalish, M.; Heitzenroeder, P.; Neumeyer, C.; Titus, P.; Zhai, Y.; Zatz, I.; Messineo, M.; Gomez, M.; Hause, C. [Princeton Plasma Physics Lab., Princeton, NJ (United States); Daly, E.; Martin, A. [ITER Organization, St. Paul-lez-Duranace (France); Wu, Y.; Jin, J.; Long, F.; Song, Y.; Wang, Z.; Yun, Zan [Chinese Academy of Sciences, Anhui (China). Institute of Plasma Physics; Hsiao, J. [Vector Resources, Annandale, VA (United States); Pillsbury, J. R. [Sherbrooke Consulting, Arlington, VA (United States); Bohm, T.; Sawan, M. [Univ. of Wisconsin-Madison, WI (United States). Fustion Technology Institute; Jiang, NFN [Southwestern Institute of Physics, Chengdu (China)

2014-07-01T23:59:59.000Z

77

Combined Field Integral Equation Based Theory of Characteristic Mode  

E-Print Network [OSTI]

Conventional electric field integral equation based theory is susceptible to the spurious internal resonance problem when the characteristic modes of closed perfectly conducting objects are computed iteratively. In this paper, we present a combined field integral equation based theory to remove the difficulty of internal resonances in characteristic mode analysis. The electric and magnetic field integral operators are shown to share a common set of non-trivial characteristic pairs (values and modes), leading to a generalized eigenvalue problem which is immune to the internal resonance corruption. Numerical results are presented to validate the proposed formulation. This work may offer efficient solutions to characteristic mode analysis which involves electrically large closed surfaces.

Qi I. Dai; Qin S. Liu; Hui Gan; Weng Cho Chew

2015-03-04T23:59:59.000Z

78

US ITER | About  

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79

US ITER | Media Corner  

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

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80

US ITER | Media Corner  

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Note: This page contains sample records for the topic "integrated iterative solution" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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81

US ITER | Media Corner  

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

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82

US ITER | Media Corner  

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

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83

US ITER | Media Corner  

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 JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's

84

US ITER | Media Corner  

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

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85

US ITER | Media Corner  

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

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86

US ITER | Media Corner  

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

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87

US ITER | Media Corner  

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88

What is ITER  

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89

US ITER | About  

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 Layeredof2014 EIA Energy Conference U.S. Crude OilITER Movingprime

90

US ITER | About  

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

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91

US ITER | About  

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 Layeredof2014 EIA Energy Conference U.S. CrudeElectronPelletIonITER

92

US ITER | Media Corner  

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

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93

US ITER | Media Corner  

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 Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER MajorIn

94

US ITER | Media Corner  

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 Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER MajorIntest

95

US ITER | Media Corner  

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 Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER

96

Department of Energy ITER Project  

E-Print Network [OSTI]

of operation to meet demand, and manageable waste. Currently, the ITER project is at the stage where the final responsible for procurements of in-kind hardware in its own territory with its own currency, a direct) for the base estimate consisting of about $4 billion for ITER hardware, initial spares, buildings

97

ECRH System For ITER  

SciTech Connect (OSTI)

A 26 MW Electron Cyclotron Heating and Current Drive (EC H and CD) system is to be installed for ITER. The main objectives are to provide, start-up assist, central H and CD and control of MHD activity. These are achieved by a combination of two types of launchers, one located in an equatorial port and the second type in four upper ports. The physics applications are partitioned between the two launchers, based on the deposition location and driven current profiles. The equatorial launcher (EL) will access from the plasma axis to mid radius with a relatively broad profile useful for central heating and current drive applications, while the upper launchers (ULs) will access roughly the outer half of the plasma radius with a very narrow peaked profile for the control of the Neoclassical Tearing Modes (NTM) and sawtooth oscillations. The EC power can be switched between launchers on a time scale as needed by the immediate physics requirements. A revision of all injection angles of all launchers is under consideration for increased EC physics capabilities while relaxing the engineering constraints of both the EL and ULs. A series of design reviews are being planned with the five parties (EU, IN, JA, RF, US) procuring the EC system, the EC community and ITER Organization (IO). The review meetings qualify the design and provide an environment for enhancing performances while reducing costs, simplifying interfaces, predicting technology upgrades and commercial availability. In parallel, the test programs for critical components are being supported by IO and performed by the Domestic Agencies (DAs) for minimizing risks. The wide participation of the DAs provides a broad representation from the EC community, with the aim of collecting all expertise in guiding the EC system optimization. Still a strong relationship between IO and the DA is essential for optimizing the design of the EC system and for the installation and commissioning of all ex-vessel components when several teams from several DAs will be involved together in the tests on the ITER site.

Darbos, C.; Henderson, M.; Gandini, F. [JTER Organization, 13067 Saint Paul-Lez-Durance cedex (France); Albajar, F.; Bomcelli, T.; Heidinger, R.; Saibene, G. [Fusion for Energy, C/Josep Pla 2, Torres Diagonal Litoral-B3, E-08019 Barcelona-Spain (Spain); Bigelow, T.; Rasmussen, D. [US ITER Project Office, Oak Ridge National Laboratory, 055 Commerce Park, PO Box 2008, Oak Ridge, TN 37831-6483 (United States); Chavan, R.; Goodman, T.; Hogge, J. P.; Sauter, O. [Association EURATOM-Confederation Suisse, EPFL Ecublens, CH-1015 Lausanne (Switzerland); Denisov, G. [Institute of Applied Physics Russian Academy of Sciences, 46 Ulyanov Street, Nizhny Novgorod, 603950 (Russian Federation); Farina, D. [Istitutodi Fisica del Plasma, Association EURATOM-ENEA-CNR, Milano (Italy); Kajiwara, K.; Kasugai, A.; Kobayashi, N.; Oda, Y.; Ramponi, G. [Japan Atomic Energy Agency (JAEA) 801-1 Mukoyama, Naka-shi, Ibaraki 311-0193 (Japan)] (and others)

2009-11-26T23:59:59.000Z

98

US ITER Project Providing a Facility for  

E-Print Network [OSTI]

US ITER Project Providing a Facility for Burning Plasma Research Ned Sauthoff Project Manager, US to position the US for Burning Plasma Research #12;U.S. ITER / Sauthoff Slide 2 Structure of the Talk... ITER

99

Iterative methods for neutron transport eigenvalue Fynn Scheben and Ivan G. Graham  

E-Print Network [OSTI]

iterative methods for computing criticality in nuclear reactors. In general this requires the solution words. neutron transport, criticality, generalised eigenvalue problem, symmetry, inexact inverse iteration. AMS subject classifications. 45C05, 65F15, 65N25, 65R20, 65Z05, 82D75 1. Reactor criticality

Graham, Ivan

100

24th IAEA Fusion Energy Conference, San Diego, CA, October 8-13, 2012 Slide 1 The ITER Blanket System Design  

E-Print Network [OSTI]

24th IAEA Fusion Energy Conference, San Diego, CA, October 8-13, 2012 Slide 1 The ITER Blanket-13, 2012 Slide 2 Blanket Effort Conducted within BIPT Blanket Integrated Product Team ITER-13, 2012 Slide 3 Blanket System Functions Main functions of ITER Blanket System: · Exhaust the majority

Raffray, A. René

Note: This page contains sample records for the topic "integrated iterative solution" 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

ITER Diagnostic First Wal  

SciTech Connect (OSTI)

The ITER Diagnostic Division is responsible for designing and procuring the First Wall Blankets that are mounted on the vacuum vessel port plugs at both the upper and equatorial levels This paper will discuss the effects of the diagnostic aperture shape and configuration on the coolant circuit design. The DFW design is driven in large part by the need to conform the coolant arrangement to a wide variety of diagnostic apertures combined with the more severe heating conditions at the surface facing the plasma, the first wall. At the first wall, a radiant heat flux of 35W/cm2 combines with approximate peak volumetric heating rates of 8W/cm3 (equatorial ports) and 5W/cm3 (upper ports). Here at the FW, a fast thermal response is desirable and leads to a thin element between the heat flux and coolant. This requirement is opposed by the wish for a thicker FW element to accommodate surface erosion and other off-normal plasma events.

G. Douglas Loesser, et. al.

2012-09-21T23:59:59.000Z

102

Bragg x-ray survey spectrometer for ITER  

SciTech Connect (OSTI)

Several potential impurity ions in the ITER plasmas will lead to loss of confined energy through line and continuum emission. For real time monitoring of impurities, a seven channel Bragg x-ray spectrometer (XRCS survey) is considered. This paper presents design and analysis of the spectrometer, including x-ray tracing by the Shadow-XOP code, sensitivity calculations for reference H-mode plasma and neutronics assessment. The XRCS survey performance analysis shows that the ITER measurement requirements of impurity monitoring in 10 ms integration time at the minimum levels for low-Z to high-Z impurity ions can largely be met.

Varshney, S. K.; Jakhar, S. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar, Gujarat 382428 (India); Barnsley, R. [ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); O'Mullane, M. G. [Department of Physics, University of Strathclyde, Glasgow G4 0NG (United Kingdom)

2012-10-15T23:59:59.000Z

103

Negative Ion Based Heating and Diagnostic Neutral Beams for ITER  

SciTech Connect (OSTI)

To meet the requirements of the four operating and one start-up scenarios foreseen in the International Tokamak Experimental Reactor (ITER) a flexible heating mix will be required, which has to include a reliable contribution from neutral beams. The current baseline of ITER foresees 2 Heating Neutral Beam (HNB) systems based on negative ion technology, each operating at 1 MeV 40 A D{sup -} ions, and each capable of delivering up to 16.7 MW of D deg. to the ITER plasma. A 3rd HNB injector is foreseen as an upgrade option. In addition a dedicated Diagnostic Neutral Beam (DNB) injecting 100 keV 60 A of negative hydrogen ions will be available for charge exchange resonant spectroscopy (CXRS). The significant R and D effort necessary to meet the design requirements will be provided in the Neutral Beam Test Facility (NBTF), which is to be constructed in Padua, Italy. This paper gives an overview of the current status of the neutral beam (NB) systems and the chosen configuration. The ongoing integration effort into the ITER plant is highlighted and open interface issues are identified. It is shown how installation and maintenance logistics has influenced the design. ITER operating scenarios are briefly discussed, including start-up and commissioning. For example it is now envisaged to have a low current hydrogen phase of ITER operations, essentially for commissioning of the many auxiliary systems used on ITER. The low current limits the achievable plasma density, and hence the NB energy due to shine through limitations. Therefore a possible reconfiguration of the auxiliary heating systems is now being discussed. Other NB related issues identified by the ongoing design review process are emphasized and possible impact on the implementations of the HNB and DNB systems is indicated.

Schunke, B.; Bora, D.; Cordier, J.-J.; Hemsworth, R.; Tanga, A. [ITER Organization, Cadarache, 13108 St.-Paul-lez-Durance (France); Antoni, V. [Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4, I-35127 (Italy); Bonicelli, T. [IPR, Bhat, Gandhinagar, Gujarat, 382428 (India); Chakraborty, A. [EFDA CSU, Boltzmannstrasse 2, D-85748, Garching (Germany); Inoue, T.; Watanabe, K. [JAEA, 801-1 Mukouyama, Naka-machi, Naka-gun, Ibaraki-ken 311-0193 (Japan)

2008-04-07T23:59:59.000Z

104

A review of ITER blanket designs  

SciTech Connect (OSTI)

Changes in ITER requirements and conditions in the Engineering Design Activity (EDA), and the desire to obtain greater operating flexibility, led to a reconsideration of the ITER Conceptual Design Activity (CDA) blanket designs. The current strategy is to follow a two-tiered development approach: The reference design blanket is non-breeding, and satisfies only the basic performance phase (BPP) functional requirements. This blanket would need to be changed out for the extended performance (EPP). A lower level development effort is also underway on a tritium-breeding blanket. The decision as to which of the two designs to adopt will be made at the end of a two-year development effort. This paper describes the present candidate blankets and the issues associated with each of them. The reference design is a non-breeding, low temperature, low pressure, water cooled, austenitic stainless steel (316SS) blanket/shield (BS). The first wall (FW), which may be integral with or separate from the BS, is a bonded copper-alloy/SS structure with a beryllium coating. Critical issues here are copper-SS bonding, fabricability, and radiation damage and stress corrosion cracking of the SS. The breeding blanket utilizes vanadium alloy structural material, with lithium as the breeder. The coolants are either lithium (self-cooled) or high pressure helium. The primary issues here are the need to electrically insulate the flow channels, the qualification of vanadium as a structural material, and the fabrication of large vanadium structures.

Green, L.; Carelli, M.D.; Stefani, F. [Westinghouse Science & Technology Center, Pittsburgh, PA (United States); Morgan, G.D. [McDonnell Douglas Corp., St. Louis, MO (United States); Mattas, R. [Argonne National Lab., IL (United States)

1994-11-01T23:59:59.000Z

105

New modeling and control solutions for integrated microgrid system with respect to thermodynamics properties of generation and demand  

E-Print Network [OSTI]

This thesis investigates microgrid control stability with respect to thermodynamics behaviors of generation and demand. First, a new integrated microgrid model is introduced. This model consists of a combined cycle power ...

Liu, Fang-Yu, S.M. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

106

Safety Analysis of the US Dual Coolant Liquid Lead-Lithium ITER Test Blanket Module  

SciTech Connect (OSTI)

The US is proposing a prototype of a dual coolant liquid lead-lithium (DCLL) DEMO blanket concept for testing in the International Thermonuclear Experimental Reactor (ITER) as an ITER Test Blanket Module (TBM). Because safety considerations are an integral part of the design process to ensure that this TBM does not adversely impact the safety of ITER, a safety assessment has been conducted for this TBM and its ancillary systems as requested by the ITER project. Four events were selected by the ITER International Team (IT) to address specific reactor safety concerns, such as VV pressurization, confinement building pressure build-up, TBM decay heat removal capability, tritium and activation products release from the TBM system, and hydrogen and heat production from chemical reactions. This paper summarizes the results of this safety assessment conducted with the MELCOR computer code.

Merrill, Brad; Reyes, Susana; Sawan, Mohamed; Wong, Clement

2006-07-01T23:59:59.000Z

107

US ITER Project Brad Nelson  

E-Print Network [OSTI]

power supply in San Giorgio di Piano, Italy #12;FY 2014 Partner Achievements 9/23/14 FESAC ITER Progress Central Solenoid Steady State Electrical Network Tokamak Cooling Water System Toroidal Field Conductor #12 Roughing pumps Pellet injection Tokamak cooling water system Vacuum auxiliary system Ion

108

The roadmap to magnetic confinement fusion Cutaway of the ITER tokamak. ( ITER)  

E-Print Network [OSTI]

The roadmap to magnetic confinement fusion Cutaway of the ITER tokamak. (© ITER) There are two ways breeding concepts [8] . Roadmap beyond ITER The ITER project has mapped out a road map to a commercial is the most promising for power generation (Table 2) [9] . #12;Table 2. "Fast track" fusion roadmap Facility

Hampshire, Damian

109

Michel Claessens michel.claessens@iter.org  

E-Print Network [OSTI]

the ITER Organization to continue the negotiations with the NEA (OECD Nuclear Energy Agency) in order of Environment. On 28 and 29 November 2012, the governing body of the ITER Organization convened for the first for the implementation of ITER. This will in particular allow for jointly addressing the causes of barriers to effective

110

D. Mundy UKAIS PhD Consortium 2003. Providing a Secure Solution For The Integration Of Electronic  

E-Print Network [OSTI]

for the patient on a paper prescription form. The health care provider signs this form by hand. The patient can Prescription Transfer Within The United Kingdom National Health Service D.P.Mundy Abstract This paper provides could be integrated successfully into the UK National Health Service (NHS), was developed. The described

Kent, University of

111

Thermo-mechanical analysis of ITER first mirrors and its use for the ITER equatorial visible/infrared wide angle viewing system optical design  

SciTech Connect (OSTI)

ITER first mirrors (FMs), as the first components of most ITER optical diagnostics, will be exposed to high plasma radiation flux and neutron load. To reduce the FMs heating and optical surface deformation induced during ITER operation, the use of relevant materials and cooling system are foreseen. The calculations led on different materials and FMs designs and geometries (100 mm and 200 mm) show that the use of CuCrZr and TZM, and a complex integrated cooling system can limit efficiently the FMs heating and reduce their optical surface deformation under plasma radiation flux and neutron load. These investigations were used to evaluate, for the ITER equatorial port visible/infrared wide angle viewing system, the impact of the FMs properties change during operation on the instrument main optical performances. The results obtained are presented and discussed.

Joanny, M.; Salasca, S.; Dapena, M.; Cantone, B.; Travere, J. M. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Thellier, C.; Ferme, J. J. [THALES SESO, 13593 Aix-en-Provence Cedex 3 (France); Marot, L. [Department of Physics, University of Basel, 4056 Basel (Switzerland); Buravand, O. [Institut d'Optique Graduate School, 91127 Palaiseau (France); Perrollaz, G. [AMETRA, 13770 Venelles (France); Zeile, C. [INR, KIT, D-76344 Eggenstein-Leopoldshafen (Germany)

2012-10-15T23:59:59.000Z

112

Overview of Recent Developments in Pellet Injection for ITER  

SciTech Connect (OSTI)

Pellet injection is the primary fueling technique planned for core fueling of ITER burning plasmas. Also, the injection of relatively small pellets to purposely trigger rapid small edge localized modes (ELMs) has been proposed as a possible solution to the heat flux damage from larger natural ELMs likely to be an issue on the ITER divertor surfaces. The ITER pellet injection system is designed to inject pellets into the plasma through both inner and outer wall guide tubes. The inner wall guide tubes will provide high throughput pellet fueling while the outerwall guide tubes will be used primarily to trigger ELMs at a high frequency (>15 Hz). The pellet fueling rate ofeach injector is to be up to 120 Pa-m3/s, which will require the formation of solid D-T at a volumetric rate of ~1500 mm3/s. Two injectors are to be provided for ITER at the startup with a provision for up to six injectorsduring the D-T phase. The required throughput of each injector is greater than that of any injector built to date, and a novel twin-screw continuous extrusion system is being developed to meet the challenging design parameters. Status of the development activities will be presented, highlighting recent progress.

Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Meitner, Steven J [ORNL; Caughman, John B [ORNL; Rasmussen, David A [ORNL; Maruyama, So [ITER Organization, Cadarache, France

2012-01-01T23:59:59.000Z

113

Solitary Waves of the MRLW Equation by Variational Iteration Method  

SciTech Connect (OSTI)

In a recent publication, Soliman solved numerically the modified regularized long wave (MRLW) equation by using the variational iteration method (VIM). In this paper, corrected numerical results have been computed, plotted, tabulated, and compared with not only the exact analytical solutions but also the Adomian decomposition method results. Solitary wave solutions of the MRLW equation are exactly obtained as a convergent series with easily computable components. Propagation of single solitary wave, interaction of two and three waves, and also birth of solitons have been discussed. Three invariants of motion have been evaluated to determine the conservation properties of the problem.

Hassan, Saleh M. [Department of Mathematics, College of Science, King Saud University, P.O. Box 2455, Riyadh 11451 (Saudi Arabia); Department of Mathematics, College of Science, Ain Shams University, Abbassia 11566, Cairo (Egypt); Alamery, D. G. [Department of Mathematics, College of Science, King Saud University, P.O. Box 2455, Riyadh 11451 (Saudi Arabia)

2009-09-09T23:59:59.000Z

114

U. S. ITER shield and blanket design activities  

SciTech Connect (OSTI)

This paper summarizes nuclear-related work in support of the U.S. effort for the Internatinoal Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/.

Baker, C.C.

1989-03-01T23:59:59.000Z

115

Engineering and manufacturing of ITER first mirror mock-ups  

SciTech Connect (OSTI)

Most of the ITER optical diagnostics aiming at viewing and monitoring plasma facing components will use in-vessel metallic mirrors. These mirrors will be exposed to a severe plasma environment and lead to an important tradeoff on their design and manufacturing. As a consequence, investigations are carried out on diagnostic mirrors toward the development of optimal and reliable solutions. The goals are to assess the manufacturing feasibility of the mirror coatings, evaluate the manufacturing capability and associated performances for the mirrors cooling and polishing, and finally determine the costs and delivery time of the first prototypes with a diameter of 200 and 500 mm. Three kinds of ITER candidate mock-ups are being designed and manufactured: rhodium films on stainless steel substrate, molybdenum on TZM substrate, and silver films on stainless steel substrate. The status of the project is presented in this paper.

Joanny, M.; Travere, J. M.; Salasca, S.; Corre, Y. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Marot, L. [Department of Physics, University of Basel, Klingelbergstrasse 82, CH-4056 Basel (Switzerland); Thellier, C.; Gallay, G.; Cammarata, C.; Passier, B.; Ferme, J. J. [SESO, 305 Rue Louis Armand CS 30504, 13593 Aix-en-Provence Cedex 3 (France)

2010-10-15T23:59:59.000Z

116

The physics role of ITER  

SciTech Connect (OSTI)

Experimental research on the International Thermonuclear Experimental Reactor (ITER) will go far beyond what is possible on present-day tokamaks to address new and challenging issues in the physics of reactor-like plasmas. First and foremost, experiments in ITER will explore the physics issues of burning plasmas--plasmas that are dominantly self-heated by alpha-particles created by the fusion reactions themselves. Such issues will include (i) new plasma-physical effects introduced by the presence within the plasma of an intense population of energetic alpha particles; (ii) the physics of magnetic confinement for a burning plasma, which will involve a complex interplay of transport, stability and an internal self-generated heat source; and (iii) the physics of very-long-pulse/steady-state burning plasmas, in which much of the plasma current is also self-generated and which will require effective control of plasma purity and plasma-wall interactions. Achieving and sustaining burning plasma regimes in a tokamak necessarily requires plasmas that are larger than those in present experiments and have higher energy content and power flow, as well as much longer pulse length. Accordingly, the experimental program on ITER will embrace the study of issues of plasma physics and plasma-materials interactions that are specific to a reactor-scale fusion experiment. Such issues will include (i) confinement physics for a tokamak in which, for the first time, the core-plasma and the edge-plasma are simultaneously in a reactor-like regime; (ii) phenomena arising during plasma transients, including so-called disruptions, in regimes of high plasma current and thermal energy; and (iii) physics of a radiative divertor designed for handling high power flow for long pulses, including novel plasma and atomic-physics effects as well as materials science of surfaces subject to intense plasma interaction. Experiments on ITER will be conducted by researchers in control rooms situated at major fusion laboratories around the world, linked by high-speed computer networks--thus extending further what is already a much-acclaimed paradigm for international collaboration in science.

Rutherford, P.H.

1997-04-01T23:59:59.000Z

117

ITER | Princeton Plasma Physics Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr FlickrGuidedCH2MLLCBasicsScience at ALCFPhysicsQualityITER

118

US ITER Moving Forward Video  

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 Layeredof2014 EIA Energy Conference U.S. Crude OilITER Moving

119

Princeton Plasma Physics Lab - ITER  

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 - SeptemberMicroneedles for4-16 FOR Primary Author Last Nameenergyiter ITER is a

120

Overview of ITER ProjectOverview of ITER Project --organizational structure,organizational structure,  

E-Print Network [OSTI]

/Research Plans 3. Basic Research in support of ITER · Experimental and Theoretical Plasma Research · R

Note: This page contains sample records for the topic "integrated iterative solution" 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

Iterative solutions to large sparse finite element equations  

E-Print Network [OSTI]

direct solvers. The theory behind the convergence rate relationship and storage requirements for the preconditioned conjugate gradient methods using the diagonal scaling, incomplete Cholesky decomposition and SSOR preconditioners is explained in detail...

Wang, Hongbing

1995-01-01T23:59:59.000Z

122

Iterative Solution of Elliptic Equations with a Small Parameter  

E-Print Network [OSTI]

and engineering are modelled by partial differ- ential equations involving a small parameter defining a certain are positive semi-definite linear partial differential operators, such that the operator t2 L1 +L0 is coercive the properties of the operators Li and the vectors x and b describe the unknown u and the load f with respect

Segatti, Antonio

123

iterative solution of augmented systems arising in interior methods  

E-Print Network [OSTI]

Analysis 1993 (Dundee, 1993), G. A. Watson and D. Griffiths, eds., vol. 303 of Pitman Res. Notes Math. Ser., Longman Sci. Tech., Harlow, UK, 1994, pp. 89

2005-09-04T23:59:59.000Z

124

Iterative multiuser detection techniques for CDMA systems  

E-Print Network [OSTI]

) with (3. 40) where (ok" )' and (a&", ) are the variances of g?" and y&", ?, respectively, &t~" is the output of the inference cain:&&ll&&i in iteration n before con&bi?ing with an improved decoder input, fr&&n& the previous iteration n ? 1, denoted...

Du, Xuechao

2012-06-07T23:59:59.000Z

125

Iterative Speech Enhancement With Spectral Constraints  

E-Print Network [OSTI]

Iterative Speech Enhancement With Spectral Constraints John H. Hansen and Mark A. Clements Georgia iterative speech enhancementtechnique based on spectral constraints is presented in this paper estimate of a speech waveform in additive white noise. Thenew approach applies inter- and intra

Texas at Dallas, University of

126

Insights from US ITER: Strategies for Accelerating  

E-Print Network [OSTI]

Insights from US ITER: Strategies for Accelerating Fusion Energy as a Project Ned Sauthoff US ITER Project Manager SOFE Town Hall Meeting | June 27, 2011 #12;1. Treat fusion energy as a project, rather than a program. Mission: ·Rapid materials and fusion systems development, leading

127

ITER --"INTERNATIONAL THERMONUCLEAR EXPERIMENTAL RESEARCH PROGRAM".  

E-Print Network [OSTI]

ITER -- "INTERNATIONAL THERMONUCLEAR EXPERIMENTAL RESEARCH PROGRAM". ORGANIZATION TO DIRECT WORLD plasmas and thermonuclear burn processes (cost -$1.5-36)2. (2) An expanded, more ambitious international Thermonuclear Experimental Research Program" by L. J. Perkins #12;NORMAL-CONDUCTING COPPER OPTIONS FOR THE ITER

128

ITER11/3/04 Y. Shimomura  

E-Print Network [OSTI]

ITER11/3/04 Y. Shimomura for the ITER International and Participant Teams The 20th Fusion Energy modules Vacuum Vessel 9 sectors Cryostat 24 m high x 28 m dia. Port Plug heating/current drive test of welded plates · Vessel/Blanket ­ support arrangement simplified ­ nine lower ports ­ blanket module has

129

ITER site contest counts down Junichi Miura  

E-Print Network [OSTI]

Thermonuclear Experimental Reactor (ITER), an international project to use nuclear fusion energy for electric on a site for the project. The ITER project envisions using thermonuclear fusion to generate huge amounts heavy hydrogen and tritium used for fuel in the fusion reaction are heated in a vacuum receptacle at 100

130

IAEA-CN-SO/F-I-4 ITER: CONCEPT DEFINITION*  

E-Print Network [OSTI]

way. 1. INTRODUCTION The activity of the International Thermonuclear Experimental Reactor (ITER. * The activity of the International Thermonuclear Experimental Reactor (ITER) is conducted under the auspices

131

Annex I ITER Organization Service Contract General Conditions...  

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

Annex I ITER Organization Service Contract General Conditions (2014) Page 1 of 21 GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS (2014) Definitions...

132

Co-simulation for performance prediction of integrated building and HVAC systems - An analysis of solution characteristics using a two-body system  

E-Print Network [OSTI]

of innovative integrated HVAC systems in buildings, infor building envelope and HVAC systems simu- lation - WillIntegrated simulation for HVAC performance prediction: State

Trcka, Marija

2010-01-01T23:59:59.000Z

133

MIMO PID Tuning via Iterated LMI Restriction S. Boyd M. Hast K. J. Astrom  

E-Print Network [OSTI]

MIMO PID Tuning via Iterated LMI Restriction S. Boyd M. Hast K. J. °Astr¨om July 2, 2014 Abstract We formulate multi-input multi-output (MIMO) proportional-integral-derivative (PID) controller design, and provides a simple automated method for tuning MIMO PID controllers. The method is readily extended in many

134

Fusion Engineering and Design 42 (1998) 235245 Verification of ITER shielding capability and FENDL data  

E-Print Network [OSTI]

of the calculated-to-experimental (C/E) data. These two objectives will guide designers with regard and calculated data that should be implemented in the design process. Both differential and integral experimentalFusion Engineering and Design 42 (1998) 235­245 Verification of ITER shielding capability and FENDL

Abdou, Mohamed

135

Systems Integration | Department of Energy  

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

Systems Integration Systems Integration Through the SunShot Initiative, the U.S. Department of Energy (DOE) supports the development of innovative, cost-effective solutions that...

136

Value iteration for (switched) homogeneous systems  

E-Print Network [OSTI]

In this note, we prove that dynamic programming value iteration converges uniformly for discrete-time homogeneous systems and continuous-time switched homogeneous systems. For discrete-time homogeneous systems, rather than ...

Dahleh, Munther A.

137

ITERATIVE METHODS FOR NEUTRON TRANSPORT EIGENVALUE PROBLEMS  

E-Print Network [OSTI]

Abstract. We discuss iterative methods for computing criticality in nuclear reactors. In general as the inner solver. Key words. neutron transport, criticality, generalised eigenvalue problem, symmetry. Reactor criticality problems. Climate change is a challenging problem of great contemporary interest

Graham, Ivan

138

Electromagnetic Analysis For The Design Of ITER Diagnostic Port Plugs During Plasma Disruptions  

SciTech Connect (OSTI)

ITER diagnostic port plugs perform many functions including structural support of diagnostic systems under high electromagnetic loads while allowing for diagnostic access to plasma. The design of diagnotic equatorial port plugs (EPP) are largely driven by electromagnetic loads and associate response of EPP structure during plasma disruptions and VDEs. This paper summarizes results of transient electromagnetic analysis using Opera 3d in support of the design activities for ITER diagnostic EPP. A complete distribution of disruption loads on the Diagnostic First Walls (DFWs). Diagnostic Shield Modules (DSMs) and the EPP structure, as well as impact on the system design integration due to electrical contact among various EPP structural components are discussed.

Zhai, Y

2014-03-03T23:59:59.000Z

139

Overview of ITER Project Activities in the U.S.  

E-Print Network [OSTI]

procurement packages for bid. ­ Need to contribute team members to international ITER Organization to the ITER Organization for common expenses ­ Staff for the ITER Organization at expected US rates #12, standard components #12;Evolution of the ITER cost from $500M to $1.122B: Sum of all components ($M

140

ITER MHD stability analysis. Final report  

SciTech Connect (OSTI)

This report summarizes the final results and conclusions from work done for ITER under the DOE Task 18 (Raytheon Task ITER-GA 4002E). The work was performed in collaboration with D. Pearlstein and R. Bulmer of the Lawrence Livermore National Laboratory (LLNL), in close conjunction with D. Boucher of the ITER Joint Central Team (JCT). The work was partly done at General Atomics in San Diego and partly at LLNL. Approximately eight hours per week were spent from August 1994 through June 1995, with a no-cost extension through December 1995. The report covers work on the ideal MHD stability analysis for the ITER TAC scenarios and DIII-D ITER Demonstration Discharges, code modifications performed in order to efficiently and accurately complete the stability calculations, and additional collaborative efforts involving code benchmarking and dissemination of the DIII-D ITER Demonstration Discharge data. The work spawned several presentations and reports, including significant contributions to published IAEA Proceedings, and these are also summarized. 8 refs., 9 figs.

Turnbull, A.D.

1996-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Curvature Integrals and Iteration Complexities in SDP and ...  

E-Print Network [OSTI]

Sep 30, 2011 ... In particular, we conduct numerical experiments in practically ...... respectively, and the fact that these operations are done in the compact...

2011-09-30T23:59:59.000Z

142

Y.ShimomuraY.Shimomura ITER Joint Central TeamITER Joint Central Team  

E-Print Network [OSTI]

Structure #12;ICRF All metal Vacuum Transmission Line Support · Avoid dielectric material · Cool through SLIP JOINT COOLING IN COOLING OUT mm VTL GETTER PUMP #12;Mode Converter Support Structure Standard Novgorod and CRPP Lausanne ECRH/ECCD for ITER: ITER-task: Remote steering antenna for ECRH/ECCD #12

143

US Burning Plasma Workshop Oak Ridge National Laboratory US Contributions to ITER Project (US ITER)  

E-Print Network [OSTI]

US Burning Plasma Workshop Oak Ridge National Laboratory US Contributions to ITER Project (US ITER Plasma Workshop Oak Ridge, TN December 7, 2005 #12;US Burning Plasma Workshop Oak Ridge National '06 Expectations · Summary #12;US Burning Plasma Workshop Oak Ridge National Laboratory Highlights

144

JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER  

E-Print Network [OSTI]

JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER: Challenges Billions ITERITER startsstarts DEMODEMO decisiondecision:: Fusion impact? Energy without greenEnergy Fusion fuel: deuterium et tritium Deuterium: plenty in the ocean Tritium: made in situ from Lithium

145

Integrated Technology Deployment  

Office of Energy Efficiency and Renewable Energy (EERE)

Integrated technology deployment is a comprehensive approach to implementing solutions that increase the use of energy efficiency and renewable energy technologies. Federal, state, and local...

146

Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material  

SciTech Connect (OSTI)

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers.

Ulrickson, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States); Manly, W.D. [Oak Ridge National Lab., TN (United States); Dombrowski, D.E. [Brush Wellman, Inc., Cleveland, OH (United States)] [and others

1995-08-01T23:59:59.000Z

147

Parallel computation of multigroup reactivity coefficient using iterative method  

SciTech Connect (OSTI)

One of the research activities to support the commercial radioisotope production program is a safety research target irradiation FPM (Fission Product Molybdenum). FPM targets form a tube made of stainless steel in which the nuclear degrees of superimposed high-enriched uranium. FPM irradiation tube is intended to obtain fission. The fission material widely used in the form of kits in the world of nuclear medicine. Irradiation FPM tube reactor core would interfere with performance. One of the disorders comes from changes in flux or reactivity. It is necessary to study a method for calculating safety terrace ongoing configuration changes during the life of the reactor, making the code faster became an absolute necessity. Neutron safety margin for the research reactor can be reused without modification to the calculation of the reactivity of the reactor, so that is an advantage of using perturbation method. The criticality and flux in multigroup diffusion model was calculate at various irradiation positions in some uranium content. This model has a complex computation. Several parallel algorithms with iterative method have been developed for the sparse and big matrix solution. The Black-Red Gauss Seidel Iteration and the power iteration parallel method can be used to solve multigroup diffusion equation system and calculated the criticality and reactivity coeficient. This research was developed code for reactivity calculation which used one of safety analysis with parallel processing. It can be done more quickly and efficiently by utilizing the parallel processing in the multicore computer. This code was applied for the safety limits calculation of irradiated targets FPM with increment Uranium.

Susmikanti, Mike [Center for Development of Nuclear Informatics, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)] [Center for Development of Nuclear Informatics, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia); Dewayatna, Winter [Center for Nuclear Fuel Technology, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)] [Center for Nuclear Fuel Technology, National Nuclear Energy Agency of Indonesia PUSPIPTEK Area, Tangerang (Indonesia)

2013-09-09T23:59:59.000Z

148

San Diego 01.05.2001 Power and Particle Exhaust in ITER Slide 1 by G. Janeschitz, et.al. _______________________________________________________________________ ITER  

E-Print Network [OSTI]

San Diego 01.05.2001 Power and Particle Exhaust in ITER Slide 1 by G. Janeschitz, et.al. ITER Exhaust in ITER Slide 2 by G. Janeschitz. ITER to pump #12;San Diego; 01.05.2001 Power and Particle Exhaust in ITER Slide 3 by G. Janeschitz. ITER

149

US solid breeder blanket design for ITER  

SciTech Connect (OSTI)

The US blanket design activity has focused on the developments and the analyses of a solid breeder blanket concept for ITER. The main function of this blanket is to produce the necessary tritium required for the ITER operation and the test program. Safety, power reactor relevance, low tritium inventory, and design flexibility are the main reasons for the blanket selection. The blanket is designed to operate satisfactorily in the physics and the technology phases of ITER without the need for hardware changes. Mechanical simplicity, predictability, performance, minimum cost, and minimum R D requirements are the other criteria used to guide the design process. The design aspects of the blanket are summarized in this paper. 2 refs., 7 figs., 3 tabs.

Gohar, Y.; Attaya, H.; Billone, M.; Lin, C.; Johnson, C.; Majumdar, S.; Smith, D. (Argonne National Lab., IL (USA)); Goranson, P.; Nelson, B.; Williamson, D.; Baker, C. (Oak Ridge National Lab., TN (USA)); Raffray, A.; Badawi, A.; Gorbis, Z.; Ying, A.; Abdou, M. (California Univ., Los Angeles, CA (USA)); Sviatoslavsky, I.; Blanchard, J.; Mogahed, E.; Sawan, M.; Kulcinski, G. (Wisconsin Univ., Madison, WI (USA))

1990-09-01T23:59:59.000Z

150

Solid breeder blanket option for the ITER conceptual design  

SciTech Connect (OSTI)

A solid-breeder water-cooled blanket option was developed for ITER based on a multilayer configuration. The blanket uses beryllium for neutron multiplication and lithium oxide for tritium breeding. The material forms are sintered products for both material with 0.8 density factor. The lithium-6 enrichment is 90%. This blanket has the capability to accommodate a factor of two change in the neutron wall loading without violating the different design guidelines. The design philosophy adopted for the blanket is to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. At the same time, the reliability and the safety aspects of the blanket are enhanced by the use of a low-pressure coolant and the separation of the tritium purge lines from the coolant system. The blanket modules are made by hot vacuum forming and diffusion bonding a double wall structure with integral cooling channels. The different aspects of the blanket design including tritium breeding, nuclear heat deposition, activation analyses, thermal-hydraulics, tritium inventory, structural analyses, and water coolant conditions are summarized in this paper. 12 refs., 2 figs., 1 tab.

Gohar, Y.; Attaya, H.; Billone, M.C.; Finn, P.; Majumdar, S.; Turner, L.R.; Baker, C.C.; Nelson, B.E.; Raffray, R. (Argonne National Lab., IL (USA); Oak Ridge National Lab., TN (USA); California Univ., Los Angeles, CA (USA))

1989-10-01T23:59:59.000Z

151

Plan and Strategy for ITER Blanket Testing in Japan  

SciTech Connect (OSTI)

The Fusion Council of Japan has established the long-term program for the development of blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan, while liquid breeder blankets and high temperature solid breeder blanket have been identified as the attractive advanced blanket. Japan Atomic Energy Research Institute (JAERI) is leading the development of solid breeder blankets, while, universities and National Institute for Fusion Science (NIFS) are developing the advanced blankets for potential options of the fusion power demonstration plant and commercial power plants. ITER blanket module testing is regarded as one of the most important milestones, by which integrity of candidate blanket design is qualified for the fusion power demonstration plant, together with material irradiation data by International Fusion Material Irradiation Facility (IFMIF). Japan is investigating the possibility of testing all types of blankets under TBWG framework with both of JAERI and universities/NIFS involvements. This paper presents a plan and strategy for the development of test blanket modules and ITER blanket module testing in Japan.

Enoeda, Mikio [Japan Atomic Energy Research Institute (Japan); Akiba, Masato [Japan Atomic Energy Research Institute (Japan); Tanaka, Satoru [University of Tokyo (Japan); Shimizu, Akihiko [Kyushu University (Japan); Hasegawa, Akira [Tohoku University (Japan); Konishi, Satoshi [Kyoto University (Japan); Kimura, Akihiko [Kyoto University (Japan); Kohyama, Akira [Kyoto University (Japan); Sagara, Akio [National Institute of Fusion Science (Japan); Muroga, Takeo [National Institute of Fusion Science (Japan)

2005-05-15T23:59:59.000Z

152

Beyond ITER: Neutral beams for DEMO  

E-Print Network [OSTI]

In the development of magnetically confined fusion as an economically sustainable power source, ITER is currently under construction. Beyond ITER is the DEMO programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed.

McAdams, R

2013-01-01T23:59:59.000Z

153

An iterative technique for solving equations of statistical equilibrium  

E-Print Network [OSTI]

Superlevel partitioning is combined with a simple relaxation procedure to construct an iterative technique for solving equations of statistical equilibrium. In treating an $N$-level model atom, the technique avoids the $N^{3}$ scaling in computer time for direct solutions with standard linear equation routines and also does not fail at large $N$ due to the accumulation of round-off errors. In consequence, the technique allows detailed model atoms with $N \\ga 10^{3}$, such as those required for iron peak elements, to be incorporated into diagnostic codes for analysing astronomical spectra. Tests are reported for a 394-level Fe II ion and a 1266-level Ni I--IV atom.

L. B. Lucy

2001-03-21T23:59:59.000Z

154

Michel Claessens michel.claessens@iter.org  

E-Print Network [OSTI]

's recommendations. The ITER Council also approved two important technical proposals that will have a positive impact of research and development on the tungsten divertor that was supported by successful experiments and testing Tokamak JET (UK). Council also noted the progress on the design and prototype development of the in

155

ITER Project Status Fusion Energy Sciences  

E-Print Network [OSTI]

. Manufacturing of an ITER vacuum vessel segment in Korea 04/09/14 FESAC/Sauthoff 12 (Photos: KO DA) #12;Russia to capped value) ORNL 100% Tokamak Cooling Water System PPPL 75% Steady State Electrical Network PPPL 14 tooling stations #12;Central Solenoid Specs: 6 independent coil packs of cable-in- conduit conductor

156

CONTRACTIVITY IN TURBO ITERATIONS Phillip A. Regalia  

E-Print Network [OSTI]

CONTRACTIVITY IN TURBO ITERATIONS Phillip A. Regalia Department of Communications, Image Fourier 91011 Evry cedex France Phillip.Regalia@int-evry.fr ABSTRACT The turbo decoding algorithm has met with intense study over the past decade, in an attempt to harness the full power of the "turbo principle". Here

Regalia, Phillip A.

157

Limited View Angle Iterative CT Reconstruction  

E-Print Network [OSTI]

;Some Prior Literature in Limited View Tomography CT with limited-angle data and few views IRR algorithm Iterative Reconstruction-Reprojection (IRR) : An Algorithm for Limited Data Cardiac- Computed-views and limited-angle data in divergent-beam CT by E. Y. Sidky, CM Kao, and X. Pan (2006) Few-View Projection

158

Status of ITER Negotiations Warren Marton  

E-Print Network [OSTI]

for decommissioning. · ITER parties met in Barcelona, Feb. 7-11, to complete the technical level negotiations construction, & costs for operation, deactivation, and decommissioning required much interaction with all · Last issue is the complicated matter of P&I and waiver thereto, involving French Nuclear Safety

159

Funding for nuclear fusion Expensive Iteration  

E-Print Network [OSTI]

producing more energy than is put in. The International Thermonuclear Experimental Reactor became plain ITER aims to produce energy by fusing together the nuclei of hydrogen atoms, confined in a magnetic field. Initial projections in 2006 put its price at 10 billion ($13 billion): 5 billion to build and another 5

160

Bold Step by the World to Fusion Energy: ITER  

E-Print Network [OSTI]

THE DESIGN OF ITER · ITER PROJECT & ROLE OF THE UNITED STATES · PATH FROM ITER TO PRACTICAL FUSION POWER #12;Elements of a D-T Fusion Energy System ~ D-Li Plasma Heating Drivers or Confinement Balance of PlantD = nT = n TOTAL THERMAL ENERGY IN FUSION FUEL, DEFINE "ENERGY CONFINEMENT TIME", E ENERGY BALANCE dW d

Note: This page contains sample records for the topic "integrated iterative solution" 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

CCFE-PR(13)44 Beyond ITER: Neutral beams  

E-Print Network [OSTI]

R. McAdams CCFE-PR(13)44 Beyond ITER: Neutral beams for DEMO #12;Enquiries about copyright Kingdom Atomic Energy Authority is the copyright holder. #12;Beyond ITER: Neutral beams for DEMO R. Mc ITER: Neutral beams for DEMOa) R. McAdamsb) EURATOM/CCFE Association, Culham Science Centre, Abingdon

162

ITER HEAT REMOVAL SYSTEM SYSTEM & PROCESS CONTROL DESIGN  

E-Print Network [OSTI]

normal pulse operation, the heat deposited in the in-vessel components is released into the environment. Ito 1 , P. Lorenzetto 4 , Y. Okawa 5 1 ITER Joint Central Team, 11025 North Torrey Pines Road, La Jolla, CA, 92037, USA; 2 ITER Joint Central Team, Naka, Japan; 3 ITER Joint Central Team, Garching

Raffray, A. René

163

On the Logic of Iterated Non-prioritised Richard Booth  

E-Print Network [OSTI]

, and of iterated revision [3, 5, 7, 8, 17, 21], i.e., the study of the behaviour of an agent's beliefs underOn the Logic of Iterated Non-prioritised Revision Richard Booth Department of Computer Science. We look at iterated non-prioritised belief revision, using as a starting point a model of non

Booth, Richard

164

A Conditional Logic for Iterated Belief Revision Laura Giordano  

E-Print Network [OSTI]

A Conditional Logic for Iterated Belief Revision Laura Giordano DSTA ­ Universit?? a del Piemonte Abstract. In this paper we propose a conditional logic IBC to rep­ resent iterated belief revision. We define an iterated belief revision system by strengthening the postulates proposed by Darwiche and Pearl

Giordano, Laura

165

on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project  

E-Print Network [OSTI]

AGREEMENT on the Establishment of the ITER International Fusion Energy Organization for the Joint Fusion Energy Organization Article 2 Purpose of the ITER Organization Article 3 Functions of the ITER://fusionforenergy.europa.eu/downloads/aboutf4e/l_35820061216en00620081.pdf #12;Preamble The European Atomic Energy Community (hereinafter

166

Development of structural design criteria for ITER.  

SciTech Connect (OSTI)

The irradiation environment experienced by the in-vessel components of fusion reactors such as HER presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the interim ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.

Majumdar, S.

1998-06-22T23:59:59.000Z

167

Thermomechanical analysis of the ITER breeding blanket  

SciTech Connect (OSTI)

Thermomechanical performance of the ITER breeding blanket is an important design issue because it requires first, that the thermal expansion mismatch between the blanket structure and the blankets internals (such as, beryllium multiplier and tritium breeders) can be accommodated without creating high stresses, and second, that the thermomechanical deformation of various interfaces within the blanket does not create high resistance to heat flow and consequent unacceptably high temperatures in the blanket materials. Thermomechanical analysis of a single beryllium block sandwiched between two stainless steel plates was carried out using the finite element code ABAQUS to illustrate the importance of elastic deformation on the temperature distributions. Such an analysis for the whole ITER blanket needs to be conducted in the future. Uncertainties in the thermomechanical contact analysis can be reduced by bonding the beryllium blocks to the stainless steel plates by a thin soft interfacial layer.

Majumdar, S.; Gruhn, H. [Argonne National Lab., IL (United States); Gohar, Y.; Giegerich, M. [Max-Planck-Institut fuer Plasmaphysik, Muenchen (Germany). ITER Joint Central Team

1997-03-01T23:59:59.000Z

168

US Demo test blankets in ITER  

SciTech Connect (OSTI)

This paper summarizes the current status of the Demo blanket test systems and how the ITER reactor design and operations are being accommodated. The US blanket program is planning to develop a liquid metal breeder and a solid breeder blanket for testing and evaluation. The test blanket modules will have prototypical components, materials, and coolants representative of power reactor systems. The modules are to be located in the ITER horizontal test ports and installed/removed with special remote handling equipment. Adjacent ITER blanket neutronic and temperature conditions suggest the use of an isolation frame surrounding the test blanket modules or submodules. This frame will also provide additional shielding to protect the adjacent vacuum vessel. The frame and blanket module are attached to the surrounding backplate to transfer static and dynamic loads. All coolants and tritium-bearing fluids will be routed out of the midplane port to special heat exchangers and tritium separation systems. Special remote handling equipment is being designed to install and extract the test blanket modules. Dedicated transporters will be used to move the blanket and shielding modules to dedicated hot cells. Special facility areas will be provided immediately outside the port areas for the heat exchangers, pumps, and tritium-separation systems. 1 ref., 6 figs.

Waganer, L.M.; Lee, V.D [McDonnell Douglas Aerospace, St. Louis, MO (United States); Abdou, M.A.; Ying, A.Y. [Univ. of California, Los Angeles, CA (United States); Hua, T.; Sze, D.K. [Argonne National Lab., IL (United States); Dagher, M.A. [Rockwell International Corp., Canoga Park, CA (United States)

1996-12-31T23:59:59.000Z

169

Neutronics and thermal design analyses of US solid breeder blanket for ITER  

SciTech Connect (OSTI)

The US Solid Breeder Blanket is designed to produce the necessary tritium required for the ITER operation and to operate at power reactor conditions as much as possible. Safety, low tritium inventory, reliability, flexibility cost, and minimum R D requirements are the other design criteria. To satisfy these criteria, the produced tritium is recovered continuously during operation and the blanket coolant operates at low pressure. Beryllium multiplier material is used to control the solid-breeder temperature. Neutronics and thermal design analyses were performed in an integrated manner to define the blanket configuration. The reference parameters of ITER including the operating scenarios, the neutron wall loading distribution and the copper stabilizer are included in the design analyses. Several analyses were performed to study the impact of the reactor parameters, blanket dimensions, material characteristics, and heat transfer coefficient at the material interfaces on the blanket performance. The design analyses and the results from the different studies are summarized. 6 refs., 3 figs., 3 tabs.

Gohar, Y.; Billone, M.; Attaya, H. (Argonne National Lab., IL (USA)); Sawan, M. (Wisconsin Univ., Madison, WI (USA))

1990-09-01T23:59:59.000Z

170

US ITER (International Thermonuclear Experimental Reactor) shield and blanket design activities  

SciTech Connect (OSTI)

This paper summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. Primary tasks carried out during the past year include design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components, and issues regarding structural materials for an ITER device. The blanket concepts considered are the aqueous/Li salt solution, a water-cooled, solid breeder blanket, a helium-cooled, solid-breeder blanket, a blanket cooled by helium containing lithium-bearing particulates, and a blanket concept based on breeding tritium from He/sup 3/. 1 ref., 2 tabs.

Baker, C.C.

1988-08-01T23:59:59.000Z

171

Nonlinear Projective-Iteration Methods for Solving Transport Problems on Regular and Unstructured Grids  

SciTech Connect (OSTI)

This is a project in the field of fundamental research on numerical methods for solving the particle transport equation. Numerous practical problems require to use unstructured meshes, for example, detailed nuclear reactor assembly-level calculations, large-scale reactor core calculations, radiative hydrodynamics problems, where the mesh is determined by hydrodynamic processes, and well-logging problems in which the media structure has very complicated geometry. Currently this is an area of very active research in numerical transport theory. main issues in developing numerical methods for solving the transport equation are the accuracy of the numerical solution and effectiveness of iteration procedure. The problem in case of unstructured grids is that it is very difficult to derive an iteration algorithm that will be unconditionally stable.

Dmitriy Y. Anistratov; Adrian Constantinescu; Loren Roberts; William Wieselquist

2007-04-30T23:59:59.000Z

172

Development and test of the ITER conductor joints  

SciTech Connect (OSTI)

Joints for the ITER superconducting Central Solenoid should perform in rapidly varying magnetic field with low losses and low DC resistance. This paper describes the design of the ITER joint and presents its assembly process. Two joints were built and tested at the PTF facility at MIT. Test results are presented, losses in transverse and parallel field and the DC performance are discussed. The developed joint demonstrates sufficient margin for baseline ITER operating scenarios.

Martovetsky, N., LLNL

1998-05-14T23:59:59.000Z

173

Twisted symmetries and integrable systems  

E-Print Network [OSTI]

Symmetry properties are at the basis of integrability. In recent years, it appeared that so called "twisted symmetries" are as effective as standard symmetries in many respects (integrating ODEs, finding special solutions to PDEs). Here we discuss how twisted symmetries can be used to detect integrability of Lagrangian systems which are not integrable via standard symmetries.

G. Cicogna; G. Gaeta

2010-02-07T23:59:59.000Z

174

US ITER toroidal field coil conductor produc  

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 Layeredof EnergyLeaseEnergyUNCLASSIFIED ITER toroidal field

175

p-points in iterated forcing extensions  

E-Print Network [OSTI]

Ma. By Fact 4, U aiterated ccc extensions whose length has uncountable cofinality. These theorems are proved in 3. In 4 we indicate how...

Roitman, Judith A.

1978-05-03T23:59:59.000Z

176

Y.ShimomuraY.Shimomura ITER Joint Central TeamITER Joint Central Team  

E-Print Network [OSTI]

mobility between ITER and domestic programmes #12;Reactor Development: Stable fusion power production;0 0.2 0.4 0.6 0.8 1 0 0.5 1 1.5 2 2.5 3 3.5 Vp, km/s 11 12 13 14 23 21 22 X HFS pellet speed ~ 300 m

177

Diverse Power Iteration Embeddings and Its Applications  

SciTech Connect (OSTI)

AbstractSpectral Embedding is one of the most effective dimension reduction algorithms in data mining. However, its computation complexity has to be mitigated in order to apply it for real-world large scale data analysis. Many researches have been focusing on developing approximate spectral embeddings which are more efficient, but meanwhile far less effective. This paper proposes Diverse Power Iteration Embeddings (DPIE), which not only retains the similar efficiency of power iteration methods but also produces a series of diverse and more effective embedding vectors. We test this novel method by applying it to various data mining applications (e.g. clustering, anomaly detection and feature selection) and evaluating their performance improvements. The experimental results show our proposed DPIE is more effective than popular spectral approximation methods, and obtains the similar quality of classic spectral embedding derived from eigen-decompositions. Moreover it is extremely fast on big data applications. For example in terms of clustering result, DPIE achieves as good as 95% of classic spectral clustering on the complex datasets but 4000+ times faster in limited memory environment.

Huang H.; Yoo S.; Yu, D.; Qin, H.

2014-12-14T23:59:59.000Z

178

Linearized Constraints in the Connection Representation: Hamilton-Jacobi Solution  

E-Print Network [OSTI]

Newman and Rovelli have used singular Hamilton-Jacobi transformations to reduce the phase space of general relativity in terms of the Ashtekar variables. Their solution of the gauge constraint cannot be inverted and indeed has no Minkowski space limit. Nonetheless, we exhibit an explicit Hamilton-Jacobi solution of all the linearized constraints. The result does not encourage an iterative solution, but it does indicate the origin of the singularity of the Newman-Rovelli result.

J. N. Goldberg; D. C. Robinson

1994-05-11T23:59:59.000Z

179

TRANSP Tests Of TGLF and Predictions For ITER  

SciTech Connect (OSTI)

Gyro kinetic simulations of turbulence capture some of the features observed in transport, fluctuations, and correlations measured in tokamak plasmas. These codes calculations are CPU intensive, and are not practical for incorporation in present time-dependant transport codes, so reduced models based on these gyro kinetic codes are being used. An example is the TGLF model [1] which is a quasilinear gyrofluid model calibrated to nonlinear results from the GYRO code [2]. Recently TGLF has been incorporated into TRANSP. Analysis of experimental data using TRANSP with such models provides fundamental understanding of turbulent transport. Predictions of ITER performance with various plasma scenarios using such models are useful for optimizing design and for exposing issues that can be addressed in present experiments and theory. For instance, which combinations of heating, torquing, and current drive are optimal. Another application is for nuclear licensing (e.g. system integrity, neutron rates). Others are generating inputs for design of diagnostic systems and for theoretical studies. An example of the later is Alfven Eigenmode and AE-induced loss of fast ions. The beam ion distribution can either enhance or reduce the alpha pressure drive of the AE instability. The AE instability can cause dangerous amounts of fast ion losses, as was seen in TFTR.

none,; Budny, Robert; Yuan, Xingqiu

2014-02-26T23:59:59.000Z

180

INTEGRATING GEOLOGIC AND GEOPHYSICAL DATA THROUGH  

E-Print Network [OSTI]

INTEGRATING GEOLOGIC AND GEOPHYSICAL DATA THROUGH ADVANCED CONSTRAINED INVERSIONS by Peter George framework (i.e. minimization of an objective function). I developed several methods to reach this goal constraints to the inverse problem. Lastly, I developed an iterative procedure for cooperatively inverting

Oldenburg, Douglas W.

Note: This page contains sample records for the topic "integrated iterative solution" 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

Neutronics Experiments Using Small Partial Mockups of the ITER Test Blanket Module with a Solid Breeder  

SciTech Connect (OSTI)

In order to evaluate the impacts of the incident neutron spectrum and the tungsten armor on the tritium production, integral experiments have been performed with small partial mockups relevant to the ITER test blanket module using DT neutrons at FNS of JAERI. The Monte Carlo calculation results for the integrated tritium productions agree well with the experimental data within 2 and 11 % for the mockups without the armor in the experiments without and with the neutron reflector, respectively. It is clarified that the tritium production can be very accurately predicted in the experiment without the reflector. In the mockups with the 12.6 and 25.2 mm thick tungsten armors, it is experimentally clarified that the integrated tritium productions are reduced by 3 and 6 % relative to the case without the armor, respectively.

Sato, Satoshi; Verzilov, Yury; Nakao, Makoto; Ochiai, Kentaro; Wada, Masayuki; Nishitani, Takeo [Japan Atomic Energy Research Institute (Japan)

2005-05-15T23:59:59.000Z

182

Proving termination by policy iteration Damien Masse1  

E-Print Network [OSTI]

NSAD 2012 Proving termination by policy iteration Damien Masse1 Lab-Sticc, UMR 6285 UBO conditions for program termination. Restricting ourselves to affine programs and the abstract domain. Keywords: Abstract interpretation, policy iteration, template constraint matrices, termination analysis. 1

Paris-Sud XI, Universit de

183

October 6, 1997 ITER L-Mode Con nement Database  

E-Print Network [OSTI]

October 6, 1997 ITER L-Mode Con nement Database S.M. Kaye and the ITER Con nement Database Working Group Abstract This paper describes the content of an L-mode database that has been compiled with data, and Tore-Supra. The database consists of a total of 2938 entries, 1881 of which are in the L-phase while

184

A Turbo Iteration Algorithm In 16QAM Hierarchical Modulation  

E-Print Network [OSTI]

A Turbo Iteration Algorithm In 16QAM Hierarchical Modulation Xu Zhe Electric and Information on the turbo code, OFDM modulation and 16QAM hierarchical modulation to increase the flexibility, and in the high SNR, it can also gain a high BER performance of low priority bit stream. Keywords- turbo iteration

Paris-Sud XI, Université de

185

Properties of Iterated Multiple Belief Revision Dongmo Zhang  

E-Print Network [OSTI]

in the community of belief revision[2][5][9][10][13][17]. The major concern in the research is the reducibilityProperties of Iterated Multiple Belief Revision Dongmo Zhang School of Computing and Information investigate the properties of iterated multiple belief revision. We examine several typical assumptions

Zhang, Dongmo

186

Iterated Belief Revision and Conditional Logic Laura Giordano  

E-Print Network [OSTI]

/01/2001; 17:22; p.1 #12; 2 well known Triviality Result [5], that claims that no signi#12;cant belief revisionIterated Belief Revision and Conditional Logic Laura Giordano DSTA - Universit#18;a del Piemonte a conditional logic called IBC to represent iterated belief revision systems. We propose a set of postulates

Torino, Università di

187

BLIND ITERATIVE RESTORATION OF IMAGES WITH SPATIALLY-VARYING BLUR  

E-Print Network [OSTI]

BLIND ITERATIVE RESTORATION OF IMAGES WITH SPATIALLY-VARYING BLUR John Bardsley Stuart Jefferies (PSF) by using a combination of methods including sectioning and phase diversity blind deconvolution whose PSFs are correlated and approximately spatially-invariant, and apply iterative blind deconvolution

Bardsley, John

188

Nested Loop Algorithm for Parallel Model Based Iterative Reconstruction  

E-Print Network [OSTI]

Nested Loop Algorithm for Parallel Model Based Iterative Reconstruction Zhou Yu, Lin Fu, Debashish. In this paper, we propose a fast converging simultaneous-update algorithm using a nested loop structure tomography, iterative reconstruction, nested loop, preconditioner. I. INTRODUCTION Recent applications

189

Recent progress on lower hybrid current drive and implications for ITER  

E-Print Network [OSTI]

The sustainment of steady-state plasmas in tokamaks requires efficient current drive systems. Lower Hybrid Current Drive (LHCD) is currently the most efficient method to generate a continuous additional off-axis toroidal plasma current as well as reduce the poloidal flux consumption during the plasma current ramp-up phase. The operation of the Tore Supra ITER-like LH launcher has demonstrated the capability to couple LH power at ITER-like power densities with very low reflected power during long pulses. In addition, the installation of eight 700kW/CW klystrons at the LH transmitter has allowed increasing the total LH power in long pulse scenarios. However, in order to achieve pure stationary LH sustained plasmas, some R\\&D are needed to increase the reliability of all the systems and codes, from the RF sources to the plasma scenario prediction. The CEA/IRFM is addressing some of these issues by leading a R\\&D program towards an ITER LH system and by the validation of an integrated LH modeling suite of...

Hillairet, Julien; Goniche, M; Achard, J; Armitano, A; Beckett, B; Belo, J; Berger-By, G; Corbel, E; Delpech, L; Decker, J; Dumont, R; Guilhem, D; Kazarian, F; Litaudon, X; Magne, R; Marfisi, L; Mollard, P; Namkung, W; Nilsson, E; Park, S; Peysson, Y; Preynas, M; Sharma, P K; Prou, M

2015-01-01T23:59:59.000Z

190

Iterative Algorithms for Ptychographic Phase Retrieval  

E-Print Network [OSTI]

Steihaug. T h e conjugate gradient method and trust regionsthe nonlinear conjugate gradient method to find the solutionPolak-Ribiere conjugate gradient method. There are a variety

Yang, Chao

2011-01-01T23:59:59.000Z

191

Financing Turnkey Efficiency Solutions for Small Buildings and...  

Energy Savers [EERE]

Financing Turnkey Efficiency Solutions for Small Buildings and Small Portfolios Commercial Buildings Integration Project for the 2013 Building Technologies Office's...

192

ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION  

SciTech Connect (OSTI)

An insulation system for ITER Central Solenoid must have sufficiently high electrical and structural strength. Design efforts to bring stresses in the turn and layer insulation within allowables failed. It turned out to be impossible to eliminate high local tensile stresses in the winding pack. When high local stresses can not be designed out, the qualification procedure requires verification of the acceptable structural and electrical strength by testing. We built two 4 x 4 arrays of the conductor jacket with two options of the CS insulation and subjected the arrays to 1.2 million compressive cycles at 60 MPa and at 76 K. Such conditions simulated stresses in the CS insulation. We performed voltage withstand tests and after end of cycling we measured the breakdown voltages between in the arrays. After that we dissectioned the arrays and studied micro cracks in the insulation. We report details of the specimens preparation, test procedures and test results.

Martovetsky, N N; Mann, T L; Miller, J R; Freudenberg, K D; Reed, R P; Walsh, R P; McColskey, J D; Evans, D

2009-06-11T23:59:59.000Z

193

ITER L-Mode Confinement Database  

SciTech Connect (OSTI)

This paper describes the content of an L-mode database that has been compiled with data from Alcator C-Mod, ASDEX, DIII, DIII-D, FTU, JET, JFT-2M, JT-60, PBX-M, PDX, T-10, TEXTOR, TFTR, and Tore-Supra. The database consists of a total of 2938 entries, 1881 of which are in the L-phase while 922 are ohmically heated (OH) only. Each entry contains up to 95 descriptive parameters, including global and kinetic information, machine conditioning, and configuration. The paper presents a description of the database and the variables contained therein, and it also presents global and thermal scalings along with predictions for ITER. The L-mode thermal confinement time scaling was determined from a subset of 1312 entries for which the thermal confinement time scaling was provided.

S.M. Kaye and the ITER Confinement Database Working Group

1997-10-01T23:59:59.000Z

194

ITER Central Solenoid Coil Insulation Qualification  

SciTech Connect (OSTI)

An insulation system for ITER Central Solenoid must have sufficiently high electrical and structural strength. Design efforts to bring stresses in the turn and layer insulation within allowables failed. It turned out to be impossible to eliminate high local tensile stresses in the winding pack. When high local stresses can not be designed out, the qualification procedure requires verification of the acceptable structural and electrical strength by testing. We built two 4x4 arrays of the conductor jacket with two options of the CS insulation and subjected the arrays to 1.2 million compressive cycles at 60 MPa and at 76 K. Such conditions simulated stresses in the CS insulation. We performed voltage withstand tests and after end of cycling we measured the breakdown voltages between in the arrays. After that we dissectioned the arrays and studied micro cracks in the insulation. We report details of the specimens preparation, test procedures and test results.

Martovetsky, Nicolai N [ORNL] [ORNL; Mann Jr, Thomas Latta [ORNL] [ORNL; Miller, John L [ORNL] [ORNL; Freudenberg, Kevin D [ORNL] [ORNL; Reed, Richard P [Cryogenic Materials, Inc.] [Cryogenic Materials, Inc.; Walsh, Robert P [Florida State University] [Florida State University; McColskey, J D [National Institute of Standards and Technology (NIST), Boulder] [National Institute of Standards and Technology (NIST), Boulder; Evans, D [Advanced Cryogenic Materials] [Advanced Cryogenic Materials

2010-01-01T23:59:59.000Z

195

Alpha Heating in ITER L-mode and H-mode Plasma  

SciTech Connect (OSTI)

There are many uses of predictions of ITER plasma performance. One is assessing requirements of different plasma regimes. For instance, what current drive and control are needed for steady state. The heating, current drive, and torque systems planned for initial DT operation are negative ion neutral beam injection (NB), ion cyclotron resonance (IC), and electron cyclotron resonance (EC). Which combinations of heating are optimal. What are benefits of the torques, current drive, and fueling using NB. What are the shine-through power and optimum voltage for the NB? What are optimal locations and aiming of the EC launchers? Another application is nuclear licensing (e.g. System integrity, how many neutrons).

R.V. Budny

2011-07-18T23:59:59.000Z

196

Nuclear Forensic Inferences Using Iterative Multidimensional Statistics  

SciTech Connect (OSTI)

Nuclear forensics involves the analysis of interdicted nuclear material for specific material characteristics (referred to as 'signatures') that imply specific geographical locations, production processes, culprit intentions, etc. Predictive signatures rely on expert knowledge of physics, chemistry, and engineering to develop inferences from these material characteristics. Comparative signatures, on the other hand, rely on comparison of the material characteristics of the interdicted sample (the 'questioned sample' in FBI parlance) with those of a set of known samples. In the ideal case, the set of known samples would be a comprehensive nuclear forensics database, a database which does not currently exist. In fact, our ability to analyze interdicted samples and produce an extensive list of precise materials characteristics far exceeds our ability to interpret the results. Therefore, as we seek to develop the extensive databases necessary for nuclear forensics, we must also develop the methods necessary to produce the necessary inferences from comparison of our analytical results with these large, multidimensional sets of data. In the work reported here, we used a large, multidimensional dataset of results from quality control analyses of uranium ore concentrate (UOC, sometimes called 'yellowcake'). We have found that traditional multidimensional techniques, such as principal components analysis (PCA), are especially useful for understanding such datasets and drawing relevant conclusions. In particular, we have developed an iterative partial least squares-discriminant analysis (PLS-DA) procedure that has proven especially adept at identifying the production location of unknown UOC samples. By removing classes which fell far outside the initial decision boundary, and then rebuilding the PLS-DA model, we have consistently produced better and more definitive attributions than with a single pass classification approach. Performance of the iterative PLS-DA method compared favorably to that of classification and regression tree (CART) and k nearest neighbor (KNN) algorithms, with the best combination of accuracy and robustness, as tested by classifying samples measured independently in our laboratories against the vendor QC based reference set.

Robel, M; Kristo, M J; Heller, M A

2009-06-09T23:59:59.000Z

197

SPARSE REPRESENTATIONS WITH DATA FIDELITY TERM VIA AN ITERATIVELY REWEIGHTED LEAST SQUARES ALGORITHM  

SciTech Connect (OSTI)

Basis Pursuit and Basis Pursuit Denoising, well established techniques for computing sparse representations, minimize an {ell}{sup 2} data fidelity term subject to an {ell}{sup 1} sparsity constraint or regularization term on the solution by mapping the problem to a linear or quadratic program. Basis Pursuit Denoising with an {ell}{sup 1} data fidelity term has recently been proposed, also implemented via a mapping to a linear program. They introduce an alternative approach via an iteratively Reweighted Least Squares algorithm, providing greater flexibility in the choice of data fidelity term norm, and computational advantages in certain circumstances.

WOHLBERG, BRENDT [Los Alamos National Laboratory; RODRIGUEZ, PAUL [Los Alamos National Laboratory

2007-01-08T23:59:59.000Z

198

Concept development for the ITER equatorial port visible/infrared wide angle viewing system  

SciTech Connect (OSTI)

The ITER equatorial port visible/infrared wide angle viewing system concept is developed from the measurement requirements. The proposed solution situates 4 viewing systems in the equatorial ports 3, 9, 12, and 17 with 4 views each (looking at the upper target, the inner divertor, and tangentially left and right). This gives sufficient coverage. The spatial resolution of the divertor system is 2 times higher than the other views. For compensation of vacuum-vessel movements, an optical hinge concept is proposed. Compactness and low neutron streaming is achieved by orienting port plug doglegs horizontally. Calibration methods, risks, and R and D topics are outlined.

Reichle, R.; Beaumont, B.; Boilson, D.; Bouhamou, R.; Direz, M.-F.; Encheva, A.; Henderson, M.; Kazarian, F.; Lamalle, Ph.; Lisgo, S.; Mitteau, R.; Patel, K. M.; Pitcher, C. S.; Pitts, R. A.; Prakash, A.; Raffray, R.; Schunke, B.; Snipes, J.; Diaz, A. Suarez; Udintsev, V. S. [ITER Organization, Route de Vinon-sur-Verdon, 13115 St Paul-lez-Durance (France); and others

2012-10-15T23:59:59.000Z

199

Intense Diagnostic Neutral Beam for ITER LANL-Park and Wurden Intense Diagnostic Neutral Beam for ITER  

E-Print Network [OSTI]

for ITER Jaeyoung Park and Glen A. Wurden Plasma Physics Group (P-24) Los Alamos National Laboratory LosIntense Diagnostic Neutral Beam for ITER LANL-Park and Wurden 2 Intense Diagnostic Neutral Beam Alamos, NM 87545 Executive Summary An intense pulsed diagnostic neutral beam (IDNB) is proposed to enable

200

The development of iterative and cascade methods for the rapid synthesis of ladder polyether natural products  

E-Print Network [OSTI]

I. The Development of Methods for the Iterative Synthesis of Polytetrahydropyrans An iterative method comprising chain homologation, epoxidation, 6-endo cyclization, and protiodesilylation was developed. Notable achievements ...

Heffron, Timothy Paul

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Iterative model-building, structure refinement, and density modification with the PHENIX AutoBuild Wizard  

E-Print Network [OSTI]

Iterative model-building, structure refinement, and densitytool for iterative model- building, structure refinement andusing RESOLVE or TEXTAL model- building, RESOLVE statistical

Terwilliger, T. C.; Los Alamos National Laboratory, Mailstop M888, Los Alamos, NM 87545, USA; Lawrence Berkeley National Laboratory, One Cyclotron Road, Building 64R0121, Berkeley, CA 94720, USA; Department of Haematology, University of Cambridge, Cambridge CB2 0XY, England

2008-01-01T23:59:59.000Z

202

A E Costley, US/ITER Town meeting, San Diego, 22 April 2004 N 55 IP 57 04-04-30 F 1 International Thermonuclear Experimental Reactor  

E-Print Network [OSTI]

for the integration have been developed and the interfaces with the re to their anticipated operational role (machine protection, control and physics studies). About 45 parameters in total). These are included in the highest level ITER design requirement document (DRG 1). · For each parameter

203

Criticality and axial offset searches based on the integrated neutron balance approach  

SciTech Connect (OSTI)

Criticality and axial offset (AO) searches are key features in the simulation of plant operation procedures. Typically, the dedicated algorithms consist of either a Newton method or a secant method that features the successive computation of difference quotients to be used as derivatives. Within this context, computational robustness and efficiency are of paramount importance. This applies in particular to when the variations imposed during the search are spatially heterogeneous, such as in the case of tuning control rod positions for achieving target AO. In order to optimize this kind of search capability in AREVA NP's reactor code ARTEMIS in accordance with this design principle, a generalized approach has been implemented that harmonizes very well numerically with the overall multi-physics iterative solution process. As embedded in the latter, the new neutronic integral re-balancing approach is defined through periodic whole-core space-energy integrations of the principal terms in the core-integrated process-rate balance terms (i.e. neutron absorption, production and leakage). This procedure yields sequences of single zero-dimensional equations from which the chosen tuning parameters can be solved directly in dependence of the imposed (and systematically fixed) values for the response quantities k{sub eff} and/or AO. The converged result of the iteration sequence of successively obtained search parameter values is final in terms of being fully consistent with the entire set of multi-physics equations while enabling the accurate fulfillment of the target response value. The k etc and AO searches can be pursued simultaneously. Judging from the results of pursued verifications, the neutronic integral re-balancing approach fulfils the above-mentioned expectations convincingly. Specific verification examples are presented, such as the determination of the insertion depth of a critical control bank, a double search on target criticality and target AO by adjusting the boron concentration and the position of a control bank, and a critical power search during reactor cycle stretch out. (authors)

Dall'Osso, A. [AREVA NP Tour AREVA, 92084 Paris La Defense Cedex (France); Van Geemert, R. [AREVA GmbH, Paul Gossenstrasse 100, D-91058 Erlangen (Germany)

2013-07-01T23:59:59.000Z

204

Design of the ITER First Wall and Blanket A. Rene Raffray  

E-Print Network [OSTI]

Design of the ITER First Wall and Blanket A. Rene Raffray TKM, Internal Components Division ITER-mail: mario.merola@iter.org Abstract--This paper summarizes the status of the ITER blanket system design and describes some of the key R&D activities in support of the design with the goal of starting procurement

Raffray, A. René

205

Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials  

E-Print Network [OSTI]

Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials, Russian Federation Abstract Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from the first day of H

Abdou, Mohamed

206

ITER: The International Thermonuclear Experimental Reactor and the Nuclear Weapons Proliferation  

E-Print Network [OSTI]

militarytechnical reasons and implications of the very probable siting of ITER (the International Thermonuclear

Andr Gsponer; Jean-pierre Hurni

2004-01-01T23:59:59.000Z

207

Inside ITER seminar on History of Fusion Page 1 History of Fusion  

E-Print Network [OSTI]

Union thermonuclear explosion 400kT #12;Inside ITER seminar on History of Fusion Page 4 Big IvanInside ITER seminar on History of Fusion Page 1 History of Fusion Personal view V. Chuyanov 9 July 2009 Special thanks to ITER Communication Division. #12;Inside ITER seminar on History of Fusion Page 2

208

Numerical simulations of welds of thick steel pieces of interest for the thermonuclear fusion ITER machine  

E-Print Network [OSTI]

Numerical simulations of welds of thick steel pieces of interest for the thermonuclear fusion ITER machine

Carmignani, B

2005-01-01T23:59:59.000Z

209

Dale M. Meade MFE Plenary Session on ITER Costs  

E-Print Network [OSTI]

FIRE Lighting the Way to Fusion http://fire.pppl.gov A Comparison of Unit Costs for FIRE and ITER #12;A Comparison of Unit Costs for FIRE and ITER · A simple rule of thumb for comparing costs of similar devices.14m) Weight FIREITERPCAS 0.25 $M/tonne 0.88 $M/tonne ARIES-RS (5.5m) First of a Kind #12;Comparison

210

Visible and Infrared Optical Design for the ITER Upper Ports  

SciTech Connect (OSTI)

This document contains the results of an optical design scoping study of visible-light and infrared optics for the ITER upper ports, performed by LLNL under contract for the US ITER Project Office. ITER is an international collaboration to build a large fusion energy tokamak with a goal of demonstrating net fusion power for pulses much longer than the energy confinement time. At the time of this report, six of the ITER upper ports are planned to each to contain a camera system for recording visible and infrared light, as well as other diagnostics. the performance specifications for the temporal and spatial resolution of this system are shown in the Section II, Functional Specifications. They acknowledge a debt to Y. Corre and co-authors of the CEA Cadarache report ''ITER wide-angle viewing and thermographic and visible system''. Several of the concepts used in this design are derived from that CEA report. The infrared spatial resolution for optics of this design is diffraction-limited by the size of the entrance aperture, at lower resolution than listed in the ITER diagnostic specifications. The size of the entrance aperture is a trade-off between spatial resolution, optics size in the port, and the location of relay optics. The signal-to-noise ratio allows operation at the specified time resolutions.

Lasnier, C; Seppala, L; Morris, K; Groth, M; Fenstermacher, M; Allen, S; Synakowski, E; Ortiz, J

2007-03-01T23:59:59.000Z

211

Numerical solution of the inversion integral  

E-Print Network [OSTI]

~ ~ ~ ~ ~ e e ~ ~ ~ ~ e o ~ ~ e Q ka ~ 14LIAQlg e ~ a ~ e a ~ e a a a e 6$ Se all% D18PSR a ~ ~ ~ ~ e ~ a e o ~ o e ~ a e C o BC8h8 CQmplft04 RS SU14 8 e e e ~ e ~ e e e e e a 93 De R. blLOgZSD2p o a ~ ~ a e e e a e o o e a a lj-9 QHAP5R I QE...

Bradford, Halley Oren

1964-01-01T23:59:59.000Z

212

Integrated Energy Solutions LLC | 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 No revision hasInformation Earth's Heat JumpInc Place: Eden Prairie,InfieldInstalledResearch CaltechIntecArea,LLC

213

Application of functional transformations in the solution of steady-state distillation problems  

E-Print Network [OSTI]

of Criteria Calculational Procedure and Discussion 117 118 121 B QUADRATIC CONVERGENCE OF ITERATES USING FUNCTIONIAL TRANSFORMATION IMBEDDED IN NEWTON"S MLTHOD 127 C FORMULATION OF MATHEMATICAL MODELS USED IN THE EXAMPI. E PROBLEMS Problem 1 ? A... 7). Comparison of initial (iterate) vapor rate of nCcH?at each stage ivith the steady-state solution vapor rate of nCcHis at each stage for Lx =50 lb-moles/min (Examp)e 7). 30 54 55 10. ]2. 13. Comparison of initial (iterate) temperature...

McLaughlin, Blaise Edward

2012-06-07T23:59:59.000Z

214

Improving DWF Simulations: the Force Gradient Integrator and the Mbius Accelerated DWF Solver  

E-Print Network [OSTI]

We have implemented a variant of the force gradient integrator proposed by Kennedy et.al. and are using it in our production 2+1 flavor DWF simulations with pion masses of 180 MeV in (4.5fm)3 volumes. We find modest speed-ups (\\sim 20%) from using the force gradient integrator, compared to our previously used Omelyan integrator. On other ensembles, primarily finite temperature 2+1 flavor DWF QCD, we have extensively tuned the Hasenbusch preconditioning masses and achieved speed-ups of 2-3x. Here we have also switched to the force gradient integrator, but this change has not had any impact on the speed. We also report on an improved solver for DWF, which uses M\\"obius fermions, with a smaller fifth dimension than the original DWF fermions, as an intermediate step in the generation of solutions of the Dirac equation. This approach cuts the number of effective Dirac applications by approximately a factor of 2 when the conjugate gradient iteration count is large.

Hantao Yin; Robert D. Mawhinney

2011-11-21T23:59:59.000Z

215

Robust parallel iterative solvers for linear and least-squares problems, Final Technical Report  

SciTech Connect (OSTI)

The primary goal of this project is to study and develop robust iterative methods for solving linear systems of equations and least squares systems. The focus of the Minnesota team is on algorithms development, robustness issues, and on tests and validation of the methods on realistic problems. 1. The project begun with an investigation on how to practically update a preconditioner obtained from an ILU-type factorization, when the coefficient matrix changes. 2. We investigated strategies to improve robustness in parallel preconditioners in a specific case of a PDE with discontinuous coefficients. 3. We explored ways to adapt standard preconditioners for solving linear systems arising from the Helmholtz equation. These are often difficult linear systems to solve by iterative methods. 4. We have also worked on purely theoretical issues related to the analysis of Krylov subspace methods for linear systems. 5. We developed an effective strategy for performing ILU factorizations for the case when the matrix is highly indefinite. The strategy uses shifting in some optimal way. The method was extended to the solution of Helmholtz equations by using complex shifts, yielding very good results in many cases. 6. We addressed the difficult problem of preconditioning sparse systems of equations on GPUs. 7. A by-product of the above work is a software package consisting of an iterative solver library for GPUs based on CUDA. This was made publicly available. It was the first such library that offers complete iterative solvers for GPUs. 8. We considered another form of ILU which blends coarsening techniques from Multigrid with algebraic multilevel methods. 9. We have released a new version on our parallel solver - called pARMS [new version is version 3]. As part of this we have tested the code in complex settings - including the solution of Maxwell and Helmholtz equations and for a problem of crystal growth.10. As an application of polynomial preconditioning we considered the problem of evaluating f(A)v which arises in statistical sampling. 11. As an application to the methods we developed, we tackled the problem of computing the diagonal of the inverse of a matrix. This arises in statistical applications as well as in many applications in physics. We explored probing methods as well as domain-decomposition type methods. 12. A collaboration with researchers from Toulouse, France, considered the important problem of computing the Schur complement in a domain-decomposition approach. 13. We explored new ways of preconditioning linear systems, based on low-rank approximations.

Saad, Yousef

2014-01-16T23:59:59.000Z

216

Perturbation Resilience and Superiorization of Iterative Algorithms  

E-Print Network [OSTI]

shown to be the case for various projection algorithms for solving the consistent ... Computational tractability with limited computing resources is a major barrier for ..... Data were collected by calculating line integrals across the digitized image for 82 ... tomography would be considered a variant of the algebraic reconstruction...

2010-04-20T23:59:59.000Z

217

DIII-D Research in Support of ITER  

SciTech Connect (OSTI)

DIII-D research is providing key information for the design and operation of ITER. Discharges that simulate ITER operating scenarios in conventional H-mode, advanced inductive, hybrid, and steady state regimes have achieved normalized performance consistent with ITER's goals for fusion performance. Stationary discharges with high {beta}{sub N} and 90% noninductive current that project to Q=5 in ITER have been sustained for a current relaxation time ({approx}2.5 s), and high-beta wall-stabilized discharges with fully non-inductive current drive have been sustained for more than one second. Detailed issues of plasma control have been addressed, including the development of a new large-bore startup scenario for ITER. A broad research program provides the physics basis for predicting the performance of ITER. Recent key results include the discovery that the L-H power threshold is reduced with low neutral beam torque, and the development of a successful model for prediction of the H-mode pedestal height in DIII-D. Research areas with the potential to improve ITER's performance include the demonstration of ELM-free 'QH-mode' discharges with both co and counter-injection, and validation of the predicted torque generated by static, non-axisymmetric magnetic fields. New diagnostics provide detailed benchmarking of turbulent transport codes and direct measurements of the anomalous transport of fast ions by Alfven instabilities. DIII-D research also contributes to the basis for reliable operation in ITER, through active control of the chief performance-limiting instabilities. Recently, ELM suppression with resonant magnetic perturbations has been demonstrated at collisionality similar to ITER's, while simultaneous stabilization of NTMs (by localized current drive) and RWMs (by magnetic feedback) has allowed stable operation at high beta and low rotation. In research aimed at improving the lifetime of material surfaces near the plasma, recent experiments have investigated several approaches to mitigation of disruptions, including injection of low-Z gas and low-Z pellets, and have shown the conditions that minimize core impurity accumulation during radiative divertor operation. Investigation of carbon erosion, transport, and co-deposition with hydrogenic species, and methods for the removal of co-deposits, will contribute to the physics basis for initial operation of ITER with a carbon divertor.

Strait, E

2008-10-14T23:59:59.000Z

218

Power Handling in ITER: Divertor and Blanket Design and R&D M. Merola 1), D. Loesser 2), R. Raffray 1) on behalf of the ITER Organization, ITER  

E-Print Network [OSTI]

the thermonuclear plasma and cover an area of about 850 m2 . The main function of the divertor is minimizing the thermonuclear plasma. One of the most technically challenging components of the ITER machine are plasma-facing components (PFCs), which directly face the thermonuclear plasma and cover an area of about 850 m2

Raffray, A. René

219

Project Management Plan Solution Stabilization  

SciTech Connect (OSTI)

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Solutions Stabilization subproject. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Integrated Project Management Plan (IPMP) for the Plutonium Finishing Plant Stabilization and Deactivation Project, HNF-3617. This project plan is the top-level definitive project management document for the PFP Solution Stabilization subproject. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Solution Stabilization subproject. Any deviations to the document must be authorized through the appropriate change control process.

SATO, P.K.

1999-08-31T23:59:59.000Z

220

Accelerated Lambda Iteration in Rapidly Expanding Envelopes  

E-Print Network [OSTI]

We discuss the current implementation of the ALI method into our HYDrodynamical RAdiation(HYDRA) code for rapidly expanding, low density envelopes commonly found in core collapse and thermonuclear supernovae, novae and WR stars. Due to the low densities, non-thermal excitation by high energy photons (e.g. by radioactive decays) and the time dependence of the problem, large departures from LTE are common throughout the envelope even at large optical depths. ALI is instrumental for both the coupling of the statistical equations and the hydrodynamical equations with the radiation transport (RT). We employ several concepts to improve the stability, and convergence rate/control including the concept of leading elements, the use of net rates, level locking, reconstruction of global photon redistribution functions, equivalent-2-level approach, and predictive corrector methods. For appropriate conditions, the solution of the time-dependent rate equations can be reduced to the time-independent problem plus an analytic solution of an ODE For the 3-D problem, we solve the radiation transport via the moment equations. To construct the Eddington tensor elements, we use a Monte Carlo scheme to determine the deviation of the solution of the RT equation from the diffusion approximation (ALI of second kind). At the example of a thermonuclear supernova (SN99by),we show an analysis of light light curves, flux and polarization spectra and discuss the limitations of our approach.

P. Hoeflich

2002-07-04T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Integrated Solar Panel Antennas for Cube Satellites.  

E-Print Network [OSTI]

??This thesis work presents an innovative solution for small satellite antennas by integrating slot antennas and solar cells on the same panel to save small (more)

Mahmoud, Mahmoud N.

2010-01-01T23:59:59.000Z

222

Description of the prototype diagnostic residual gas analyzer for ITER  

SciTech Connect (OSTI)

The diagnostic residual gas analyzer (DRGA) system to be used during ITER tokamak operation is being designed at Oak Ridge National Laboratory to measure fuel ratios (deuterium and tritium), fusion ash (helium), and impurities in the plasma. The eventual purpose of this instrument is for machine protection, basic control, and physics on ITER. Prototyping is ongoing to optimize the hardware setup and measurement capabilities. The DRGA prototype is comprised of a vacuum system and measurement technologies that will overlap to meet ITER measurement requirements. Three technologies included in this diagnostic are a quadrupole mass spectrometer, an ion trap mass spectrometer, and an optical penning gauge that are designed to document relative and absolute gas concentrations.

Younkin, T. R., E-mail: tyounkin@gatech.edu [Fusion and Materials for Nuclear Systems Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States); Georgia Institute of Technology, Woodruff School of Mechanical Engineering Nuclear and Radiological Engineering Program, Atlanta, Georgia 30332 (United States); Biewer, T. M.; Klepper, C. C.; Marcus, C. [Fusion and Materials for Nuclear Systems Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States)

2014-11-15T23:59:59.000Z

223

Diamond neutral particle spectrometer for fusion reactor ITER  

SciTech Connect (OSTI)

A compact diamond neutral particle spectrometer with digital signal processing has been developed for fast charge-exchange atoms and neutrons measurements at ITER fusion reactor conditions. This spectrometer will play supplementary role for Neutral Particle Analyzer providing 10 ms time and 30 keV energy resolutions for fast particle spectra in non-tritium ITER phase. These data will also be implemented for independent studies of fast ions distribution function evolution in various plasma scenarios with the formation of a single fraction of high-energy ions. In tritium ITER phase the DNPS will measure 14 MeV neutrons spectra. The spectrometer with digital signal processing can operate at peak counting rates reaching a value of 10{sup 6} cps. Diamond neutral particle spectrometer is applicable to future fusion reactors due to its high radiation hardness, fast response and high energy resolution.

Krasilnikov, V.; Amosov, V.; Kaschuck, Yu.; Skopintsev, D. [Institution PROJECT CENTER ITER, 1, Akademik Kurchatov Sq., Moscow (Russian Federation)

2014-08-21T23:59:59.000Z

224

STELLOPT Modeling of the 3D Diagnostic Response in ITER  

SciTech Connect (OSTI)

The ITER three dimensional diagnostic response to an n=3 resonant magnetic perturbation is modeled using the STELLOPT code. The in-vessel coils apply a resonant magnetic perturbation (RMP) fi eld which generates a 4 cm edge displacement from axisymmetry as modeled by the VMEC 3D equilibrium code. Forward modeling of flux loop and magnetic probe response with the DIAGNO code indicates up to 20 % changes in measured plasma signals. Simulated LIDAR measurements of electron temperature indicate 2 cm shifts on the low field side of the plasma. This suggests that the ITER diagnostic will be able to diagnose the 3D structure of the equilibria.

Lazerson, Samuel A

2013-05-07T23:59:59.000Z

225

Iterative methods for solving nonlinear problems of nuclear reactor criticality  

SciTech Connect (OSTI)

The paper presents iterative methods for calculating the neutron flux distribution in nonlinear problems of nuclear reactor criticality. Algorithms for solving equations for variations in the neutron flux are considered. Convergence of the iterative processes is studied for two nonlinear problems in which macroscopic interaction cross sections are functionals of the spatial neutron distribution. In the first problem, the neutron flux distribution depends on the water coolant density, and in the second one, it depends on the fuel temperature. Simple relationships connecting the vapor content and the temperature with the neutron flux are used.

Kuz'min, A. M., E-mail: mephi.kam@mail.ru [National Research Nuclear University MEPhI (Russian Federation)

2012-12-15T23:59:59.000Z

226

Iterative reconstruction of the detector response for medical gamma cameras  

E-Print Network [OSTI]

Statistical event reconstruction techniques can give better results for gamma cameras than the traditional centroid method. However, implementation of such techniques requires detailed knowledge of the PMT light response functions. Here we describe an iterative technique which allows to obtain the response functions from flood irradiation data without imposing strict requirements on the spatial uniformity of the event distribution. A successful application of the technique for medical gamma cameras is demonstrated using both simulated and experimental data. We show that this technique can be used for monitoring of the photomultiplier gain variations. An implementation of the iterative reconstruction technique capable of operating in real-time is also presented.

Morozov, A; Alves, F; Domingos, V; Martins, R; Neves, F; Chepel, V

2015-01-01T23:59:59.000Z

227

An Empirical Study on Integrating Agile and User Centered Design  

E-Print Network [OSTI]

challenges. Agile Software Development Processes; User Centred Design; Agile User Centred Design Integration 1. INTRODUCTION Agile methods are lightweight software development methods that tackle perceived. They are iterative and are used to develop software incrementally. Different Agile processes implement these ideas

Cairns, Paul

228

ISIS++Reference Guide (Iterative Scalable Implicit Solver in C++) Version 1.1  

SciTech Connect (OSTI)

ISIS++ (Iterative Scalable Implicit Solver in C++) Version 1.1 is a portable, object-oriented framework for solving sparse linear systems of equations. It includes a collection of Krylov solution methods and preconditioners, as well as both uni-processor (serial) and multi-processor (scalable) matrix and vector classes. Though it was developed to solve systems of equations originating from large-scale, 3-D, finite element analyses, it has application in many other fields. This document supersedes the ISIS++ V1.0 Reference Guide, defines the V1. 1 interface specification, and includes the necessary instructions for building and running ISIS++ v 1.1 on Unix platforms. The interface is presented in annotated header format, along with background on design and implementation considerations. A finite difference modeling example problem is included to demonstrate the overall setup and use.

Alan B. Williams; Benjamin A. Allan; Kyran D. Mish; Robert L. Clay

1999-04-01T23:59:59.000Z

229

Brussels advocates a lone rider for ITER 09/22/2004 Edition  

E-Print Network [OSTI]

can advance alone to establish the thermonuclear reactor experimental ITER in Cadarache. France in the construction of the future experimental thermonuclear reactor ITER, if Brussels does not manage to convince

230

Perspectives on US program support of FNSF and ITER in coming decade  

E-Print Network [OSTI]

-pulse PMI, stellarator) U.S. Burning Plasma Organization could also expand beyond ITER to incorporate FNSP facility support a staged approach? (PMI FNSF CTF Pilot?) Which ITER physics and technology can

231

Brussels, 13 May 2003 Europe moves into position to host ITER  

E-Print Network [OSTI]

by the EU on the agreement on the construction, operation and decommissioning of ITER. For further://www.iter.org/ #12;3 ANNEX What is energy from nuclear fusion? Research in the field of fusion has been going

232

Iterative finite-difference solution analysis of acoustic wave equation in the Laplace-Fourier domain  

E-Print Network [OSTI]

R. , 1992, Conjugate gradient type methods for linearthis case, a conjugate gradient (CG) method can also be theE. Stiefel, 1952, Methods of conjugate gradients for solving

Um, E.S.

2013-01-01T23:59:59.000Z

233

An iterative technique for approximating solutions to certain differential equations by truncated Legendre series  

E-Print Network [OSTI]

in 3. 18. i, n+1 i, n -7 Fair results, functional values. of at most 10, were obtained by combining ordinary scanning and Stirling's inverse interpolation for [5] mula . The scan increment equaled . 001. The points about the changes in sign gave a... basis for the difference table used in Stirling's formula. Stirling, 's formula states f(a+xw) = f(a) + ? [ hf(a) + A(a-w)] + ? 6 f (a-w) + ~ [ 6'f(a-w) + 6'f(a-2w) ] 12 &' f(a-2 ) + 24 Since a + xw is to be a root, f(a + xw) must equal zero...

Heckrotte, Robert Platt

1964-01-01T23:59:59.000Z

234

Iteration Method for the Solution of the Eigenvalue Problem of Linear Differential and  

E-Print Network [OSTI]

memories and limited computational capabilities. The SWAC, for instance, the NBS Western Automatic Computer

235

An Iterative Aggregation/Disaggregation Approach for the Solution of a Mixed Integer Nonlinear Oilfield  

E-Print Network [OSTI]

Oilfield Infrastructure Planning Model Susara A. van den Heever* and Ignacio E. Grossmann** Department of Chemical Engineering, Carnegie Mellon University Pittsburgh, PA, 15213 August 1999 Keywords Oilfield planning, MINLP, aggregation, decomposition Abstract A multiperiod MINLP model for offshore oilfield

Grossmann, Ignacio E.

236

A Transport Synthetic Acceleration method for transport iterations  

E-Print Network [OSTI]

that discretization enhances TSA performance. We then propose to implement a Conjugate Gradient method on the low-order problem, to use a crude quadrature set in the low-order problem and to set the number of low-order iterations per transport sweep to a finite value...

Ramone, Gilles Lionel

1996-01-01T23:59:59.000Z

237

Sabina Griffith Email: Sabina.Griffith@iter.org  

E-Print Network [OSTI]

Energy Agency (IAEA). In recognition of his life-long contribution to ITER, a moment of silence was approved at the extraordinary IC on July 28, 2010. This report included a new strategy for cost savings with representatives of the local communities, were invited to celebrate the official start of construction

238

Industrial opportunities on the International Thermonuclear Experimental Reactor (ITER) project  

SciTech Connect (OSTI)

Industry has been a long-term contributor to the magnetic fusion program, playing a variety of important roles over the years. Manufacturing firms, engineering-construction companies, and the electric utility industry should all be regarded as legitimate stakeholders in the fusion energy program. In a program focused primarily on energy production, industry`s future roles should follow in a natural way, leading to the commercialization of the technology. In a program focused primarily on science and technology, industry`s roles, in the near term, should be, in addition to operating existing research facilities, largely devoted to providing industrial support to the International Thermonuclear Experimental Reactor (ITER) Project. Industrial opportunities on the ITER Project will be guided by the amount of funding available to magnetic fusion generally, since ITER is funded as a component of that program. The ITER Project can conveniently be discussed in terms of its phases, namely, the present Engineering Design Activities (EDA) phase, and the future (as yet not approved) construction phase. 2 refs., 3 tabs.

Ellis, W.R. [Raytheon Engineers and Constructors, New York, NY (United States)

1996-12-01T23:59:59.000Z

239

Plans for U.S. Contributions to ITER  

E-Print Network [OSTI]

Project Management/Support International Team Support Magnets, Cooling Water, Blanket Shielding transmission lines 15% of port-based diagnostics 7 Central Solenoid windings 75% Cooling for divertor, vacuum components 8% of Toroidal Field conductor Steady-state power supplies #12;US ITER In-kind Hardware

240

Iterative Detection and Channel Estimation for Thomas Zemen  

E-Print Network [OSTI]

Iterative Detection and Channel Estimation for MC­CDMA Thomas Zemen Siemens Austria, PSE PRO RCD Erdbergerl?ande 26 A­1031 Vienna, Austria E­mail: thomas.zemen@siemens.com Joachim Wehinger, Christoph wireless communication systems. Their equalization is based on the fast Fourier transform, allowing

Müller, Ralf R.

Note: This page contains sample records for the topic "integrated iterative solution" 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

Iterative Detection and Channel Estimation for Thomas Zemen  

E-Print Network [OSTI]

Iterative Detection and Channel Estimation for MC-CDMA Thomas Zemen Siemens Austria, PSE PRO RCD Erdbergerl¨ande 26 A-1031 Vienna, Austria E-mail: thomas.zemen@siemens.com Joachim Wehinger, Christoph communication systems. Their equalization is based on the fast Fourier transform, allowing for an efficient

Zemen, Thomas

242

Enantioselective Total Synthesis of (-)-Pironetin: Iterative Aldol Reactions  

E-Print Network [OSTI]

titanium mediated iterative aldol reactions. Key steps in this synthesis include an acetal aldol reaction to establish the stereochemistry at C8 and C9, an acetate aldol reaction, and "Evans" syn aldol reaction and allylation methods,4m Enders and co-workers have disclosed a convergent total synthesis relying on RAMP

243

About the Limiting Behaviour of Iterated Robust Morphological Operators  

E-Print Network [OSTI]

Guanajuato, Gto., Mexico horebeek@cimat.mx 2 Freie Universitat Berlin, Institut fur Informatik Tacostr. 9 of morphological operators. To this purpose, we describe the implied iterative process by a discrete dynamical morphology is an important branch of non-linear signal process- ing. It has its roots in discrete geometry

Van Horebeek, Johan

244

ACCELERATED SPATIO-TEMPORAL WAVELET TRANSFORMS: AN ITERATIVE TRAJECTORY ESTIMATION. *  

E-Print Network [OSTI]

ACCELERATED SPATIO-TEMPORAL WAVELET TRANSFORMS: AN ITERATIVE TRAJECTORY ESTIMATION. * Jean accelerated motion in spatio-temporal discrete sig- nals. It is assumed that the digital signals of inter- est, they contain all the orders of acceleration. The purpose of this work is to estimate the trajectory

Wickerhauser, M. Victor

245

ACCELERATING REGULARIZED ITERATIVE CT RECONSTRUCTION ON COMMODITY GRAPHICS HARDWARE (GPU)  

E-Print Network [OSTI]

overhead to very moderate levels. Index Terms-- Iterative Reconstruction, Computed Tomography, Ordered Klaus Mueller Center for Visual Computing, Computer Science Department, Stony Brook University ABSTRACT) is the overall theme in many efforts to lower these exposures. Effective methods here include limiting either

Mueller, Klaus

246

Iteration Bounds for Finding the ?-Stationary Points for Structured ...  

E-Print Network [OSTI]

Oct 15, 2014 ... where ? = p/q with 1/p + 1/q = 1, then we prove that the new algorithms have an overall iteration complexity bound of O(1/?q) in finding an ?-stationary ...... + Mr,. (35) which means that if the perturbation is small, then the...

2014-10-15T23:59:59.000Z

247

Analysis of Disruption Scenarios Their Possible Mitigation in ITER  

E-Print Network [OSTI]

of the design) - Database analysis and physics guidelines for current quench rate and halo current - Simulation [MA/m2 ] Te=2eV Te=5eV Te=8eV ITER 9 MA 24 MA =0.72 m-3 #12;· Good measure for quench time

248

Joint News Release CHINA AND THE U.S. JOIN ITER NEGOTIATIONS  

E-Print Network [OSTI]

to the importance of ITER both in the Summit meeting with President Putin and in his speech at the Kurchatov

249

On the Strategy and Requirements for Neutronics Testing in ITER  

SciTech Connect (OSTI)

Neutronics testing is among the several types of fusion technology testing scheduled to be performed in ITER. The three ports assigned for testing will test several blanket concepts proposed by the various parties with test blanket modules (TBM) that utilize different breeders and coolants. Nevertheless, neutronics issues to be resolved in ITER-TBM are generic in nature and are important to each TBM type. Dedicated neutronics tests specifically address the accuracy involved in predicting key neutronics parameters such as tritium production rate, TPR, volumetric heating rate, induced activation and decay heat, and radiation damage to the reactor components. In this paper, we address some strategies for performing the neutronics tests. Tritium self-sufficiency cannot be confirmed by testing in ITER, however, the testing can provide valuable information regarding the main parameters needed to assess the feasibility of achieving tritium self-sufficiency. The paper also addresses the operational requirement (i.e. flux and fluence) as well as the geometrical requirement of the test module (i.e. minimum size) in order to have meaningful and useful tests. Measured neutronics data require high spatial resolution. This necessitates that the measured quantity be as flat as possible in the innermost locations inside the test module. This requirement has been confirmed in the present work based on results from two-dimensional calculations. The US and Japan solid breeder test blanket modules are placed inside half a port in ITER. The R-{theta} model used accounts for the presence of the ITER shielding blanket and the surrounding frame of the port.

Youssef, M.Z. [University of California-Los Angeles (United States); Sawan, M.E. [University of Wisconsin-Madison (United States)

2005-05-15T23:59:59.000Z

250

The Role of the Inner Product in Stopping Criteria for Conjugate Gradient Iterations  

E-Print Network [OSTI]

stopping criteria are derived for conjugate gradient (CG) methods, based on iteration parameters criteria, conjugate gradient methods, B-normal matrices 1 Introduction Unlike a direct method, an iterative1 The Role of the Inner Product in Stopping Criteria for Conjugate Gradient Iterations S. F. Ashby

Holst, Michael J.

251

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part I --Vertical wells  

E-Print Network [OSTI]

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part a new linear iterative refinement method to simulate nuclear borehole measurements accurately included in the in- tegral form of Boltzmann's equation. The linear iterative refine- ment method accounts

Torres-Verdín, Carlos

252

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT  

E-Print Network [OSTI]

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT S. ZHENG,a * R aimed at updating the ITER radioactive inventory assessment and assisting the waste manage- ment operations, and waste management processes and services. KEYWORDS: ITER, radioactive waste management

253

36.th EPS-CPP, June 30.th 2009 -Sofia ITER Session  

E-Print Network [OSTI]

36.th EPS-CPP, June 30.th 2009 - Sofia ITER Session F. Zonca - The FAST Proposal Associazione Tor Vergata Univ. of Catania #12;36.th EPS-CPP, June 30.th 2009 - Sofia ITER Session F. Zonca & construction #12;36.th EPS-CPP, June 30.th 2009 - Sofia ITER Session F. Zonca - The FAST Proposal Associazione

Zonca, Fulvio

254

TRITIUM ANALYSIS OF A WATER-COOLED SOLID BREEDER BLANKET FOR ITER*  

E-Print Network [OSTI]

TRITIUM ANALYSIS OF A WATER-COOLED SOLID BREEDER BLANKET FOR ITER* G. Federici, A.R. Raffray, M breeder blanket for the InternationalThermonuclearExperimental Reac- tor (ITER) obtained from the tritium-cooled solid breeder blanket has been proposed for the ITER tritium-producing blanket [2]. The breeder is oper

Abdou, Mohamed

255

FPA 30 year Anniversary Meeting, Washington, 2 December 2009 Slide 1 Status of ITER  

E-Print Network [OSTI]

FPA 30 year Anniversary Meeting, Washington, 2 December 2009 Slide 1 Status of ITER Fusion Power, 2 December 2009 Slide 2 Machine mass: 23350 t (cryostat + VV + magnets) - shielding, divertor Anniversary Meeting, Washington, 2 December 2009 Slide 3 TheThe Final ITER SiteFinal ITER Site Tokamak Hall

256

Annual Report of the EURATOM/CCFE Fusion Programme 2011/12 8 ITER Systems  

E-Print Network [OSTI]

and undertake leading or major roles in the design and R&D of ITER specialist systems (Heating, Diagnostics and Remote Handling etc.) in Europe; 8ITERSystems · Seek to play other design roles in R&D of ITER specialist its substantial role in the following key ITER systems: · Ion Cyclotron Resonance Heating (ICRH

257

ITER & Fusion Research Reference: MEMO/10/165 Date: 05/05/2010  

E-Print Network [OSTI]

ITER & Fusion Research Reference: MEMO/10/165 Date: 05/05/2010 HTML: EN PDF: EN DOC: EN MEMO/10/165 Brussels, 5th May 2010 ITER & Fusion Research The Commission has adopted a Communication to the European for International Thermonuclear Experimental Reactor (ITER), which have more than doubled the costs for Europe (to

258

Exact exchange potential evaluated from occupied Kohn-Sham and Hartree-Fock solutions  

SciTech Connect (OSTI)

The reported algorithm determines the exact exchange potential v{sub x} in an iterative way using energy shifts (ESs) and orbital shifts (OSs) obtained with finite-difference formulas from the solutions (occupied orbitals and their energies) of the Hartree-Fock-like equation and the Kohn-Sham-like equation, the former used for the initial approximation to v{sub x} and the latter for increments of ES and OS due to subsequent changes of v{sub x}. Thus, the need for solution of the differential equations for OSs, used by Kuemmel and Perdew [Phys. Rev. Lett. 90, 043004 (2003)], is bypassed. The iterated exchange potential, expressed in terms of ESs and OSs, is improved by modifying ESs at odd iteration steps and OSs at even steps. The modification formulas are related to the optimized-effective-potential equation (satisfied at convergence) written as the condition of vanishing density shift (DS). They are obtained, respectively, by enforcing its satisfaction through corrections to approximate OSs and by determining the optimal ESs that minimize the DS norm. The proposed method, successfully tested for several closed-(sub)shell atoms, from Be to Kr, within the density functional theory exchange-only approximation, proves highly efficient. The calculations using the pseudospectral method for representing orbitals give iterative sequences of approximate exchange potentials (starting with the Krieger-Li-Iafrate approximation) that rapidly approach the exact v{sub x} so that, for Ne, Ar, and Zn, the corresponding DS norm becomes less than 10{sup -6} after 13, 13, and 9 iteration steps for a given electron density. In self-consistent density calculations, orbital energies of 10{sup -4} hartree accuracy are obtained for these atoms after, respectively, 9, 12, and 12 density iteration steps, each involving just two steps of v{sub x} iteration, while the accuracy limit of 10{sup -6} to 10{sup -7} hartree is reached after 20 density iterations.

Cinal, M.; Holas, A. [Institute of Physical Chemistry of the Polish Academy of Sciences, 44/52 Kasprzaka, 01-224 Warsaw (Poland)

2011-06-15T23:59:59.000Z

259

Building America Technology Solutions for New and Existing Homes...  

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

In this project, the Raleigh Housing Authority worked with Building America team, the Advanced Residential Integrated Solutions Collaborative, to determine the most cost-effective...

260

Explicit global integrators  

E-Print Network [OSTI]

be advantageous. For this purpose, forward interpolation utilizing Radau Quadrature will be employed. An explicit method of global integration has been developed to estimate a solution to a differential equation. A set of functions P (x), P (x), , P (x) and a... set of points n+1 x , x , , x can be found such that n+1 r x n+1 f(u)du = g P. (x)i'(x. ) 0 i=1 for all x when f(u) is a polynomial of degree n or less. The above process is described by Axelsson as global integration. In . th the cases...

Merriam, Robert Stevens

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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
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261

Grid Integration  

SciTech Connect (OSTI)

Summarizes the goals and activities of the DOE Solar Energy Technologies Program efforts within its grid integration subprogram.

Not Available

2008-09-01T23:59:59.000Z

262

An iterative technique for the factorization of polynomials  

E-Print Network [OSTI]

FACTOR NUMBER 1 A(I, J) COEFFICIENTS OF F(X) 0. 09999999E 01 0. 40000000E 01 0. 0. 0. 20000000E 01 0. 80000000E 01 0. 9 00000 0. OE 01 0. 36000000E 02 0. 0. 0. 18000000E 02 0. 72000000E 02 ITER P(I, J) FOR THIS SET Of ITERATIONS 0. 09999999...E 0. 09999999E 0. 09999999E 0. 73 02 2 808E 0. 09999999E 0. 14229858E 0. 09999999E 0. 11079702E 0. 09999999E 0. 14843886E 0, 09999999E 0. 17027360E 0. 09999999E 0. 188503 02E 0. 09999999E 01 01 01 00 01 01 01 01 01 01 01 01...

Gray, Jerry Edwin

2012-06-07T23:59:59.000Z

263

Water-cooled solid-breeder blanket concept for ITER  

SciTech Connect (OSTI)

A water cooled solid-breeder blanket concept was developed for ITER. The main function of this blanket is to produce the necessary tritium for the ITER operation. Several design features are incorporated in this blanket concept to increase its attractiveness. The main features are the following: (a) a multilayer concept which reduces fabrication cost; (b) a simple blanket configuration which results in reliability advantages; (c) a very small breeder volume is employed to reduce the tritium inventory and the blanket cost; (d) a high tritium breeding ratio eliminates the need for an outside tritium supply; (e) a low-pressure system decreases the required steel fraction for structural purposes; (f) a low-temperature operation reduces the swelling concerns for beryllium; and (g) the small fractions of structure and breeder materials used in the blanket reduce the decay heat source. The key features and design analyses of this blanket are summarized in this paper.

Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

1989-03-01T23:59:59.000Z

264

Krylov subspace iteration for eigenvalue response matrix calculations  

SciTech Connect (OSTI)

Recent work has revisited the eigenvalue response matrix method as an approach for reactor core analyses. In its most straightforward form, the method consists of a two-level Eigen problem. An outer Picard iteration updates the k-eigenvalue, while the inner Eigen problem imposes current continuity between coarse meshes. In this paper, several Eigen solvers are evaluated for this inner problem, using several 2-D diffusion benchmarks as test cases. The results indicate both the explicitly-restarted Arnoldi and the Krylov-Schur methods are up to an order of magnitude more efficient than power iteration. This increased efficiency makes the nested eigenvalue formulation more effective than the ILU-preconditioned Newton-Krylov formulation previously studied. (authors)

Roberts, J. A.; Forget, B. [Massachusetts Inst. of Technology, 77 Massachusetts Ave., Cambridge, MA 02141 (United States)

2012-07-01T23:59:59.000Z

265

Dynamic simulation of a proposed ITER tritium processing system  

SciTech Connect (OSTI)

Dynamically simulating the fuel cycle in a fusion reactor is crucial to developing a better understanding of the safe and reliable operation of this complex system. In this work, we propose a tritium processing system for ITER`s plasma exhaust. The dynamic simulation of this proposed system is then performed with the TRUFFLES (TRitiUm Fusion Fuel cycLE dynamic Simulation) model. The fuel management, storage, and fueling operations are developed and coupled with previous cryopump and fuel cleanup unit subsystems to fully realize the complete torus exhaust flow cycle. Results show that tritium inventories will vary widely depending upon reactor operation, individual subsystem and unit operation designs. A diverse collection of batch-controlled subsystems with changes in their processing parameters are simulated in this work. In particular, the effects from the fuel management subsystem`s fuel reserve and tank switching times are quantified using sensitivity studies. 6 refs., 10 figs., 2 tabs.

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

1995-10-01T23:59:59.000Z

266

An Overview of US ITER Test Blanket Module Program  

SciTech Connect (OSTI)

A testing strategy and corresponding test plan have been presented for the two proposed US candidate breeder blankets: 1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplier, but without a fully independent TBM, and 2) a dual-coolant helium-cooled ferritic steel structure with self-cooled LiPb breeding zone that uses a flow channel insert as MHD and thermal insulator. Example test module designs, and configuration choices for each line of ITER TBM are shown and discussed in the paper. In addition, near-term R&D items for decision-making on testing of both solid breeder and dual-coolant PbLi liquid breeder blanket concepts in ITER are identified.

Ying, A.; Abdou, Mohamed A.; Wong, Clement; Malang, S.; Morley, Neil B.; Sawan, M.; Merrill, Brad; Sze, Dai Kai; Kurtz, Richard J.; Willms, Scott; Ulrickson, Mike; Zinkle, Steven J.

2006-01-01T23:59:59.000Z

267

Atomic Physics in the Quest for Fusion Energy and ITER  

SciTech Connect (OSTI)

The urgent quest for new energy sources has led developed countries, representing over half of the world population, to collaborate on demonstrating the scientific and technological feasibility of magnetic fusion through the construction and operation of ITER. Data on high-Z ions will be important in this quest. Tungsten plasma facing components have the necessary low erosion rates and low tritium retention but the high radiative efficiency of tungsten ions leads to stringent restrictions on the concentration of tungsten ions in the burning plasma. The influx of tungsten to the burning plasma will need to be diagnosed, understood and stringently controlled. Expanded knowledge of the atomic physics of neutral and ionized tungsten will be important to monitor impurity influxes and derive tungsten concentrations. Also, inert gases such as argon and xenon will be used to dissipate the heat flux flowing to the divertor. This article will summarize the spectroscopic diagnostics planned for ITER and outline areas where additional data is needed.

Charles H. Skinner

2008-02-27T23:59:59.000Z

268

Qualification of the Joints for the ITER Central Solenoid  

SciTech Connect (OSTI)

The ITER Central Solenoid has 36 interpancake joints, 12 bus joints, and 12 feeder joints in the magnet. The joints are required to have resistance below 4 nOhm at 45 kA at 4.5 K. The US ITER Project Office developed two different types of interpancake joints with some variations in details in order to find a better design, qualify the joints, and establish a fabrication process. We built and tested four samples of the sintered joints and two samples with butt-bonded joints (a total of eight joints). Both designs met the specifications. Results of the joint development, test results, and selection of the baseline design are presented and discussed in the paper. The ITER Central Solenoid (CS) consists of six modules. Each module is composed of six wound hexapancakes and one quadrapancake. The multipancakes are connected electrically and hydraulically by in-line interpancake joints. The joints are located at the outside diameter (OD) of the module. Cable in conduit conductor (CICC) high-current joints are critical elements in the CICC magnets. In addition to low resistivity, the CS joints must fit a space envelope equivalent to the regular conductor cross section and must have low hydraulic impedance and enough structural strength to withstand the hoop and compressive forces during operation, including cycling. This paper is the continuation of the work reported on the intermodule joints.

Martovetsky, N; Berryhill, A; Kenney, S

2011-09-01T23:59:59.000Z

269

Improved criticality convergence via a modified Monte Carlo iteration method  

SciTech Connect (OSTI)

Nuclear criticality calculations with Monte Carlo codes are normally done using a power iteration method to obtain the dominant eigenfunction and eigenvalue. In the last few years it has been shown that the power iteration method can be modified to obtain the first two eigenfunctions. This modified power iteration method directly subtracts out the second eigenfunction and thus only powers out the third and higher eigenfunctions. The result is a convergence rate to the dominant eigenfunction being |k{sub 3}|/k{sub 1} instead of |k{sub 2}|/k{sub 1}. One difficulty is that the second eigenfunction contains particles of both positive and negative weights that must sum somehow to maintain the second eigenfunction. Summing negative and positive weights can be done using point detector mechanics, but this sometimes can be quite slow. We show that an approximate cancellation scheme is sufficient to accelerate the convergence to the dominant eigenfunction. A second difficulty is that for some problems the Monte Carlo implementation of the modified power method has some stability problems. We also show that a simple method deals with this in an effective, but ad hoc manner.

Booth, Thomas E [Los Alamos National Laboratory; Gubernatis, James E [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

270

Water-cooled solid-breeder concept for ITER  

SciTech Connect (OSTI)

A water-cooled solid-breeder blanket concept was developed for ITER. The main function of this blanket is to produce the necessary tritium for the ITER operation. Several design features are incorporated in this blanket concept to increase its attractiveness. It is assumed that the blanket operation at commercial power reactor conditions can be sacrificed to achieve a high tritium breeding ratio with minimum additional research and development, and minimal impact on reactor design and operation. Operating temperature limits are enforced for each material to insure a satisfactory blanket performance. In fact, the design was iterated to maximize the tritium breeding ratio and satisfy these temperature limits. The other design constraint is to permit a large increase in the neutron wall loading without exceeding the temperature limits for the different blanket materials. The blanket concept contains 1.8 cm of Li/sub 2/O and 22.5 cm of beryllium both with a 0.8 density factor. The water coolant is isolated from the breeder material by several zones which reduces the tritium buildup in the water by permeation, reduces the chance for water-breeder interaction, and permits the breeder to operate at high temperature with a low temperature coolant. This improves the safety and environmental aspects of the blanket and eliminates the costly process of the tritium recovery from the water. The key features and design analysis of this blanket are summarized in this paper. 11 refs., 2 figs., 3 tabs.

Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

1988-08-01T23:59:59.000Z

271

Progress and present status of ITER cryoline system  

SciTech Connect (OSTI)

The cryoline system at ITER forms a very complex network localized inside the Tokamak building, on a dedicated plant bridge and in cryoplant areas. The cooling power produced in the cryoplant is distributed via these lines with a total length of about 3.7 km and interconnecting all the cold boxes of the cryogenic system as well as the cold boxes of various clients (magnets, cryopumps and thermal shield). Distinct layouts and polygonal geometry, nuclear safety and confinement requirements, difficult installation and in-service inspection/repair demand very high reliability and availability for the cryolines. The finalization of the building-embedded plates for supporting the lines, before the detailed design, has made this project technologically more challenging. The conceptual design phase has been completed and procurement arrangements have been signed with India, responsible for providing the system of cryolines and warm lines to ITER, as in kind contribution. The prototype test for the design and performance validation has been planned on a representative cryoline section. After describing the basic features and general layout of the ITER cryolines, the paper presents key design requirements, conceptual design approach, progress and status of the cryolines project as well as challenges to build such a complex cryoline system.

Badgujar, S.; Bonneton, M.; Chalifour, M.; Forgeas, A.; Serio, L. [ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul lez Durance (France); Sarkar, B.; Shah, N. [ITER-India, Institute for Plasma Research, Bhat, Gandhinagar 382428 (India)

2014-01-29T23:59:59.000Z

272

The neutral beam system for ITER is composed of two Heating and Current Drive (H&CD) injectors and  

E-Print Network [OSTI]

incorporated into ITER's Product Lifecycle Management (PLM) system Figure 3: Illustration of design progress

273

Iterative linear solvers in a 2D radiation-hydrodynamics code: Methods and performance  

SciTech Connect (OSTI)

Computer codes containing both hydrodynamics and radiation play a central role in simulating both astrophysical and inertial confinement fusion (ICF) phenomena. A crucial aspect of these codes is that they require an implicit solution of the radiation diffusion equations. The authors present in this paper the results of a comparison of five different linear solvers on a range of complex radiation and radiation-hydrodynamics problems. The linear solvers used are diagonally scaled conjugate gradient, GMRES with incomplete LU preconditioning, conjugate gradient with incomplete Cholesky preconditioning, multigrid, and multigrid-preconditioned conjugate gradient. These problems involve shock propagation, opacities varying over 5--6 orders of magnitude, tabular equations of state, and dynamic ALE (Arbitrary Lagrangian Eulerian) meshes. They perform a problem size scalability study by comparing linear solver performance over a wide range of problem sizes from 1,000 to 100,000 zones. The fundamental question they address in this paper is: Is it more efficient to invert the matrix in many inexpensive steps (like diagonally scaled conjugate gradient) or in fewer expensive steps (like multigrid)? In addition, what is the answer to this question as a function of problem size and is the answer problem dependent? They find that the diagonally scaled conjugate gradient method performs poorly with the growth of problem size, increasing in both iteration count and overall CPU time with the size of the problem and also increasing for larger time steps. For all problems considered, the multigrid algorithms scale almost perfectly (i.e., the iteration count is approximately independent of problem size and problem time step). For pure radiation flow problems (i.e., no hydrodynamics), they see speedups in CPU time of factors of {approx}15--30 for the largest problems, when comparing the multigrid solvers relative to diagonal scaled conjugate gradient.

Baldwin, C.; Brown, P.N.; Falgout, R.; Graziani, F.; Jones, J.

1999-09-01T23:59:59.000Z

274

Applying Quadrature Rules with Multiple Nodes to Solving Integral Equations  

SciTech Connect (OSTI)

There are many procedures for the numerical solution of Fredholm integral equations. The main idea in these procedures is accuracy of the solution. In this paper, we use Gaussian quadrature with multiple nodes to improve the solution of these integral equations. The application of this method is illustrated via some examples, the related tables are given at the end.

Hashemiparast, S. M. [Department of Mathematics, Islamic Azad University Karaj Branch, K. N. Toosi University of Technology, Tehran (Iran, Islamic Republic of); Avazpour, L. [Department of Mathematics, K. N. Toosi University of Technology, P.O. Box 16315-1618 (Iran, Islamic Republic of)

2008-09-01T23:59:59.000Z

275

MAPCUMBA : a fast iterative multi-grid map-making algorithm for CMB experiments  

E-Print Network [OSTI]

The data analysis of current Cosmic Microwave Background (CMB) experiments like BOOMERanG or MAXIMA poses severe challenges which already stretch the limits of current (super-) computer capabilities, if brute force methods are used. In this paper we present a practical solution to the optimal map making problem which can be used directly for next generation CMB experiments like ARCHEOPS and TopHat, and can probably be extended relatively easily to the full PLANCK case. This solution is based on an iterative multi-grid Jacobi algorithm which is both fast and memory sparing. Indeed, if there are N_tod data points along the one dimensional timeline to analyse, the number of operations is O(N_tod ln N_tod) and the memory requirement is O(N_tod). Timing and accuracy issues have been analysed on simulated ARCHEOPS and TopHat data, and we discuss as well the issue of the joint evaluation of the signal and noise statistical properties.

O. Dor; R. Teyssier; F. R. Bouchet; D. Vibert; S. Prunet

2001-01-08T23:59:59.000Z

276

A new nonlinear solution method for phase-change problems  

SciTech Connect (OSTI)

Numerical simulation is playing an increasingly important role in support of industrial casting processes. The goal of simulations is to capture accurately the solidification dynamics in pure materials, and in multicomponent alloys. To achieve this goal a numerical algorithm must evolve accurately the latent heat in an isothermal solidification process, and it must also couple accurately the temperature and concentration fields in the nonisothermal solidification of multicomponent alloys. The authors present a new nonlinear algorithm for the efficient and accurate solution of isothermal and nonisothermal phase-change problems. The method correctly evolves latent heat release in isothermal and nonisothermal phase change, and more important, it provides a means for the efficient and accurate coupling between temperature and concentration fields in multispecies nonisothermal phase change. Newton-like superlinear convergence is achieved in the global nonlinear iteration, without the complexity of forming or inverting the Jacobian matrix. This Jacobian-free method is a combination of an outer Newton-based iteration and an inner conjugate gradient-like (krylov) iteration. The effects of the Jacobian are probed only through approximate matrix-vector products required in the conjugate gradient-like iteration.

Knoll, D.A.; Kothe, D.B.; Lally, B. [Los Alamos National Lab., NM (United States)

1999-06-01T23:59:59.000Z

277

Overview of ASDEX Upgrade Results Development of integrated operating scenarios for ITER  

E-Print Network [OSTI]

, Romania; Consorzio RFX, Padova, Italy; Centro de Fusão Nuclear, IST Lisbon, Portugal; IFP Milano, Italy

278

INNOVATIVE DESIGN AND MATERIAL SOLUTIONS OF THERMAL CONTACT LAYERS FOR HIGH HEAT FLUX APPLICATIONS IN FUSION  

E-Print Network [OSTI]

INNOVATIVE DESIGN AND MATERIAL SOLUTIONS OF THERMAL CONTACT LAYERS FOR HIGH HEAT FLUX APPLICATIONS of sacrificial plasma facing components that have to handle the high heat and particle fluxes in ITER armour thermal and electrical contact with the cooled sub-structure while promoting remote, in

Tillack, Mark

279

Insolation integrator  

DOE Patents [OSTI]

An electric signal representative of the rate of insolation is integrated to determine if it is adequate for operation of a solar energy collection system.

Dougherty, John J. (Norristown, PA); Rudge, George T. (Lansdale, PA)

1980-01-01T23:59:59.000Z

280

MELCOR ex-vessel LOCA simulations for ITER{sup +}  

SciTech Connect (OSTI)

Ex-vessel Loss-of-Coolant-Accident (LOCA) simulations for the International Thermonuclear Experimental Reactor (ITER) were performed using the MELCOR code. The main goals of this work were to estimate the ultimate pressurization of the heat transport system (HTS) vault in order to gauge the potential for stack releases and to estimate the total amount of hydrogen generated during a design basis ex-vessel LOCA. Simulation results indicated that the amount of hydrogen produced in each transient was below the flammability limit for the plasma chamber. In addition, only moderate pressurization of the HTS vault indicated a very small potential for releases through the stack.

Gaeta, M.J.; Merrill, B.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Bartels, H.W. [ITER San Diego Joint Work Site, La Jolla, CA (United States)] [and others

1995-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Status of the ITER IC H and CD System  

SciTech Connect (OSTI)

The ITER Ion Cyclotron Heating and Current Drive system will deliver 20 MW of radio frequency power to the plasma in quasi continuous operation during the different phases of the experimental programme. The system also has to perform conditioning of the tokamak first wall at low power between main plasma discharges. This broad range of requirements imposes a high flexibility and a high availability. The paper highlights the physics and design requirements on the IC system, the main features of its subsystems, the predicted performance, and the current procurement and installation schedule.

Lamalle, P. U.; Beaumont, B.; Gassmann, T.; Kazarian, F.; Arambhadiya, B.; Bora, D.; Jacquinot, J.; Mitteau, R.; Schueller, F. C.; Tanga, A. [ITER Organization, CS 90 046, 13067 Saint-Paul-Lez-Durance (France); Baruah, U.; Bhardwaj, A.; Kumar, R.; Mukherjee, A.; Singh, N. P.; Singh, R. [ITER India, A29, Sector 25, GIDC, Gandhinagar, Gujarat (India); Goulding, R.; Rasmussen, D.; Swain, D. [US ITER Project Office, Oak Ridge National Laboratory, P.O. Box 2008, 1055 CM, MS 6483, Oak Ridge, TN 37831-6483 (United States); Agarici, G. [Fusion for Energy, Josep Pla 2, 08019 Barcelona (Spain)] (and others)

2009-11-26T23:59:59.000Z

282

U.S. ITER | Princeton Plasma Physics Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest RegionatSearchScheduled SystemReleasesFeedback Provide‹ SeeITER

283

Copper wafer bonding in three-dimensional integration  

E-Print Network [OSTI]

Three-dimensional (3D) integration, in which multiple layers of devices are stacked with high density of interconnects between the layers, offers solutions for problems when the critical dimensions in integrated circuits ...

Chen, Kuan-Neng, 1974-

2005-01-01T23:59:59.000Z

284

Report of panel 1: The appropriate scope and mission of ITER  

SciTech Connect (OSTI)

This panel looked at the mission of ITER, and how the US should address the present plans, and considers a number of alternative plans to arrive at the eventual goals of ITER. The panel considered three major approaches which have been discussed on the international scale, and tries to present the strengths, weaknesses, and possible changes to these plans. It suggests that any of these plans can arrive at the eventual aim, but may involve differing risks and time commitments. All plans involve ITER design studies, development work on technologies which must be in place for ITER design to succeed, and testing of materials and components for application in the device.

Linford, R.K. (Los Alamos National Lab., NM (United States)); Weitzner, H.; Abdou, M.A.; Baldwin, D.E.; Berkner, K.H.; Berry, L.A.; Culler, F.L.; Dean, S.O.; DeFreece, D.A.; Gauster, W.B. (and others)

1992-12-01T23:59:59.000Z

285

PPPL and ITER: Lab teams support the world's largest fusion experiment...  

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

port plugs inside the ITER tokamak. Included in the modular design are stainless steel components called diagnostic first walls that will directly face the plasma. These...

286

AdS String: Classical Solutions and Moduli Dynamics  

E-Print Network [OSTI]

We review some recent work and techniques for constructing dynamical string solutions in AdS spacetime. These solutions generalize the folded string and multi-spike solutions of GKP and Kruczenski. The methods developed for constructing these dynamical solutions are based on Pohlmeyer reduction to integrable sinh-Gordon type equations. The integrability of the equations is seen as the crucial tool for reconstruction of the string configurations. We discuss the physical meaning of these dynamical spike solutions and the question of their moduli space.

Antal Jevicki; Kewang Jin

2010-01-29T23:59:59.000Z

287

Modeling results for the ITER cryogenic fore pump  

SciTech Connect (OSTI)

The cryogenic fore pump (CFP) is designed for ITER to collect and compress hydrogen isotopes during the regeneration process of torus cryopumps. Different from common cryopumps, the ITER-CFP works in the viscous flow regime. As a result, both adsorption boundary conditions and transport phenomena contribute unique features to the pump performance. In this report, the physical mechanisms of cryopumping are studied, especially the diffusion-adsorption process and these are coupled with standard equations of species, momentum and energy balance, as well as the equation of state. Numerical models are developed, which include highly coupled non-linear conservation equations of species, momentum and energy and equation of state. Thermal and kinetic properties are treated as functions of temperature, pressure, and composition. To solve such a set of equations, a novel numerical technique, identified as the Group-Member numerical technique is proposed. It is presented here a 1D numerical model. The results include comparison with the experimental data of pure hydrogen flow and a prediction for hydrogen flow with trace helium. An advanced 2D model and detailed explanation of the Group-Member technique are to be presented in following papers.

Zhang, D. S.; Miller, F. K.; Pfotenhauer, J. M. [University of Wisconsin-Madison, Madison, WI 53706 (United States)

2014-01-29T23:59:59.000Z

288

Benchmarking FENDL libraries through analysis of bulk shielding experiments on large SS316 assemblies for verification of ITER shielding characteristics  

SciTech Connect (OSTI)

FENDL-1 data base has been developed recently for use in ITER/EDA phase and other fusion-related design activities. It is now undergoing extensive testing and benchmarking using experimental data of differential and integral measured parameters obtained from fusion-oriented experiments. As part of co-operation between UCLA (U.S.) with JAERI (Japan) on executing the required neutronics R&D tasks for ITER shield design, two bulk shielding experiments on large SS316 assemblies were selected for benchmarking FENDL/MG-1 multigroup data base and FENDL/MC-1 continous energy data base. The analyses with the multigroup data (performed with S8, P5, DORT calculations with shielded and unshielded data) also included library derived from ENDF/B-VI data base for comparison purposes. The MCNP Monte Carlo code was used by JAERI with the FENDL/MC-1 data. The results of this benchmarking is reported in this paper along with the observed deficiencies and discrepancies. 20 refs., 27 figs., 1 tab.

Youssef, M.Z.; Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Konno, Chikara; Maekawa, Fujio; Wada, Masayuki; Oyama, Yukio; Maekawa, Hiroshi; Ikeda, Yujiro [Japan Atomic Energy Research Inst., Ibaraki (Japan)

1996-12-31T23:59:59.000Z

289

Iterative image-domain decomposition for dual-energy CT  

SciTech Connect (OSTI)

Purpose: Dual energy CT (DECT) imaging plays an important role in advanced imaging applications due to its capability of material decomposition. Direct decomposition via matrix inversion suffers from significant degradation of image signal-to-noise ratios, which reduces clinical values of DECT. Existing denoising algorithms achieve suboptimal performance since they suppress image noise either before or after the decomposition and do not fully explore the noise statistical properties of the decomposition process. In this work, the authors propose an iterative image-domain decomposition method for noise suppression in DECT, using the full variance-covariance matrix of the decomposed images. Methods: The proposed algorithm is formulated in the form of least-square estimation with smoothness regularization. Based on the design principles of a best linear unbiased estimator, the authors include the inverse of the estimated variance-covariance matrix of the decomposed images as the penalty weight in the least-square term. The regularization term enforces the image smoothness by calculating the square sum of neighboring pixel value differences. To retain the boundary sharpness of the decomposed images, the authors detect the edges in the CT images before decomposition. These edge pixels have small weights in the calculation of the regularization term. Distinct from the existing denoising algorithms applied on the images before or after decomposition, the method has an iterative process for noise suppression, with decomposition performed in each iteration. The authors implement the proposed algorithm using a standard conjugate gradient algorithm. The method performance is evaluated using an evaluation phantom (Catphan600) and an anthropomorphic head phantom. The results are compared with those generated using direct matrix inversion with no noise suppression, a denoising method applied on the decomposed images, and an existing algorithm with similar formulation as the proposed method but with an edge-preserving regularization term. Results: On the Catphan phantom, the method maintains the same spatial resolution on the decomposed images as that of the CT images before decomposition (8 pairs/cm) while significantly reducing their noise standard deviation. Compared to that obtained by the direct matrix inversion, the noise standard deviation in the images decomposed by the proposed algorithm is reduced by over 98%. Without considering the noise correlation properties in the formulation, the denoising scheme degrades the spatial resolution to 6 pairs/cm for the same level of noise suppression. Compared to the edge-preserving algorithm, the method achieves better low-contrast detectability. A quantitative study is performed on the contrast-rod slice of Catphan phantom. The proposed method achieves lower electron density measurement error as compared to that by the direct matrix inversion, and significantly reduces the error variation by over 97%. On the head phantom, the method reduces the noise standard deviation of decomposed images by over 97% without blurring the sinus structures. Conclusions: The authors propose an iterative image-domain decomposition method for DECT. The method combines noise suppression and material decomposition into an iterative process and achieves both goals simultaneously. By exploring the full variance-covariance properties of the decomposed images and utilizing the edge predetection, the proposed algorithm shows superior performance on noise suppression with high image spatial resolution and low-contrast detectability.

Niu, Tianye; Dong, Xue; Petrongolo, Michael; Zhu, Lei, E-mail: leizhu@gatech.edu [Nuclear and Radiological Engineering and Medical Physics Programs, The George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States)] [Nuclear and Radiological Engineering and Medical Physics Programs, The George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, Georgia 30332 (United States)

2014-04-15T23:59:59.000Z

290

Nebraska Statewide Wind Integration Study: Executive Summary  

SciTech Connect (OSTI)

Wind generation resources in Nebraska will play an increasingly important role in the environmental and energy security solutions for the state and the nation. In this context, the Nebraska Power Association conducted a state-wide wind integration study.

EnerNex Corporation, Knoxville, Tennessee; Ventyx, Atlanta, Georgia; Nebraska Power Association, Lincoln, Nebraska

2010-03-01T23:59:59.000Z

291

Integrated Brush Management Systems for Texas  

E-Print Network [OSTI]

Integrated Brush Management Systems (IBMS) involve careful analysis of range resources and ranch goals in order to develop solutions to brush problems. Successful use of IBMS should result in improved management processes and greater profitability...

Hanselka, C. Wayne; Hamilton, Wayne T.; Rector, Barron S.

2001-01-04T23:59:59.000Z

292

Integrable viscous conservation laws  

E-Print Network [OSTI]

We propose an extension of the Dubrovin-Zhang perturbative approach to the study of normal forms for non-Hamiltonian integrable scalar conservation laws. The explicit computation of the first few corrections leads to the conjecture that such normal forms are parameterized by one single functional parameter, named viscous central invariant. A constant valued viscous central invariant corresponds to the well-known Burgers hierarchy. The case of a linear viscous central invariant provides a viscous analog of the Camassa-Holm equation, that formerly appeared as a reduction of a two-component Hamiltonian integrable systems. We write explicitly the negative and positive hierarchy associated with this equation and prove the integrability showing that they can be mapped respectively into the heat hierarchy and its negative counterpart, named the Klein-Gordon hierarchy. A local well-posedness theorem for periodic initial data is also proven. We show how transport equations can be used to effectively construct asymptotic solutions via an extension of the quasi-Miura map that preserves the initial datum. The method is alternative to the method of the string equation for Hamiltonian conservation laws and naturally extends to the viscous case. Using these tools we derive the viscous analog of the Painlev\\'e I2 equation that describes the universal behaviour of the solution at the critical point of gradient catastrophe.

Alessandro Arsie; Paolo Lorenzoni; Antonio Moro

2014-06-25T23:59:59.000Z

293

Optimization of the ITER electron cyclotron equatorial launcher for improved heating and current drive functional capabilities  

SciTech Connect (OSTI)

The design of the ITER Electron Cyclotron Heating and Current Drive (EC H and CD) system has evolved in the last years both in goals and functionalities by considering an expanded range of applications. A large effort has been devoted to a better integration of the equatorial and the upper launchers, both from the point of view of the performance and of the design impact on the engineering constraints. However, from the analysis of the ECCD performance in two references H-mode scenarios at burn (the inductive H-mode and the advanced non-inductive scenario), it was clear that the EC power deposition was not optimal for steady-state applications in the plasma region around mid radius. An optimization study of the equatorial launcher is presented here aiming at removing this limitation of the EC system capabilities. Changing the steering of the equatorial launcher from toroidal to poloidal ensures EC power deposition out to the normalized toroidal radius ????0.6, and nearly doubles the EC driven current around mid radius, without significant performance degradation in the core plasma region. In addition to the improved performance, the proposed design change is able to relax some engineering design constraints on both launchers.

Farina, D.; Figini, L. [Istituto di Fisica del Plasma, Consiglio Nazionale delle Ricerche, EURATOM-ENEA-CNR Association, via Cozzi 53, 20125 Milano (Italy); Henderson, M. [ITER Organization, 13108 Saint-Paul-lez-Durance (France); Saibene, G. [Fusion for Energy, c/Josep Pla 2, Torres Diagonal Litoral-B3, E-08019 Barcelona (Spain)

2014-06-15T23:59:59.000Z

294

IBM and Johnson Controls Integrated  

E-Print Network [OSTI]

IBM and Johnson Controls Integrated Smarter Building Solution IBM and Johnson Controls make it simpler to reduce energy and operational costs while reducing greenhouse emissions. IBM and Johnson and more. IBM and Johnson Controls work with you to identify high-priority energy consumption areas

295

Fusion Engineering and Design 46 (1999) 177183 ITER reference breeding blanket design  

E-Print Network [OSTI]

available from the Canadian heavy-water fission reactors. The ITER breeding blanket (BB) has to satisfy its The ITER reference breeding blanket design is water-cooled and is characterised by the use of the neutronic and SB modules have to adopt a common supply and supporting system, as well as the same installation

Raffray, A. René

296

First ITER Council convened in Cadarache Historic step in the quest for clean Energy  

E-Print Network [OSTI]

First ITER Council convened in Cadarache Historic step in the quest for clean Energy Cadarache, 28 of age in a world in desperate need of clean, abundant, and carbon dioxide-free energy." Setting a new Energy Agency (IAEA), said: "Let me congratulate all who have contributed to the achievements of the ITER

297

A E Costley ITER Diagnostics, 21st IAEA of 5 slides  

E-Print Network [OSTI]

Costley ITER Diagnostics, 21st IAEA 2 of 5 slides PLAN Requirements for Plasma and First Wall MeasurementsA E Costley ITER Diagnostics, 21st IAEA 1 of 5 slides A E Costley1, C Walker2, L Bertalot2, R, Germany THE DESIGN AND IMPLEMENTATIONTHE DESIGN AND IMPLEMENTATION OF DIAGNOSTIC SYSTEMS ON ITEROF

298

S12.9Constrained Iterative Speech Enhance with Application to  

E-Print Network [OSTI]

S12.9Constrained Iterative Speech Enhance with Application to Automatic Speech Recognition John H Atlanta, GA 30332 set of iterative speech enhancement techniques employing spec- ral constraints. FinalIy, the enhancement algorithms are evaluated to determine their ability as preproces- and speech

Texas at Dallas, University of

299

Fusion Engineering and Design 81 (2006) 433441 An overview of US ITER test blanket module program  

E-Print Network [OSTI]

blankets: (1) a helium-cooled solid breeder concept with ferritic steel structure and Be neutron multiplierLi liquid breeder blanket concepts in ITER are identified. 2005 Elsevier B.V. All rights reserved. Keywords: ITER test blanket module program; Helium-cooled solid breeder blanket; Dual-coolant lead

Abdou, Mohamed

2006-01-01T23:59:59.000Z

300

Soft-Input, Iterative, Reed-Solomon Decoding using Redundant Parity-Check Equations  

E-Print Network [OSTI]

approach to the iterative decoding of Reed-Solomon (RS) codes. The pre- sented methodology utilizesSoft-Input, Iterative, Reed-Solomon Decoding using Redundant Parity-Check Equations Jason Bellorado techniques is achievable with the presented methodology. The complexity of the proposed algorithm is orders

Kavcic, Aleksandar

Note: This page contains sample records for the topic "integrated iterative solution" 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

FPA, Annual meeting, 3-4 December 2008 Slide 1 Status of ITER  

E-Print Network [OSTI]

FPA, Annual meeting, 3-4 December 2008 Slide 1 of 25 Status of ITER Fusion Power Associates Annual Organization #12;FPA, Annual meeting, 3-4 December 2008 Slide 2 of 25 Main Outline · History of ITER Project Program · External Relations · International School #12;FPA, Annual meeting, 3-4 December 2008 Slide 3

302

PISCES FY11 Research Highlight Tritium accumulation within the ITER vessel is expected to be dominated  

E-Print Network [OSTI]

PISCES FY11 Research Highlight Tritium accumulation within the ITER vessel is expected injected into the vessel. ITER has focused considerable effort into the ability to thermally remove tritium vessel. Another possible technique to mitigate tritium accumulation in these codeposited surfaces

303

Looking on bright side of losing ITER Risa Kato and Tetsuro Yamada / Yomiuri Shimbun Staff Writers  

E-Print Network [OSTI]

to have a remote-controlled ITER experiment unit, and one for the development of super heat candidate to have a remote-control facility is of especially high significance, according to experts. The remote-control facility is envisaged as playing a key role in the ITER project, as it will be able

304

A three-dimensional adaptive method based on the iterative grid redistribution  

E-Print Network [OSTI]

such as fluid dynamics, combustion and heat transfer and others, the required density of grid pointsA three-dimensional adaptive method based on the iterative grid redistribution Desheng Wang on iterative grid redistribution technique introduced in [J. Comput. Phys. 159 (2000) 246]. The key step

Wang, Desheng

305

Presented by Y.Shimomura ITER Joint Central Team and Home Teams  

E-Print Network [OSTI]

of reliability of the operation Full commissioning of the ITER systemin a non-nuclear environment DevelopmentPresented by Y.Shimomura ITER Joint Central Team and Home Teams Oct. 5, 2000 Sorrento, Italy #12 Elevation Layout #12;Phased Operations Hydrogen Phase Confirmation of the machine performance and increase

306

A Generalized Diffusion Based Inter-Iteration Nonlinear Bilateral Filtering Scheme for PET  

E-Print Network [OSTI]

A Generalized Diffusion Based Inter-Iteration Nonlinear Bilateral Filtering Scheme for PET Image inter-iteration filtering scheme based diffusion MAP estimate for PET image reconstruction is proposed,version1 #12;1. Introduction Positron emission tomography (PET) is one of the most important imaging tools

Paris-Sud XI, Université de

307

An iterative process for international negociations on acid rain in Northern Europe  

E-Print Network [OSTI]

An iterative process for international negociations on acid rain in Northern Europe using a general 138.48.4.14) #12; An iterative process for international negotiations on acid rain in Northern Europe transboundary pollution problem related to acid rain in Northern Europe. This simulation shows the need

Toint, Philippe

308

Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER Era  

E-Print Network [OSTI]

Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER of Directors 8:20 Presentation of Awards ­ S. Dean, President, FPA 8:30 Fusion at the Department of Energy Technology Program­ Stan Milora, ORNL 1:40 Issues and Opportunities from ITER Review ­ R. Hawryluk, PPPL 2

309

NESTED ITERATION AND FIRST-ORDER SYSTEM LEAST SQUARES FOR INCOMPRESSIBLE, RESISTIVE MAGNETOHYDRODYNAMICS  

E-Print Network [OSTI]

NESTED ITERATION AND FIRST-ORDER SYSTEM LEAST SQUARES FOR INCOMPRESSIBLE, RESISTIVE. This paper develops a nested iteration algorithm to solve time-dependent nonlinear systems of partial a sequence of nested spaces, where the resolution of the approximations increases as the algorithm progresses

McCormick, Steve

310

ISFNT-11, Barcelona, Spain, September 16-20, 2013 2013, ITER Organization  

E-Print Network [OSTI]

, Fabrication and Testing of the ITER First Wall and Shielding Blanket Presented by A. René Raffray Blanket Domestic Agency; 7SNL , US ITER Domestic Agency; 11th International Symposium on Fusion Nuclear Technology and neutron loads in the vacuum vessel and ex-vessel components · Provide a plasma-facing surface which

Raffray, A. René

311

Annual Report of the EURATOM/CCFE Fusion Programme 2010/11 8 ITER Systems  

E-Print Network [OSTI]

to the ITER heating, diagnostic and remote handling systems in particular. Fusion for Energy (F4E its substantial role in five key ITER systems: · Ion Cyclotron Resonance Heating (ICRH) system) content, the ion temperature and flow; · Remote handling system, in particular the design for the Neutral

312

Annual Report of the EURATOM/CCFE Fusion Programme 2013 8 ITER SYSTEMS  

E-Print Network [OSTI]

and undertake leading or major roles in the design and R&D of ITER specialist systems (Plasma Heating, Diagnostics and Remote Handling etc.). Seek to play other design roles in R&D of ITER specialist systems Resonance Heating (ICRH) system. Neutral Beam Injection heating system. Core LIDAR Thompson scattering

313

Annual Report of the EURATOM/CCFE Fusion Programme 2012/13 8 ITER SYSTEMS  

E-Print Network [OSTI]

Heating, Diagnostics and Remote Handling etc). · Seek to play other design roles in R&D of ITER specialist in the following key ITER systems: · Ion Cyclotron Resonance Heating (ICRH) system. · Neutral Beam Injection heating system. · Core LIDAR Thompson scattering to measure the electron temperature and density profiles

314

Contents of ITER deal revealed The Yomiuri Shimbun (May 27, 2005, 4 am)  

E-Print Network [OSTI]

in thermonuclear fusion. The country also will supply 20 percent of workers to ITER facilities. The four other on the roles of host and non-hosting countries involved in the International Thermonuclear Experimental Reactor. The planned ITER is an experimental facility for a thermonuclear reactor designed to produce power by fusing

315

The User Oriented Evaluation process: A process for preserving user needs during iterative system test and evaluation  

SciTech Connect (OSTI)

A system development process, called the User Oriented Evaluation (UOE) process, and an evaluation tool were created to place greater emphasis on user needs during computer system development. The UOE process is an iterative method for design that emphasizes the role of the user as the initiator of system requirements; evolutionary design requirement definition by enabling users and development to experiment through the use of prototypes at all phases of system design; and appropriate utilization of developer and user areas of expertise. The evaluation tool is an integral part of the UOE process and provides the ability to solicit on-line meaningful feedback from users in real-time, and a means to capture on a user's on-going experience with the computer system. The paper contains a description of the UOE process and the evaluation tool, the capabilities of each and the history of their development. 12 figs., 3 tabs.

Hunt, S.; Schur, A.

1991-09-01T23:59:59.000Z

316

Nuclear systems and testing programs for ITER. Progress report for FY 1998  

SciTech Connect (OSTI)

The effort during this performance period focused on a number of TBWG activities (including test module design and analysis) that were identified and agreed upon (in the presence of the ITER Director and Deputy Director) at TBWG-4. These include: (a) DEMO test module design and performance analysis under pulsed operation; (b) Test program operation plan; (c) Test port design and analysis; (d) Decay heat calculations and safety analysis; (e) Further discussion among the parties to define collaboratory on R and D for the test program as well as possible collaboration on the construction and operation of test articles; (f) Remote handling and ancillary equipment; (g) Criteria for qualifying a blanket module or submodule for actual insertion and testing in ITER; (h) Definition of test module instrumentation and verification of capability to perform in the ITER fusion environment (magnetic field, radiation, heating, etc.); and (i) Analysis to show that the results to be obtained from the test modules as designed can be extrapolated to DEMO and reactor conditions (e.g., higher wall loads and the need to demonstrate tritium self-sufficiency). The main achievements during this performance period include: (1) updating and finalizing the US DDDs for the ITER Blanket Program to form part of the ITER Final Design Report (FDR). Specific revisions were in response to the minimal lithium volume test blanket design requirements and safety impact and (2) evaluating the feasibility of the US test program, including instrumentation and the benefits of the ITER test program. Details of this assessment, including solid breeder and liquid breeder blanket test plans, are documented in UCLA-IFNT-13 (attached). In addition, dose mapping calculations were performed for the ITER Building, including equipment and layout of coolant pipes/heat exchangers. A report on ITER Building dose calculations was sent to UD ITER management and to the Garching Task Coordinator in April, 1998. The report entitled Three-Dimensional Calculations of ITER Building Dose Rate Profiles and Assessment of Accessibility Inside the Building During Operation and After Shutdown of ITER can be located through ITER Reference Number of ITER Task S 62 TD 12, ID No: D325 ITER/US/98/S62TD12-D325 UCLA-FNT-100 UCLA-ENG-98-190.

NONE

1998-12-31T23:59:59.000Z

317

THE DAYLIGHTING SOLUTION  

E-Print Network [OSTI]

1980, pp.l4-20 THE DAYLIGHTING SOLUTION Stephen SelkowitzEEB-W-80-19 W-74 THE DAYLIGHTING SOLUTION Stephen Selkowitz

Selkowitz, Stephen

2013-01-01T23:59:59.000Z

318

An Integrated View on Plasma Power Exhaust and In-vessel Components  

E-Print Network [OSTI]

divertor plates able to remove 10 MW/m2 have been produced (ITER water cooled) or are under developmentAn Integrated View on Plasma Power Exhaust and In-vessel Components 20% of the energy produced generated during these transition phases. In addition, instabilities of plasma will produce off

319

Fusion Engineering and Design 82 (2007) 22172225 Integrated thermo-fluid analysis towards helium flow  

E-Print Network [OSTI]

Fusion Engineering and Design 82 (2007) 2217­2225 Integrated thermo-fluid analysis towards helium. Andob, I. Komadab a Fusion Engineering Sciences, Mechanical and Aerospace Eng. Department, University the ITER test blanket module (TBM) warrants the need of extensive computer aided engineering (CAE

Abdou, Mohamed

320

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part 2 --High-angle and horizontal wells  

E-Print Network [OSTI]

Linear iterative refinement method for the rapid simulation of borehole nuclear measurements: Part refinement method to rapidly simulate borehole nuclear measurements acquired in vertical wells neutron and density measurements. Based on new research, we implemented the linear iterative refinement

Torres-Verdín, Carlos

Note: This page contains sample records for the topic "integrated iterative solution" 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

Iterative methods for dose reduction and image enhancement in tomography  

DOE Patents [OSTI]

A system and method for creating a three dimensional cross sectional image of an object by the reconstruction of its projections that have been iteratively refined through modification in object space and Fourier space is disclosed. The invention provides systems and methods for use with any tomographic imaging system that reconstructs an object from its projections. In one embodiment, the invention presents a method to eliminate interpolations present in conventional tomography. The method has been experimentally shown to provide higher resolution and improved image quality parameters over existing approaches. A primary benefit of the method is radiation dose reduction since the invention can produce an image of a desired quality with a fewer number projections than seen with conventional methods.

Miao, Jianwei; Fahimian, Benjamin Pooya

2012-09-18T23:59:59.000Z

322

Simulations of Alpha Wall Load in ITER. Final report  

SciTech Connect (OSTI)

The partially DOE funded International Thermonuclear Experimental Reactor (ITER) will produce massive amounts of energetic charged alpha particles, which are imperfectly confined by a strong magnetic field. The wall of the experiment is designed to withstand an estimated wall load from these fusion alpha particles, but the accuracy of this estimate needs to be improved to avoid potentially catastrophic surprises when the experiment becomes operational. We have added a more accurate, gyro-dynamic model of particle motion to the existing drift-dynamic model in the DELTA5D simulation software used for the project. We have also added the ability to load a detailed engineering model of the wall and use it in the simulations.

Carlsson, Johan

2010-10-20T23:59:59.000Z

323

Ideal MHD Stability of ITER Steady State Scenarios with ITBs  

SciTech Connect (OSTI)

One of ITER goals is to demonstrate feasibility of continuous operations using non-inductive current drive. Two main candidates have been identified for advanced operations: the long duration, high neutron fluency hybrid scenario and the steady state scenario, both operating at a plasma current lower than the reference ELMy scenario [1][2] to minimize the required current drive. The steady state scenario targets plasmas with current 7-10 MA in the flat-top, 50% of which will be provided by the self-generated, pressure-driven bootstrap current. It has been estimated that, in order to obtain a fusion gain Q > 5 at a current of 9 MA, it should be ?N > 2.5 and H > 1.5 [3]. This implies the presence of an Internal Transport Barrier (ITB). This work discusses how the stability of steady state scenarios with ITBs is affected by the external heating sources and by perturbations of the equilibrium profiles.

F.M. Poli, C.E. Kessel, S. Jardin, J. Manickam, M. Chance, J. Chen

2011-07-27T23:59:59.000Z

324

Occupational Radiation Exposure Analysis of US ITER DCLL TBM  

SciTech Connect (OSTI)

This report documents an Occupational Radiation Exposure (ORE) analysis that was performed for the US International Thermonuclear Experimental Reactor (ITER) Dual Coolant Lead Lithium (DCLL) Test Blanket Module (TBM). This analysis was performed with the QADMOD dose code for anticipated maintenance activities for this TBM concept and its ancillary systems. The QADMOD code was used to model the PbLi cooling loop of this TBM concept by specifying gamma ray source terms that simulated radioactive material within the piping, valves, heat exchanger, permeator, pump, drain tank, and cold trap of this cooling system. Estimates of the maintenance tasks that will have to be performed and the time required to perform these tasks where developed based on either expert opinion or on industrial maintenance experience for similar technologies. This report details the modeling activity and the calculated doses for the maintenance activities envisioned for the US DCLL TBM.

Merrill, Brad J; Cadwallader, Lee C; Dagher, Mohamad

2007-08-01T23:59:59.000Z

325

DESIGN OF THE ITER IN-VESSEL COILS  

SciTech Connect (OSTI)

The ITER project is considering the inclusion of two sets of in-vessel coils, one to mitigate the effect of Edge Localized Modes (ELMs) and another to provide vertical stabilization (VS). The in-vessel location (behind the blanket shield modules, mounted to the vacuum vessel inner wall) presents special challenges in terms of nuclear radiation (~3000 MGy) and temperature (100oC vessel during operations, 200oC during bakeout). Mineral insulated conductors are well suited to this environment but are not commercially available in the large cross section required. An R&D program is underway to demonstrate the production of mineral insulated (MgO or Spinel) hollow copper conductor with stainless steel jacketing needed for these coils. A preliminary design based on this conductor technology has been developed and is presented herein.

Neumeyer, C; Bryant, L; Chrzanowski, J; Feder, R; Gomez, M; Heitzenroeder, P; Kalish, M; Lipski, A; Mardenfeld, M; Simmons, R; Titus, P; Zatz, I; Daly, E; Martin, A; Nakahira, M; Pillsbury, R; Feng, J; Bohm, T; Sawan, M; Stone, H; Griffiths, I

2010-11-27T23:59:59.000Z

326

Status of ITER neutral beam cell remote handling system  

E-Print Network [OSTI]

The ITER neutral beam cell will contain up to three heating neutral beams and one diagnostic neutral beam, and four upper ports. Though manual maintenance work is envisaged within the cell, when containment is breached, or the radiological protection is removed the maintenance must be conducted remotely. This maintenance constitutes the removal and replacement of line replaceable units, and their transport to and from a cask docked to the cell. A design of the remote handling system has been prepared to concept level which this paper describes including the development of a beam line transporter, beam source remote handling equipment, upper port remote handling equipment and equipment for the maintenance of the neutral shield. This equipment has been developed complete the planned maintenance tasks for the components of the neutral beam cell and to have inherent flexibility to enable as yet unforeseen tasks and recovery operations to be performed.

Sykes, N; Choi, C-H; Crofts, O; Crowe, R; Damiani, C; Delavalle, S; Meredith, L; Mindham, T; Raimbach, J; Tesini, A; Van Uffelen, M

2013-01-01T23:59:59.000Z

327

Power Transmission From The ITER Model Negative Ion Source  

SciTech Connect (OSTI)

In Cadarache development on negative ion sources is being carried out on the KAMABOKO III ion source on the MANTIS test bed. This is a model of the ion source designed for the neutral beam injectors of ITER. This ion source has been developed in collaboration with JAERI, Japan, who also designed and supplied the ion source. Its target performance is to accelerate a D- beam, with a current density of 200 A/m2 and <1 electron extracted per accelerated D- ion, at a source filling pressure of 0.3 Pa. For ITER a continuous ion beam must be assured for pulse lengths of 1000 s, but beams of up to 3,600 s are also envisaged. The ion source is attached to a 3 grid 30 keV accelerator (also supplied by JAERI) and the accelerated negative ion current is determined from the energy deposited on a calorimeter. During long pulse operation ({<=}1000 s) it was found that the current density of both D- and H- beams, measured at the calorimeter was lower than expected and that a large discrepancy existed between the accelerated currents measured electrically and those transmitted to the calorimeter. The possibility that this discrepancy arose because the accelerated current included electrons (which would not be able to reach the calorimeter) was investigated and subsequently eliminated. Further studies have shown that the fraction of the electrical current reaching the calorimeter varies with the pulse length, which led to the suggestion that one or more of the accelerator grids were distorting due to the incident power during operation, leading to a progressive deterioration in the beam quality.. New extraction and acceleration grids have been designed and installed, which should have a better tolerance to thermal loads than those previously used. This paper describes the measurements of the power transmission and distribution using these grids.

Boilson, D. [Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland); Esch, H. P. L. de; Grand, C.; Hemsworth, R. S.; Krylov, A. [Association EURATOM-CEA, CEA/DSM/DRFC, CEA-Cadarache, 13108 St Paul-Lez-Durance (France)

2007-08-10T23:59:59.000Z

328

Development of the bus joint for the ITER Central Solenoid  

SciTech Connect (OSTI)

The terminations of the Central Solenoid (CS) modules are connected to the bus extensions by joints located outside the CS in the gap between the CS and Torodial Field (TF) assemblies. These joints have very strict space limitations. Low resistance is a common requirement for all ITER joints. In addition, the CS bus joints will experience and must be designed to withstand significant variation in the magnetic field of several tenths of a Tesla per second during initiation of plasma. The joint resistance is specified to be less than 4 nOhm. The joints also have to be soldered in the field and designed with the possibility to be installed and dismantled in order to allow cold testing in the cold test facility. We have developed coaxial joints that meet these requirements and have demonstrated the feasibility to fabricate and assemble them in the vertical configuration. We introduced a coupling cylinder with superconducting strands soldered to the surface of the cable that can be installed in the ITER assembly hall and at the Cold Test Facility. This cylinder serves as a transition area between the CS module and the bus extension. We made two racetrack samples and tested four bus joints in our Joint Test Apparatus. Resistance of the bus joints was measured by a decay method and by a microvoltmeter; the value of the current was measured by the Hall probes. This measurement method was verified in the previous tests. The resistance of the joints varied insignificantly from 1.5 to 2 nOhm. One of the challenges associated with a soldered joint is the inability to use corrosive chemicals that are difficult to clean. This paper describes our development work on cable preparation, chrome removal, compaction, soldering, and final assembly and presents the test results.

Martovetsky, Nicolai N [ORNL] [ORNL; Irick, David Kim [ORNL] [ORNL; Kenney, Steven J [ORNL] [ORNL

2013-01-01T23:59:59.000Z

329

Evolution of Plasma Parameters in the Termination Phase of High Confinement H-modes at JET and Implications for ITER  

E-Print Network [OSTI]

Evolution of Plasma Parameters in the Termination Phase of High Confinement H-modes at JET and Implications for ITER

330

Reconstruction of Distribution Functions of Fast Ions and Runaway Electrons in ITER Plasmas Using Gamma-Ray Spectrometry  

E-Print Network [OSTI]

Reconstruction of Distribution Functions of Fast Ions and Runaway Electrons in ITER Plasmas Using Gamma-Ray Spectrometry

331

High-Energy Fuel Ion Diagnostics on ITER Derived from Neutron Emission Spectroscopy Measurements on JET DT Plasmas  

E-Print Network [OSTI]

High-Energy Fuel Ion Diagnostics on ITER Derived from Neutron Emission Spectroscopy Measurements on JET DT Plasmas

332

Analysis of Rotating Collectors from the Private Region of JET with Carbon Wall and Metallic ITER-Like Wall  

E-Print Network [OSTI]

Analysis of Rotating Collectors from the Private Region of JET with Carbon Wall and Metallic ITER-Like Wall

333

The ITERThe ITER eraera : the 10: the 10 yearyear roadmaproadmap for the French fusion programmefor the French fusion programme  

E-Print Network [OSTI]

-2035 : The Fusion Energy Era of magnetic fusion research ITER thermonuclear plasmasITER thermonuclear plasmasThe ITERThe ITER eraera : the 10: the 10 yearyear roadmaproadmap for the French fusion programmefor the French fusion programme E. Tsitrone1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint

334

Smart Grid Integration Laboratory  

SciTech Connect (OSTI)

The initial federal funding for the Colorado State University Smart Grid Integration Laboratory is through a Congressionally Directed Project (CDP), DE-OE0000070 Smart Grid Integration Laboratory. The original program requested in three one-year increments for staff acquisition, curriculum development, and instrumentation ?? all which will benefit the Laboratory. This report focuses on the initial phase of staff acquisition which was directed and administered by DOE NETL/ West Virginia under Project Officer Tom George. Using this CDP funding, we have developed the leadership and intellectual capacity for the SGIC. This was accomplished by investing (hiring) a core team of Smart Grid Systems engineering faculty focused on education, research, and innovation of a secure and smart grid infrastructure. The Smart Grid Integration Laboratory will be housed with the separately funded Integrid Laboratory as part of CSU??s overall Smart Grid Integration Center (SGIC). The period of performance of this grant was 10/1/2009 to 9/30/2011 which included one no cost extension due to time delays in faculty hiring. The Smart Grid Integration Laboratory??s focus is to build foundations to help graduate and undergraduates acquire systems engineering knowledge; conduct innovative research; and team externally with grid smart organizations. Using the results of the separately funded Smart Grid Workforce Education Workshop (May 2009) sponsored by the City of Fort Collins, Northern Colorado Clean Energy Cluster, Colorado State University Continuing Education, Spirae, and Siemens has been used to guide the hiring of faculty, program curriculum and education plan. This project develops faculty leaders with the intellectual capacity to inspire its students to become leaders that substantially contribute to the development and maintenance of Smart Grid infrastructure through topics such as: (1) Distributed energy systems modeling and control; (2) Energy and power conversion; (3) Simulation of electrical power distribution system that integrates significant quantities of renewable and distributed energy resources; (4) System dynamic modeling that considers end-user behavior, economics, security and regulatory frameworks; (5) Best practices for energy management IT control solutions for effective distributed energy integration (including security with the underlying physical power systems); (6) Experimental verification of effects of various arrangements of renewable generation, distributed generation and user load types along with conventional generation and transmission. Understanding the core technologies for enabling them to be used in an integrated fashion within a distribution network remains is a benefit to the future energy paradigm and future and present energy engineers.

Wade Troxell

2011-09-30T23:59:59.000Z

335

Financing Solutions | Department of Energy  

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

Solution Center Financing Solutions Financing Solutions Transitioning to a clean energy economy requires innovative financing solutions that enable state, local, and tribal...

336

Numerical integration of variational equations  

E-Print Network [OSTI]

We present and compare different numerical schemes for the integration of the variational equations of autonomous Hamiltonian systems whose kinetic energy is quadratic in the generalized momenta and whose potential is a function of the generalized positions. We apply these techniques to Hamiltonian systems of various degrees of freedom, and investigate their efficiency in accurately reproducing well-known properties of chaos indicators like the Lyapunov Characteristic Exponents (LCEs) and the Generalized Alignment Indices (GALIs). We find that the best numerical performance is exhibited by the \\textit{`tangent map (TM) method'}, a scheme based on symplectic integration techniques which proves to be optimal in speed and accuracy. According to this method, a symplectic integrator is used to approximate the solution of the Hamilton's equations of motion by the repeated action of a symplectic map $S$, while the corresponding tangent map $TS$, is used for the integration of the variational equations. A simple and systematic technique to construct $TS$ is also presented.

Ch. Skokos; E. Gerlach

2010-09-29T23:59:59.000Z

337

Formation and Sustainment of ITPs in ITER with the Baseline Heating Mix  

SciTech Connect (OSTI)

Plasmas with internal transport barriers (ITBs) are a potential and attractive route to steady-state operation in ITER. These plasmas exhibit radially localized regions of improved con nement with steep pressure gradients in the plasma core, which drive large bootstrap current and generate hollow current pro les and negative shear. This work examines the formation and sustainment of ITBs in ITER with electron cyclotron heating and current drive. It is shown that, with a trade-o of the power delivered to the equatorial and to the upper launcher, the sustainment of steady-state ITBs can be demonstrated in ITER with the baseline heating con guration.

Francesca M. Poli and Charles Kessel

2012-12-03T23:59:59.000Z

338

RF-sheath heat flux estimates on Tore Supra and JET ICRF antennae. Extrapolation to ITER  

SciTech Connect (OSTI)

RF-sheath induced heat loads are identified from infrared thermography measurements on Tore Supra ITER-like prototype and JET A2 antennae, and are quantified by fitting thermal calculations. Using a simple scaling law assessed experimentally, the estimated heat fluxes are then extrapolated to the ITER ICRF launcher delivering 20 MW RF power for several plasma scenarios. Parallel heat fluxes up to 6.7 MW/m{sup 2} are expected very locally on ITER antenna front face. The role of edge density on operation is stressed as a trade-off between easy RF coupling and reasonable heat loads. Sources of uncertainty on the results are identified.

Colas, L.; Portafaix, C.; Goniche, M. [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Jacquet, Ph. [EURATOM/UKAEA Fusion Association, Culham, OX14 3DB (United Kingdom); Agarici, G. [Fusion for Energy, C/Josep Pla 2, E-08019 Barcelona (Spain)

2009-11-26T23:59:59.000Z

339

DECAY OF SOLUTIONS TO A WATER WAVE MODEL WITH A ...  

E-Print Network [OSTI]

present article, we restrict the analysis of (1.1) to one-way waves. With the usual ..... In order to derive the integral form of the solution to (2.2), we apply the...

2009-07-15T23:59:59.000Z

340

Integrative Bioengineering Institute  

SciTech Connect (OSTI)

Microfabrication enables many exciting experimental possibilities for medicine and biology that are not attainable through traditional methods. However, in order for microfabricated devices to have an impact they must not only provide a robust solution to a current unmet need, but also be simple enough to seamlessly integrate into standard protocols. Broad dissemination of bioMEMS has been stymied by the common aim of replacing established and well accepted protocols with equally or more complex devices, methods, or materials. The marriage of a complex, difficult to fabricate bioMEMS device with a highly variable biological system is rarely successful. Instead, the design philosophy of my lab aims to leverage a beneficial microscale phenomena (e.g. fast diffusion at the microscale) within a bioMEMS device and adapt to established methods (e.g. multiwell plate cell culture) and demonstrate a new paradigm for the field (adapt instead of replace). In order for the field of bioMEMS to mature beyond novel proof-of-concept demonstrations, researchers must focus on developing systems leveraging these phenomena and integrating into standard labs, which have largely been ignored. Towards this aim, the Integrative Bioengineering Institute has been established.

Eddington, David; Magin,L,Richard; Hetling, John; Cho, Michael

2009-01-09T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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 the Long Pulse Negative Ion Source for ITER  

SciTech Connect (OSTI)

A model of the ion source designed for the neutral beam injectors of the International Thermonuclear Experimental Reactor (ITER), the KAMABOKO III ion source, is being tested on the MANTIS test stand at the DRFC Cadarache in collaboration with JAERI, Japan, who designed and supplied the ion source. The ion source is attached to a 3 grid 30 keV accelerator (also supplied by JAERI) and the accelerated negative ion current is determined from the energy deposited on a calorimeter located 1.6 m from the source.During experiments on MANTIS three adverse effects of long pulse operation were found: The negative ion current to the calorimeter is {approx_equal}50% of that obtained from short pulse operation Increasing the plasma grid (PG) temperature results in {<=}40% enhancement in negative ion yield, substantially below that reported for short pulse operation, {>=}100%. The caesium 'consumption' is up to 1500 times that expected.Results presented here indicate that each of these is, at least partially, explained by thermal effects. Additionally presented are the results of a detailed characterisation of the source, which enable the most efficient mode of operation to be identified.

Hemsworth, R.S.; Svensson, L.; Esch, H.P.L. de; Krylov, A.; Massmann, P. [Association EURATOM-CEA, CEA/DSM/DRFC, CEA-Cadarache, 13108 St Paul-lez-Durance (France); Boilson, D. [Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland); Fanz, U. [Association EURATOM-IPP, Max-Planck-Institut fuer Plasmaphysik D-85748 Garching (Germany); Zaniol, B. [CONSORZIO RFX Association EURATOM-ENEA, Corso Stati Uniti 4, I-35127 Padova (Italy)

2005-04-06T23:59:59.000Z

342

Status of the Design of the ITER ECE Diagnostic  

SciTech Connect (OSTI)

The baseline design for the ITER electron cyclotron emission (ECE) diagnostic has entered the detailed preliminary design phase. Two plasma views are planned, a radial view and an oblique view that is sensitive to distortions in the electron momentum distribution near the average thermal momentum. Both views provide high spatial resolution electron temperature profiles when the momentum distribution remains Maxwellian. The ECE diagnostic system consists of the front-end optics, including two 1000 K calibration sources, in equatorial port plug EP9, the 70-1000 GHz transmission system from the front-end to the diagnostics hall, and the ECE instrumentation in the diagnostics hall. The baseline ECE instrumentation will include two Michelson interferometers that can simultaneously measure ordinary and extraordinary mode ECE from 70 to 1000 GHz, and two heterodyne radiometer systems, covering 122-230 GHz and 244-355 GHz. Significant design challenges include 1) developing highly-reliable 1000 K calibration sources and the associated shutters/mirrors, 2) providing compliant couplings between the front-end optics and the polarization splitter box that accommodate displacements of the vacuum vessel during plasma operations and bake out, 3) protecting components from damage due to stray ECH radiation and other intense millimeter wave emission and 4) providing the low-loss broadband transmission system.

Taylor, Gary [PPPL

2014-04-01T23:59:59.000Z

343

An assessment of the base blanket for ITER  

SciTech Connect (OSTI)

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inventory. However, some concerns regarding the risk, cost and benefit of the base blanket have been raised. These include uncertainties associated with the solid breeder thermal control and the potentially high cost of the amount of Be used to achieve high TBR and to provide the necessary thermal barrier between the high temperature solid breeder and low temperature coolant. This work addresses these concerns. The basis for the selection of a breeding blanket is first discussed in light of the incremental risk, cost and benefits relative to a non-breeding blanket. Key issues associated with the CDA breeding blanket configurations are then analyzed. Finally, alternative schemes that could enhance the attractiveness and flexibility of a breeding blanket are explored.

Raffray, A.R.; Abdou, M.A.; Ying, A.

1991-01-01T23:59:59.000Z

344

Helium-cooled solid breeder blanket for ITER  

SciTech Connect (OSTI)

This paper summarizes the latest results of a design study of a helium-cooled solid breeder blanket for ITER. Attractive features of this design include the following: (1) There is a significant design margin since only part of the allowable solid breeder temperature window needs to be used. (2) There is an expanding data base available from solid breeder experiments carried out internationally. (3) The solid breeder can be designed to operate at high reactor-relevant temperature, while the helium is kept at moderate temperature and pressure for safety and reliability. In addition, since helium is a gas, it can be run so as to optimize the structure temperature and accommodate long term power variation without incurring any substantial pressure penalty. (4) The use of helium, an inert gas minimizing any chemical reaction and corrosion, in combination with a low activation solid breeder, is a safety advantage. An extensive list of the blanket operating parameters is provided and key factors are discussed.

Raffray, A.R.; Abdou, M.A.; Chou, P.; Gorbis, Z.; Tillack, M.; Watanabe, Y.; Ying, A.

1989-03-01T23:59:59.000Z

345

An Overview of the US DCLL ITER-TBM Program  

SciTech Connect (OSTI)

Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based flow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a thermal insulator to separate the high-temperature Pb-17Li (650700 C) from the RAF/M structure, which has a corrosion temperature limit of 480 C. The RAF/M material must also operate at temperatures above 350 C but less than 550 C. We are continuing the development of the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. This paper is a summary report on the progress and results of recent DCLL TBM development activities.

C.P.C. Wong; M. Abdou; M. Dagher; Y. Katoh; B. J. Merrill

2010-12-01T23:59:59.000Z

346

An overview of the US DCLL ITER-TBM program  

SciTech Connect (OSTI)

Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal ef?ciency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the ?rst wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based ?ow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a ther- mal insulator to separate the high-temperature Pb-17Li (?650700 ? C) from the RAF/M structure, which has a corrosion temperature limit of ?480 ? C. The RAF/M material must also operate at temperatures above 350 ? C but less than 550 ? C. We are continuing the development of the mechanical design and per- forming neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. This paper is a summary report on the progress and results of recent DCLL TBM development activities.

Wong, Clement; Abdou, Mohamed A.; Dagher, Mohamad; Katoh, Yutai; Kurtz, Richard J.; Malang, S.; Marriott, Edward P.; Merrill, Brad; Messadek, Karim; Morley, Neil; Sawan, M.; Sharafat, Shahran; Smolentsev, S.; Sze, Dai Kai; Willms, Scott; Ying, A. Y.; Youssef, M.

2010-12-01T23:59:59.000Z

347

An Overview of the US DCLL ITER TBM Program  

SciTech Connect (OSTI)

Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM) for testing in ITER. The DCLL blanket concept has the potential to be a high-performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled Pb-17Li breeder is circulated for power conversion and for tritium extraction. A SiC-based flow channel insert (FCI) is used as an electrical insulator for magnetohydrodynamic pressure drop reduction from the circulating Pb-17Li and as a thermal insulator to separate the high-temperature Pb-17Li ({approx}650-700 C) from the RAF/M structure, which has a corrosion temperature limit of {approx}480 C. The RAF/M material must also operate at temperatures above 350 C but less than 550 C. We are continuing the development of the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. Prototypical FCI structures were fabricated and further attention was paid to MHD effects and the design of the inboard blanket for DEMO. We are also making progress on related R&D needs to address key areas. This paper is a summary report on the progress and results of recent DCLL TBM development activities.

Wong, C. P. C. [General Atomics, San Diego; Abdou, M [University of California, Los Angeles; Dagher, M [University of California, Los Angeles; Katoh, Yutai [ORNL; Kurtz, Richard [Pacific Northwest National Laboratory (PNNL); Malang, Siegfried [Consultant; Marriott, Edward [University of Wisconsin, Madison; Merrill, Brad [Idaho National Laboratory (INL); Messadek, K [University of California, Los Angeles; Morley, N.B. [University of California, Los Angeles; Pint, Bruce A [ORNL; Sawan, M. [University of Wisconsin; Sharafat, S [University of California, Los Angeles; Smolentsev, Sergey [University of California, Los Angeles; Sze, Dai-Kai [University of California, San Diego; Willms, Scott [Los Alamos National Laboratory (LANL); Ying, Alice [University of California, Los Angeles; Youssef, M Z [University of California, Los Angeles

2010-01-01T23:59:59.000Z

348

An assessment of the base blanket for ITER  

SciTech Connect (OSTI)

Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inventory. However, some concerns regarding the risk, cost and benefit of the base blanket have been raised. These include uncertainties associated with the solid breeder thermal control and the potentially high cost of the amount of Be used to achieve high TBR and to provide the necessary thermal barrier between the high temperature solid breeder and low temperature coolant. This work addresses these concerns. The basis for the selection of a breeding blanket is first discussed in light of the incremental risk, cost and benefits relative to a non-breeding blanket. Key issues associated with the CDA breeding blanket configurations are then analyzed. Finally, alternative schemes that could enhance the attractiveness and flexibility of a breeding blanket are explored.

Raffray, A.R.; Abdou, M.A.; Ying, A.

1991-12-31T23:59:59.000Z

349

Integrable cases of gravitating static isothermal fluid spheres  

E-Print Network [OSTI]

It is shown that different approaches towards the solution of the Einstein equations for a static spherically symmetric perfect fluid with a gamma-law equation of state lead to an Abel differential equation of the second kind. Its only integrable cases at present are flat spacetime, de Sitter solution and its Buchdahl transform, Einstein static universe and the Klein-Tolman solution.

B. V. Ivanov

2001-07-17T23:59:59.000Z

350

Attachment to Joint Declaration of the Ministerial Meeting for ITER Moscow, 28th  

E-Print Network [OSTI]

centre for fusion science a centre for remote experimentation - Fusion power plant technology co include: - IFMIF (EVEDA and/or facility) - ITER research centre(s): including, a computational simulation

351

Iterative nonlinear beam propagation method and its application in nonlinear devices  

E-Print Network [OSTI]

In this thesis, an iterative nonlinear beam propagation method is introduced and applied to optical devices. This method is based on Hamiltonian ray tracing and the Wigner distribution function. First, wave propagation ...

Gao, Hanhong

2011-01-01T23:59:59.000Z

352

BPO Inputs to ITER Design Review on Pellet Pacing, RMP and RWM Coils,  

E-Print Network [OSTI]

by Energy Loss Loarte estimated the maximum fueling rate consistent with a convective power loss to ITER. Convective power loss constrains to 5.4 1022 atoms/s consistent with Q=10 performance. #12;A

353

Annual Report of the EURATOM/UKAEA Fusion Programme 2006/07 8 ITER and IFMIF  

E-Print Network [OSTI]

of the International Fusion Materials Irradiation Facility (IFMIF), the main facility other than ITER that is needed.1), the components in the plug and the remainder of the systems (relay optics etc to areas with detectors

354

Calculation and measurement of higher order mode losses in ITER ECH transmission lines  

E-Print Network [OSTI]

The ITER transmission lines (TLs) must be designed to deliver 20 MW from a 24 MW, 170 GHz gyrotron system. Miter bends are the main source of loss for these highly overmoded, corrugated, cylindrical waveguide TLs. Previous ...

Temkin, Richard J.

355

Iterative equalization and decoding using reduced-state sequence estimation based soft-output algorithms  

E-Print Network [OSTI]

We study and analyze the performance of iterative equalization and decoding (IED) using an M-BCJR equalizer. We use bit error rate (BER), frame error rate simulations and extrinsic information transfer (EXIT) charts to study and compare...

Tamma, Raja Venkatesh

2004-09-30T23:59:59.000Z

356

Tritium inventory control in ITER Charles Skinner with key contributions from  

E-Print Network [OSTI]

Tritium inventory control in ITER Charles Skinner with key contributions from Charles Gentile permitted" Tritium inventory control Worrisome issue: Once at the tritium limit there won't be any more

Princeton Plasma Physics Laboratory

357

robustly minimal iterated function systems Department of Mathematics, Ferdowsi University of Mashhad, Iran  

E-Print Network [OSTI]

University of Mashhad, Iran f h ghane@yahoo.com A.J. Homburg Korteweg-de Vries Institute for Mathematics University of Mashhad, Iran ali.sarizadeh@gmail.com August 6, 2009 Abstract We construct iterated function

Homburg, Ale Jan

358

Predictive capabilities, analysis and experiments for Fusion Nuclear Technology, and ITER R D  

SciTech Connect (OSTI)

This report discusses the following topics on ITER research and development: trituim modeling; liquid metal blanket modeling; free surface liquid metal studies; and thermal conductance and thermal control experiments and modeling. (LIP)

Not Available

1991-01-01T23:59:59.000Z

359

The European Joint Undertaking for ITER and the Development of Fusion Energy  

E-Print Network [OSTI]

· Manage procurement and Quality Assurance · Arrange to make European staff available to ITER · Interface · Transparency ­ decision making process and Financial Regulation rules · Synergy and Complementarity

360

Future Climate Engineering Solutions  

E-Print Network [OSTI]

Future Climate Engineering Solutions Joint report 13 engineering participating engeneering. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11 Engineering Solutions A Climate call from engineers. . . . . . . . . . . . . . . . . . . . .23 Summaries of National Reports . . . . . . . . . . . . . . . . . . . .25 Summary of The Climate Plan

Note: This page contains sample records for the topic "integrated iterative solution" 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

ITER as a Physics Experiment K.Lackner, D. Campbell and many others  

E-Print Network [OSTI]

: -> only full CD,ELMy H-mode cases shown JT-60U RS JT-60U high bp ITER & Power Plant: higher n-mode access, ELMs, NTMs..) · qualify a-particle heating as a heating method · high power/long pulse (on wall of sawteeth (JET) AUG DIII- D #12;Q =10: ITER-simulation discharges on JET JET-operating space #12;Q =10

362

Vacuum photodiode detectors for soft x-ray ITER plasma tomography  

SciTech Connect (OSTI)

A special type of vacuum photodiode detector (VPD) for x-ray tomography of (ITER) plasma is described. Laboratory experiments demonstrate that VPD has high sensitivity to thermal x-rays and low sensitivity to hard gamma rays and neutrons. It was shown that in ITER environment the signal due to thermal x-rays will surpass the background signal by more than a factor of 100.

Gott, Yu.V.; Stepanenko, M.M. [RRC, Nuclear Fusion Institute, Kurchatov sq.1, Moscow, 123182 (Russian Federation)

2005-07-15T23:59:59.000Z

363

Qualification of the US made conductors for ITER TF magnet system  

SciTech Connect (OSTI)

The US Domestic Agency (USDA) is one of the six suppliers of the TF conductor for ITER. In order to qualify conductors according to ITER requirements we prepared several lengths of the CICC and short samples for testing in the SULTAN facility in CRPP, Switzerland. We also fully characterized the strands that were used in these SULTAN samples. Fabrication experience and test results are presented and discussed.

Martovetsky, N; Hatfield, D; Miller, J; Bruzzone, P; Stepanov, B; Seber, B

2009-10-08T23:59:59.000Z

364

Toroidal field coil replacement study for the International Thermonuclear Experimental Reactor (ITER)  

SciTech Connect (OSTI)

The objective of this study is to develop an estimate of the time required to replace a failed toroidal field (TF) coil in the International Thermonuclear Experimental Reactor (ITER). This estimate is based on the current ITER design which resulted from the Conceptual Design Activities began in spring of 1988 and ending in December 1990. Although the TF Coils in ITER are designated permanent components and expected to last the life of the plant, the history of failures of large coils in fusion devices has prompted an assessment of the down time that might be required for replacement of a failed TF coil in ITER. The difficulty of replacement of a TF Coil in ITER is compounded by the large physical size of ITER, and the radiation fields which necessitate the use of remote handling equipment for most maintenance activities. Since 10 out of 16 TF coils are adjacent to either a Neutral Beam Injector (NBI) port or a remote handling (RH) port, it is probable that a failed TF Coil will be in one of these inconvenient locations. For this study, TF coil number 3 is assumed to fail and its replacement will be evaluated as a typical case. TF coil number 3 is located between a remote handling port ({number sign}3) and a port allocated to the lower hybrid ({number sign}4).

Not Available

1991-08-01T23:59:59.000Z

365

Toroidal field coil replacement study for the International Thermonuclear Experimental Reactor (ITER)  

SciTech Connect (OSTI)

The objective of this study is to develop an estimate of the time required to replace a failed toroidal field (TF) coil in the International Thermonuclear Experimental Reactor (ITER). This estimate is based on the current ITER design which resulted from the Conceptual Design Activities began in spring of 1988 and ending in December 1990. Although the TF Coils in ITER are designated permanent components and expected to last the life of the plant, the history of failures of large coils in fusion devices has prompted an assessment of the down time that might be required for replacement of a failed TF coil in ITER. The difficulty of replacement of a TF Coil in ITER is compounded by the large physical size of ITER, and the radiation fields which necessitate the use of remote handling equipment for most maintenance activities. Since 10 out of 16 TF coils are adjacent to either a Neutral Beam Injector (NBI) port or a remote handling (RH) port, it is probable that a failed TF Coil will be in one of these inconvenient locations. For this study, TF coil number 3 is assumed to fail and its replacement will be evaluated as a typical case. TF coil number 3 is located between a remote handling port ({number_sign}3) and a port allocated to the lower hybrid ({number_sign}4).

Not Available

1991-08-01T23:59:59.000Z

366

Lightweight Steel Solutions for Automotive Industry  

SciTech Connect (OSTI)

Recently, improvement in fuel efficiency and safety has become the biggest issue in worldwide automotive industry. Although the regulation of environment and safety has been tightened up more and more, the majority of vehicle bodies are still manufactured from stamped steel components. This means that the optimized steel solutions enable to demonstrate its ability to reduce body weight with high crashworthiness performance instead of expensive light weight materials such as Al, Mg and composites. To provide the innovative steel solutions for automotive industry, POSCO has developed AHSS and its application technologies, which is directly connected to EVI activities. EVI is a technical cooperation program with customer covering all stages of new car project from design to mass production. Integrated light weight solutions through new forming technologies such as TWB, hydroforming and HPF are continuously developed and provided for EVI activities. This paper will discuss the detailed status of these technologies especially light weight steel solutions based on innovative technologies.

Lee, Hong Woo; Kim, Gyosung; Park, Sung Ho [Technical Research Laboratories, POSCO, 699, Gumho-dong, Gwangyang-si, Jeonnam, 545-090 (Korea, Republic of)

2010-06-15T23:59:59.000Z

367

Helium-cooled lithiuim compound suspension blanket concept for ITER  

SciTech Connect (OSTI)

This blanket concept uses a dilute suspension of fine solid breeder particles (Li/sub 2/O, LiAlO/sub 2/, or Li/sub 4/SiO/sub 4/) in a carrier gas (He) as the coolant and the tritium breeding stream. A small fraction of this stream is processed outside the reactor for tritium recovery. The blanket consists of a beryllium multiplier and carbon/steel reflector. A steel clad is used for all materials. A carbon reflector is employed to reduce the beryllium thickness used in the blanket for a specific tritium breeding ratio. The breeder particle size has to exceed few microns (greater than or equal to2 microns) to avoid sticking problems on the cold surfaces of the heat exchanger. The helium gas pressure is in the range of 2 to 3 MPa to carry the blanket and the heat exchanger loop. The solid breeder concentration in the helium stream is 1 to 5 volume percent. A high lithium-6 enrichment is used to produce a high tritium breeding ratio and to reduce the breeder concentration in the helium gas. At a lithium-6 enrichment of 90%, the local tritium breeding ratio is 2.03 based on a one-dimensional poloidal model. The total thickness of the helium stream is only 4 cm out of the 50 cm total blanket thickness. The blanket uses a 35 cm of beryllium for neutron multiplication. A simple multi-layer design is employed where the blanket sector has the helium coolant flowing in the poloidal direction. The blanket concept has several unique advantages which are very beneficial for fusion reactors including ITER. 10 refs., 2 tabs.

Gohar, Y.; Baker, C.C.; Attaya, H.; Billone, M.; Clemmer, R.C.; Finn, P.A.; Hassanein, A.; Johnson, C.E.; Majumdar, S.; Mattas, R.F.

1988-08-01T23:59:59.000Z

368

Pellet Fueling Technology Development Leading to Efficient Fueling of ITER Burning Plasmas  

SciTech Connect (OSTI)

Pellet injection is the primary fueling technique planned for central fueling of the ITER burning plasma, which is a requirement for achieving high fusion gain. Injection of pellets from the inner wall has been shown on present day tokamaks to provide efficient fueling and is planned for use on ITER [1,2]. Significant development of pellet fueling technology has occurred as a result of the ITER R&D process. Extrusion rates with batch extruders have reached more than 1/2 of the ITER design specification of 1.3 cm3/s [3] and the ability to fuel efficiently from the inner wall by injecting through curved guide tubes has been demonstrated on several fusion devices. Modeling of the fueling deposition from inner wall pellet injection has been done using the Parks et al. ExB drift model [4] shows that inside launched pellets of 3mm size and speeds of 300 m/s have the capability to fuel well inside the separatrix. Gas fueling on the other hand is calculated to have very poor fueling efficiency due to the high density and wide scrape off layer compared to current machines. Isotopically mixed D/T pellets can provide efficient tritium fueling that will minimize tritium wall loading when compared to gas puffing of tritium. In addition, the use of pellets as an ELM trigger has been demonstrated and continues to be investigated as an ELM mitigation technique. During the ITER CDA and EDA the U.S. was responsible for ITER fueling system design and R&D and is in good position to resume this role for the ITER pellet fueling system. Currently the performance of the ITER guide tube design is under investigation. A mockup is being built that will allow tests with different pellet sizes and repetition rates. The results of these tests and their implication for fueling efficiency and central fueling will be discussed. The ITER pellet injection technology developments to date, specified requirements, and remaining development issues will be presented along with a plan to reach the design goal in time for employment on ITER.

Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Jernigan, Thomas C [ORNL; Houlberg, Wayne A [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; Owen, Larry W [ORNL; Parks, P. B. [General Atomics; Rasmussen, David A [ORNL

2005-01-01T23:59:59.000Z

369

A Comparison of Some Iterative Methods in Scientific Shawn Sickel  

E-Print Network [OSTI]

is available, Bi-Conjugate Gradient method is then the best choice for the solution of the linear system. In the case where AH is not available, Bi-Conjugate Gradient Stabilized method should be used. #12.2.1 Conjugate gradient method (CG) . . . . . . . . . . . . . . . . . . . . . . 5 2.2.2 Bi-conjugate gradient

Yeung, Man-Chung

370

ITERATE: A Conceptual Clustering Knowledge Discovery in Databases  

E-Print Network [OSTI]

exploration and geology? It is common knowledge that drilling costs for new o shore prospects are in the range in drilling technology and data collection methods have led to oil companies and ancilliary companies new plays and prospects. A possible solution may be in developing the capability for retrieving

371

Parallelization of the Value-Iteration algorithm for  

E-Print Network [OSTI]

and stochastic environment. To determine the solution of a POMDP, algorithms with a running time in the PSPACE using the massive parallel processing power of modern Graphic Processing Units (GPU). Our experiments synchronization features are needed to exploit the full potential. #12;ii #12;Summary (Danish) Delvist

372

Integrated Building Management System (IBMS)  

SciTech Connect (OSTI)

This project provides a combination of software and services that more easily and cost-effectively help to achieve optimized building performance and energy efficiency. Featuring an open-platform, cloud- hosted application suite and an intuitive user experience, this solution simplifies a traditionally very complex process by collecting data from disparate building systems and creating a single, integrated view of building and system performance. The Fault Detection and Diagnostics algorithms developed within the IBMS have been designed and tested as an integrated component of the control algorithms running the equipment being monitored. The algorithms identify the normal control behaviors of the equipment without interfering with the equipment control sequences. The algorithms also work without interfering with any cooperative control sequences operating between different pieces of equipment or building systems. In this manner the FDD algorithms create an integrated building management system.

Anita Lewis

2012-07-01T23:59:59.000Z

373

On convergence of an iterative technique for solution of the implicit relationship between variables in the equations for moist convection  

E-Print Network [OSTI]

N)+M+ Sa (37) (3) a a (O) e a (O) and D) (3S~ R~ R~ ) Ds + (Ss 38~ R~ ) D) + (Ry M + Sr N)+N+ Sa (38) Ifn=3 Dq ? (Sg -6S R +Rq) Dq ? (4S~R~ - 4Sa R') D) + ~(Sj R~)M (2SyR~)N] + (SyM RyN) + M + Sa (39) and 12 D~ = (4SI3RI - I R ) Dk + (Sl ? 6SIRj... CONTINUE )rR I TE ( 6 r 9) I rRR ~ R ( rFC( I ) 9 FORFAT (Tier 'DR( ' r IZr ) r T3lrEl ~ 6 r(R ( TE (6 ~ I I ) I r IF, ( I, IC ( ( ) ll FOR& AT(Tle, rn I(' l2, ') ', T31, El4. 6, T6l, f14. 6, T9[, E14. 6) 200 CONTINUE 119o CONT(NUE RETURN ENO FUNCT...

Perry, Richard Allan

2012-06-07T23:59:59.000Z

374

ITER Building Design (D230-B), Task No. 28. Final report  

SciTech Connect (OSTI)

The International Thermonuclear Experimental Reactor (ITER) Project requires a set of buildings, each with its own distinct function, to support ITER`s mission. The Joint Central Team (JCT) has identified all the buildings in the set and has placed them in an efficient arrangement on the site. The JCT has developed a conceptual layout of each individual building. The buildings have been categorized into two main groups: (1) {open_quotes}Level 1 Buildings{close_quotes} which are on the construction schedule critical path and (2) {open_quotes}Level 2 Buildings{close_quotes} which, while important, are not on the critical path. The buildings are further categorized according to construction material, that is, {open_quotes}reinforced concrete{close_quotes} or {open_quotes}steel-frame on concrete slab{close_quotes}. This Report responds to the Project`s request to perform the initial structural steel design for all the {open_quotes}steel-frame on concrete slab{close_quotes} buildings. Of the twelve (12) {open_quotes}steel-frame on concrete slab{close_quotes} buildings, four (4) are Level 1 and eight (8) are Level 2 Buildings. This Report is a deliverable for the ITER Task Assignment entitled {open_quotes}ITER Buildings Design (D230-B){close_quotes}, also designated as Task No. 28. ITER U.S. Home Team Industrial Consortium members, Raytheon Engineers & Constructors (RE&C) and Stone & Webster Engineering Corporation (SWEC), teamed to perform Task 28. This task commenced in May 1995. It was performed in accordance with the design criteria specified by the ITER-JCT, San Diego Joint Work Site.

NONE

1995-12-01T23:59:59.000Z

375

High Efficiency Integrated Package  

SciTech Connect (OSTI)

Solid-state lighting based on LEDs has emerged as a superior alternative to inefficient conventional lighting, particularly incandescent. LED lighting can lead to 80 percent energy savings; can last 50,000 hours 2-50 times longer than most bulbs; and contains no toxic lead or mercury. However, to enable mass adoption, particularly at the consumer level, the cost of LED luminaires must be reduced by an order of magnitude while achieving superior efficiency, light quality and lifetime. To become viable, energy-efficient replacement solutions must deliver system efficacies of ? 100 lumens per watt (LPW) with excellent color rendering (CRI > 85) at a cost that enables payback cycles of two years or less for commercial applications. This development will enable significant site energy savings as it targets commercial and retail lighting applications that are most sensitive to the lifetime operating costs with their extended operating hours per day. If costs are reduced substantially, dramatic energy savings can be realized by replacing incandescent lighting in the residential market as well. In light of these challenges, Cree proposed to develop a multi-chip integrated LED package with an output of > 1000 lumens of warm white light operating at an efficacy of at least 128 LPW with a CRI > 85. This product will serve as the light engine for replacement lamps and luminaires. At the end of the proposed program, this integrated package was to be used in a proof-of-concept lamp prototype to demonstrate the components viability in a common form factor. During this project Cree SBTC developed an efficient, compact warm-white LED package with an integrated remote color down-converter. Via a combination of intensive optical, electrical, and thermal optimization, a package design was obtained that met nearly all project goals. This package emitted 1295 lm under instant-on, room-temperature testing conditions, with an efficacy of 128.4 lm/W at a color temperature of ~2873K and 83 CRI. As such, the packages performance exceeds DOEs warm-white phosphor LED efficacy target for 2013. At the end of the program, we assembled an A19 sized demonstration bulb housing the integrated package which met Energy Star intensity variation requirements. With further development to reduce overall component cost, we anticipate that an integrated remote converter package such as developed during this program will find application in compact, high-efficacy LED-based lamps, particularly those requiring omnidirectional emission.

Ibbetson, James

2013-09-15T23:59:59.000Z

376

Solution deposition assembly  

DOE Patents [OSTI]

Methods and devices are provided for improved deposition systems. In one embodiment of the present invention, a deposition system is provided for use with a solution and a substrate. The system comprises of a solution deposition apparatus; at least one heating chamber, at least one assembly for holding a solution over the substrate; and a substrate curling apparatus for curling at least one edge of the substrate to define a zone capable of containing a volume of the solution over the substrate. In another embodiment of the present invention, a deposition system for use with a substrate, the system comprising a solution deposition apparatus; at heating chamber; and at least assembly for holding solution over the substrate to allow for a depth of at least about 0.5 microns to 10 mm.

Roussillon, Yann; Scholz, Jeremy H; Shelton, Addison; Green, Geoff T; Utthachoo, Piyaphant

2014-01-21T23:59:59.000Z

377

STATEMENT OF CONSIDERATIONS REQUEST BY GED INTEGRATED SOLUTIONS...  

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

and commercialize a high volume, low material, and low labor cost lnsulating Glass Automation Manufacturing System (IGAMS) for production of reliable highly insulating windows....

378

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

built, and each have been used by researchers from labs in New York. Learn More California Lithium Battery, Inc. Argonne National Laboratory 626 likes California Lithium...

379

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

include transport and stationery power plants, marine, cars and trucks. Learn More California Lithium Battery, Inc. Argonne National Laboratory 626 likes California Lithium...

380

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

to existing buildings with costs comparable to conventional HVAC. Learn More California Lithium Battery, Inc. Argonne National Laboratory 626 likes California Lithium...

Note: This page contains sample records for the topic "integrated iterative solution" 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

Geometric Integration: Numerical Solution of Differential Equations on Manifolds  

E-Print Network [OSTI]

and the solar system. Conserved quantities of a Hamiltonian system, such as energy, linear and angular momentum that they encapsulate. The importance of geometry has been widely acknowledged in both pure and ap­ plied research

Burton, Geoffrey R.

382

Integrating Security Solutions to Support nanoCMOS Electronics Research .  

E-Print Network [OSTI]

??The UK Engineering and Physical Sciences Research Council (EPSRC) funded Meeting the Design Challenges of nanoCMOS Electronics (nanoCMOS) is developing a research infrastructure for collaborative (more)

SINNOTT, RICHARD

2008-01-01T23:59:59.000Z

383

Integrating Security Solutions to Support nanoCMOS Electronics Research  

E-Print Network [OSTI]

Sinnott,R.O. Asenov,A. Bayliss,C. Davenhall,C. Doherty,T. Harbulot,B. Jones,M. Martin,D. Millar,C. Roy,G. Roy,S. Stewart,G. Watt,J. IEEE International Symposium on Parallel and Distributed Processing Systems with Applications, Sydney Australia, December 2008.

Sinnott, R.O.

384

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

is developing a low-cost, advanced lithium-ion battery that employs a novel silicon graphene composite material that will substantially improve battery cycle life. When combined...

385

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomentheATLANTA,Fermi NationalBusiness PlanPostingOctoberof Energy U.S. goal to333

386

Enhancing Performance Contracts: Integrating IAQ Solutions in Hot & Humid Climates  

E-Print Network [OSTI]

into performance contract offerings, these enhancements can add value to an energy service company's qualifications and proposals. This translation of IAQ insight into market advantage is a significant opportunity for energy senrice companies in an increasingly...

Turner, S. C.

1998-01-01T23:59:59.000Z

387

Demonstrating & Deploying Integrated Retrofit Technologies & Solutions  

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 Pump Models | Department1 Prepared1217 Release Notes Dekkerbegins on

388

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartmentJune 20, 2012 The12,1, 2005ForCONFERENCELandfill7AC

389

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartmentJune 20, 2012 The12,1,

390

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartmentJune 20, 2012 The12,1,TrakLok Corporation Oak Ridge

391

Integrated Dynamic Electron Solutions, Inc. | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarly Career Scientists'Montana.ProgramJulietipDepartmentJune 20, 2012 The12,1,TrakLok Corporation Oak

392

Demonstrating and Deploying Integrated Retrofit Technologies and Solutions  

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 in Review: TopEnergy DOEDealing With the Issues of NuclearHighStatement| Department of-

393

Exhibit 1C Patent Rights Retention by the Seller ITER UT-B Contracts Div Page 1 of 5  

E-Print Network [OSTI]

Exhibit 1C ­ Patent Rights ­ Retention by the Seller ­ ITER UT-B Contracts Div March 2007 Page 1 of 5 ex1c-ITER-mar07.doc Exhibit 1C ­ ITER Ref: DEAR 952.227-11 PATENT RIGHTS - RETENTION BY THE SELLER is or may be patentable or otherwise protectable under title 35 of the United States Code, or any novel

Pennycook, Steve

394

Mixed oxide solid solutions  

DOE Patents [OSTI]

The present invention is a mixed oxide solid solution containing a tetravalent and a pentavalent cation that can be used as a support for a metal combustion catalyst. The invention is furthermore a combustion catalyst containing the mixed oxide solid solution and a method of making the mixed oxide solid solution. The tetravalent cation is zirconium(+4), hafnium(+4) or thorium(+4). In one embodiment, the pentavalent cation is tantalum(+5), niobium(+5) or bismuth(+5). Mixed oxide solid solutions of the present invention exhibit enhanced thermal stability, maintaining relatively high surface areas at high temperatures in the presence of water vapor.

Magno, Scott (Dublin, CA); Wang, Ruiping (Fremont, CA); Derouane, Eric (Liverpool, GB)

2003-01-01T23:59:59.000Z

395

ITER vacuum vessel fabrication plan and cost study (D 68) for the international thermonuclear experimental reactor  

SciTech Connect (OSTI)

ITER Task No. 8, Vacuum Vessel Fabrication Plan and Cost Study (D68), was initiated to assess ITER vacuum vessel fabrication, assembly, and cost. The industrial team of Raytheon Engineers & Constructors and Chicago Bridge & Iron (Raytheon/CB&I) reviewed the current vessel basis and prepared a manufacturing plan, assembly plan, and cost estimate commensurate with the present design. The guidance for the Raytheon/CB&I assessment activities was prepared by the ITER Garching Work Site. This guidance provided in the form of work descriptions, sketches, drawings, and costing guidelines for each of the presently identified vacuum vessel Work Breakdown Structure (WBS) elements was compiled in ITER Garching Joint Work Site Memo (Draft No. 9 - G 15 MD 01 94-17-05 W 1). A copy of this document is provided as Appendix 1 to this report. Additional information and clarifications required for the Raytheon/CB&I assessments were coordinated through the US Home Team (USHT) and its technical representative. Design details considered essential to the Task 8 assessments but not available from the ITER Joint Central Team (JCT) were generated by Raytheon/CB&I and documented accordingly.

NONE

1995-01-01T23:59:59.000Z

396

Status of the 1 MeV Accelerator Design for ITER NBI  

SciTech Connect (OSTI)

The beam source of neutral beam heating/current drive system for ITER is needed to accelerate the negative ion beam of 40A with D{sup -} at 1 MeV for 3600 sec. In order to realize the beam source, design and R and D works are being developed in many institutions under the coordination of ITER organization. The development of the key issues of the ion source including source plasma uniformity, suppression of co-extracted electron in D beam operation and also after the long beam duration time of over a few 100 sec, is progressed mainly in IPP with the facilities of BATMAN, MANITU and RADI. In the near future, ELISE, that will be tested the half size of the ITER ion source, will start the operation in 2011, and then SPIDER, which demonstrates negative ion production and extraction with the same size and same structure as the ITER ion source, will start the operation in 2014 as part of the NBTF. The development of the accelerator is progressed mainly in JAEA with the MeV test facility, and also the computer simulation of beam optics also developed in JAEA, CEA and RFX. The full ITER heating and current drive beam performance will be demonstrated in MITICA, which will start operation in 2016 as part of the NBTF.

Kuriyama, M.; Boilson, D.; Hemsworth, R.; Svensson, L.; Graceffa, J.; Schunke, B.; Decamps, H.; Tanaka, M. [ITER Organization, 13067 Saint-Paul-lez-Durance Cede (France); Bonicelli, T.; Masiello, A. [Fusion for Energy, C/Josep Pla 2, 08019 Barcelona (Spain); Bigi, M.; Chitarin, G.; Luchetta, A.; Marcuzzi, D.; Pasqualotto, R.; Pomaro, N.; Serianni, G.; Sonato, P.; Toigo, V.; Zaccaria, P. [Consorzio RFX. Corso Stati Uniti 4 35127 Padova (Italy)

2011-09-26T23:59:59.000Z

397

An Integrated ACO Approach for the Joint Production and Preventive Maintenance Scheduling  

E-Print Network [OSTI]

An Integrated ACO Approach for the Joint Production and Preventive Maintenance Scheduling Problem, an integrated ACO approach to solve joint production and preventive maintenance scheduling problem very effective solutions for this problem. Key words-- ACO, Production, Preventive maintenance

Paris-Sud XI, Université de

398

Dispersant solutions for dispersing hydrocarbons  

DOE Patents [OSTI]

A dispersant solution includes a hydrocarbon dispersing solution derived from a bacterium from ATCC 75527, ATCC 75529, or ATCC 55638.

Tyndall, Richard L. (Clinton, TN)

1997-01-01T23:59:59.000Z

399

Dispersant solutions for dispersing hydrocarbons  

DOE Patents [OSTI]

A dispersant solution includes a hydrocarbon dispersing solution derived from a bacterium from ATCC 75527, ATCC 75529, or ATCC 55638.

Tyndall, R.L.

1997-03-11T23:59:59.000Z

400

Separations and safeguards model integration.  

SciTech Connect (OSTI)

Research and development of advanced reprocessing plant designs can greatly benefit from the development of a reprocessing plant model capable of transient solvent extraction chemistry. This type of model can be used to optimize the operations of a plant as well as the designs for safeguards, security, and safety. Previous work has integrated a transient solvent extraction simulation module, based on the Solvent Extraction Process Having Interaction Solutes (SEPHIS) code developed at Oak Ridge National Laboratory, with the Separations and Safeguards Performance Model (SSPM) developed at Sandia National Laboratory, as a first step toward creating a more versatile design and evaluation tool. The goal of this work was to strengthen the integration by linking more variables between the two codes. The results from this integrated model show expected operational performance through plant transients. Additionally, ORIGEN source term files were integrated into the SSPM to provide concentrations, radioactivity, neutron emission rate, and thermal power data for various spent fuels. This data was used to generate measurement blocks that can determine the radioactivity, neutron emission rate, or thermal power of any stream or vessel in the plant model. This work examined how the code could be expanded to integrate other separation steps and benchmark the results to other data. Recommendations for future work will be presented.

Cipiti, Benjamin B.; Zinaman, Owen

2010-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Integrated Deployment Model: A Comprehensive Approach to Transforming the Energy Economy  

SciTech Connect (OSTI)

This paper describes the Integrated Deployment model to accelerate market adoption of alternative energy solutions to power homes, businesses, and vehicles through a comprehensive and aggressive approach.

Werner, M.

2010-11-01T23:59:59.000Z

402

Experimental Results with the New ITER-like 1 MV SINGAP Accelerator  

SciTech Connect (OSTI)

A new 'ITER-like' accelerator, which is a scaled down version of the ITER SINGAP (SINgle GAP, SINGle APerture) accelerator, has been built and installed on the Cadarache 1 MV test bed. The objective is to demonstrate reliable D- beam acceleration as close as possible to 1 MeV with a current density j- {approx_equal} 200 A/m2 with the beam optics required for ITER, i.e. a beamlet divergence of {<=}7 mrad and beamlet steering within {+-}2 mrad of that specified. High voltage hold off tests have been performed and 940 kV has been held without breakdowns. The first beams up to 850 keV (D-, 15 A/m2) have been obtained after 4 weeks of experiments and the highest current density that has been obtained so far is 85 A/m2 (D-, 580 keV)

Svensson, L.; Esch, H.P.L. de; Hemsworth, R.S.; Massmann, P. [Association EURATOM-CEA, CEA/DSM/DRFC, CEA -Cadarache, 13108 St Paul-lez-Durance (France); Boilson, D. [Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland)

2005-04-06T23:59:59.000Z

403

Implementation of the Iterative Proportion Fitting Algorithm for Geostatistical Facies Modeling  

SciTech Connect (OSTI)

In geostatistics, most stochastic algorithm for simulation of categorical variables such as facies or rock types require a conditional probability distribution. The multivariate probability distribution of all the grouped locations including the unsampled location permits calculation of the conditional probability directly based on its definition. In this article, the iterative proportion fitting (IPF) algorithm is implemented to infer this multivariate probability. Using the IPF algorithm, the multivariate probability is obtained by iterative modification to an initial estimated multivariate probability using lower order bivariate probabilities as constraints. The imposed bivariate marginal probabilities are inferred from profiles along drill holes or wells. In the IPF process, a sparse matrix is used to calculate the marginal probabilities from the multivariate probability, which makes the iterative fitting more tractable and practical. This algorithm can be extended to higher order marginal probability constraints as used in multiple point statistics. The theoretical framework is developed and illustrated with estimation and simulation example.

Li Yupeng, E-mail: yupeng@ualberta.ca; Deutsch, Clayton V. [University of Alberta (Canada)

2012-06-15T23:59:59.000Z

404

Tungsten spectroscopy relevant to the diagnostics development of ITER divertor plasmas  

SciTech Connect (OSTI)

The ITER tokamak will have tungsten divertor tiles and, consequently, the divertor plasmas are expected to contain tungsten ions. The spectral emission from these ions can serve to diagnose the divertor for plasma parameters such as tungsten concentrations, densities, ion and electron temperatures, and flow velocities. The ITER divertor plasmas will likely have densities around 10{sup 14-15} cm{sup -3} and temperatures below 150 eV. These conditions are similar to the plasmas at the Sustained Spheromak Physics Experiment (SSPX) in Livermore. To simulate ITER divertor plasmas, a tungsten impurity was introduced into the SSPX spheromak by prefilling it with tungsten hexacarbonyl prior to the usual hydrogen gas injection and initiation of the plasma discharge. The possibility of using the emission from low charge state tungsten ions to diagnose tokamak divertor plasmas has been investigated using a high-resolution extreme ultraviolet spectrometer.

Clementson, J; Beiersdorfer, P; Magee, E W; McLean, H S; Wood, R D

2009-12-01T23:59:59.000Z

405

A new iterative approach to solving the transport equation  

E-Print Network [OSTI]

directions, and apply the divergence theorem to the spatial integral of the second term: 4 ( )? ? ?, , ,E V N dS dE d r t E n t ??? ? = ? ? ? ? ? ? ? ? ? ? arrowrightnospintegralloop ( ) ( )?, , , ,tV EdV dE d r E r t E? ?? ?? ? ? ?? ? ? arrowrightnosp... arrowrightnosp ( ) ( ) ( )4 0 ?, , ? ? ?' ' , ' , ' ', , , 'V E s Q r E dV dE d d dE r E E r t Epi ? ? ? ? ? ? ?? ? ? ? ?+ ? ? ? ?+ ? ? ? ? ? ? ? ?? ? ? ? ? ? ? arrowrightnosp arrowrightnosp arrowrightnosp , (3) where =?? tN total change rate...

Maslowski Olivares, Alexander Enrique

2009-05-15T23:59:59.000Z

406

A special exact spherically symmetric solution in f(T) gravity theories  

E-Print Network [OSTI]

A non-diagonal spherically symmetric tetrad field, involving four unknown functions of radial coordinate $r$, is applied to the equations of motion of f(T) gravity theory. A special exact vacuum solution with one constant of integration is obtained. The scalar torsion related to this special solution vanishes. To understand the physical meaning of the constant of integration we calculate the energy associated with this solution and show how it is related to the gravitational mass of the system.

G. G. L. Nashed

2015-02-17T23:59:59.000Z

407

A special exact spherically symmetric solution in f(T) gravity theories  

E-Print Network [OSTI]

A non-diagonal spherically symmetric tetrad field, involving four unknown functions of radial coordinate $r$, is applied to the equations of motion of f(T) gravity theory. A special exact vacuum solution with one constant of integration is obtained. The scalar torsion related to this special solution vanishes. To understand the physical meaning of the constant of integration we calculate the energy associated with this solution and show how it is related to the gravitational mass of the system.

Nashed, G G L

2015-01-01T23:59:59.000Z

408

Characterization of the ITER model negative ion source during long pulse operation  

SciTech Connect (OSTI)

It is foreseen to operate the neutral beam system of the International Thermonuclear Experimental Reactor (ITER) for pulse lengths extending up to 1 h. The performance of the KAMABOKO III negative ion source, which is a model of the source designed for ITER, is being studied on the MANTIS test bed at Cadarache. This article reports the latest results from the characterization of the ion source, in particular electron energy distribution measurements and the comparison between positive ion and negative ion extraction from the source.

Hemsworth, R.S.; Boilson, D.; Crowley, B.; Homfray, D.; Esch, H.P.L. de; Krylov, A.; Svensson, L. [Association EURATOM-CEA, CEA Cadarache, F-13108, St. Paul lez Durance (France); Association EURATOM-DCU, PRL/NCPST, Glasnevin, Dublin 13 (Ireland); Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Association EURATOM-CEA, CEA Cadarache, F-13108, St. Paul lez Durance (France)

2006-03-15T23:59:59.000Z

409

Beyond ITER: Neutral beams for a demonstration fusion reactor (DEMO) (invited)  

SciTech Connect (OSTI)

In the development of magnetically confined fusion as an economically sustainable power source, International Tokamak Experimental Reactor (ITER) is currently under construction. Beyond ITER is the demonstration fusion reactor (DEMO) programme in which the physics and engineering aspects of a future fusion power plant will be demonstrated. DEMO will produce net electrical power. The DEMO programme will be outlined and the role of neutral beams for heating and current drive will be described. In particular, the importance of the efficiency of neutral beam systems in terms of injected neutral beam power compared to wallplug power will be discussed. Options for improving this efficiency including advanced neutralisers and energy recovery are discussed.

McAdams, R., E-mail: roy.mcadams@ccfe.ac.uk [EURATOM/CCFE Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB (United Kingdom)

2014-02-15T23:59:59.000Z

410

Non-destructive qualification tests for ITER cryogenic axial insulating breaks  

SciTech Connect (OSTI)

In the ITER superconducting magnets the dielectric separation between the CICC (Cable-In-Conduit Conductors) and the helium supply pipes is made through the so-called insulating breaks (IB). These devices shall provide the required dielectric insulation at a 30 kV level under different types of stresses and constraints: thermal, mechanical, dielectric and ionizing radiations. As part of the R and D program, the ITER Organization launched contracts with industrial companies aimed at the qualification of the manufacturing techniques. After reviewing the main functional aspects, this paper describes and discusses the protocol established for non-destructive qualification tests of the prototypes.

Kosek, Jacek [Wroclaw University of Technology, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw, Poland and CERN, Geneva 23,CH-1211 (Switzerland); Lopez, Roberto; Tommasini, Davide [CERN, Geneva 23,CH-1211 (Switzerland); Rodriguez-Mateos, Felix [CERN, Geneva 23,CH-1211, Switzerland and ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul lez Durance (France)

2014-01-29T23:59:59.000Z

411

Bounds on the map threshold of iterative decoding systems with erasure noise  

E-Print Network [OSTI]

BOUNDS ON THE MAP THRESHOLD OF ITERATIVE DECODING SYSTEMS WITH ERASURE NOISE A Thesis by CHIA-WEN WANG 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 2008 Major Subject: Electrical Engineering BOUNDS ON THE MAP THRESHOLD OF ITERATIVE DECODING SYSTEMS WITH ERASURE NOISE A Thesis by CHIA-WEN WANG Submitted to the O ce of Graduate Studies of Texas A&M University in partial ful llment...

Wang, Chia-Wen

2008-10-10T23:59:59.000Z

412

Nebraska Statewide Wind Integration Study: April 2008 - January 2010  

SciTech Connect (OSTI)

Wind generation resources in Nebraska will play an increasingly important role in the environmental and energy security solutions for the state and the nation. In this context, the Nebraska Power Association conducted a state-wide wind integration study.

EnerNex Corporation, Knoxville, Tennessee; Ventyx, Atlanta, Georgia; Nebraska Power Association, Lincoln, Nebraska

2010-03-01T23:59:59.000Z

413

Optimization With Parity Constraints: From Binary Codes to Discrete Integration  

E-Print Network [OSTI]

Optimization With Parity Constraints: From Binary Codes to Discrete Integration Stefano Ermon guarantees on the quality of the solution found. Markov Chain Monte Carlo [17, 21, 32] and Importance

Bejerano, Gill

414

Out of Equilibrium Solutions in the $XY$-Hamiltonian Mean Field model  

E-Print Network [OSTI]

Out of equilibrium magnetised solutions of the $XY$-Hamiltonian Mean Field ($XY$-HMF) model are build using an ensemble of integrable uncoupled pendula. Using these solutions we display an out-of equilibrium phase transition using a specific reduced set of the magnetised solutions.

Xavier Leoncini; Tineke L. Van Den Berg; Duccio Fanelli

2009-04-30T23:59:59.000Z

415

Comparisons of Predicted Plasma Performance in ITER H-mode Plasmas with Various Mixes of External He  

SciTech Connect (OSTI)

Performance in H-mode DT plasmas in ITER with various choices of heating systems are predicted and compared. Combinations of external heating by Negative Ion Neutral Beam Injection (NNBI), Ion Cyclotron Range of Frequencies (ICRF), and Electron Cyclotron Heating (ECH) are assumed. Scans with a range of physics assumptions about boundary temperatures in the edge pedestal, alpha ash transport, and toroidal momentum transport are used to indicate effects of uncertainties. Time-dependent integrated modeling with the PTRANSP code is used to predict profiles of heating, beam torque, and plasma profiles. The GLF23 model is used to predict temperature profiles. Either GLF23 or the assumption of a constant ratio for ?/?i is used to predict toroidal rotation profiles driven by the beam torques. Large differences for the core temperatures are predicted with different mixes of the external heating during the density and current ramp-up phase, but the profiles are similar during the flattop phase. With ?/?i = 0.5, the predicted toroidal rotation is relatively slow and the flow shear implied by the pressure, toroidal rotation, and neoclassical poloidal rotation are not sufficient to cause significant changes in the energy transport or steady state temperature profiles. The GLF23-predicted toroidal rotation is faster by a factor of six, and significant flow shear effects are predicted.

R.V. Budny

2009-03-20T23:59:59.000Z

416

The effect of axial strain cycling on the critical current density and n-value of ITER niobium-tin  

E-Print Network [OSTI]

The effect of axial strain cycling on the critical current density and n-value of ITER niobium-tin niobium-tin VAC and EM-LMI strands and the detailed characterisation of the EM-LMI-TFMC strand at -0 current density and n-value of two ITER candidate niobium-tin strands (EM- LMI and VAC). The strands were

Hampshire, Damian

417

IEEE TRANSACTIONS ON AUDIO, SPEECH, AND LANGUAGE PROCESSING, VOL. 20, NO. 6, AUGUST 2012 1869 Constrained Iterative Speech Enhancement  

E-Print Network [OSTI]

Constrained Iterative Speech Enhancement Using Phonetic Classes Amit Das, Student Member, IEEE, and John H. L enhancement algorithms like Auto-LSP, log-minimum mean squared error (log-MMSE), and log-MMSE with speech--Auditory masked threshold, Auto-LSP, con- strained iterative speech enhancement. I. INTRODUCTION NOISE is present

Texas at Dallas, University of

418

DEVELOPMENT STATUS OF A SiC-FOAM BASED FLOW CHANNEL INSERT FOR A U.S.-ITER DCLL TBM  

E-Print Network [OSTI]

, CA, 91331, U.S.A. The U.S.-ITER DCLL (Dual Coolant Liquid Lead) TBM (Test Blanket Module) uses a Flow structure. I. INTRODUCTION The U.S. ITER Double Coolant Lead Lithium (DCLL) Test Blanket Module (TBM liquid breeder (PbLi) at elevated temperatures of more than 700 o C and at low velocities of ~10 cm

Ghoniem, Nasr M.

419

5506 IEEE TRANSACTIONS ON SIGNAL PROCESSING, VOL. 55, NO. 11, NOVEMBER 2007 On the New Stopping Criteria of Iterative Turbo  

E-Print Network [OSTI]

Criteria of Iterative Turbo Decoding by Using Decoding Threshold Fan-Min Li and An-Yeu (Andy) Wu, Member--Decoding threshold, early termination (ET), extrinsic information transform (EXIT) chart, iterative decoding, turbo codes, turbo principle. I. INTRODUCTION IN 1993, a new class of forward-error-correction (FEC) code

Hung, Shih-Hao

420

Hydrogen Permeability and Integrity of Hydrogen  

E-Print Network [OSTI]

Hydrogen Permeability and Integrity of Hydrogen Delivery Pipelines Z. Feng*, L.M. Anovitz*, J and industry expectations · DOE Pipeline Working Group and Tech Team activities - FRP Hydrogen Pipelines - Materials Solutions for Hydrogen Delivery in Pipelines - Natural Gas Pipelines for Hydrogen Use #12;3 OAK

Note: This page contains sample records for the topic "integrated iterative solution" 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

Strategic Biomass Solutions (Mississippi)  

Broader source: Energy.gov [DOE]

The Strategic Biomass Solutions (SBS) was formed by the Mississippi Technology Alliance in June 2009. The purpose of the SBS is to provide assistance to existing and potential companies, investors...

422

Solution to Quiz 1  

E-Print Network [OSTI]

Sep 5, 2013 ... over the next four years: Cash Flow at End of Year Amount of Cash Flow. 1. 1 Million. 2 ... project is 8%. Calculate X . Solution: By definition, the...

jeffb_000

2014-01-14T23:59:59.000Z

423

Thermal Control & System Integration  

Broader source: Energy.gov [DOE]

The thermal control and system integration activity focuses on issues such as the integration of motor and power control technologies and the development of advanced thermal control technologies....

424

Distribution Grid Integration  

Broader source: Energy.gov [DOE]

The DOE Systems Integration team funds distribution grid integration research and development (R&D) activities to address the technical issues that surround distribution grid planning,...

425

Solutions of Penrose's Equation  

E-Print Network [OSTI]

The computational use of Killing potentials which satisfy Penrose's equation is discussed. Penrose's equation is presented as a conformal Killing-Yano equation and the class of possible solutions is analyzed. It is shown that solutions exist in spacetimes of Petrov type O, D or N. In the particular case of the Kerr background, it is shown that there can be no Killing potential for the axial Killing vector.

E. N. Glass; Jonathan Kress

1998-09-27T23:59:59.000Z

426

Q-balls, Integrability and Duality  

E-Print Network [OSTI]

This paper is concerned with the dynamics and interactions of Q-balls in (1+1)-dimensions. The asymptotic force between well-separated Q-balls is calculated to show that Q-balls can be attractive or repulsive depending upon their relative internal phase. An integrable model with exact multi-Q-ball solutions is investigated and found to be of use in explaining the dynamics in non-integrable theories. In particular, it is demonstrated that the dynamics of small Q-balls in a generic class of non-integrable models tends towards integrable dynamics as the charge decreases. Long-lived oscillations of a single Q-ball can also be understood in terms of a deformation of an exact breather solution in the integrable model. Finally, we show that any theory with Q-ball solutions has a dual description in which a stationary Q-ball is dual to a static kink, with an interchange of Noether and topological charges.

Peter Bowcock; David Foster; Paul Sutcliffe

2009-01-08T23:59:59.000Z

427

The Japan Times Printer Friendly Articles France has won the competition to host the International Thermonuclear Experimental Reactor (ITER), the world's first nuclear-  

E-Print Network [OSTI]

the International Thermonuclear Experimental Reactor (ITER), the world's first nuclear- fusion reactor. Japan fought wins by withdrawing ITER bid Thermonuclear fusion utilizes the same process that powers the sun

428

A Comparison of Iterative Methods for Least Squares Support Vector Machine Classi ers  

E-Print Network [OSTI]

and Krylov methods (conjugate gradient, block-conjugate gra- dient). The latter show the best performance focus on two iter- ative algorithms: the successive overrelaxation method and the conjugate gradient steps, they are outperformed by the Krylov methods (conjugate gradient). Because, as will be shown later

429

Print this article Close This Window EU OKs India joining ITER nuclear reactor project  

E-Print Network [OSTI]

Print this article Close This Window EU OKs India joining ITER nuclear reactor project Fri Dec 2-billion-euro project to build an experimental nuclear fusion reactor that in the long-run could provide virtually unlimited, cheap and clean energy. The EU's willingness to work with India on a civil nuclear

430

AN ITERATIVE ROUTE CONSTRUCTION AND IMPROVEMENT ALGORITHM FOR THE VEHICLE ROUTING PROBLEM WITH SOFT  

E-Print Network [OSTI]

time windows exceeds the number of available vehicles, (b) a study of cost-service tradeoffs of available vehicles, (b) a study of cost-service tradeoffs is required, and (c) the dispatcher has1 AN ITERATIVE ROUTE CONSTRUCTION AND IMPROVEMENT ALGORITHM FOR THE VEHICLE ROUTING PROBLEM

Bertini, Robert L.

431

ITER-like wall sliced beryllium tiles The JET Enhanced Performance 2 (EP2) shutdown  

E-Print Network [OSTI]

ITER-like wall sliced beryllium tiles Background The JET Enhanced Performance 2 (EP2) shutdown and remote handling equipment. JET remote handling systems #12;Outcome The EP2 shutdown was successful of the remote handling system are compatible with the required component manipulation. Pre EP2 shutdown Mid

432

Improved Confinement in JET High {beta} Plasmas with an ITER-Like Wall  

E-Print Network [OSTI]

The replacement of the JET carbon wall (C-wall) by a Be/W ITER-like wall (ILW) has affected the plasma energy confinement. To investigate this, experiments have been performed with both the C-wall and ILW to vary the heating power over a wide range for plasmas with different shapes.

Challis, C D; Beurskens, M; Buratti, P; Delabie, E; Drewelow, P; Frassinetti, L; Giroud, C; Hawkes, N; Hobirk, J; Joffrin, E; Keeling, D; King, D B; Maggi, C F; Mailloux, J; Marchetto, C; McDonald, D; Nunes, I; Pucella, G; Saarelma, S; Simpson, J

2015-01-01T23:59:59.000Z

433

ITER Export Control Awareness Information UT-B Contracts Div. Page 1 of 8  

E-Print Network [OSTI]

to manage and implement identified work elements within the ITER Fusion facility to be built in Cadarache with the Department of Energy and/or Nuclear Regulatory Commission. It should be noted that the design information.pdf #12;Commodity Classification Request Work Item Reference Number ITR1007 Status: ACCEPTED Print

Pennycook, Steve

434

PPPL3246 Preprint: April 1997, UC420 THE PHYSICS ROLE OF ITER  

E-Print Network [OSTI]

Plasma Physics Laboratory ABSTRACT Experimental research on the International Thermonuclear Experimental­called ``disruptions'', in regimes of high plasma current and thermal energy; and (iii) physics of a ``radiative issues in the physics of reactor­like plasmas. First and foremost, experiments in ITER will explore

435

PPPL-3246 -Preprint: April 1997, UC-420 THE PHYSICS ROLE OF ITER  

E-Print Network [OSTI]

Plasma Physics Laboratory ABSTRACT Experimental research on the International Thermonuclear Experimental issues in the physics of reactor-like plasmas. First and foremost, experiments in ITER will explore the physics issues of "burning plasmas" -- plasmas that are dominantly self-heated by alpha-particles created

436

Paradigm Changes in High Temperature Plasma Physics Research and Implications for ITER  

SciTech Connect (OSTI)

Significant high temperature plasma research in both the magnetic and inertial confinement regimes led to the official launching of the International Thermonuclear Experimental Reactor (ITER) project which is aimed at challenging controlled fusion power for human kind. In particular, such an endeavor originated from the fruitful research outcomes from the world wide magnetic confinement devices (primarily based on the Tokamak approach) mainly in advanced countries (US, EU, and Japan). In recent years, all new steady state capable Tokamak devices are operated and/or constructed in Asian countries and incidentally, the majority of the ITER consortium consists of Asian countries. This provides an opportunity to revisit the unresolved essential physics issues and/or extend the understanding of the transient physics to the required steady state operation so that ITER can benefit from these efforts. The core physics of a magnetically confined hot plasma has two essential components; plasma stability and cross-field energy transport physics. Complete understanding of these two areas is critical for the successful operation of ITER and perhaps, Demo reactor construction. In order to have stable high beta plasmas with a sufficiently long confinement time, the physics of an abrupt disruption and sudden deterioration of the energy transport must be understood and conquered. Physics issues associated with transient harmful MHD behavior and turbulence based energy transport are extremely complicated and theoretical understanding needs a clear validation and verification with a new research approach such as a multi-dimensional visualization.

Hyeon K. Park

2008-02-22T23:59:59.000Z

437

Europe and Japan with the elbow-with-elbow to accomodate engine ITER  

E-Print Network [OSTI]

.12.03|13h1713h17 ? The competition for the machine installation of with thermonuclear fusion is announced, selected after a survey campaign, where the experimental engine with thermonuclear fusion ITER experts - thermonuclear fusion, who come to supra establish a new record in the engine with Tore fusion

438

Non-iterative joint decoding and signal processing: universal coding approach for channels with memory  

E-Print Network [OSTI]

in an error free manner through the use of a capacity achieving code for a memoryless channel. Computational complexity of the proposed receiver structure is less than that of one iteration of the turbo receiver. We also provide the proof showing...

Nangare, Nitin Ashok

2006-08-16T23:59:59.000Z

439

NATURE | Q&A Five-year delay would spell end of ITER  

E-Print Network [OSTI]

States has high scientific and technological capability in fusion energy and has been one of the leading on Earth has long been a dream for physicists. In 2006, a team from the European Union, China, India, Japan of weight-loss Elizabeth Gibney Print #12;Related stories ITER keeps eye on prize Japan quake rocks fusion

440

AN ITERATIVE SPATIO-TEMPORAL SPEECH ENHANCEMENT ALGORITHM FOR MICROPHONE ARRAYS  

E-Print Network [OSTI]

AN ITERATIVE SPATIO-TEMPORAL SPEECH ENHANCEMENT ALGORITHM FOR MICROPHONE ARRAYS !"#"$ %&'t" "nd +c ABSTRACT We present a new spatio-temporal algorithm for speech enhancement using microphone arrays. Our-dependent parameter settings. Index Terms4 Speech enhancement, acoustic arrays, adaptive arrays, eigenvalues

Douglas, Scott C.

Note: This page contains sample records for the topic "integrated iterative solution" 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

Disruption mitigation for ITER Disruptions are sudden unplanned terminations of the plasma that can  

E-Print Network [OSTI]

damage the plasma chamber from thermal loads, high magnetic forces, and runaway electrons. A reliable fast acting tool to mitigate these effects in ITER burning plasmas by the injection of large quantities be located inside a port plug for close proximity to the plasma and fast injection. Multiple injectors can

442

Fuel Source Isotopic Tailoring Impact on ITER Design, Operation and Safety  

E-Print Network [OSTI]

1 Fuel Source Isotopic Tailoring and Its Impact on ITER Design, Operation and Safety M. J. Gouge, W. The isotopic tailoring concept consists of utilizing a tritium-rich pellet source for core fueling and a deuterium- rich gas source for edge fueling. Because of the improved particle confinement associated

443

HEART SEGMENTATION WITH AN ITERATIVE CHAN-VESE OLIVIER ROUSSEAU, YVES BOURGAULT  

E-Print Network [OSTI]

HEART SEGMENTATION WITH AN ITERATIVE CHAN-VESE ALGORITHM OLIVIER ROUSSEAU, YVES BOURGAULT Abstract. This paper presents 2D and 3D applications of the Chan-Vese model to heart and trachea segmentation. We is to segment the heart muscle from high resolution CT scans of the thorax and to produce meshes

Paris-Sud XI, Université de

444

Iteration Space Tiling for Distributed Memory Machines J. Ramanujam y and P. Sadayappan z  

E-Print Network [OSTI]

levels of flexibility, scalability and performance but programming these machines remains a difficultIteration Space Tiling for Distributed Memory Machines J. Ramanujam y and P. Sadayappan z y Department of Electrical and Computer Engineering, Louisiana State University, Baton Rouge, LA 70803

Ramanujam, J. "Ram"

445

On the Logic of Iterated Belief Revision Adnan Darwiche and Judea Pearl  

E-Print Network [OSTI]

and inadequacies of the operator--based approach to belief revision [3, 4, 5, 13]. This paper addresses oneOn the Logic of Iterated Belief Revision Adnan Darwiche and Judea Pearl Cognitive Systems preservation of conditional beliefs during belief revision, thus permitting improper responses to sequences

California at Los Angeles, University of

446

Fabrication of the First US ITER TF Conductor Sample for Qualification in SULTAN Facility  

E-Print Network [OSTI]

A pair of 3.5 m long ITER TF size straight conductors has been fabricated into a conductor short sample and submitted to the SULTAN facility at CRPP for cold test. The sample used a triplet-based cabling pattern in one leg ...

Miller, John R.

447

Analysis of a Classification-based Policy Iteration Algorithm Alessandro Lazaric alessandro.lazaric@inria.fr  

E-Print Network [OSTI]

be solved exactly and approximation techniques are required. In approximate policy iteration (API issues, mainly 3 and 4,1 variants of API have been proposed that replace the usual value function label. In this case, (x, a) for the rest of the actions are labeled negative and added to the training

448

EXPERIMENTALSTUDY OF THE EFFECTIVETHERMAL CONDUCTIVITYOFA PACKED BED AS A TEMPERATURECONTROL MECHANISMFOR ITER CERAMICBREEDERBLANKETDESIGNS *  

E-Print Network [OSTI]

to maximize reli- ability. A novel and practical concept was proposed for the thermal resistance gap between were used as alternate low thermal conductivity gases. With this set of materials, a good range the coolant and solid breeder to allow their operating temperatures to be optimized for ITER.[11 This thermal

Raffray, A. René

449

Generics, habituals, and iteratives Sentences may express information about particular events, such as  

E-Print Network [OSTI]

cough or flap (a wing)'. In English, John coughed can be understood as saying that he coughed once implications, especially those of intensity and/or prolongation. In English, John coughed and coughed is iterative in interpretation, like one understanding of the simple John coughed, but in addition implies

Makous, Walter

450

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago  

E-Print Network [OSTI]

Thirty states sign ITER nuclear fusion plant deal 1 hour, 28 minutes ago Representatives of more than 30 countries signed a deal on Tuesday to build the world's most advanced nuclear fusion reactor nuclear reactors, but critics argue it could be at least 50 years before a commercially viable reactor

451

U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING , M. Sawan4  

E-Print Network [OSTI]

U.S. PLANS AND STRATEGY FOR ITER BLANKET TESTING M. Abdou1 , D. Sze2 , C. Wong3 , M. Sawan4 , A. Ying1 , N. B. Morley1 , S. Malang5 1 UCLA Fusion Engineering Sciences, Los Angeles, CA, abdou

Abdou, Mohamed

452

Test Strategy for the European HCPB Test Blanket Module in ITER  

SciTech Connect (OSTI)

According to the European Blanket Programme two blanket concepts, the Helium Cooled Pebble Bed (HCPB) and a Helium Cooled Lithium Lead (HCLL) will be tested in ITER. During 2004 the test blanket modules (TBM) of both concepts were redesigned with the goal to use as much as possible similar design options and fabrication techniques for both types in order to reduce the European effort for TBM development. The result is a robust TBM box being able to withstand 8 MPa internal pressure in case of in-box LOCA; the TBM box consists of First wall (FW), caps, stiffening grid and manifolds. The box is filled with typically 18 and 24 breeding units (BU), for HCPB and HCLL respectively. A breeding unit has about 200 mm in poloidal and toroidal direction and about 400 mm in radial direction; the design is adapted to contain and cooling ceramic breeder/beryllium pebble beds for the HCPB and eutectic Lithium-Lead for the HCLL.The use of a new material, EUROFER, and the innovative design of these Helium Cooled components call for a large qualification programme before the installation in ITER; availability and safety of ITER should not be jeopardised by a failure of these components. Fabrication technologies especially in the welding processes (diffusion welding, EB, TIG, LASER) need to be tested in the manufacturing of large mock-ups; an extensive out-of-pile programme in Helium facility should be foreseen for the verification of the concept from basic helium cooling functions (uniformity of flow in parallel channels, heat transfer coefficient in FW, etc.) up to the verification of large portions of the TBM design under relevant ITER loading.In ITER the TBM will have the main objective to collect information that will contribute to the final design of DEMO blankets. A strategy has been proposed in 2001 that leads to the tests in ITER 4 different Test Blanket Modules (TBM's) type during the first 10 years of ITER operation. For the new HCPB design this strategy is confirmed with some additional possibilities taking into account the modular design of the breeding zone.

Boccaccini, L.V.; Meyder, R.; Fischer, U. [Forschungszentrum Karlsruhe (Germany)

2005-05-15T23:59:59.000Z

453

Is Symplectic-Energy-Momentum Integration Well-Posed?  

E-Print Network [OSTI]

We provide new existence and uniqueness results for the discrete-time Hamilton (DTH) equations of a symplectic-energy-momentum (SEM) integrator. In particular, we identify points in extended-phase space where the DTH equations of SEM integration have no solution for arbitrarily small time steps. We use the nonlinear pendulum to illustrate the main ideas.

Yosi Shibberu

2006-08-04T23:59:59.000Z

454

Well performance under solutions gas drive  

SciTech Connect (OSTI)

A fully implicit black-oil simulator was written to predict the drawdown and buildup responses for a single well under Solution Gas Drive. The model is capable of handling the following reservoir behaviors: Unfractured reservoir, Double-Porosity system, and Double Permeability-Double Porosity model of Bourdet. The accuracy of the model results is tested for both single-phase liquid flow and two-phase flow. The results presented here provide a basis for the empirical equations presented in the literature. New definitions of pseudopressure and dimensionless time are presented. By using these two definitions, the multiphase flow solutions correlate with the constant rate liquid flow solution for both transient and boundary-dominated flow. For pressure buildup tests, an analogue for the liquid solution is constructed from the drawdown pseudopressure, similar to the reservoir integral of J. Jones. The utility of using the producing gas-oil ration at shut in to compute pseudopressures and pseudotimes is documented. The influence of pressure level and skin factor on the Inflow Performance Relationship (IPR) of wells producing solution gas drive systems is examined. A new definition of flow efficiency that is based on the structure of the deliverability equations is proposed. This definition avoids problems that result when the presently available methods are applied to heavily stimulated wells. The need for using pseudopressures to analyze well test data for fractured reservoirs is shown. Expressions to compute sandface saturations for fractured systems are presented.

Camacho-Velazquez, R.G.

1987-01-01T23:59:59.000Z

455

Iterative acceleration methods for Monte Carlo and deterministic criticality calculations  

SciTech Connect (OSTI)

If you have ever given up on a nuclear criticality calculation and terminated it because it took so long to converge, you might find this thesis of interest. The author develops three methods for improving the fission source convergence in nuclear criticality calculations for physical systems with high dominance ratios for which convergence is slow. The Fission Matrix Acceleration Method and the Fission Diffusion Synthetic Acceleration (FDSA) Method are acceleration methods that speed fission source convergence for both Monte Carlo and deterministic methods. The third method is a hybrid Monte Carlo method that also converges for difficult problems where the unaccelerated Monte Carlo method fails. The author tested the feasibility of all three methods in a test bed consisting of idealized problems. He has successfully accelerated fission source convergence in both deterministic and Monte Carlo criticality calculations. By filtering statistical noise, he has incorporated deterministic attributes into the Monte Carlo calculations in order to speed their source convergence. He has used both the fission matrix and a diffusion approximation to perform unbiased accelerations. The Fission Matrix Acceleration method has been implemented in the production code MCNP and successfully applied to a real problem. When the unaccelerated calculations are unable to converge to the correct solution, they cannot be accelerated in an unbiased fashion. A Hybrid Monte Carlo method weds Monte Carlo and a modified diffusion calculation to overcome these deficiencies. The Hybrid method additionally possesses reduced statistical errors.

Urbatsch, T.J.

1995-11-01T23:59:59.000Z

456

Slide 1/14Fusion Power Associate Washington DC 10-11 December 2013OM13897 Status Report of the ITER Project  

E-Print Network [OSTI]

as an independent international organization ­ Develop a process where objectives and strategy defined by the DG-General of the ITER Organization Aerial view of ITER Site in September 2013 (F4E) #12;Slide 2/14Fusion Power Associate more power than it receives; · The ITER Project creates a new collaborative culture and standard

457

HyperKhaler Metrics Building and Integrable Models  

E-Print Network [OSTI]

Methods developed for the analysis of integrable systems are used to study the problem of hyperK\\"ahler metrics building as formulated in D=2 N=4 supersymmetric harmonic superspace. We show, in particular, that the constraint equation $\\beta\\partial^{++2}\\omega -\\xi^{++2}\\exp 2\\beta\\omega =0$ and its Toda like generalizations are integrable. Explicit solutions together with the conserved currents generating the symmetry responsible of the integrability of these equations are given. Other features are also discussed

E. H. Saidi; M. B. Sedra

2005-12-18T23:59:59.000Z

458

U.S. Energy Infrastructure Investment: Large-Scale Integrated Smart Grid  

E-Print Network [OSTI]

U.S. Energy Infrastructure Investment: Large-Scale Integrated Smart Grid Solutions with High: LargeScale Integrated Smart Grid Solutions with High Penetration of Renewable Resources, Dispersed- ing electricity grid. Much attention is being given to smart grid development in the U.S. and around

459

Fissile solution measurement apparatus  

DOE Patents [OSTI]

An apparatus for determining the content of a fissile material within a solution by detecting delayed fission neutrons emitted by the fissile material after it is temporarily irradiated by a neutron source. The apparatus comprises a container holding the solution and having a portion defining a neutron source cavity centrally disposed within the container. The neutron source cavity temporarily receives the neutron source. The container has portions defining a plurality of neutron detector ports that form an annular pattern and surround the neutron source cavity. A plurality of neutron detectors count delayed fission neutrons emitted by the fissile material. Each neutron detector is located in a separate one of the neutron detector ports.

Crane, T.W.; Collinsworth, P.R.

1984-06-11T23:59:59.000Z

460

Wind Integration Study Methods (Presentation)  

SciTech Connect (OSTI)

This presentation provides an overview of common elements, differences, integration costs, and errors in integration analysis.

Milligan, M.; Kirby, B.

2011-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Offshore Renewable Energy Solutions  

E-Print Network [OSTI]

power ­ to meet its target of achieving 15% of energy consumption from renewable sources by 2020. CefasOffshore Renewable Energy Solutions #12;Cefas: meeting complex requirements The Centre and maximise resource input on field and lab-based studies ­ saving you time and money.Recognised expertise

462

Buried waste integrated demonstration technology integration process  

SciTech Connect (OSTI)

A Technology integration Process was developed for the Idaho National Energy Laboratories (INEL) Buried Waste Integrated Demonstration (BWID) Program to facilitate the transfer of technology and knowledge from industry, universities, and other Federal agencies into the BWID; to successfully transfer demonstrated technology and knowledge from the BWID to industry, universities, and other Federal agencies; and to share demonstrated technologies and knowledge between Integrated Demonstrations and other Department of Energy (DOE) spread throughout the DOE Complex. This document also details specific methods and tools for integrating and transferring technologies into or out of the BWID program. The document provides background on the BWID program and technology development needs, demonstrates the direction of technology transfer, illustrates current processes for this transfer, and lists points of contact for prospective participants in the BWID technology transfer efforts. The Technology Integration Process was prepared to ensure compliance with the requirements of DOE's Office of Technology Development (OTD).

Ferguson, J.S.; Ferguson, J.E.

1992-04-01T23:59:59.000Z

463

Buried waste integrated demonstration technology integration process  

SciTech Connect (OSTI)

A Technology integration Process was developed for the Idaho National Energy Laboratories (INEL) Buried Waste Integrated Demonstration (BWID) Program to facilitate the transfer of technology and knowledge from industry, universities, and other Federal agencies into the BWID; to successfully transfer demonstrated technology and knowledge from the BWID to industry, universities, and other Federal agencies; and to share demonstrated technologies and knowledge between Integrated Demonstrations and other Department of Energy (DOE) spread throughout the DOE Complex. This document also details specific methods and tools for integrating and transferring technologies into or out of the BWID program. The document provides background on the BWID program and technology development needs, demonstrates the direction of technology transfer, illustrates current processes for this transfer, and lists points of contact for prospective participants in the BWID technology transfer efforts. The Technology Integration Process was prepared to ensure compliance with the requirements of DOE`s Office of Technology Development (OTD).

Ferguson, J.S.; Ferguson, J.E.

1992-04-01T23:59:59.000Z

464

Better Buildings Residential Program Solution Center Demonstration...  

Energy Savers [EERE]

Better Buildings Residential Program Solution Center Demonstration Better Buildings Residential Program Solution Center Demonstration Better Buildings Residential Program Solution...

465

Hybrid preconditioning for iterative diagonalization of ill-conditioned generalized eigenvalue problems in electronic structure calculations  

SciTech Connect (OSTI)

The iterative diagonalization of a sequence of large ill-conditioned generalized eigenvalue problems is a computational bottleneck in quantum mechanical methods employing a nonorthogonal basis for ab initio electronic structure calculations. We propose a hybrid preconditioning scheme to effectively combine global and locally accelerated preconditioners for rapid iterative diagonalization of such eigenvalue problems. In partition-of-unity finite-element (PUFE) pseudopotential density-functional calculations, employing a nonorthogonal basis, we show that the hybrid preconditioned block steepest descent method is a cost-effective eigensolver, outperforming current state-of-the-art global preconditioning schemes, and comparably efficient for the ill-conditioned generalized eigenvalue problems produced by PUFE as the locally optimal block preconditioned conjugate-gradient method for the well-conditioned standard eigenvalue problems produced by planewave methods.

Cai, Yunfeng, E-mail: yfcai@math.pku.edu.cn [LMAM and School of Mathematical Sciences, Peking University, Beijing 100871 (China) [LMAM and School of Mathematical Sciences, Peking University, Beijing 100871 (China); Department of Computer Science, University of California, Davis 95616 (United States); Bai, Zhaojun, E-mail: bai@cs.ucdavis.edu [Department of Computer Science and Department of Mathematics, University of California, Davis 95616 (United States)] [Department of Computer Science and Department of Mathematics, University of California, Davis 95616 (United States); Pask, John E., E-mail: pask1@llnl.gov [Condensed Matter and Materials Division, Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States); Sukumar, N., E-mail: nsukumar@ucdavis.edu [Department of Civil and Environmental Engineering, University of California, Davis 95616 (United States)

2013-12-15T23:59:59.000Z

466

ITER vacuum vessel design (D201 subtask 1.3 and subtask 3). Final report  

SciTech Connect (OSTI)

ITER Task No. D201, Vacuum Vessel Design (Subtask 1.3 and Subtask 3), was initiated to propose and evaluate local vacuum vessel reinforcement alternatives in proximity to the Neutral Beam, Radial Mid-Plane, Top, and Divertor Ports. These areas were reported to be highly stressed regions based on the results of preliminary stress analyses performed by the USHT (US Home Team) and the ITER Joint Central Team (JCT) at the Garching JWS (Joint Work Site). Initial design activities focused on the divertor port region which was reported to experience the highest stress intensities. Existing stress analysis models and results were reviewed with the USHT stress analysts to obtain an overall understanding of the vessel response to the various applied loads. These reviews indicated that the reported stress intensities in the divertor port region were significantly affected by the loads applied to the vessel in adjacent regions.

NONE

1996-08-01T23:59:59.000Z

467

Assessment of database for interaction of tritium with ITER plasma facing materials  

SciTech Connect (OSTI)

The present work surveys recent literature on hydrogen isotope interactions with Be, SS and Inconels, Cu, C, and V, and alloys of Cu and V. The goals are (1) to provide input to the International Thermonuclear Experimental Reactor (ITER) team to help with tritium source term estimates for the Early Safety and Environmental Characterization Study and (2) to provide guidance for planning additional research that will be needed to fill gaps in the present materials database. Properties of diffusivity, solubility, permeability, chemical reactions, Soret effect, recombination coefficient, surface effects, trapping, porosity, layered structures, interfaces, and oxides are considered. Various materials data are tabulated, and a matrix display shows an assessment of the quality of the data available for each main property of each material. Recommendations are made for interim values of diffusivity and solubility to be used, pending further discussion by the ITER community.

Dolan, T.J.; Anderl, R.A.

1994-09-01T23:59:59.000Z

468

Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report  

SciTech Connect (OSTI)

Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest.

NONE

1997-04-18T23:59:59.000Z

469

The ITER pre-compression rings A first in cryogenic composite technology  

SciTech Connect (OSTI)

The ITER Pre-Compression Rings represent one of the heaviest composite structures ever manufactured as a single piece and the largest - the outer diameter will be above 5.5 meters - intended for use in a cryogenic environment. With a cross section of 337 mm 288 mm, each item will weigh more than 3,000 kg. A development program, based on filament wound and dry wound S2 glass unidirectional fibers, the latter processed by VARTM, was completed on one fifth scale rings, and these materials and techniques were shown to be satisfactory. The paper describes how a technology applied to build up primary structures of European launchers is being accommodated to produce the ITER Pre-Compression Rings, fulfilling its extremely challenging requirements. In addition, we will describe how the structural analysis is correlated with the test results of scaled down rings, as well as how the pre-compression rings manufacturing process will be qualified.

Rajainmaki, Hannu; Fanthome, John; Losasso, Marcello [Fusion for Energy, C/ Josep Pla, n. 2, E-08019 Barcelona (Spain); Foussat, Arnaud [ITER Organisation, 13108 St. Paul-lez-Durance (France); Rodriguez, Jesus [EADS CASA Espacio S.L., Av. de Aragn 404, E-28022 Madrid (Spain); Evans, David; Diaz, Victor [Advanced Cryogenic Materials Ltd, Abingdon, OX14 2HQ (United Kingdom)

2014-01-27T23:59:59.000Z

470

Experimental neutronics tests for a neutron activation system for the European ITER TBM  

SciTech Connect (OSTI)

We are investigating methods for neutron flux measurement in the ITER TBM. In particular we have tested sets of activation materials leading to induced gamma activities with short half-lives of the order of tens of seconds up to minutes and standard activation materials. Packages of activation foils have been irradiated with the intense neutron generator of Technical University of Dresden in a pure DT neutron field as well as in a neutronics mock-up of the European ITER HCLL TBM. An important aim was to check whether the gamma activity induced in the activation foils in these packages could be measured simultaneously. It was indeed possible to identify gamma lines of interest in gamma-ray measurements immediately after extraction from the irradiation.

Klix, A.; Fischer, U. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Gehre, D. [Technical University of Dresden, IKTP, Zellescher Weg 19, 01062 Dresden (Germany); Kleizer, G. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Raj, P. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Universit Paris-Sud, 15 rue Georges Clemenceau, F-91405 Paris (France); Rovni, I. [Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Ruecker, Tom [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and University of Applied Sciences Zittau-Goerlitz, Theodor-Krner-Allee 16, D-02754 Zittau (Germany)

2014-08-21T23:59:59.000Z

471

In-Vessel Coil Material Failure Rate Estimates for ITER Design Use  

SciTech Connect (OSTI)

The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

L. C. Cadwallader

2013-01-01T23:59:59.000Z

472

Clover Action for Blue Gene-Q and Iterative solvers for DWF  

E-Print Network [OSTI]

In Lattice QCD, a major challenge in simulating physical quarks is the computational complexity of these simulations. In this proceeding, we describe the optimisation of Clover fermion action for Blue gene-Q architecture and how different iterative solvers behave for Domain Wall Fermion action. We find that the optimised Clover term achieved a maximum efficiency of 29.1% and 20.2% for single and double precision respectively for iterative Conjugate Gradient solver. For Domain Wall Fermion action (DWF) we found that Modified Conjugate Residual(MCR) as the most efficient solver compared to CG and GCR. We have developed a new multi-shift MCR algorithm that is 18.5% faster compared to multi-shift CG for the evaluation of rational functions in RHMC.

Karthee Sivalingam; Peter Boyle

2014-08-28T23:59:59.000Z

473

Iterative procedure for in-situ EUV optical testing with an incoherent source  

SciTech Connect (OSTI)

We propose an iterative method for in-situ optical testing under partially coherent illumination that relies on the rapid computation of aerial images. In this method a known pattern is imaged with the test optic at several planes through focus. A model is created that iterates through possible aberration maps until the through-focus series of aerial images matches the experimental result. The computation time of calculating the through-focus series is significantly reduced by a-SOCS, an adapted form of the Sum Of Coherent Systems (SOCS) decomposition. In this method, the Hopkins formulation is described by an operator S which maps the space of pupil aberrations to the space of aerial images. This operator is well approximated by a truncated sum of its spectral components.

Miyawaka, Ryan; Naulleau, Patrick; Zakhor, Avideh

2009-12-01T23:59:59.000Z

474

Design and Overview of 100 kV Bushing for the DNB Injector of ITER  

SciTech Connect (OSTI)

The 100 kV bushing is one of the most important and technologically challenging Safety Important Class (SIC) components of the Diagnostic Neutral Beam (DNB) injector of ITER. It forms interface between gas insulated electrical transmission line and torus primary vacuum and acts as a vacuum feedthrough of ITER. Design optimization has been carried out to meet the electric and structural requirements based on its classification. Unlike HNB bushing, single stage bushing is designed to provide 100 kV isolation. Finite Element Analysis (FEA) based optimization has been carried out for electrostatic and structural analysis. Manufacturing assembly sequence is studied and presented in this paper. However validation of the same is foreseen from manufacturer.

Shah, Sejal; Bandyopadhyay, M.; Rotti, C.; Singh, M. J.; Roopesh, G.; Chakraborty, A. K. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Rajesh, S. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Microelectronics and Materials Physics Labs, P.O.Box 4500, FIN-90014 University of Oulu (Finland); Nishad, S.; Srusti, B. [DesignTech Systems Ltd, Banjara Hills, Hyderabad, Andhra Pradesh-500034 (India); Schunke, B.; Hemsworth, R.; Chareyre, J.; Svensson, L. [ITER Organisation, Route de Vinon, CS 90 046, 13067 St. Paul lez Durance Cedex (France)

2011-09-26T23:59:59.000Z

475

Current Control in ITER Steady State Plasmas With Neutral Beam Steering  

SciTech Connect (OSTI)

Predictions of quasi steady state DT plasmas in ITER are generated using the PTRANSP code. The plasma temperatures, densities, boundary shape, and total current (9 - 10 MA) anticipated for ITER steady state plasmas are specified. Current drive by negative ion neutral beam injection, lower-hybrid, and electron cyclotron resonance are calculated. Four modes of operation with different combinations of current drive are studied. For each mode, scans with the NNBI aimed at differing heights in the plasma are performed to study effects of current control on the q profile. The timeevolution of the currents and q are calculated to evaluate long duration transients. Quasi steady state, strongly reversed q profiles are predicted for some beam injection angles if the current drive and bootstrap currents are sufficiently large.

R.V. Budny

2009-09-10T23:59:59.000Z

476

Irradiation tests of ITER candidate Hall sensors using two types of neutron spectra  

SciTech Connect (OSTI)

We report on irradiation tests of InSb based Hall sensors at two irradiation facilities with two distinct types of neutron spectra. One was a fission reactor neutron spectrum with a significant presence of thermal neutrons, while another one was purely fast neutron field. Total neutron fluence of the order of 10{sup 16} cm{sup -2} was accumulated in both cases, leading to significant drop of Hall sensor sensitivity in case of fission reactor spectrum, while stable performance was observed at purely fast neutron spectrum. This finding suggests that performance of this particular type of Hall sensors is governed dominantly by transmutation. Additionally, it further stresses the need to test ITER candidate Hall sensors under neutron flux with ITER relevant spectrum.

Duran, I. [Institute of Plasma Physics AS CR, v. v. i., Association EURATOM/IPP.CR, 182 00 Prague 8 (Czech Republic); Bolshakova, I.; Holyaka, R. [Magnetic Sensor Laboratory, Lviv Polytechnic National University, 790 31 Lviv (Ukraine); Viererbl, L.; Lahodova, Z. [Nuclear Research Institute plc., 250 68 Husinec-Rez (Czech Republic); Sentkerestiova, J. [Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, 115 19 Prague 1 (Czech Republic); Bem, P. [Nuclear Physics Institute AS CR, v. v. i., 250 68 Husinec-Rez (Czech Republic)

2010-10-15T23:59:59.000Z

477

Tritium processing system for the ITER Li/V blanket test module  

SciTech Connect (OSTI)

The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refueling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.

Sze, D.K.; Hua, T.Q. [Argonne National Lab., IL (United States); Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Dagher, M.A.; Waganer, L.M.

1997-04-01T23:59:59.000Z

478

Solution generating theorems for the TOV equation  

E-Print Network [OSTI]

The Tolman-Oppenheimer-Volkov [TOV] equation constrains the internal structure of general relativistic static perfect fluid spheres. We develop several "solution generating" theorems for the TOV, whereby any given solution can be "deformed" to a new solution. Because the theorems we develop work directly in terms of the physical observables -- pressure profile and density profile -- it is relatively easy to check the density and pressure profiles for physical reasonableness. This work complements our previous article [Phys. Rev. D71 (2005) 124307; gr-qc/0503007] wherein a similar "algorithmic" analysis of the general relativistic static perfect fluid sphere was presented in terms of the spacetime geometry -- in the present analysis the pressure and density are primary and the spacetime geometry is secondary. In particular, our "deformed" solutions to the TOV equation are conveniently parameterized in terms of delta rho_c and delta p_c, the finite shift in the central density and central pressure. We conclude by presenting a new physical and mathematical interpretation of the TOV equation -- as an integrability condition on the density and pressure profiles.

Petarpa Boonserm; Matt Visser; Silke Weinfurtner

2007-07-17T23:59:59.000Z

479

A Pseudo Random Numbers Generator Based on Chaotic Iterations. Application to Watermarking  

E-Print Network [OSTI]

In this paper, a new chaotic pseudo-random number generator (PRNG) is proposed. It combines the well-known ISAAC and XORshift generators with chaotic iterations. This PRNG possesses important properties of topological chaos and can successfully pass NIST and TestU01 batteries of tests. This makes our generator suitable for information security applications like cryptography. As an illustrative example, an application in the field of watermarking is presented.

Christophe Guyeux; Qianxue Wang; Jacques M. Bahi

2010-12-21T23:59:59.000Z

480

CHINA SPALLATION NEUTRON SOURCE PROJECT: DESIGN ITERATIONS AND R AND D STATUS.  

SciTech Connect (OSTI)

The China Spallation Neutron Source (CSNS) is an accelerator based high power project currently under preparation in China. The accelerator complex is based on an H{sup -} linear accelerator and a rapid cycling proton synchrotron. During the past year, the design of most accelerator systems went through major iterations, and initial research and developments were started on the prototyping of several key components. This paper summarizes major activities of the past year.

WEI,J.

2006-09-21T23:59:59.000Z

Note: This page contains sample records for the topic "integrated iterative solution" 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

Absolutely and uniformly convergent iterative approach to inverse scattering with an infinite radius of convergence  

DOE Patents [OSTI]

A method and system for solving the inverse acoustic scattering problem using an iterative approach with consideration of half-off-shell transition matrix elements (near-field) information, where the Volterra inverse series correctly predicts the first two moments of the interaction, while the Fredholm inverse series is correct only for the first moment and that the Volterra approach provides a method for exactly obtaining interactions which can be written as a sum of delta functions.

Kouri, Donald J. (Houston, TX); Vijay, Amrendra (Houston, TX); Zhang, Haiyan (Houston, TX); Zhang, Jingfeng (Houston, TX); Hoffman, David K. (Ames, IA)

2007-05-01T23:59:59.000Z

482

Design of irradiation rig for reactor testing of prototype bolometers for ITER  

SciTech Connect (OSTI)

We describe the design of an experimental rig, which was developed to allow reactor testing at relevant conditions, i.e. vacuum and {approx}400 deg.C temperature, of prototype resistive bolometers, which will be used in ITER to acquire information on the radiated power distribution from the main plasma and in the diverter region. The main feature of the design is that the rig has no active temperature control. (authors)

Gusarov, A.; Huysmans, S. [SCK.CEN Belgian Nucrear Research Center, 2400 Mol (Belgium); Meister, H. [Max-Planck-Institut fuer Plasmaphysik, Boltzmannstr. 2, D-85748 Garching b. Muenchen (Germany); Hodgson, E. [Euratom/CIEMAT Fusion Association, Avenida Complutense 22, 28040 Madrid (Spain)

2011-07-01T23:59:59.000Z

483

Atomic data for the ITER Core Imaging X-ray Spectrometer  

SciTech Connect (OSTI)

The parameters of the ITER core plasmas will be measured using the Core Imaging X-ray Spectrometer (CIXS), a high-resolution crystal spectrometer focusing on the L-shell spectra of highly ionized tungsten atoms. In order to correctly infer the plasma properties accurate atomic data are required. Here, some aspects of the underlying physics are discussed using experimental data and theoretical predictions from modeling.

Clementson, J; Beiersdorfer, P; Biedermann, C; Bitter, M; Delgado-Aparicio, L F; Graf, A; Gu, M F; Hill, K W; Barnsley, R

2012-06-15T23:59:59.000Z

484

Going with the group in a competitive game of iterated reasoning Seth Frey (sethfrey@indiana.edu)  

E-Print Network [OSTI]

Going with the group in a competitive game of iterated reasoning Seth Frey (sethfrey their strategy individually. John Nash proved that every game has at least one such equilib- rium. Mapped onto

Goldstone, Robert

485

Detailed search US supports Japanese bid to host ITER as France urges Europe to go it alone  

E-Print Network [OSTI]

support of his country for the Japanese bid to host the international thermonuclear site (ITER thermonuclear site if the French candidate is not selected for the international project. However

486

White Paper for Developing Electromagnetic Particle Injector system for ITER on NSTX-U University of Washington (19 July 2012)  

E-Print Network [OSTI]

discharges in ITER, both the time response of this system and the controllability on demand - Conventional gas guns will inject gas before capsule and trigger pre rail gun We plan to finish the design during 2012 and to build

487

Elasticity solutions for plane anisotropic functionally graded beams  

E-Print Network [OSTI]

Elasticity solutions for plane anisotropic functionally graded beams H.J. Ding a , D.J. Huang a This paper considers the plane stress problem of generally anisotropic beams with elastic compliance of anisotropic functionally graded plane beams, with the integral constants completely determined from boundary

Wang, Ji

488

PETROLEUM ALLOCATION AT PETROBRAS: MATHEMATICAL MODEL AND A SOLUTION  

E-Print Network [OSTI]

PETROLEUM ALLOCATION AT PETROBRAS: MATHEMATICAL MODEL AND A SOLUTION ALGORITHM Roger Rocha1 Petroleum Allocation is an important link for the integration of Petroleum Supply Chain at PETROBRAS. In this work we describe how mathematical programming is being used to solve the Petroleum Allocation Problem

Grossmann, Ignacio E.

489

Electronic forms solutions To support your business objectives  

E-Print Network [OSTI]

Electronic forms solutions To support your business objectives Easily integrate your offline forms are using electronic forms instead of paper, so that their existing forms are always in stock, easy to locate and have a consistent look and feel. IBM® Lotus® Forms software provides an open electronic forms

490

Accurate solution and approximations of the linearized bgk equation ...  

E-Print Network [OSTI]

Jan 7, 2015 ... We present an accurate and efficient high-order collocation method to solve the integral equation with a singular kernel ..... where A is an N ? N matrix whose element is amn ? An?ym?, and b and c are ...... some classical problems in flow and heat transfer. .... Algorithms for the numerical solution of a finite-.

Wei Li

2015-01-30T23:59:59.000Z

491

Radioactivity measurements of ITER materials using TFTR D-T neutron field  

SciTech Connect (OSTI)

TFTR successfully initiated trace tritium plasma experiments in mid-November 1993. During the coming year, the TFTR plasma tritium fraction is scheduled to be increased to at least 50%. The availability of larger amounts of D-T fusion neutrons in the high power D-T plasma phase of TFTR provides an useful opportunity to directly measure D-T neutron induced radioactivity in a realistic tokamak-environment in materials of vital interest to ITER. These measurements are invaluable for characterizing short and long lived radioactivity in various ITER candidate materials, for validating complex neutron transport calculations, and for meeting fusion reactor licensing requirements. The radioactivity measurements at TFTR will involve potential ITER materials that include stainless steel 316, vanadium-alloy, copper, iron, nickel, chromium, vanadium, titanium, manganese, cobalt, molybdenum, zinc, niobium, zirconium, tungsten, lead, tin, silicon, etc. Small samples of these materials will be irradiated in varying neutron energy spectra at the vacuum vessel first wall. These irradiated samples will then be counted for {gamma}-radioactivity at different cooling times to get extensive information on as many {gamma}-emitting radioactive products as feasible.

Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Kugel, H.W. [Princeton Univ., NJ (United States)] [and others

1994-12-31T23:59:59.000Z

492

INTEGRATING PHOTOVOLTAIC SYSTEMS  

E-Print Network [OSTI]

INTEGRATING PHOTOVOLTAIC SYSTEMS INTO PUBLIC SECTOR PERFORMANCE CONTRACTS IN DELAWARE FINAL for Energy and Environmental Policy University of Delaware February 2006 #12;INTEGRATING PHOTOVOLTAIC..................................................................................................... 1 1.2 Photovoltaics in Performance Contracts: An Overview

Delaware, University of

493

Energy Systems Integration: A Convergence of Ideas  

SciTech Connect (OSTI)

Energy systems integration (ESI) enables the effective analysis, design, and control of these interactions and interdependencies along technical, economic, regulatory, and social dimensions. By focusing on the optimization of energy from all systems, across all pathways, and at all scales, we can better understand and make use of the co-benefits that result to increase reliability and performance, reduce cost, and minimize environmental impacts. This white paper discusses systems integration and the research in new control architectures that are optimized at smaller scales but can be aggregated to optimize energy systems at any scale and would allow replicable energy solutions across boundaries of existing and new energy pathways.

Kroposki, B.; Garrett, B.; MacMillan, S.; Rice, B.; Komomua, C.; O'Malley, M.; Zimmerle, D.

2012-07-01T23:59:59.000Z

494

Analytical solutions of a generalized non-central potential in N-dimensions  

SciTech Connect (OSTI)

We present that N-dimensional non-relativistic wave equation for the generalized non-central potential with arbitrary angular momentum is analytically solvable in the hyperspherical coordinates. Asymptotic iteration method as a different approach is applied to obtain N-dimensional energy eigenvalues and the corresponding eigenfunctions. In hyperspherical coordinates, the wave function solutions are obtained in terms of hypergeometric functions and Jacobi polynomials. The bound states of quantum systems under consideration for some special cases, such as Hartmann and Makarov potentials, have been discussed in N-dimensions.

Durmus, Aysen, E-mail: aysend@erciyes.edu.tr [Department of Physics, Erciyes University, Kayseri 38039 (Turkey); zfidan, Aysel [Institute of Science, Erciyes University, Kayseri 38039 (Turkey)

2014-10-15T23:59:59.000Z

495

Transmission Commercial Project Integration  

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

Improvement (CBPI) Customer Forum Energy Imbalance Market Generator Interconnection Reform Implementation Network Integration Transmission Service (NT Service) Network Open...

496

An investigation into optimization of iteration parameters for solving partial differential equations by the alternating-direction implicit procedure  

E-Print Network [OSTI]

AN INVESTIGATION INTO OPTIMIZATION OF ITERATION PARAMETERS FOR SOLVING PARTIAL DIFFERENTIAL EQUATIONS BY THE ALTERNATING-DIRECTION IMPLICIT PROCEDURE A Thesis GERALD NELSON PITTS Submitted to the Graduate College of the Texas A&M University... in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1967 Major Subject Com uter Science AN INVESTIGATION INTO OPTIMIZATION OF ITERATION PARAMETERS FOR SOLVING PARTIAL DIFFERENTIAL EQUATIONS BY THE ALTERNATING...

Pitts, Gerald Nelson

1967-01-01T23:59:59.000Z

497

Metallocene/carbon hybrids prepared by a solution process for supercapacitor applications  

E-Print Network [OSTI]

Efficient and scalable solution-based processes are not generally available to integrate well-studied pseudocapacitive materials (i.e., metal oxides and conducting polymers) with other components such as porous carbon, ...

Mao, Xianwen

498

Solution to plasma-etching puzzle could mean more powerful microchips...  

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

Solution to plasma-etching puzzle could mean more powerful microchips By John Greenwald February 11, 2014 Tweet Widget Google Plus One Share on Facebook An integrated-circuit...

499

A Case Study of Modern PLC and LabVIEW Controls: Power Supply Controls for the ORNL ITER ECH Test Stand  

SciTech Connect (OSTI)

Power Supply Controls are being developed at Oak Ridge National Laboratory (ORNL) to test transmission line components of the Electron Cyclotron Heating (ECH) system, with a focus on gyrotrons and waveguides, in support of the International Thermonuclear Experimental Reactor (ITER). The control is performed by several Programmable Logic Controllers (PLC s) located near the different equipment. A technique of Supervisory Control and Data Acquisition (SCADA) is presented to monitor, control, and log actions of the PLC s on a PC through use of Allen Bradley s Remote I/O communication interface coupled with an Open Process Control/Object Linking and Embedding [OLE] for Process Control (OPC) Server/Client architecture. The OPC data is then linked to a National Instruments (NI) LabVIEW system for monitoring and control. Details of the architecture and insight into applicability to other systems are presented in the rest of this paper. Future integration with an EPICS (Experimental Physics Industrial Control System) based mini-CODAC (Control, Data Access and Communication) SCADA system is under consideration, and integration considerations will be briefly introduced.

Barker, Alan M [ORNL; Killough, Stephen M [ORNL; Bigelow, Tim S [ORNL; White, John A [ORNL; Munro Jr, John K [ORNL

2011-01-01T23:59:59.000Z

500

Advanced Integrated Systems Technology Development  

E-Print Network [OSTI]

conditioning in buildings featuring integrated design withconditioning in buildings featuring integrated design withof a building with advanced integrated design involving one

2013-01-01T23:59:59.000Z