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1

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

2

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

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

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

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

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

8

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

9

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"

10

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

11

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

12

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

13

A Robust Iterative Unfolding Method for Signal Processing  

E-Print Network [OSTI]

There is a well-known series expansion (Neumann series) in functional analysis for perturbative inversion of specific operators on Banach spaces. However, operators that appear in signal processing (e.g. folding and convolution of probability density functions), in general, do not satisfy the usual convergence condition of that series expansion. This article provides some theorems on the convergence criteria of a similar series expansion for this more general case, which is not covered yet by the literature. The main result is that a series expansion provides a robust unbiased unfolding and deconvolution method. For the case of the deconvolution, such a series expansion can always be applied, and the method always recovers the maximum possible information about the initial probability density function, thus the method is optimal in this sense. A very significant advantage of the presented method is that one does not have to introduce ad hoc frequency regulations etc., as in the case of usual naive deconvolution methods. For the case of general unfolding problems, we present a computer-testable sufficient condition for the convergence of the series expansion in question. Some test examples and physics applications are also given. The most important physics example shall be (which originally motivated our survey on this topic) the case of pi^0 --> gamma+gamma particle decay: we show that one can recover the initial pi^0 momentum density function form the measured single gamma momentum density function by our series expansion.

Andrs Lszl

2006-01-09T23:59:59.000Z

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

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

16

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

17

Process for the extraction of strontium from acidic solutions  

DOE Patents [OSTI]

The invention is a process for selectively extracting strontium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant solution is a macrocyclic polyether in an aliphatic hydrocarbon diluent containing a phase modifier. The process will selectively extract strontium values from nitric acid solutions which are up to 6 molar in nitric acid.

Horwitz, E. Philip (Naperville, IL); Dietz, Mark L. (Evanston, IL)

1994-01-01T23:59:59.000Z

18

Process for the extraction of strontium from acidic solutions  

DOE Patents [OSTI]

The invention is a process for selectively extracting strontium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant solution is a macrocyclic polyether in an aliphatic hydrocarbon diluent containing a phase modifier. The process will selectively extract strontium values from nitric acid solutions which are up to 6 molar in nitric acid.

Horwitz, E.P.; Dietz, M.L.

1993-01-01T23:59:59.000Z

19

Process for the extraction of strontium from acidic solutions  

DOE Patents [OSTI]

The invention is a process for selectively extracting strontium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant solution is a macrocyclic polyether in an aliphatic hydrocarbon diluent containing a phase modifier. The process will selectively extract strontium values from nitric acid solutions which are up to 6 molar in nitric acid. 4 figs.

Horwitz, E.P.; Dietz, M.L.

1994-09-06T23:59:59.000Z

20

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

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

A third and a fourth order iteration process for non-linear equations  

E-Print Network [OSTI]

derivatives continuous in a closed region R and the solution point y c R, define an iterar. ive process g by g (x) g l(x) ? J (x)Y(g l(x)) where p & 2, g (x) x, and J(x) is the matrix of the Jacobian of the system of functions. The order of the process... of S. 1 2 n Let x = [x x x ], and let f(x) = [fl(x) f2(x) ''' f (x)] n 1 n n be a vector valued function from S to R such that r(y) g -+ -+ Require f (x), 11r, s, t, u~n, to be continuous in S. gx gx Sx gx ~] We write the matrix J(x) = ? f. (x...

Crawley, Alton Rudolph

1967-01-01T23:59:59.000Z

22

Process for removing mercury from aqueous solutions  

DOE Patents [OSTI]

A process for removing mercury from water to a level not greater than two parts per billion wherein an anion exchange material that is insoluble in water is contacted first with a sulfide containing compound and second with a compound containing a bivalent metal ion forming an insoluble metal sulfide. To this treated exchange material is contacted water containing mercury. The water containing not more than two parts per billion of mercury is separated from the exchange material.

Googin, J.M.; Napier, J.M.; Makarewicz, M.A.; Meredith, P.F.

1985-03-04T23:59:59.000Z

23

Process for removing mercury from aqueous solutions  

DOE Patents [OSTI]

A process for removing mercury from water to a level not greater than two parts per billion wherein an anion exchange material that is insoluble in water is contacted first with a sulfide containing compound and second with a compound containing a bivalent metal ion forming an insoluble metal sulfide. To this treated exchange material is contacted water containing mercury. The water containing not more than two parts per billion of mercury is separated from the exchange material.

Googin, John M. (Oak Ridge, TN); Napier, John M. (Oak Ridge, TN); Makarewicz, Mark A. (Knoxville, TN); Meredith, Paul F. (Knoxville, TN)

1986-01-01T23:59:59.000Z

24

Business Process driven solutions for innovative enterprise information systems  

E-Print Network [OSTI]

Business Process driven solutions for innovative enterprise information systems F. Taglino, M. In particular, it will be argued about business process driven approach to information systems development and overcome current limits. Business process driven approach to IS development is here characterized by: (i

Paris-Sud XI, Université de

25

Process for the recovery of strontium from acid solutions  

DOE Patents [OSTI]

The invention is a process for selectively extracting strontium and technetium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant is a macrocyclic polyether in a diluent which is insoluble in water, but which will itself dissolve a small amount of water. The process will extract strontium and technetium values from nitric acid solutions which are up to 6 molar in nitric acid.

Horwitz, E. Philip (Naperville, IL); Dietz, Mark L. (Evanston, IL)

1992-01-01T23:59:59.000Z

26

Process for the recovery of strontium from acid solutions  

DOE Patents [OSTI]

The invention is a process for selectively extracting strontium and technetium values from aqueous nitric acid waste solutions containing these and other fission product values. The extractant is a macrocyclic polyether in a diluent which is insoluble in water, but which will itself dissolve a small amount of water. The process will extract strontium and technetium values from nitric acid solutions which are up to 6 molar in nitric acid. 5 figs.

Horwitz, E.P.; Dietz, M.L.

1992-03-31T23:59:59.000Z

27

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

28

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

29

Solution-processed coreshell nanowires for efficient photovoltaic cells  

E-Print Network [OSTI]

Solution-processed coreshell nanowires for efficient photovoltaic cells Jinyao Tang1,3 , Ziyang are promising for photovoltaic appli- cations111 , but, so far, nanowire-based solar cells have had lower efficiencies than planar cells made from the same materials610,12,13 , even allowing for the generally lower

Yang, Peidong

30

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

31

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

32

TRUEX processing of plutonium analytical solutions at Argonne National Laboratory  

SciTech Connect (OSTI)

The TRUEX (TRansUranic EXtraction) solvent extraction process was developed at Argonne National Laboratory (ANL) for the Department of Energy. A TRUEX demonstration completed at ANL involved the processing of analytical and experimental waste generated there and at the New Brunswick Laboratory. A 20-stage centrifugal contactor was used to recover plutonium, americium, and uranium from the waste. Approximately 84 g of plutonium, 18 g of uranium, and 0.2 g of americium were recovered from about 118 liters of solution during four process runs. Alpha decontamination factors as high as 65,000 were attained, which was especially important because it allowed the disposal of the process raffinate as a low-level waste. The recovered plutonium and uranium were converted to oxide; the recovered americium solution was concentrated by evaporation to approximately 100 ml. The flowsheet and operational procedures were modified to overcome process difficulties. These difficulties included the presence of complexants in the feed, solvent degradation, plutonium precipitation, and inadequate decontamination factors during startup. This paper will discuss details of the experimental effort.

Chamberlain, D.B.; Conner, C.; Hutter, J.C.; Leonard, R.A.; Wygmans, D.G.; Vandegrift, G.F. [Argonne National Lab., IL (United States). Chemical Technology Div.

1995-12-31T23:59:59.000Z

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

Process of concentrating ethanol from dilute aqueous solutions thereof  

DOE Patents [OSTI]

Relatively dilute aqueous solutions of ethanol are concentrated by passage through a bed of a crystalline silica polymorph, such as silicalite, to adsorb the ethanol with residual dilute feed in contact with the bed, which is displaced by passing concentrated aqueous ethanol through the bed without displacing the adsorbed ethanol. A product concentrate is then obtained by removing the adsorbed ethanol from the bed together with at least a portion of the concentrated aqueous ethanol used as the displacer liquid. This process permits ethanol to be concentrated from dilute fermentation beers, which may contain from 6 to 10% ethanol, to obtain a concentrate product at very low energy cost having an ethanol concentration in excess of 95%, such as a concentration of from 98 to 99.5%.

Oulman, Charles S. [Ames, IA; Chriswell, Colin D. [Slater, IA

1981-07-07T23:59:59.000Z

35

Process of concentrating ethanol from dilute aqueous solutions thereof  

DOE Patents [OSTI]

Relatively dilute aqueous solutions of ethanol are concentrated by passage through a bed of a crystalline silica polymorph, such as silicalite, to adsorb the ethanol with residual dilute feed in contact with the bed, which is displaced by passing concentrated aqueous ethanol through the bed without displacing the adsorbed ethanol. A product concentrate is then obtained by removing the adsorbed ethanol from the bed together with at least a portion of the concentrated aqueous ethanol used as the displacer liquid. This process permits ethanol to be concentrated from dilute fermentation beers, which may contain from 6 to 10% ethanol, to obtain a concentrate product at very low energy cost having an ethanol concentration in excess of 95%, such as a concentration of from 98 to 99.5%. 5 figs.

Oulman, C.S.; Chriswell, C.D.

1981-07-07T23:59:59.000Z

36

Investigation of solution-processed bismuth-niobium-oxide films  

SciTech Connect (OSTI)

The characteristics of bismuth-niobium-oxide (BNO) films prepared using a solution process were investigated. The BNO film annealed at 550?C involving three phases: an amorphous phase, Bi{sub 3}NbO{sub 7} fluorite microcrystals, and Nb-rich cubic pyrochlore microcrystals. The cubic pyrochlore structure, which was the main phase in this film, has not previously been reported in BNO films. The relative dielectric constant of the BNO film was approximately 140, which is much higher than that of a corresponding film prepared using a conventional vacuum sputtering process. Notably, the cubic pyrochlore microcrystals disappeared with increasing annealing temperature and were replaced with triclinic ?-BiNbO{sub 4} crystals at 590?C. The relative dielectric constant also decreased with increasing annealing temperature. Therefore, the high relative dielectric constant of the BNO film annealed at 550?C is thought to result from the BNO cubic pyrochlore structure. In addition, the BNO films annealed at 500?C contained approximately 6.5?atm.?% carbon, which was lost at approximately 550?C. This result suggests that the carbon in the BNO film played an important role in the formation of the cubic pyrochlore structure.

Inoue, Satoshi, E-mail: s-inoue@jaist.ac.jp [Green Device Research Center, Japan Advanced Institute of Science and Technology (JAIST), 2-13 Asahidai, Nomi, Ishikawa 923-1211 (Japan); School of Material Science, Japan Advanced Institute of Science and Technology (JAIST), 1-1 Asahidai, Nomi, Ishikawa 923-1292 (Japan); Ariga, Tomoki [Green Device Research Center, Japan Advanced Institute of Science and Technology (JAIST), 2-13 Asahidai, Nomi, Ishikawa 923-1211 (Japan); ERATO Shimoda Nano-Liquid Process Project, Japan Science and Technology Agency (JST), 2-13 Asahidai, Nomi, Ishikawa 923-1211 (Japan); Matsumoto, Shin [School of Material Science, Japan Advanced Institute of Science and Technology (JAIST), 1-1 Asahidai, Nomi, Ishikawa 923-1292 (Japan); Onoue, Masatoshi; Miyasako, Takaaki [ERATO Shimoda Nano-Liquid Process Project, Japan Science and Technology Agency (JST), 2-13 Asahidai, Nomi, Ishikawa 923-1211 (Japan); Tokumitsu, Eisuke; Shimoda, Tatsuya [Green Device Research Center, Japan Advanced Institute of Science and Technology (JAIST), 2-13 Asahidai, Nomi, Ishikawa 923-1211 (Japan); School of Material Science, Japan Advanced Institute of Science and Technology (JAIST), 1-1 Asahidai, Nomi, Ishikawa 923-1292 (Japan); ERATO Shimoda Nano-Liquid Process Project, Japan Science and Technology Agency (JST), 2-13 Asahidai, Nomi, Ishikawa 923-1211 (Japan); Chinone, Norimichi; Cho, Yasuo [Research Institute of Electrical Communication, Tohoku University, 2-1-1 Katahira, Aoba-ku, Sendai, Miyagi 980-8577 (Japan)

2014-10-21T23:59:59.000Z

37

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

38

Nonaqueous solution synthesis process for preparing oxide powders of lead zirconate titanate and related materials  

DOE Patents [OSTI]

A process is disclosed for producing powders of perovskite-type compounds which comprises mixing a metal alkoxide solution with a lead acetate solution to form a homogeneous, clear metal solution, adding an oxalic acid/n-propanol solution to this metal solution to form an easily filterable, free-flowing precursor powder and then calcining this powder. This process provides fine perovskite-phase powders with ferroelectric properties which are particularly useful in a variety of electronic applications. 4 figs.

Voigt, J.A.; Sipola, D.L.; Tuttle, B.A.; Anderson, M.T.

1999-06-01T23:59:59.000Z

39

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

40

ITER Project  

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

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

Photoinduced electron transfer processes in homogeneous and microheterogeneous solutions  

SciTech Connect (OSTI)

The studies have focused on rapid, efficient bond-fragmentation reactions initiated through photoinduced electron transfer. Electron transfer induced fragmentation of a number of donors have been examined, especially 1,2 diamines and related compounds. Two of the amines fragment with rate constants of 3 [times] 10[sup 8] to 2 [times] 10[sup 9] M[sup [minus]1]sec[sup [minus]1]. A series of amino-substituted pinacols and related compounds have also been examined; they undergo similar but slower fragmentation processes when converted to their cation radicals by photoinduced electron transfer. The studies with linked and polymeric electron donor- electron acceptor coupled molecules have also progressed. Several polymers containing diamine repeat units and anthraquinone or nitroaromatic acceptors have also been prepared that can be photoactivated by visible irradiation; they fragment efficiently in solution and photodegrade even in the solid state. The studies of singlet oxygen initiated fragmentation reactions of diamines, amino alcohols, and aminoketones have nearly been completed. Attention have been turned to fragmentable electron acceptors such as p- cyanobenzyl bromide; irradiation of electron donors such as methyl- or methoxy-naphthalenes can initiate efficient fragmentation of the electron deficient bromide.

Whitten, D.G.

1992-12-01T23:59:59.000Z

42

QUANTIFYING THE CONVERGENCE TIME OF DISTRIBUTED DESIGN PROCESSES  

E-Print Network [OSTI]

QUANTIFYING THE CONVERGENCE TIME OF DISTRIBUTED DESIGN PROCESSES Erich Devendorf Research Engineer design processes. In distributed design, large systems are decomposed into smaller, coupled design individual objectives. The number of iterations required to reach equilibrium solutions in distributed design

Lewis, Kemper E.

43

MODELING OF A NOVEL SOLUTION POTASH MINING PROCESS Sergio Almada, Harvey Haugen  

E-Print Network [OSTI]

by drilling followed by a number of steps to develop a solution mining cavern. Water is injected to dissolve a sump area within the salt at the base of the solution mining cavern. The sump allows insoluble materials settle within the cavern to avoid affecting the solution mining process and the dissolved salt can

44

Separation processes using expulsion from dilute supercritical solutions  

DOE Patents [OSTI]

A process is described for separating isotopes as well as other mixtures by utilizing the behavior of dilute repulsive or weakly attractive elements of the mixtures as the critical point of the solvent is approached.

Cochran, H.D. Jr.

1993-04-20T23:59:59.000Z

45

Separation processes using expulsion from dilute supercritical solutions  

DOE Patents [OSTI]

A process for separating isotopes as well as other mixtures by utilizing the behavior of dilute repulsive or weakly attractive elements of the mixtures as the critical point of the solvent is approached.

Cochran, Jr., Henry D. (Oak Ridge, TN)

1993-01-01T23:59:59.000Z

46

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

47

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

48

Uniqueness of Solutions to Single-Stage Isobaric Flash Processes Involving  

E-Print Network [OSTI]

of material stability, the Gibbs-Duhem equation, and the Cauchy interlace theorem. Results for the other solutions. Solution curves for the energy balance equation (for the QP case) and the vapor specification. The question of uniqueness arises because the set of model equations that describeseparation processes

Lucia, Angelo

49

Solution-processed infrared photovoltaic devices with >10% monochromatic internal quantum efficiency  

E-Print Network [OSTI]

, solution-cast photovoltaics are of urgent interest to realize low-cost solar cells. Polymer, polymerSolution-processed infrared photovoltaic devices with >10% monochromatic internal quantum-fullerene, and polymer-nanocrystal photovoltaics absorb light only to wavelengths as long as 750 nm, with the exception

50

Development of low-temperature solution-processed colloidal quantum dot-based solar cells  

E-Print Network [OSTI]

Solution-processed solar cells incorporating organic semiconductors and inorganic colloidal quantum dots (QDs) are potential alternatives to conventional solar cells fabricated via vacuum or high-temperature sintering ...

Chang, Liang-Yi, Ph. D. Massachusetts Institute of Technology

2013-01-01T23:59:59.000Z

51

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

52

A Membrane Process for Recycling Die Lube from Wastewater Solutions  

SciTech Connect (OSTI)

An active-surface membrane technology was used to separate a die lube manufacturing wastewater stream consisting of various oils, hydrocarbons, heavy metals, and silicones. The ultrafiltration membranes reduced organics from initial oil and grease contents by 20?25X, carbon oxygen demand (COD) by 1.5 to 2X, and total organic carbon (TOC) by 0.6, while the biological oxygen demand (BOD) remained constant. The active-surface membranes were not fouled as badly as non-active-surface systems and the active-surface membrane flux levels were consistently higher and more stable than those of the non-active-surface membranes tested. Field testing demonstrated that the rotary microfilter can concentrate the die lube, i.e. remove the glycerin component, and produce a die lube suitable for recycling. The recycling system operated for six weeks with only seven cleaning cycles and no mechanical or electrical failures. Test data and quality records indicate that the die casting scrap was reduced from 8.4 to 7.8%. There is no doubt that this test yielded tremendous results. This separation process presents significant opportunities that can be evaluated further.

Peterson, E.S.; Trudeau, J.; Cleary, B.; Hackett, M.; Greene, W.A.

2003-04-30T23:59:59.000Z

53

Solvent extraction and recovery of the transuranic elements from waste solutions using the TRUEX process  

SciTech Connect (OSTI)

High-level liquid waste is produced during the processing of irradiated nuclear fuel by the PUREX process. In some cases the treatment of metallurgical scrap to recover the plutonium values also generates a nitric acid waste solution. Both waste solutions contain sufficient concentrations of transuranic elements (mostly /sup 241/Am) to require handling and disposal as a TRU waste. This paper describes a recently developed solvent extraction/recovery process called TRUEX (transuranium extraction) which is designed to reduce the TRU concentration in nitric waste solutions to <100 nCi/g of disposed form (1,2). (In the USA, non-TRU waste is defined as <100 nCi of TRU/g of disposed form.) The process utilizes PUREX process solvent (TBP in a normal paraffinic hydrocarbon or carbon tetrachloride) modified by a small concentration of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (abbrev. CMPO). The presence of CMPO enables the modified PUREX process solvent to extract trivalent actinides as well as tetra- and hexavalent actinides. A major feature of the TRUEX process is that is is applicable to waste solutions containing a wide range of nitric acid, salt, and fission product concentrations and at the same time is very compatible with existing liquid-liquid extraction technology as usually practiced in a fuel reprocessing plant. To date the process has been tested on two different types of synthetic waste solutions. The first solution is a typical high-level nitric acid waste and the second a typical waste solution generated in metallurgical scrap processing. Results are discussed. 4 refs., 1 fig., 4 tabs.

Horwitz, E.P.; Schulz, W.W.

1985-01-01T23:59:59.000Z

54

Process for separating and recovering an anionic dye from an aqueous solution  

DOE Patents [OSTI]

A solid/liquid phase process for the separation and recovery of an anionic dye from an aqueous solution is disclosed. The solid phase comprises separation particles having surface-bonded poly(ethylene glycol) groups, whereas the aqueous solution from which the anionic dye molecules are separated contains a poly(ethylene glycol) liquid/liquid biphase-forming amount of a dissolved lyotropic salt. After contact between the aqueous solution and separation particles, the anionic dye is bound to the particles. The bound anionic dye molecules are freed from the separation particles by contacting the anionic dye-bound particles with an aqueous solution that does not contain a poly(ethylene glycol) liquid/liquid biphase-forming amount of a dissolved lyotropic salt to form an aqueous anionic dye solution whose anionic dye concentration is preferably higher than that of the initial dye-containing solution.

Rogers, Robin (DeKalb, IL); Horwitz, E. Philip (Naperville, IL); Bond, Andrew H. (Tallahassee, FL)

1998-01-01T23:59:59.000Z

55

Process for separating and recovering an anionic dye from an aqueous solution  

DOE Patents [OSTI]

A solid/liquid phase process for the separation and recovery of an anionic dye from an aqueous solution is disclosed. The solid phase comprises separation particles having surface-bonded poly(ethylene glycol) groups, whereas the aqueous solution from which the anionic dye molecules are separated contains a poly(ethylene glycol) liquid/liquid biphase-forming amount of a dissolved lyotropic salt. After contact between the aqueous solution and separation particles, the anionic dye is bound to the particles. The bound anionic dye molecules are freed from the separation particles by contacting the anionic dye-bound particles with an aqueous solution that does not contain a poly(ethylene glycol) liquid/liquid biphase-forming amount of a dissolved lyotropic salt to form an aqueous anionic dye solution whose anionic dye concentration is preferably higher than that of the initial dye-containing solution. 7 figs.

Rogers, R.; Horwitz, E.P.; Bond, A.H.

1998-01-13T23:59:59.000Z

56

Fully Solution-Processed Copper Chalcopyrite Thin Film Solar Cells: Materials Chemistry, Processing, and Device Physics  

E-Print Network [OSTI]

nanowire networks as window layers in thin film solar cells.window layer for fully solution-deposited thin filmITO) thin films by silver nanowire composite window layers

Chung, Choong-Heui

2012-01-01T23:59:59.000Z

57

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

58

Surfactant based imbibition and induced solution gas drive process: investigation by nuclear magnetic resonance  

E-Print Network [OSTI]

drive mechanism. This imbibition and induced solution gas drive study employed nuclear magnetic resonance (NMR) spectroscopy techniques to monitor and characterize the progress of oil recovery inside the rock sample core. A specially designed core...SURFACTANT BASED IMBIBITION AND INDUCED SOLUTION GAS DRIVE PROCESS: INVESTIGATION BY NUCLEAR MAGNETIC RESONANCE A Thesis by JAMES CALVIN COX Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment...

Cox, James Calvin

1993-01-01T23:59:59.000Z

59

Process for recovering chaotropic anions from an aqueous solution also containing other ions  

DOE Patents [OSTI]

A solid/liquid process for the separation and recovery of chaotropic anions from an aqueous solution is disclosed. The solid support comprises separation particles having surface-bonded poly(ethylene glycol) groups, whereas the aqueous solution from which the chaotropic anions are separated contains a poly(ethylene glycol) liquid/liquid biphase-forming amount of a dissolved salt (lyotrope). A solid/liquid phase admixture of separation particles containing bound chaotropic anions in such an aqueous solution is also contemplated, as is a chromatography apparatus containing that solid/liquid phase admixture. 19 figs.

Rogers, R.; Horwitz, E.P.; Bond, A.H.

1999-03-30T23:59:59.000Z

60

Evaluation of the Magnesium Hydroxide Treatment Process for Stabilizing PFP Plutonium/Nitric Acid Solutions  

SciTech Connect (OSTI)

This document summarizes an evaluation of the magnesium hydroxide [Mg(OH)2] process to be used at the Hanford Plutonium Finishing Plant (PFP) for stabilizing plutonium/nitric acid solutions to meet the goal of stabilizing the plutonium in an oxide form suitable for storage under DOE-STD-3013-99. During the treatment process, nitric acid solutions bearing plutonium nitrate are neutralized with Mg(OH)2 in an air sparge reactor. The resulting slurry, containing plutonium hydroxide, is filtered and calcined. The process evaluation included a literature review and extensive laboratory- and bench-scale testing. The testing was conducted using cerium as a surrogate for plutonium to identify and quantify the effects of key processing variables on processing time (primarily neutralization and filtration time) and calcined product properties.

Gerber, Mark A.; Schmidt, Andrew J.; Delegard, Calvin H.; Silvers, Kurt L.; Baker, Aaron B.; Gano, Susan R.; Thornton, Brenda M.

2000-09-28T23:59:59.000Z

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


61

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

62

IEEE TRANSACTIONS ON SIGNAL PROCESSING, VOL. 50, NO. 4, APRIL 2002 923 Adaptive Solution for Blind  

E-Print Network [OSTI]

IEEE TRANSACTIONS ON SIGNAL PROCESSING, VOL. 50, NO. 4, APRIL 2002 923 Adaptive Solution for Blind, and Mila Nikolova Abstract--A deterministic maximum likelihood (DML) ap- proach is presented for the blind of the recursive and adap- tive algorithm are presented. Index Terms--Adaptive algorithm, blind equalization, deter

Nikolova, Mila

63

Composition and process for separating cesium ions from an acidic aqueous solution also containing other ions  

DOE Patents [OSTI]

A crown ether cesium ion extractant is disclosed as is its synthesis. The crown ether cesium ion extractant is useful for the selective purification of cesium ions from aqueous acidic media, and more particularly useful for the isolation of radioactive cesium-137 from nuclear waste streams. Processes for isolating cesium ions from aqueous acidic media using the crown ether cesium extractant are disclosed as are processes for recycling the crown ether cesium extractant and processes for recovering cesium from a crown ether cesium extractant solution.

Dietz, Mark L. (Elmhurst, IL); Horwitz, E. Philip (Naperville, IL); Bartsch, Richard A. (Lubbock, TX); Barrans, Jr., Richard E. (Downers Grove, IL); Rausch, David (Naperville, IL)

1999-01-01T23:59:59.000Z

64

Composition and process for separating cesium ions from an acidic aqueous solution also containing other ions  

DOE Patents [OSTI]

A crown ether cesium ion extractant is disclosed as is its synthesis. The crown ether cesium ion extractant is useful for the selective purification of cesium ions from aqueous acidic media, and more particularly useful for the isolation of radioactive cesium-137 from nuclear waste streams. Processes for isolating cesium ions from aqueous acidic media using the crown ether cesium extractant are disclosed as are processes for recycling the crown ether cesium extractant and processes for recovering cesium from a crown ether cesium extractant solution. 4 figs.

Dietz, M.L.; Horwitz, E.P.; Bartsch, R.A.; Barrans, R.E. Jr.; Rausch, D.

1999-03-30T23:59:59.000Z

65

Enhancing performing characteristics of organic semiconducting films by improved solution processing  

DOE Patents [OSTI]

Improved processing methods for enhanced properties of conjugated polymer films are disclosed, as well as the enhanced conjugated polymer films produced thereby. Addition of low molecular weight alkyl-containing molecules to solutions used to form conjugated polymer films leads to improved photoconductivity and improvements in other electronic properties. The enhanced conjugated polymer films can be used in a variety of electronic devices, such as solar cells and photodiodes.

Bazan, Guillermo C; Moses, Daniel; Peet, Jeffrey; Heeger, Alan J

2014-05-13T23:59:59.000Z

66

Enhancing performance characteristics of organic semiconducting films by improved solution processing  

DOE Patents [OSTI]

Improved processing methods for enhanced properties of conjugated polymer films are disclosed, as well as the enhanced conjugated polymer films produced thereby. Addition of low molecular weight alkyl-containing molecules to solutions used to form conjugated polymer films leads to improved photoconductivity and improvements in other electronic properties. The enhanced conjugated polymer films can be used in a variety of electronic devices, such as solar cells and photodiodes.

Bazan, Guillermo C; Mikhailovsky, Alexander; Moses, Daniel; Nguyen, Thuc-Quyen; Peet, Jeffrey; Soci, Cesare

2012-11-27T23:59:59.000Z

67

Enhancing performance characteristics of organic semiconducting films by improved solution processing  

DOE Patents [OSTI]

Improved processing methods for enhanced properties of conjugated polymer films are disclosed, as well as the enhanced conjugated polymer films produced thereby. Addition of low molecular weight alkyl-containing molecules to solutions used to form conjugated polymer films leads to improved photoconductivity and improvements in other electronic properties. The enhanced conjugated polymer films can be used in a variety of electronic devices, such as solar cells and photodiodes.

Bazan, Guillermo C. (Santa Barbara, CA); Heeger, Alan J. (Santa Barbara, CA); Moses, Daniel (Santa Barbara, CA); Peet, Jeffrey (Goleta, CA)

2013-09-25T23:59:59.000Z

68

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

69

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

70

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

71

A NEW PROCESS DEVELOPED FOR SEPARATION OF LIGNIN FROM AMMONIUM HYDROXIDE PRETREATMENT SOLUTIONS  

SciTech Connect (OSTI)

A method is described for separating lignin from liquid solutions resulting from the pretreatment of lignocellulosic materials such as switchgrass with ammonium hydroxide. The method involves a sequence of steps including acidification, evaporation, and precipitation or centrifugation that are performed under defined conditions, and results in a relatively pure, solid lignin product. The method is tested on ammonium hydroxide solutions containing lignin extracted from switchgrass. Experimental results show that the method is capable of recovering between 66-95% of dissolved lignin as a precipitated solid. Cost estimates of pilot-scale and industrial-scale expressions of the process indicate that breakeven lignin prices of $2.36/kg and $0.78/kg, respectively, may be obtainable with this recovery method.

Sherman, S.; Gorensek, M.; Milliken, C.

2010-12-14T23:59:59.000Z

72

Solution-processed high-performance colloidal quantum dot tandem photodetectors on flexible substrates  

SciTech Connect (OSTI)

We report a high-performance colloidal quantum dot (CQD)-based near-infrared tandem photodetector fabricated on flexible substrates via solution-processed method. The tandem photodetector on poly(ethylene terephthalate) substrates exhibited low dark current and high detectivities over ?8.8??10{sup 11} Jones at near infrared range at ?0.5?V bias and over ?10{sup 13} Jones near 0 bias. The critical bend radii of ?8?mm and ?3?mm have been demonstrated for tensile and compressive bending, respectively. The performance of photodetectors remains stable under mechanical stress, making PbSe CQD material a promise candidate for flexible infrared sensing applications.

Jiang, Zhenyu; You, Guanjun; Wang, Li; Liu, Jie; Xu, Jian, E-mail: jianxu@engr.psu.edu [Department of Engineering Science and Mechanics, Pennsylvania State University, University Park, Pennsylvania 16802 (United States); Hu, Wenjia [China Tianchen Engineering Corporation, Tianjin 300400 (China); Zhang, Yu [State Key Laboratory on Integrated Optoelectronics and College of Electronic Science and Engineering, Jilin University, Changchun 130012 (China)

2014-08-28T23:59:59.000Z

73

Solution of relativistic quantum optics problems using clusters of graphical processing units  

SciTech Connect (OSTI)

Numerical solution of relativistic quantum optics problems requires high performance computing due to the rapid oscillations in a relativistic wavefunction. Clusters of graphical processing units are used to accelerate the computation of a time dependent relativistic wavefunction in an arbitrary external potential. The stationary states in a Coulomb potential and uniform magnetic field are determined analytically and numerically, so that they can used as initial conditions in fully time dependent calculations. Relativistic energy levels in extreme magnetic fields are recovered as a means of validation. The relativistic ionization rate is computed for an ion illuminated by a laser field near the usual barrier suppression threshold, and the ionizing wavefunction is displayed.

Gordon, D.F., E-mail: daviel.gordon@nrl.navy.mil; Hafizi, B.; Helle, M.H.

2014-06-15T23:59:59.000Z

74

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 centralNewUSUS ITER ships

75

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 centralNewUSUS ITER

76

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 centralNewUSUS ITER6 News

77

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 centralNewUSUS ITER6 News7

78

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 centralNewUSUS ITER6 News78

79

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 centralNewUSUS ITER6 News789

80

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 centralNewUSUS ITER6

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


81

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 centralNewUSUS ITER6Videos

82

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

83

Studies of solution-processed organic light-emitting diodes and their materials  

SciTech Connect (OSTI)

A hitherto unexplored approach is presented in which a small molecule is used as a host to polymer guests in solution-processed OLEDs. We find that the small molecule host results in much more efficient devices than the often-used alternative polymer host when used for the guests presented. It is likely that nano- and microstructural differences between the hosts contribute to the improvements, which highlights some interesting characteristics that can help to better understand the nature of these mixtures. A number of the guests used in this study were newly synthesized benzobisoxazole-based copolymers. New organic copolymers are presented that are based on the chemical structure of benzobisoxazoles, which have been shown in the past to have good electron transporting properties. The novel concept in this publication pertains to a change in the direction of polymerization, also known as the conjugation pathway, which we show increases the emission efficiency. This work highlights a unique and useful property of organic semiconducting materials in that they can be synthesized to create the desired characteristics. Earlier work is described that kick-started in our research group the use of small molecules in solution-processed OLEDs. Originally these devices were to be used in magnetoresistance studies, but the project took a different path when the devices were more efficient than expected. The efficient use of small molecules in solution-processed OLEDs is highlighted, which at the time was not often the case. Also, the important observation of the effect of solvent choice on the resultant film is emphasized, with discussion of the likely cause of these effects. Microcavity OLEDs are introduced in which the transparent anode ITO is replaced with semi-transparent thin silver, which creates an optical cavity within the devices. The goal was to expand a previous work that created an on-chip spectrometer covering wavelengths 493 to 639 nm. In this case, a spin-coated mixed emitting layer (EML) is used, consisting of a polymer and a small molecule that both emit in the near UV and blue. The resulting combined spectra gives a wide band that can be used to create narrow microcavity emission peaks of 373 to 469 nm, depending on the device thickness (i.e. the cavitys optical length). In the process of this effort, the mixed EML presented interesting complexities that we attempt to explain via simulation and morphology study.

Hellerich, Emily [Ames Laboratory] [Ames Laboratory

2013-05-15T23:59:59.000Z

84

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

85

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

86

Processing results of 1,800 gallons of mercury and radioactively contaminated mixed waste rinse solution  

SciTech Connect (OSTI)

The mercury-contaminated rinse solution (INEL waste ID{number_sign} 123; File 8 waste) was successfully treated at the Idaho National Engineering Laboratory (INEL). This waste was generated during the decontamination of the Heat Transfer Reactor Experiment 3 (HTRE-3) reactor shield tank. Approximately 1,800 gal of waste was generated and was placed into 33 drums. Each drum contained precipitated sludge material ranging from 1--10 in. in depth, with the average depth of about 2.5 in. The pH of each drum varied from 3--11. The bulk liquid waste had a mercury level of 7.0 mg/l, which exceeded the Resource Conservation and Recovery Act (RCRA) limit of 0.2 mg/l. The average liquid bulk radioactivity was about 2.1 pCi/ml, while the average sludge contamination was about 13,800 pci/g. Treatment of the waste required separation of the liquid from the sludge, filtration, pH adjustment, and ion exchange. Because of difficulties in processing, three trials were required to reduce the mercury levels to below the RCRA limit. In the first trial, insufficient filtration of the waste allowed solid particulate produced during pH adjustment to enter into the ion exchange columns and ultimately the waste storage tank. In the second trial, the waste was filtered down to 0.1 {mu} to remove all solid mercury compounds. However, before filtration could take place, a solid mercury complex dissolved and mercury levels exceeded the RCRA limit after filtration. In the third trial, the waste was filtered through 0.3-A filters and then passed through the S-920 resin to remove the dissolved mercury. The resulting solution had mercury levels at 0.0186 mg/l and radioactivity of 0.282 pCi/ml. This solution was disposed of at the TAN warm waste pond, TAN782, TSF-10.

Thiesen, B.P.

1993-01-01T23:59:59.000Z

87

Low-Temperature, Solution-Processed Molybdenum Oxide Hole-Collection Layer for Organic Photovoltaics  

SciTech Connect (OSTI)

We have utilized a commercially available metal-organic precursor to develop a new, low-temperature, solution-processed molybdenum oxide (MoO{sub x}) hole-collection layer (HCL) for organic photovoltaic (OPV) devices that is compatible with high-throughput roll-to-roll manufacturing. Thermogravimetric analysis indicates complete decomposition of the metal-organic precursor by 115 C in air. Acetonitrile solutions spin-cast in a N{sub 2} atmosphere and annealed in air yield continuous thin films of MoO{sub x}. Ultraviolet, inverse, and X-ray photoemission spectroscopies confirm the formation of MoO{sub x} and, along with Kelvin probe measurements, provide detailed information about the energetics of the MoO{sub x} thin films. Incorporation of these films into conventional architecture bulk heterojunction OPV devices with poly(3-hexylthiophene) and [6,6]-phenyl-C{sub 61} butyric acid methyl ester afford comparable power conversion efficiencies to those obtained with the industry-standard material for hole injection and collection: poly(3,4-ethylenedioxythiophene):poly(styrene sulfonate) (PEDOT:PSS). The MoO{sub x} HCL devices exhibit slightly reduced open circuit voltages and short circuit current densities with respect to the PEDOT:PSS HCL devices, likely due in part to charge recombination at Mo{sup 5+} gap states in the MoO{sub x} HCL, and demonstrate enhanced fill factors due to reduced series resistance in the MoO{sub x} HCL.

Hammond, S. R.; Meyer, J.; Widjonarko, N. E.; Ndione, P. F.; Sigdel, A. K.; Garcia, A.; Miedaner, A.; Lloyd, M. T.; Kahn, A.; Ginley, D. S.; Berry, J. J.; Olson, D. C.

2012-02-21T23:59:59.000Z

88

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

89

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

90

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

91

US ITER | Media Corner  

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92

US ITER | Media Corner  

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93

US ITER | Media Corner  

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94

US ITER | Media Corner  

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95

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

96

US ITER | About  

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97

US ITER | Media Corner  

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98

US ITER | Media Corner  

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

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99

US ITER | Media Corner  

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

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100

US ITER | Media Corner  

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Note: This page contains sample records for the topic "iterative solution process" from the National Library of EnergyBeta (NLEBeta).
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101

US ITER | Media Corner  

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102

US ITER | Media Corner  

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

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103

US ITER | Media Corner  

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104

US ITER | Media Corner  

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105

US ITER | Media Corner  

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106

What is ITER  

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

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107

US ITER | About  

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

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108

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

109

US ITER | About  

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

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110

US ITER | Media Corner  

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111

US ITER | Media Corner  

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

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112

US ITER | Media Corner  

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

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113

US ITER | Media Corner  

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

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114

ParaText : scalable solutions for processing and searching very large document collections : final LDRD report.  

SciTech Connect (OSTI)

This report is a summary of the accomplishments of the 'Scalable Solutions for Processing and Searching Very Large Document Collections' LDRD, which ran from FY08 through FY10. Our goal was to investigate scalable text analysis; specifically, methods for information retrieval and visualization that could scale to extremely large document collections. Towards that end, we designed, implemented, and demonstrated a scalable framework for text analysis - ParaText - as a major project deliverable. Further, we demonstrated the benefits of using visual analysis in text analysis algorithm development, improved performance of heterogeneous ensemble models in data classification problems, and the advantages of information theoretic methods in user analysis and interpretation in cross language information retrieval. The project involved 5 members of the technical staff and 3 summer interns (including one who worked two summers). It resulted in a total of 14 publications, 3 new software libraries (2 open source and 1 internal to Sandia), several new end-user software applications, and over 20 presentations. Several follow-on projects have already begun or will start in FY11, with additional projects currently in proposal.

Crossno, Patricia Joyce; Dunlavy, Daniel M.; Stanton, Eric T.; Shead, Timothy M.

2010-09-01T23:59:59.000Z

115

Efficient solution-processed small molecule: Cadmium selenide quantum dot bulk heterojunction solar cells  

SciTech Connect (OSTI)

We report bulk heterojunction solar cells based on blends of solution-processed small molecule [7,7?-(4,4-bis(2-ethylhexyl)-4H-silolo[3,2-b:4,5-b?]dithiophene-2,6-diyl) bis(6-fluoro-4-(5?-hexyl-[2,2?-bithiophen]-5yl)benzo[c] [1,2,5] thiadiazole)] p-DTS(FBTTh{sub 2}){sub 2}: Cadmium Selenide (CdSe) (70:30, 60:40, 50:50, and 40:60) in the device configuration: Indium Tin Oxide /poly(3,4-ethylenedioxythiophene):poly(styrenesulfonate) (PEDOT:PSS)/p-DTS(FBTTh{sub 2}){sub 2}: CdSe/Ca/Al. The optimized ratio of p-DTS(FBTTh{sub 2}){sub 2}:CdSe::60:40 leads to a short circuit current density (J{sub sc})?=?5.45?mA/cm{sup 2}, open circuit voltage (V{sub oc})?=?0.727?V, and fill factor (FF)?=?51%, and a power conversion efficiency?=?2.02% at 100 mW/cm{sup 2} under AM1.5G illumination. The J{sub sc} and FF are sensitive to the ratio of p-DTS(FBTTh{sub 2}){sub 2}:CdSe, which is a crucial factor for the device performance.

Gupta, Vinay, E-mail: drvinaygupta@netscape.net [Physics of Energy Harvesting Division, Organic and Hybrid Solar Cell Group, CSIR-National Physical Laboratory, New Delhi-110012 (India) [Physics of Energy Harvesting Division, Organic and Hybrid Solar Cell Group, CSIR-National Physical Laboratory, New Delhi-110012 (India); Department of Physics, University of California, Santa Barbara, California 93106 (United States); Upreti, Tanvi; Chand, Suresh [Physics of Energy Harvesting Division, Organic and Hybrid Solar Cell Group, CSIR-National Physical Laboratory, New Delhi-110012 (India)] [Physics of Energy Harvesting Division, Organic and Hybrid Solar Cell Group, CSIR-National Physical Laboratory, New Delhi-110012 (India)

2013-12-16T23:59:59.000Z

116

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

117

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

118

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

119

Solution Processed Tungsten Oxide Interfacial Layer for Efficient Hole-Injection in Quantum Dot Light-Emitting Diodes  

E-Print Network [OSTI]

2/2014 Solution Processed Tungsten Oxide Interfacial Layer for Efficient Hole-Injection in Quantum Layer for Efficient Hole-Injection in Quantum Dot Light- Emitting Diodes Xuyong Yang, Evren Mutlugun-based devices, the organic interfacial buffer layers have inferior thermal stability. Efforts to replace PEDOT

Demir, Hilmi Volkan

120

Vacuum-free lamination of low work function cathode for efficient solution-processed organic light-emitting diodes  

E-Print Network [OSTI]

-coated organic light-emitting diode is transferred from a soft polydimethylsiloxane (PDMS) mold by lamination, or blade coating [1,2] for organic light emitting diode (OLED) as well as solar cell. The top electrodeVacuum-free lamination of low work function cathode for efficient solution-processed organic light-emitting

Meng, Hsin-Fei

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

122

Guiding Cooperative Stakeholders to Compromise Solutions Using an Interactive Tradespace Exploration Process  

E-Print Network [OSTI]

Engineering projects frequently involve the cooperation of multiple stakeholders with varying objectives and preferences for the resulting system. Finding a mutually agreeable solution is of paramount importance in order ...

Fitzgerald, Matthew E.

123

Solution-Processable Transparent Conductive Hole Injection Electrode for OLED SSL  

SciTech Connect (OSTI)

An interconnected network of silver nanowires has been used as transparent anode in OLED devices. This layer was deposited by spin-coating and slot-die coating from an aqueous nanowire suspension. The sheet resistance of the film was 10ohms/sq with a transmission (including the glass substrate) of higher than 85%. The first phase of the project focused on the implementation of this nanowire layer with a hole-injection-layer (HIL) which has been developed at Plextronics and has been shown to provide good stability and efficiency in conventional OLED devices. We modified the HIL solution such that it coated reasonably well with suitable surface morphology so that actual devices can be manufactured. During the second phase we investigated the hole-injection and stability of hole-onlydevices. We determined that the use of the nanowire network as anode does not introduce an additional degradation mechanism since the observed device characteristics did not differ from those made with ITO anode. We then proceeded to make actual OLED devices with this nanowire / HIL stack and achieved device characteristics similar state-of-the-art OLED devices with a single junction. In order to gain traction with potential OLED manufacturers, we decided to contract Novaled to prepare large-area demonstrators for us. For these devices, we used an allevaporated stack, i.e. we did use Novaled??s HIL material instead of Plextronics??. We successfully fabricated demonstrators with an area of 25cm2 with a double or triple junction stack. Minor stack optimizations were necessary to achieve efficacies and lifetime equivalent with ITO devices made with the same devices stack. Due to the reduced microcavity effect, the color of the emitted light is significantly more stable with respect to the viewing angle compared to ITO devices. This fact in conjunction with the promise of lower production cost due to the elimination of the ITO sputtering process and the direct patterning of the anode layer are the obvious advantages of this technology. The project has shown that this nanowire technology is a viable option to achieve OLED devices with good lifetime and efficiency and we are currently working with manufacturers to utilize this technology in a production setting.

None

2012-07-15T23:59:59.000Z

124

Luminescence and electrical properties of solution-processed ZnO thin films by adding fluorides and annealing atmosphere  

SciTech Connect (OSTI)

Highlights: {yields} Systematic study of the fluorides doped solution-processed ZnO thin films via the luminescence and electrical behaviors. {yields} Defect-related visible emission bands are affected by annealing ambient and fluoride addition. {yields} Adding lithium fluoride followed by annealing in oxygen ambient leads to a controlled defect density with proper TFT performance. -- Abstract: To develop an efficient channel layer for thin film transistors (TFTs), understanding the defect-related luminescence and electrical property is crucial for solution-processed ZnO thin films. Film growth with the fluorides addition, especially using LiF, followed by the oxygen ambient post-annealing leads to decreased defect-related emission as well as enhanced switching property. The saturation mobility and current on/off ratio are 0.31 cm{sup 2} V{sup -1} s{sup -1} and 1.04 x 10{sup 3}. Consequently, we can visualize an optimized process condition and characterization method for solution-processed TFT based on the fluorine-doped ZnO film channel layer by considering the overall emission behavior.

Choi, Sungho, E-mail: shochoi@krict.re.kr [Advanced Materials Division, Korea Research Institute of Chemical Technology, Yuseong, Daejeon 305-600 (Korea, Republic of)] [Advanced Materials Division, Korea Research Institute of Chemical Technology, Yuseong, Daejeon 305-600 (Korea, Republic of); Park, Byung-Yoon [Chemical and Electronic Materials Division, LG Electronics, Hyangjeong-dong, Heungdeok-gu, Cheongju (Korea, Republic of)] [Chemical and Electronic Materials Division, LG Electronics, Hyangjeong-dong, Heungdeok-gu, Cheongju (Korea, Republic of); Jung, Ha-Kyun [Advanced Materials Division, Korea Research Institute of Chemical Technology, Yuseong, Daejeon 305-600 (Korea, Republic of)] [Advanced Materials Division, Korea Research Institute of Chemical Technology, Yuseong, Daejeon 305-600 (Korea, Republic of)

2011-06-15T23:59:59.000Z

125

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

126

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

127

Extraction and recovery of plutonium and americium from nitric acid waste solutions by the TRUEX process - continuing development studies  

SciTech Connect (OSTI)

This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX process solvent in these experiments was a solution of TBP and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) dissolved in carbon tetrachloride. A flowsheet was designed on the basis of measured batch distribution ratios to reduce the TRU content of the solidified raffinate to less than or equal to 10 nCi/g and was tested in a countercurrent experiment performed in a 14-stage Argonne-model centrifugal contractor. The process solvent was recycled without cleanup. An unexpectedly high evaporative loss of CCl/sub 4/ resulted in concentration of the active extractant, CMPO, to nearly 0.30M in the solvent. Results are consistent with this higher CMPO concentration. The raffinate contained only 2 nCi/g of TRU, but the higher CMPO concentration resulted in reduced effectiveness in the stripping of americium from the solvent. Conditions can be easily adjusted to give high yields and good separation of americium and plutonium. Experimental studies of the hydrolytic and gamma-radiolytic degradation of the TRUEX-CCl/sub 4/ showed that solvent degradation would be (1) minimal for a year of processing this typical feed, which contained no fission products, and (2) could be explained almost entirely by hydrolytic and radiolytic damage to TBP. Even for gross amounts of solvent damage, scrubbing with aqueous sodium carbonate solution restored the original americium extraction and stripping capability of the solvent. 43 refs., 5 figs., 36 tabs.

Leonard, R.A.; Vandegrift, G.F.; Kalina, D.G.; Fischer, D.F.; Bane, R.W.; Burris, L.; Horwitz, E.P.; Chiarisia, R.; Diamond, H.

1985-09-01T23:59:59.000Z

128

MODELING AN ION EXCHANGE PROCESS FOR CESIUM REMOVAL FROM ALKALINE RADIOACTIVE WASTE SOLUTIONS  

SciTech Connect (OSTI)

The performance of spherical Resorcinol-Formaldehyde ion-exchange resin for the removal of cesium from alkaline radioactive waste solutions has been investigated through computer modeling. Cesium adsorption isotherms were obtained by fitting experimental data using a thermodynamic framework. Results show that ion-exchange is an efficient method for cesium removal from highly alkaline radioactive waste solutions. On average, two 1300 liter columns operating in series are able to treat 690,000 liters of waste with an initial cesium concentration of 0.09 mM in 11 days achieving a decontamination factor of over 50,000. The study also tested the sensitivity of ion-exchange column performance to variations in flow rate, temperature and column dimensions. Modeling results can be used to optimize design of the ion exchange system.

Smith, F; Luther Hamm, L; Sebastian Aleman, S; Johnston Michael, J

2008-08-26T23:59:59.000Z

129

Precipitation of jarosite-type double salts from spent acid solutions from a chemical coal cleaning process  

SciTech Connect (OSTI)

The precipitation of jarosite compounds to remove Na, K, Fe, and SO{sub 4}{sup 2{minus}} impurities from spent acid solutions from a chemical coal cleaning process was studied. Simple heating of model solutions containing Fe{sub 2}(SO{sub 4}){sub 3}, Na{sub 2}SO{sub 4}, and K{sub 2}SO{sub 4} caused jarosite (KFe{sub 3}(SO{sub 4}){sub 2}(OH){sub 6}) to form preferentially to natrojarosite (NaFe{sub 3}(SO{sub 4}){sub 2}(OH){sub 6}). Virtually all of the K, about 90% of the Fe, and about 30% of the SO{sub 4}{sup 2{minus}} could be precipitated from those solutions at 95{degree}C, while little or no Na was removed. However, simple heating of model solutions containing only Fe{sub 2}(SO{sub 4}){sub 3} and Na{sub 2}SO{sub 4} up to 95{degree}C for {le}12 hours produced low yields of jarosite compounds, and the Fe concentration in the solution had to be increased to avoid the formation of undesirable Fe compounds. Precipitate yields could be increased dramatically in model solutions of Na{sub 2}SO{sub 4}/Fe{sub 2}(SO{sub 4}){sub 3} containing excess Fe by using either CaCO{sub 3}, Ca(OH){sub 2}, or ZnO to neutralize H{sub 2}SO{sub 4} released during hydrolysis of the Fe{sub 2}(SO{sub 4}){sub 3} and during the precipitation reactions. Results obtained from the studies with model solutions were applied to spent acids produced during laboratory countercurrent washing of coal which had been leached with a molten NaOH/KOH mixture. Results indicated that jarosite compounds can be precipitated effectively from spent acid solutions by heating for 6 hours at 80{degree}C while maintaining a pH of about 1.5 using CaCO{sub 3}.

Norton, G.

1990-09-21T23:59:59.000Z

130

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

131

Process for preparing chemically modified micas for removal of cesium salts from aqueous solution  

DOE Patents [OSTI]

A chemically modified mica composite formed by heating a trioctahedral mica in an aqueous solution of sodium chloride having a concentration of at least 1 mole/liter at a temperature greater than 180 degrees Centigrade for at least 20 hours, thereby replacing exchangeable ions in the mica with sodium. Formation is accomplished at temperatures and pressures which are easily accessed by industrial equipment. The reagent employed is inexpensive and non-hazardous, and generates a precipitate which is readily separated from the modified mica.

Yates, Stephen Frederic (1539 S. Kennicott Dr., Arlington Heights, IL 60005); DeFilippi, Irene (208 E. Edgewood La., Palatine, IL 60067); Gaita, Romulus (6646 Davis Rd., Morton Grove, IL 60053); Clearfield, Abraham (Department of Chemistry, Texas A& M University, College Station, TX 77843); Bortun, Lyudmila (Department of Chemistry, Texas A& M University, College Station, TX 77843); Bortun, Anatoly (Department of Chemistry, Texas A& M University, College Station, TX 77843)

2000-09-05T23:59:59.000Z

132

Processing results of 1800 gallons of mercury and radioactively contaminated mixed waste rinse solution  

SciTech Connect (OSTI)

Mercury-contaminated rinse solution was successfully treated at the Idaho National Engineering Laboratory. This waste was generated during the decontamination of the Heat Transfer Reactor Experiment 3 reactor shield tank. Approximately 6.8 m{sup 3} (1,800 pi) of waste was generated and placed into 33 drums. Each drum contained precipitated sludge material ranging from 2--5 cm in depth, with the average depth of about 6 cm. The pH of each drum varied from 3--11. The bulk liquid waste had a mercury level of 7.0 mg/l, which exceeded the Resource Conservation and Recovery Act limit of 0.2 mg/l. The average liquid bulk radioactivity was about 2.1 pCi/mL while the average sludge contamination was about 13,800 pCi/g. Treatment of the waste required separation of the liquid from the sludge, filtration, pH adjustment, and ion exchange. The resulting solution after treatment had mercury levels at 0.0186 mg/l and radioactivity of 0.282 pCi/ml.

Thiesen, B.P.

1993-05-01T23:59:59.000Z

133

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

134

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

135

Modeling and the Adaptive Solution of CVD Fiber-Coating Processes  

E-Print Network [OSTI]

guidance for improving the process. 1 Introduction Ceramic composites are designed for use in high permeate the matrix and react with the bers to weaken the composite. Coating the bers can protect them from, New York 12180, USA Abstract We develop a mathematical model for the coating of ceramic bers

Adjerid, Slimane

136

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

137

The Role of Advanced Process Control in Your Energy Management Solution  

E-Print Network [OSTI]

as cost savings are proven ? Custom application development and protocol emulation services are available Presentation title Service, Customization, Innovation Typical System Architecture DCS/PLC/OPC L1 Interface DCS Manual Entry ASCII files... Other computersPLC Process Lan RDBMS LIMS Other OPC Server Direct Interface SCADA Custom Application Systems ERP WEB Server RBV Corporate WAN EAMS Server & Historian Plant LAN LAB Presentation title Service, Customization...

Johnson, K.; Van Wyk, L.

2010-01-01T23:59:59.000Z

138

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

139

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

140

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

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

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

142

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

143

Coupled modeling of groundwater flow solute transport, chemical reactions and microbial processes in the 'SP' island  

SciTech Connect (OSTI)

The Redox Zone Experiment was carried out at the Aespoe HRL in order to study the redox behavior and the hydrochemistry of an isolated vertical fracture zone disturbed by the excavation of an access tunnel. Overall results and interpretation of the Redox Zone Project were reported by /Banwart et al, 1995/. Later, /Banwart et al, 1999/ presented a summary of the hydrochemistry of the Redox Zone Experiment. Coupled groundwater flow and reactive transport models of this experiment were carried out by /Molinero, 2000/ who proposed a revised conceptual model for the hydrogeology of the Redox Zone Experiment which could explain simultaneously measured drawdown and salinity data. The numerical model was found useful to understand the natural system. Several conclusions were drawn about the redox conditions of recharge waters, cation exchange capacity of the fracture zone and the role of mineral phases such as pyrite, calcite, hematite and goethite. This model could reproduce the measured trends of dissolved species, except for bicarbonate and sulfate which are affected by microbially-mediated processes. In order to explore the role of microbial processes, a coupled numerical model has been constructed which accounts for water flow, reactive transport and microbial processes. The results of this model is presented in this report. This model accounts for groundwater flow and reactive transport in a manner similar to that of /Molinero, 2000/ and extends the preliminary microbial model of /Zhang, 2001/ by accounting for microbially-driven organic matter fermentation and organic matter oxidation. This updated microbial model considers simultaneously the fermentation of particulate organic matter by yeast and the oxidation of dissolved organic matter, a product of fermentation. Dissolved organic matter is produced by yeast and serves also as a substrate for iron-reducing bacteria. Model results reproduce the observed increase in bicarbonate and sulfate concentration, thus adding additional evidence for the possibility of organic matter oxidation as the main source of bicarbonate. Model results indicate that pH and Eh are relatively stable. The dissolution-precipitation trends of hematite, pyrite and calcite also coincide with those indicated by the conceptual model. A thorough sensitivity analysis has been performed for the most relevant microbial parameters as well as for initial and boundary POC and DOC concentrations. The results of such analysis indicate that computed concentrations of bicarbonate, sulfate and DOC are sensitive to most of the microbial parameters, including specific growth rates, half-saturation constants, proportionality coefficients and yield coefficients. Model results, however, are less sensitive to the yield coefficient of DOC to iron-reducer bacteria. The sensitivity analysis indicates that changes in fermentation microbial parameters affect the growth of the iron-reducer, thus confirming the interconnection of both microbial processes. Computed concentrations of bicarbonate and sulfate are found to be sensitive to changes in the initial concentration of POC and the boundary concentration of DOC, but they lack sensitivity to the initial concentration of DOC and the boundary concentration of POC. The explanation for such result is related to the fact that POC has a low mobility due to its large molecular weight. DOC, however, can migrate downwards. Although a coupled hydro-bio-geochemical 1-D model can reproduce the observed ''unexpected'' increase of concentrations of bicarbonate and sulfate at a depth of 70 m, further modeling work is required in order to obtain a similar conclusion under the more realistic two dimensional conditions of the fracture zone.

Samper, Javier; Molinero, Jorg; Changbing, Yang; Zhang, Guoxiang

2003-12-01T23:59:59.000Z

144

Regeneration of an aqueous solution from an acid gas absorption process by matrix stripping  

DOE Patents [OSTI]

Carbon dioxide and other acid gases are removed from gaseous streams using aqueous absorption and stripping processes. By replacing the conventional stripper used to regenerate the aqueous solvent and capture the acid gas with a matrix stripping configuration, less energy is consumed. The matrix stripping configuration uses two or more reboiled strippers at different pressures. The rich feed from the absorption equipment is split among the strippers, and partially regenerated solvent from the highest pressure stripper flows to the middle of sequentially lower pressure strippers in a "matrix" pattern. By selecting certain parameters of the matrix stripping configuration such that the total energy required by the strippers to achieve a desired percentage of acid gas removal from the gaseous stream is minimized, further energy savings can be realized.

Rochelle, Gary T. (Austin, TX); Oyenekan, Babatunde A. (Katy, TX)

2011-03-08T23:59:59.000Z

145

INDEX - a solution to the high cost of processing transient workers  

SciTech Connect (OSTI)

In 1985 twelve midwestern utilities formed the Nuclear Employee Data System for the US Nuclear Regulatory Commission's (NRC's) Region III (NEDS III) group. These utilities are Cleveland Electric Illuminating Company, Commonwealth Edison Company, Consumers Power Company, Detroit Edison Company, Illinois Power Company, Indiana and Michigan Electric Company, Iowa Electric Light and Power Company, Northern States Power Company, Toledo Edison Company, Union Electric Company, and Wisconsin Public Service Corporation. Early in 1986, Kansas Gas and Electric of NRC's Region IV joined the group and a cost-benefit study of a nuclear employee data system was initiated. The purpose of this system is to reduce the cost of processing workers requiring unescorted access to nuclear power plants. The involved utilities continued this project as the Integrated Nuclear Data Exchange (INDEX). In 1987 the following additional utilities joined INDEX: Houston Lighting and Power, Pacific Gas and Electric, Texas Utilities Electric Company, Arkansas Power and Light, Louisiana Power and Light, Systems Energy Resources Inc., and Southern California Edison. This paper summarizes the results of the study and discusses the current status of the program.

Stroupe, E.P.

1987-01-01T23:59:59.000Z

146

Roll-to-Roll Solution-Processible Small-Molecule OLEDs  

SciTech Connect (OSTI)

The objective of this program is to develop key knowledge and make critical connections between technologies needed to enable low-cost manufacturing of OLED lighting products. In particular, the program was intended to demonstrate the feasibility of making high performance Small-Molecule OLEDs (SM-OLED) using a roll-to-roll (R2R) wet-coating technique by addressing the following technical risks (1) Whether the wet-coating technique can provide high performance OLEDs, (2) Whether SM-OLED can be made in a R2R manner, (3) What are the requirements for coating equipment, and (4) Whether R2R OLEDs can have the same performance as the lab controls. The program has been managed and executed according to the Program Management Plan (PMP) that was first developed at the beginning of the program and further revised accordingly as the program progressed. Significant progress and risk reductions have been accomplished by the end of the program. Specific achievements include: (1) Demonstrated that wet-coating can provide OLEDs with high LPW and long lifetime; (2) Demonstrated R2R OLEDs can be as efficient as batch controls (Figure 1) (3) Developed & validated basic designs for key equipment necessary for R2R SM-OLEDs; (4) Developed know-hows & specifications on materials & ink formulations critical to wetcoating; (5) Developed key R2R processes for each OLED layer (6) Identified key materials and components such as flexible barrier substrates necessary for R2R OLEDs.

Liu, Jie Jerry

2012-07-31T23:59:59.000Z

147

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

148

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

149

Oxidation-resistant, solution-processed plasmonic Ni nanochain-SiO{sub x} (x?  

SciTech Connect (OSTI)

Metal oxidation at high temperatures has long been a challenge in cermet solar thermal absorbers, which impedes the development of atmospherically stable, high-temperature, high-performance concentrated solar power (CSP) systems. In this work, we demonstrate solution-processed Ni nanochain-SiO{sub x} (x?processed by low-cost solution-chemical methods for future generations of CSP systems.

Yu, Xiaobai; Wang, Xiaoxin; Liu, Jifeng, E-mail: Jifeng.Liu@dartmouth.edu [Thayer School of Engineering, Dartmouth College, 14 Engineering Drive, Hanover, New Hampshire 03755 (United States); Zhang, Qinglin [Department of Chemical and Materials Engineering, University of Kentucky, 177 F. Paul Anderson Tower, Lexington, Kentucky 40506 (United States); Li, Juchuan [Materials Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (United States)

2014-08-21T23:59:59.000Z

150

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

151

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

152

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

153

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

154

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

155

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

156

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

157

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

158

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

159

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

160

Modulation of physical and photocatalytic properties of (Cr, N) codoped TiO{sub 2} nanorods using soft solution processing  

SciTech Connect (OSTI)

Facile polymerized complex reactions together with a hydrothermal reaction were implemented to make single crystalline TiO{sub 2} nanorods for the first time. Chromium (Cr) and nitrogen (N{sub 2}) co-doping was performed to tailor the physical properties. Transmission electron microscopy and x-ray diffraction study illustrated that highly reactive facets of (101), (111), and (001) dominated rutile TiO{sub 2} nanorods. A growth model, based on formation of complex species, was proposed to elucidate effectiveness of the soft solution processing in making TiO{sub 2} nanorods. X-ray photoelectron spectroscopy analysis and consideration of fundamentals of charge neutrality showed N{sub 2} doping could inhibit formation of Cr{sup 6+} and oxygen vacancies (V{sub O}{sup 2+}). An investigation of the photocatalytic properties exhibited high efficiency of photodegradation of methylene blue in 15?min under pH?=?10, using a nanocomposite of (7% Cr, 0.0021% N) codoped and 3% Cr doped TiO{sub 2} nanorods.

Lu, Wen-Chung [Institute of Nanotechnology and Microsystems Engineering, National Cheng Kung University, No. 1, University Road, Tainan City 70101, Taiwan (China); Department of Materials Science and Engineering, National Cheng Kung University, No. 1, University Road, Tainan City 70101, Taiwan (China); Nguyen, Hoang-Diem; Wu, Chun-Yi [Department of Materials Science and Engineering, National Cheng Kung University, No. 1, University Road, Tainan City 70101, Taiwan (China); Chang, Kao-Shuo, E-mail: kschang@mail.ncku.edu.tw; Yoshimura, Masahiro [Department of Materials Science and Engineering, National Cheng Kung University, No. 1, University Road, Tainan City 70101, Taiwan (China); Promotion Center for Global Materials Research (PCGMR), National Cheng Kung University, No. 1, University Road, Tainan City 70101, Taiwan (China)

2014-04-14T23:59:59.000Z

Note: This page contains sample records for the topic "iterative solution process" from the National Library of EnergyBeta (NLEBeta).
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161

Photoinduced electron transfer processes in homogeneous and microheterogeneous solutions. Progress report, April 16, 1992--December 1, 1992  

SciTech Connect (OSTI)

The studies have focused on rapid, efficient bond-fragmentation reactions initiated through photoinduced electron transfer. Electron transfer induced fragmentation of a number of donors have been examined, especially 1,2 diamines and related compounds. Two of the amines fragment with rate constants of 3 {times} 10{sup 8} to 2 {times} 10{sup 9} M{sup {minus}1}sec{sup {minus}1}. A series of amino-substituted pinacols and related compounds have also been examined; they undergo similar but slower fragmentation processes when converted to their cation radicals by photoinduced electron transfer. The studies with linked and polymeric electron donor- electron acceptor coupled molecules have also progressed. Several polymers containing diamine repeat units and anthraquinone or nitroaromatic acceptors have also been prepared that can be photoactivated by visible irradiation; they fragment efficiently in solution and photodegrade even in the solid state. The studies of singlet oxygen initiated fragmentation reactions of diamines, amino alcohols, and aminoketones have nearly been completed. Attention have been turned to fragmentable electron acceptors such as p- cyanobenzyl bromide; irradiation of electron donors such as methyl- or methoxy-naphthalenes can initiate efficient fragmentation of the electron deficient bromide.

Whitten, D.G.

1992-12-01T23:59:59.000Z

162

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

163

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

164

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

165

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

166

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

167

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

168

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

169

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

170

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

171

Process for production of solution-derived (Pb,La)(Nb,Sn,Zr,Ti)O{sub 3} thin films and powders  

DOE Patents [OSTI]

A simple and rapid process for synthesizing (Pb,La)(Nb,Sn,Zr,Ti)O{sub 3} precursor solutions and subsequent ferroelectric thin films and powders of the perovskite phase of these materials has been developed. This process offers advantages over standard methods, including: rapid solution synthesis (<10 minutes), use of commercially available materials, film production under ambient conditions, ease of lanthanum dissolution at high concentrations, and no heating requirements during solution synthesis. For lanthanum-doped ferroelectric materials, the lanthanum source can be added with total synthesis time less than 10 minutes. Films and powders are crystallized at approximately 650 C and exhibit ferroelectric properties comparable to films and powders produced by other techniques which require higher crystallization temperatures. 2 figs.

Boyle, T.J.

1999-01-12T23:59:59.000Z

172

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

173

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...

174

Infrared and visible laser double resonance studies of vibrational energy transfer processes in polyatomic molecules. [Chromyl chloride solutions  

SciTech Connect (OSTI)

A study of the spectroscopy of chromyl chloride (CrO{sub 2}Cl{sub 2} ) in dilute solutions has been initiated. A discussion is given of its spectra and emission bands. 17 refs, 5 figs, 1 tab. (DLC)

Bhatnagar, R. (Texas Southern Univ., Houston, TX (United States). Dept. of Chemistry)

1991-01-01T23:59:59.000Z

175

Novel Regenerated Solvent Extraction Processes for the Recovery of Carboxylic Acids or Ammonia from Aqueous Solutions Part I. Regeneration of Amine-Carboxylic Acid Extracts  

SciTech Connect (OSTI)

Two novel regenerated solvent extraction processes are examined. The first process has the potential to reduce the energy costs inherent in the recovery of low-volatility carboxylic acids from dilute aqueous solutions. The second process has the potential for reducing the energy costs required for separate recovery of ammonia and acid gases (e.g. CO{sub 2} and H{sub 2}S) from industrial sour waters. The recovery of carboxylic acids from dilute aqueous solution can be achieved by extraction with tertiary amines. An approach for regeneration and product recovery from such extracts is to back-extract the carboxylic acid with a water-soluble, volatile tertiary amine, such as trimethylamine. The resulting trimethylammonium carboxylate solution can be concentrated and thermally decomposed, yielding the product acid and the volatile amine for recycle. Experimental work was performed with lactic acid, succinic acid, and fumaric acid. Equilibrium data show near-stoichiometric recovery of the carboxylic acids from an organic solution of Alamine 336 into aqueous solutions of trimethylamine. For fumaric and succinic acids, partial evaporation of the aqueous back extract decomposes the carboxylate and yields the acid product in crystalline form. The decomposition of aqueous solutions of trimethylammonium lactates was not carried out to completion, due to the high water solubility of lactic acid and the tendency of the acid to self-associate. The separate recovery of ammonia and acid gases from sour waters can be achieved by combining steam-stripping of the acid gases with simultaneous removal of ammonia by extraction with a liquid cation exchanger. The use of di-2,4,4-trimethylpentyl phosphinic acid as the liquid cation exchanger is explored in this work. Batch extraction experiments were carried out to measure the equilibrium distribution ratio of ammonia between an aqueous buffer solution and an organic solution of the phosphinic acid (0.2N) in Norpar 12. The concentration-based distribution ratios increase from 0.11 to 0.46 as the aqueous phase pH increases from 7.18 to 8.15. Regeneration of the organic extractant solution was carried out by stripping at elevated temperatures to remove the ammonia, with 99% recovery of the ammonia being obtained at 125 C.

Poole, L.J.; King, C.J.

1990-03-01T23:59:59.000Z

176

Novel Regenerated Solvent Extraction Processes for the Recovery of Carboxylic Acids or Ammonia from Aqueous Solutions Part II. Recovery of Ammonia from Sour Waters  

SciTech Connect (OSTI)

Two novel regenerated solvent extraction processes are examined. The first process has the potential to reduce the energy costs inherent in the recovery of low-volatility carboxylic acids from dilute aqueous solutions. The second process has the potential for reducing the energy costs required for separate recovery of ammonia and acid gases (e.g. CO{sub 2} and H{sub 2}S) from industrial sour waters. The recovery of carboxylic acids from dilute aqueous solution can be achieved by extraction with tertiary amines. An approach for regeneration and product recovery from such extracts is to back-extract the carboxylic acid with a water-soluble, volatile tertiary amine, such as trimethylamine. The resulting trimethylammonium carboxylate solution can be concentrated and thermally decomposed, yielding the product acid and the volatile amine for recycle. Experimental work was performed with lactic acid, SUCCiOlC acid, and fumaric acid. Equilibrium data show near-stoichiometric recovery of the carboxylic acids from an organic solution of Alamine 336 into aqueous solutions of trimethylamine. For fumaric and succinic acids, partial evaporation of the aqueous back extract decomposes the carboxylate and yields the acid product in crystalline form. The decomposition of aqueous solutions of trimethylammonium lactates was not carried out to completion, due to the high water solubility of lactic acid and the tendency of the acid to self-associate. The separate recovery of ammonia and acid gases from sour waters can be achieved by combining steam-stripping of the acid gases with simultaneous removal of ammonia by extraction with a liquid cation exchanger. The use of di-2,4,4-trimethylpentyl phosphinic acid as the liquid cation exchanger is explored in this work. Batch extraction experiments were carried out to measure the equilibrium distribution ratio of ammonia between an aqueous buffer solution and an organic solution of the phosphinic acid (0.2N) in Norpar 12. The concentration-based distribution ratios increase from 0.11 to 0.46 as the aqueous phase pH increases from 7.18 to 8.15. Regeneration of the organic extractant solution was carried out by stripping at elevated temperatures to remove the ammonia, with 99% recovery of the ammonia being obtained at 125 C.

Poole, L.J.; King, C.J.

1990-03-01T23:59:59.000Z

177

Mission-Critical Platform for Online Transaction Processing (OLTP) SQL Server 2008 Mission-Critical Platform for OLTP Data Solutions  

E-Print Network [OSTI]

Mission-Critical Platform for Online Transaction Processing (OLTP) SQL Server 2008 Mission Data Collector to troubleshoot and tune SQL Server 2008 instances. Help ensure compliance 2008 high- performance query processing engine for industry leading performance and scalability. Define

Bernstein, Phil

178

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.

179

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

180

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

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

An evaluation of membrane materials for the treatment of highly concentrated suspended salt solutions in reverse osmosis and nanofiltration processes for desalination  

E-Print Network [OSTI]

of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2006 Major Subject: Civil Engineering AN EVALUATION OF MEMBRANE MATERIALS FOR THE TREATMENT OF HIGHLY... CONCENTRATED SUSPENDED SALT SOLUTIONS IN REVERSE OSMOSIS AND NANOFILTRATION PROCESSES FOR DESALINATION A Thesis by TRENTON WHITING HUGHES Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment...

Hughes, Trenton Whiting

2009-05-15T23:59:59.000Z

182

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

183

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

184

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

185

Advances in solar photovoltaics are urgently needed to increase the performance and reduce the cost of harvesting solar power. Solution-processed photovoltaics are cost-effective to manufacture and offer the potential for physical flexibility.  

E-Print Network [OSTI]

Advances in solar photovoltaics are urgently needed to increase the performance and reduce the cost of harvesting solar power. Solution-processed photovoltaics are cost-effective to manufacture and offer.Controllingthecollectionandminimizingthetrappingofchargecarriersattheseboundariesiscrucialtoefficiency. Materials interface engineering for solution-processed photovoltaics Michael Graetzel1 , René A. J. Janssen2

186

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions  

SciTech Connect (OSTI)

The scope of this program is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 {times} 3.0 {times} 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by RBOSC to carry out this study. Research objectives were designed to evaluate hydrologic, geotechnical, and chemical properties and conditions which would affect the design and performance of large-scale embankments. The objectives of this research are: assess the unsaturated movement and redistribution of water and the development of potential saturated zones and drainage in disposed processed oil shale under natural and simulated climatic conditions; assess the unsaturated movement of solubles and major chemical constituents in disposed processed oil shale under natural and simulated climatic conditions; assess the physical and constitutive properties of the processed oil shale and determine potential changes in these properties caused by disposal and weathering by natural and simulated climatic conditions; assess the use of previously developed computer model(s) to describe the infiltration, unsaturated movement, redistribution, and drainage of water in disposed processed oil shale; evaluate the stability of field scale processed oil shale solid waste embankments using computer models.

Reeves, T.L.; Turner, J.P.; Hasfurther, V.R.; Skinner, Q.D.

1992-06-01T23:59:59.000Z

187

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions  

SciTech Connect (OSTI)

The scope of this program is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 [times] 3.0 [times] 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by RBOSC to carry out this study. Research objectives were designed to evaluate hydrologic, geotechnical, and chemical properties and conditions which would affect the design and performance of large-scale embankments. The objectives of this research are: assess the unsaturated movement and redistribution of water and the development of potential saturated zones and drainage in disposed processed oil shale under natural and simulated climatic conditions; assess the unsaturated movement of solubles and major chemical constituents in disposed processed oil shale under natural and simulated climatic conditions; assess the physical and constitutive properties of the processed oil shale and determine potential changes in these properties caused by disposal and weathering by natural and simulated climatic conditions; assess the use of previously developed computer model(s) to describe the infiltration, unsaturated movement, redistribution, and drainage of water in disposed processed oil shale; evaluate the stability of field scale processed oil shale solid waste embankments using computer models.

Reeves, T.L.; Turner, J.P.; Hasfurther, V.R.; Skinner, Q.D.

1992-06-01T23:59:59.000Z

188

Transverse transport of solutes between co-flowing pressure-driven streams for microfluidic studies of diffusion/reaction processes  

E-Print Network [OSTI]

We consider a situation commonly encountered in microfluidics: two streams of miscible liquids are brought at a junction to flow side by side within a microchannel, allowing solutes to diffuse from one stream to the other and possibly react. We focus on two model problems: (i) the transverse transport of a single solute from a stream into the adjacent one, (ii) the transport of the product of a diffusion-controlled chemical reaction between solutes originating from the two streams. Our description is made general through a non-dimensionalized formulation that incorporates both the parabolic Poiseuille velocity profile along the channel and thermal diffusion in the transverse direction. Numerical analysis over a wide range of the streamwise coordinate $x$ reveal different regimes. Close to the top and the bottom walls of the microchannel, the extent of the diffusive zone follows three distinct power law regimes as $x$ is increased, characterized respectively by the exponents 1/2, 1/3 and 1/2. Simple analytical arguments are proposed to account for these results.

Jean-Baptiste Salmon; Armand Ajdari

2007-02-01T23:59:59.000Z

189

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

190

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

191

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

192

Reduced cycle time and work in process in a medical device factory : the problem and a proposed solution  

E-Print Network [OSTI]

Many manufacturing firms have improved their operations by implementing a work-in-process (WIP) limiting control strategy. This project explores the application of this concept to limit WIP and reduce cycle time for the ...

Qian, Yi, M. Eng. Massachusetts Institute of Technology

2007-01-01T23:59:59.000Z

193

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

194

Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering  

DOE Patents [OSTI]

In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved.

Vijayan, Sivaraman (Deep River, CA); Wong, Chi F. (Pembroke, CA); Buckley, Leo P. (Deep River, CA)

1994-01-01T23:59:59.000Z

195

Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering  

DOE Patents [OSTI]

In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved. 1 fig.

Vijayan, S.; Wong, C.F.; Buckley, L.P.

1994-11-22T23:59:59.000Z

196

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions  

SciTech Connect (OSTI)

The scope of the research program and the continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 [times] 3.0 [times] 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. (RBOSC) through a separate cooperative agreement with the University of Wyoming (UW) to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin of Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which was filled in the lysimeter cells.

Turner, J.P.; Hasfurther, V.

1992-05-04T23:59:59.000Z

197

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

198

Calcium niobate nanosheets as a novel electron transport material for solution-processed multi-junction polymer solar cells  

E-Print Network [OSTI]

from a common solvent. Nanoscale interpenetrating networks are formed as the donor and acceptor phase-junction polymer solar cells Lilian Chang,a Michael A. Holmes,b Mollie Waller,b Frank E. Osterlohb and Adam J-processed tandem polymer solar cells are demonstrated using stacked perovskite, (TBA,H) Ca2Nb3O10 (CNO

Osterloh, Frank

199

Solution Processed MoS2-PVA Composite for Sub-Bandgap Mode-Locking of a Wideband Tunable Ultrafast Er:Fiber Laser  

E-Print Network [OSTI]

with stable, picosecond pulses, tunable from 1535 nm to 1565 nm 2 Solution Processed MoS2-PVA Composite for Sub-Bandgap Mode-Locking of a Wideband Tunable Ultrafast Er:Fiber Laser Meng Zhang1, Richard C. T. Howe2, Robert I. Woodward1... ! to! relaxation! of! thermalized! electron! and!phonon! distribution! [3].! This! combination! of!properties!makes!MoS2!a!suitable!saturable!absorber!(SA)! for! ultrafast! mode+locked! pulsed! lasers,! with!the! potential! for! pulse! generation! at...

Zhang, Meng; Howe, Richard C. T.; Woodward, Robert I.; Kelleher, Edmund J. R.; Torrisi, Felice; Hu, Guohua; Popov, Sergei V.; Taylor, J. Roy; Hasan, Tawfique

2014-11-11T23:59:59.000Z

200

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

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

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

202

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

203

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

204

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

205

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.

206

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

207

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

208

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

209

CdS and CdS/CdSe sensitized ZnO nanorod array solar cells prepared by a solution ions exchange process  

SciTech Connect (OSTI)

Graphical abstract: - Highlights: CdS and CdS/CdSe quantum dots are assembled on ZnO nanorods by ion exchange process. The CdS/CdSe sensitization of ZnO effectively extends the absorption spectrum. The performance of ZnO/CdS/CdSe cell is improved by extending absorption spectrum. - Abstract: In this paper, cadmium sulfide (CdS) and cadmium sulfide/cadmium selenide (CdS/CdSe) quantum dots (QDs) are assembled onto ZnO nanorod arrays by a solution ion exchange process for QD-sensitized solar cell application. The morphology, composition and absorption properties of different photoanodes were characterized with scanning electron microscope, transmission electron microscope, energy-dispersive X-ray spectrum and Raman spectrum in detail. It is shown that conformal and uniform CdS and CdS/CdSe shells can grow on ZnO nanorod cores. Quantum dot sensitized solar cells based on ZnO/CdS and ZnO/CdS/CdSe nanocable arrays were assembled with gold counter electrode and polysulfide electrolyte solution. The CdS/CdSe sensitization of ZnO can effectively extend the absorption spectrum up to 650 nm, which has a remarkable impact on the performance of a photovoltaic device by extending the absorption spectrum. Preliminary results show one fourth improvement in solar cell efficiency.

Chen, Ling; Gong, Haibo; Zheng, Xiaopeng; Zhu, Min; Zhang, Jun [Key Laboratory of Inorganic Functional Materials in Universities of Shandong, School of Materials Science and Engineering, University of Jinan, Jinan 250022, Shandong (China); Yang, Shikuan [Department of Engineering Science and Mechanics, The Pennsylvania State University, University Park, PA 16802-6812 (United States); Cao, Bingqiang, E-mail: mse_caobq@ujn.edu.cn [Key Laboratory of Inorganic Functional Materials in Universities of Shandong, School of Materials Science and Engineering, University of Jinan, Jinan 250022, Shandong (China)

2013-10-15T23:59:59.000Z

210

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

211

Using Process Modeling for Process Understanding Dewayne E. Perry  

E-Print Network [OSTI]

Using Process Modeling for Process Understanding Dewayne E. Perry Systems and Software Research to improving processes is first understanding them. I report here a case study in process understanding using the process modeling language Interact. I illustrate both the language and the process iteratively, somewhat

Perry, Dewayne E.

212

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

213

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

214

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

215

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

216

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

217

DEVELOPMENT OF A KINETIC MODEL OF BOEHMITE DISSOLUTION IN CAUSTIC SOLUTIONS APPLIED TO OPTIMIZE HANFORD WASTE PROCESSING  

SciTech Connect (OSTI)

Boehmite (e.g., aluminum oxyhydroxide) is a major non-radioactive component in Hanford and Savannah River nuclear tank waste sludge. Boehmite dissolution from sludge using caustic at elevated temperatures is being planned at Hanford to minimize the mass of material disposed of as high-level waste (HLW) during operation of the Waste Treatment Plant (WTP). To more thoroughly understand the chemistry of this dissolution process, we have developed an empirical kinetic model for aluminate production due to boehmite dissolution. Application of this model to Hanford tank wastes would allow predictability and optimization of the caustic leaching of aluminum solids, potentially yielding significant improvements to overall processing time, disposal cost, and schedule. This report presents an empirical kinetic model that can be used to estimate the aluminate production from the leaching of boehmite in Hanford waste as a function of the following parameters: (1) hydroxide concentration; (2) temperature; (3) specific surface area of boehmite; (4) initial soluble aluminate plus gibbsite present in waste; (5) concentration of boehmite in the waste; and (6) (pre-fit) Arrhenius kinetic parameters. The model was fit to laboratory, non-radioactive (e.g. 'simulant boehmite') leaching results, providing best-fit values of the Arrhenius A-factor, A, and apparent activation energy, E{sub A}, of A = 5.0 x 10{sup 12} hour{sup -1} and E{sub A} = 90 kJ/mole. These parameters were then used to predict boehmite leaching behavior observed in previously reported actual waste leaching studies. Acceptable aluminate versus leaching time profiles were predicted for waste leaching data from both Hanford and Savannah River site studies.

DISSELKAMP RS

2011-01-06T23:59:59.000Z

218

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

219

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

220

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

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

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

222

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

223

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

224

A first order iteration process for simultaneous equations  

E-Print Network [OSTI]

let n n n (5a) g . (X) = (d(X) /Sp(J (X) J(X) I ] I f . (X) f . (E) Ri Rj t and let (3b) G(X) = [g (X) ], 1& i, j &n Then clearly (see (4)) X ? Y ? H(K) = (I ? G(X))(X - Y) The only use we want of the above in the present section is to show... are satisfied: a. For 1 & i & n, f (Y) b. In a neighborhood of Y continuous (1 & i, 0 Bf the partial derivatives ? are Bx) n) c. For f (X) ? f (X), the n x n matrix. J(X) = [f (X)] is a ax ij nonsingular at Y. Let the eigenvalues of [I/Sp(J (Y) J...

Stewart, Wallace Franklin

1966-01-01T23:59:59.000Z

225

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

226

SOLUTION-PROCESSED INORGANIC ELECTRONICS  

E-Print Network [OSTI]

Electrodes for Dye-Sensitized Solar Cells, Nano Letters,diodes (OLEDs), dye- sensitized solar cells, as well as

Bakhishev, Teymur

2011-01-01T23:59:59.000Z

227

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

228

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

229

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

230

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

231

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

232

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

233

Novel Regenerated Solvent Extraction Processes for the Recovery of Carboxylic Acids or Ammonia from Aqueous Solutions Part II. Recovery of Ammonia from Sour Waters  

E-Print Network [OSTI]

Ashbrook, A.W. , Process Metallurgy I , Solvent Extraction,and Applications to Process Metallurgy, Elsevier ScienceAshbrook, A.W. , Process Metallurgy 1, Solvent Extraction:

Poole, L.J.

2008-01-01T23:59:59.000Z

234

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

235

Modifying the organic/electrode interface in Organic Solar Cells (OSCs) and improving the efficiency of solution-processed phosphorescent Organic Light-Emitting Diodes (OLEDs)  

SciTech Connect (OSTI)

Organic semiconductors devices, such as, organic solar cells (OSCs), organic light-emitting diodes (OLEDs) and organic field-effect transistors (OFETs) have drawn increasing interest in recent decades. As organic materials are flexible, light weight, and potentially low-cost, organic semiconductor devices are considered to be an alternative to their inorganic counterparts. This dissertation will focus mainly on OSCs and OLEDs. As a clean and renewable energy source, the development of OSCs is very promising. Cells with 9.2% power conversion efficiency (PCE) were reported this year, compared to < 8% two years ago. OSCs belong to the so-called third generation solar cells and are still under development. While OLEDs are a more mature and better studied field, with commercial products already launched in the market, there are still several key issues: (1) the cost of OSCs/OLEDs is still high, largely due to the costly manufacturing processes; (2) the efficiency of OSCs/OLEDs needs to be improved; (3) the lifetime of OSCs/OLEDs is not sufficient compared to their inorganic counterparts; (4) the physics models of the behavior of the devices are not satisfactory. All these limitations invoke the demand for new organic materials, improved device architectures, low-cost fabrication methods, and better understanding of device physics. For OSCs, we attempted to improve the PCE by modifying the interlayer between active layer/metal. We found that ethylene glycol (EG) treated poly(3,4-ethylenedioxythiophene): polystyrenesulfonate (PEDOT: PSS) improves hole collection at the metal/polymer interface, furthermore it also affects the growth of the poly(3- hexylthiophene) (P3HT):phenyl-C61-butyric acid methyl ester (PCBM) blends, making the phase segregation more favorable for charge collection. We then studied organic/inorganic tandem cells. We also investigated the effect of a thin LiF layer on the hole-collection of copper phthalocyanine (CuPc)/C70-based small molecular OSCs. A thin LiF layer serves typically as the electron injection layer in OLEDs and electron collection interlayer in the OSCs. However, several reports showed that it can also assist in holeinjection in OLEDs. Here we first demonstrate that it assists hole-collection in OSCs, which is more obvious after air-plasma treatment, and explore this intriguing dual role. For OLEDs, we focus on solution processing methods to fabricate highly efficient phosphorescent OLEDs. First, we investigated OLEDs with a polymer host matrix, and enhanced charge injection by adding hole- and electron-transport materials into the system. We also applied a hole-blocking and electron-transport material to prevent luminescence quenching by the cathode. Finally, we substituted the polymer host by a small molecule, to achieve more efficient solution processed small molecular OLEDs (SMOLEDs); this approach is cost-effective in comparison to the more common vacuum thermal evaporation. All these studies help us to better understand the underlying relationship between the organic semiconductor materials and the OSCs and OLEDs performance and will subsequently assist in further enhancing the efficiencies of OSCs and OLEDs. With better efficiency and longer lifetime, the OSCs and OLEDs will be competitive with their inorganic counterparts.

Xiao, Teng

2012-04-27T23:59:59.000Z

236

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

237

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

238

Novel Regenerated Solvent Extraction Processes for the Recovery of Carboxylic Acids or Ammonia from Aqueous Solutions Part I. Regeneration of Amine-Carboxylic Acid Extracts  

E-Print Network [OSTI]

production of citric acid by fermentation, recovery of theof Citric Acid from Aqueous Fermentation Solutions byof citric acid was 1.1.1 Lactic Acid Currently, fermentation

Poole, L.J.

2008-01-01T23:59:59.000Z

239

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

240

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

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

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

242

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

243

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

244

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

245

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

246

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

247

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

248

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

249

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

250

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

251

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

252

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

253

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

254

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

255

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

256

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

257

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

258

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

259

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

260

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

Note: This page contains sample records for the topic "iterative solution process" from the National Library of EnergyBeta (NLEBeta).
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261

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

262

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

263

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

264

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

265

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

266

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

267

The Carnoules mine. Generation of As-rich acid mine drainage, natural attenuation processes and solutions for passive in-situ remediation  

E-Print Network [OSTI]

and solutions for passive in-situ remediation F.ELBAZ-POULICHET, UMR Hydrosciences, CNRS-University Montpellier-Zn mine (Department of Gard, France) has produced 1.5 Mt of solid waste containing pyrite and associated oxidation they generate acid (pH3) water containing up to 350mg/l of arsenic, 750 to 2700mg/L of iron

Paris-Sud XI, Université de

268

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

269

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

270

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

271

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

272

Misfit layered Ca{sub 3}Co{sub 4}O{sub 9} as a high figure of merit p-type transparent conducting oxide film through solution processing  

SciTech Connect (OSTI)

Ca{sub 3}Co{sub 4}O{sub 9} thin films synthesized through solution processing are shown to be high-performing, p-type transparent conducting oxides (TCOs). The synthesis method is a cost-effective and scalable process that consists of sol-gel chemistry, spin coating, and heat treatments. The process parameters can be varied to produce TCO thin films with sheet resistance as low as 5.7?k?/sq (????57 m? cm) or with average visible range transparency as high as 67%. The most conductive Ca{sub 3}Co{sub 4}O{sub 9} TCO thin film has near infrared region optical transmission as high as 85%. The figure of merit (FOM) for the top-performing Ca{sub 3}Co{sub 4}O{sub 9} thin film (151 M?{sup ?1}) is higher than FOM values reported in the literature for all other solution processed, p-type TCO thin films and higher than most others prepared by physical vapor deposition and chemical vapor deposition. Transparent conductivity in misfit layered oxides presents new opportunities for TCO compositions.

Aksit, M.; Kolli, S. K.; Slauch, I. M.; Robinson, R. D., E-mail: rdr82@cornell.edu [Materials Science and Engineering, Cornell University, Ithaca, New York 14853 (United States)

2014-04-21T23:59:59.000Z

273

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

274

Novel Regenerated Solvent Extraction Processes for the Recovery of Carboxylic Acids or Ammonia from Aqueous Solutions Part II. Recovery of Ammonia from Sour Waters  

E-Print Network [OSTI]

of Economic Materials from Oil Shale Retort Water by anDerived from In Situ Oil Shale Processing", Proceedings, 2ndWastewaters Sour Waters from Oil Shale Retorting Sour Waters

Poole, L.J.

2008-01-01T23:59:59.000Z

275

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

276

Implementation of a cell-wise Block-Gauss-Seidel iterative method for SN transport on a hybrid parallel computer architecture  

SciTech Connect (OSTI)

We have implemented a cell-wise, block-Gauss-Seidel (bGS) iterative algorithm, for the solution of the S{sub n} transport equations on the Roadrunner hybrid, parallel computer architecture. A compute node of this massively parallel machine comprises AMD Opteron cores that are linked to a Cell Broadband Engine{trademark} (Cell/B.E.). LAPACK routines have been ported to the Cell/B.E. in order to make use of its parallel Synergistic Processing Elements (SPEs). The bGS algorithm is based on the LU factorization and solution of a linear system that couples the fluxes for all S{sub n} angles and energy groups on a mesh cell. For every cell of a mesh that has been parallel decomposed on the higher-level Opteron processors, a linear system is transferred to the Cell/B.E. and the parallel LAPACK routines are used to compute a solution, which is then transferred back to the Opteron, where the rest of the computations for the S{sub n} transport problem take place. Compared to standard parallel machines, a hundred-fold speedup of the bGS was observed on the hybrid Roadrunner architecture. Numerical experiments with strong and weak parallel scaling demonstrate the bGS method is viable and compares favorably to full parallel sweeps (FPS) on two-dimensional, unstructured meshes when it is applied to optically thick, multi-material problems. As expected, however, it is not as efficient as FPS in optically thin problems.

Rosa, Massimiliano [Los Alamos National Laboratory; Warsa, James S [Los Alamos National Laboratory; Perks, Michael [Los Alamos National Laboratory

2010-12-14T23:59:59.000Z

277

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions. Third quarterly report, April 1993--June 1993  

SciTech Connect (OSTI)

This report presents research objectives, discusses activities, and presents technical progress for the period April 1, 1993 through June 31, 1993 on Contract No. DE-FC21-86LC11084 with the Department of Energy, Laramie Project Office. The scope of the research program and the continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 {times} 3.0 {times} 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. (RBOSC) through a separate cooperative agreement with the University of Wyoming (UW) to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin of Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which was filled in the lysimeter cells.

Reeves, T.L.; Turner, J.P.; Rangarajan, S.; Skinner, Q.D.; Hasfurther, V.

1993-08-11T23:59:59.000Z

278

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions. Second quarterly report, January 1, 1992--March 31, 1992  

SciTech Connect (OSTI)

The scope of the research program and the continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 {times} 3.0 {times} 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. (RBOSC) through a separate cooperative agreement with the University of Wyoming (UW) to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin of Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which was filled in the lysimeter cells.

Turner, J.P.; Hasfurther, V.

1992-05-04T23:59:59.000Z

279

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions. Fourth quarterly report, July--September 1993  

SciTech Connect (OSTI)

The scope of the research program and the continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 {times} 3.0 {times} 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. (RBOSC) through a separate cooperative agreement with the University of Wyoming (UW) to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin of Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which was filled in the lysimeter cells.

Turner, J.P.; Hasfurther, V.

1993-10-08T23:59:59.000Z

280

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

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

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

282

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

283

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

284

Novel Regenerated Solvent Extraction Processes for the Recovery of Carboxylic Acids or Ammonia from Aqueous Solutions Part II. Recovery of Ammonia from Sour Waters  

E-Print Network [OSTI]

19,20). In the coking step, coal is heated III the absencethe "coking" process in In the second step the which coal isCoal Liquefaction Wastewaters Sour Waters from Oil Shale Retorting Sour Waters from Petroleum Refining Sour Waters from Coking

Poole, L.J.

2008-01-01T23:59:59.000Z

285

Adaptive schemes for incomplete quantum process tomography  

SciTech Connect (OSTI)

We propose an iterative algorithm for incomplete quantum process tomography with the help of quantum state estimation. The algorithm, which is based on the combined principles of maximum likelihood and maximum entropy, yields a unique estimator for an unknown quantum process when one has less than a complete set of linearly independent measurement data to specify the quantum process uniquely. We apply this iterative algorithm adaptively in various situations and so optimize the amount of resources required to estimate a quantum process with incomplete data.

Teo, Yong Siah [Centre for Quantum Technologies, National University of Singapore, Singapore 117543 (Singapore); NUS Graduate School for Integrative Sciences and Engineering, Singapore 117597 (Singapore); Englert, Berthold-Georg [Centre for Quantum Technologies, National University of Singapore, Singapore 117543 (Singapore); Department of Physics, National University of Singapore, Singapore 117542 (Singapore); Rehacek, Jaroslav; Hradil, Zdenek [Department of Optics, Palacky University, 17. listopadu 12, CZ-77146 Olomouc (Czech Republic)

2011-12-15T23:59:59.000Z

286

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

287

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

288

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

289

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

290

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

291

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

292

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

293

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

294

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

295

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.

296

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

297

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

298

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

299

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

300

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 "iterative solution process" 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

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

302

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

303

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

304

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

305

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

306

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

307

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

308

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

309

Energy Level Alignment in PCDTBT:PC70BM Solar Cells: Solution Processed NiOx for Improved Hole Collection and Efficiency  

SciTech Connect (OSTI)

Solution-based NiO{sub x} outperforms PEDOT:PSS in device performance and stability when used as a hole-collection layer in bulk-heterojunction (BHJ) solar cells formed with poly[N-9'-heptadecanyl-2,7-carbazole-alt-5,5-(4',7'-di-2-thienyl-2',1',3'-benzothiadiazole)] (PCDTBT) and PC70BM. The origin of the enhancement is clarified by studying the interfacial energy level alignment between PCDTBT or the 1:4 blended heterojunctions and PEDOT:PSS or NiO{sub x} using ultraviolet and inverse photoemission spectroscopies. The 1.6 eV electronic gap of PEDOT:PSS and energy level alignment with the BHJ result in poor hole selectivity of PEDOT:PSS and allows electron recombination at the PEDOT:PSS/BHJ interface. Conversely, the large band gap (3.7 eV) of NiO{sub x} and interfacial dipole (0.6 eV) with the organic active layer leads to a hole-selective interface. This interfacial dipole yields enhanced electron blocking properties by increasing the barrier to electron injection. The presence of such a strong dipole is predicted to further promote hole collection from the organic layer into the oxide, resulting in increased fill factor and short circuit current. An overall decrease in recombination is manifested in an increase in open circuit voltage and power conversion efficiency of the device on NiO{sub x} versus PEDOT:PSS interlayers.

Ratcliff, E. L.; Meyer, J.; Steirer, K. X.; Armstrong, N. R.; Olson, D.; Kahn, A.

2012-05-01T23:59:59.000Z

310

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

311

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.

312

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

313

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

314

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

315

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

316

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

317

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

318

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

319

The ITER Project: Advancing Hydrogen Fusion  

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

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

320

Simultaneous impact of neutron irradiation and sputtering on the surface structure of selfdamaged ITERgrade tungsten  

SciTech Connect (OSTI)

Simultaneous effects of neutron irradiation and longterm sputtering on the surface relief of ITERgrade tungsten were studied. The effects of neutroninduced displacement damage have been simulated by irradiation of tungsten target with W{sup 6+} ions of 20?MeV energy. Ar{sup +} ions with energy 600?eV were used as imitation of charge exchange atoms in ITER. The surface relief was studied after each sputtering act. The singularity in the WJIG surface relief was ascertained experimentally at the first time, which determines the law of roughness extension under sputtering. As follows from the experimental data, the neutron irradiation has not to make a decisive additional contribution in the processes developing under impact of charge exchange atoms only.

Belyaeva, A. I., E-mail: aibelyaeva@mail.ru; Savchenko, A. A. [National Technical University Kharkov Politechnical Institute, Kharkov, 61002 (Ukraine); Galuza, A. A.; Kolenov, I. V. [Institute of Electrophysics and Radiation Technologies, National Academy of Science of Ukraine, Kharkov, 61024 (Ukraine)

2014-07-15T23:59:59.000Z

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

Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions. Final report, November 1995  

SciTech Connect (OSTI)

A study is described on the hydrological and geotechnical behavior of an oil shale solid waste. The objective was to obtain information which can be used to assess the environmental impacts of oil shale solid waste disposal in the Green River Basin. The spent shale used in this study was combusted by the Lurgi-Ruhrgas process by Rio Blanco Oil Shale Company, Inc. Laboratory bench-scale testing included index properties, such as grain size distribution and Atterberg limits, and tests for engineering properties including hydraulic conductivity and shear strength. Large-scale tests were conducted on model spent shale waste embankments to evaluate hydrological response, including infiltration, runoff, and seepage. Large-scale tests were conducted at a field site in western Colorado and in the Environmental Simulation Laboratory (ESL)at the University of Wyoming. The ESL tests allowed the investigators to control rainfall and temperature, providing information on the hydrological response of spent shale under simulated severe climatic conditions. All experimental methods, materials, facilities, and instrumentation are described in detail, and results are given and discussed. 34 refs.

NONE

1995-12-31T23:59:59.000Z

322

Beryllium fabrication/cost assessment for ITER (International Thermonuclear Experimental Reactor)  

SciTech Connect (OSTI)

A fabrication and cost estimate of three possible beryllium shapes for the International Thermonuclear Experimental Reactor (ITER) blanket is presented. The fabrication method by hot pressing (HP), cold isostatic pressing plus sintering (CIP+S), cold isostatic pressing plus sintering plus hot isostatic pressing (CIP+S+HIP), and sphere production by atomization or rotary electrode will be discussed. Conventional hot pressing blocks of beryllium with subsequent machining to finished shapes can be more expensive than production of a net shape by cold isostatic pressing and sintering. The three beryllium shapes to be considered here and proposed for ITER are: (1) cubic blocks (3 to 17 cm on an edge), (2) tubular cylinders (33 to 50 mm i.d. by 62 mm o.d. by 8 m long), and (3) spheres (1--5 mm dia.). A rough cost estimate of the basic shape is presented which would need to be refined if the surface finish and tolerances required are better than the sintering process produces. The final cost of the beryllium in the blanket will depend largely on the machining and recycling of beryllium required to produce the finished product. The powder preparation will be discussed before shape fabrication. 10 refs., 6 figs.

Beeston, J.M. (Beeston (J.M.), Garrison, UT (USA)); Longhurst, G.R. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Parsonage, T. (Brush Wellman, Inc., Elmore, OH (USA))

1990-06-01T23:59:59.000Z

323

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

324

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

325

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

326

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

327

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

328

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

329

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

330

Optimizing Process Loads in Industrial Cogeneration Energy Systems  

E-Print Network [OSTI]

applied to power generation and industrial cogeneration are extended to solving this trigeneration problem where the optimum dispatch of the final load devices (i.e. compressors, fans, pumps, etc.) are an integral part of the total energy system...-04-29 Proceedings from the Seventeenth Industrial Energy Technology Conference, Houston, TX, April 5-6, 1995 optimum dispatch solutions, and an iterative simultaneous solution of the integrated system is required. The solution dependency arises when the end use...

Ahner, D. J.; Babson, P. E.

331

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

332

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

333

Quantum mechanical Hamiltonian models of discrete processes that erase their own histories: application to Turing machines  

SciTech Connect (OSTI)

Work done before on the construction of quantum mechanical Hamiltonian models of Turing machines and general descrete processes is extended here to include processes which erase their own histories. The models consist of three phases, the forward process phase in which a map T is iterated and a history of iterations is generated, a copy phase which is activated if and only if T reaches a fix point, and an erase phase which erases the iteration history, undoes the iterations of T and recovers the initial state except for the copy system. A ballast system is used to stop the evolution at the desired state. The general model so constructed is applied to Turing machines. The main changes are that the system undergoing the evolution corresponding to T iterations becomes three systems corresponding to the internal machine, the computation tape, and computation head. Also the copy phase becomes more complex since it is desired that this correspond also to a copying Turing machine.

Benioff, P.A.

1981-01-01T23:59:59.000Z

334

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

335

Efficient indium-tin-oxide free inverted organic solar cells based on aluminum-doped zinc oxide cathode and low-temperature aqueous solution processed zinc oxide electron extraction layer  

SciTech Connect (OSTI)

Indium-tin-oxide (ITO) free inverted organic solar cells (IOSCs) based on aluminum-doped zinc oxide (AZO) cathode, low-temperature aqueous solution processed zinc oxide (ZnO) electron extraction layer, and poly(3-hexylthiophene-2, 5-diyl):[6, 6]-phenyl C{sub 61} butyric acid methyl ester blend were realized in this work. The resulted IOSC with ZnO annealed at 150?C shows the superior power conversion efficiency (PCE) of 3.01%, if decreasing the ZnO annealing temperature to 100?C, the obtained IOSC also shows a PCE of 2.76%, and no light soaking issue is observed. It is found that this ZnO film not only acts as an effective buffer layer but also slightly improves the optical transmittance of AZO substrates. Further, despite the relatively inferior air-stability, these un-encapsulated AZO/ZnO IOSCs show comparable PCEs to the referenced ITO/ZnO IOSCs, which demonstrates that the AZO cathode is a potential alternative to ITO in IOSCs. Meanwhile, this simple ZnO process is compatible with large area deposition and plastic substrates, and is promising to be widely used in IOSCs and other relative fields.

Chen, Dazheng; Zhang, Chunfu, E-mail: cfzhang@xidian.edu.cn; Wang, Zhizhe; Zhang, Jincheng; Tang, Shi; Wei, Wei; Sun, Li; Hao, Yue, E-mail: yhao@xidian.edu.cn [State Key Discipline Laboratory of Wide Band Gap Semiconductor Technology, School of Microelectronics, Xidian University, No. 2 South Taibai Road, Xi'an 710071 (China)

2014-06-16T23:59:59.000Z

336

Enhanced safeguards via solution monitoring  

SciTech Connect (OSTI)

Solution monitoring is defined as the essentially continuous monitoring of solution level, density, and temperature in all tanks in the process that contain, or could contain, safeguards-significant quantities of nuclear material. This report describes some of the enhancements that solution monitoring could make to international safeguards. The focus is on the quantifiable benefits of solution monitoring, but qualitatively, solution monitoring can be viewed as a form of surveillance. Quantitatively, solution monitoring can in some cases improve diversion detection probability. For example, the authors show that under certain assumptions, solution monitoring can be used to reduce the standard deviation of the annual material balance, {sigma}{sub MB}, from approximately 17 kg to approximately 4 kg. Such reduction in {sigma}{sub MB} will not always be possible, as they discuss. However, in all cases, solution monitoring would provide assurance that the measurement error models are adequate so that one has confidence in his estimate of {sigma}{sub MB}. Some of the results in this report were generated using data that were simulated with prototype solution monitoring software that they are developing. An accompanying document describes that software.

Burr, T.; Wangen, L.

1996-09-01T23:59:59.000Z

337

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

338

Loca study for a helium-cooled solid breeder design for ITER  

SciTech Connect (OSTI)

The analysis of thermal processes after a loss-of-coolant accident (LOCA) in a solid breeder blanket is important because of the first wall and solid breeder maximum allowable temperature constraints. The objective is to design for a LOCA so that following a LOCA, the maximum solid breeder and structure temperatures are less than the limit beyond which irreversible damage is done, which would lead to loss of investment. The temporal temperature profiles for the solid breeder and first wall regions of a helium-cooled solid breeder design for ITER were calculated based on afterheat values for adiabatic and non-adiabatic conditions and the results are presented in this paper. It is found that, for this design, even when excluding radiation to the cooled inboard, a LOCA can be recommended by energy removal through a flowing purge with a reasonable flow rate.

Gorbis, Z.R.; Raffray, A.R.; Fujimura, K.; Jun, I.; Abdou, M.A.

1989-03-01T23:59:59.000Z

339

Separation Processes, Second Edition  

E-Print Network [OSTI]

by; Uranium isotopes separation) Iteration methods (seemethod for activity coefficients, 43, 481 Uranium isotopes separation,

King, C. Judson

1980-01-01T23:59:59.000Z

340

Nanocrystal solar cells processed from solution  

DOE Patents [OSTI]

A photovoltaic device having a first electrode layer, a high resistivity transparent film disposed on the first electrode, a second electrode layer, and an inorganic photoactive layer disposed between the first and second electrode layers, wherein the inorganic photoactive layer is disposed in at least partial electrical contact with the high resistivity transparent film, and in at least partial electrical contact with the second electrode. The photoactive layer has a first inorganic material and a second inorganic material different from the first inorganic material, wherein the first and second inorganic materials exhibit a type II band offset energy profile, and wherein the photoactive layer has a first population of nanostructures of a first inorganic material and a second population of nanostructures of a second inorganic material.

Alivisatos, A. Paul; Gur, Ilan; Milliron, Delia

2013-05-14T23:59:59.000Z

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

Engineering report (conceptual design) PFP solution stabilization  

SciTech Connect (OSTI)

This Engineering Report (Conceptual Design) addresses remediation of the plutonium-bearing solutions currently in inventory at the Plutonium Finishing Plant (PFP). The recommendation from the Environmental Impact Statement (EIS) is that the solutions be treated thermally and stabilized as a solid for long term storage. For solutions which are not discardable, the baseline plan is to utilize a denitration process to stabilize the solutions prior to packaging for storage.

Witt, J.B.

1997-07-17T23:59:59.000Z

342

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

343

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

344

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

345

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

346

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...

347

RAMI Analysis for Designing and Optimizing Tokamak Cooling Water System (TCWS) for the ITER's Fusion Reactor  

SciTech Connect (OSTI)

U.S.-ITER is responsible for the design, engineering, and procurement of the Tokamak Cooling Water System (TCWS). TCWS is designed to provide cooling and baking for client systems that include the first wall/blanket, vacuum vessel, divertor, and neutral beam injector. Additional operations that support these primary functions include chemical control of water provided to client systems, draining and drying for maintenance, and leak detection/localization. TCWS interfaces with 27 systems including the secondary cooling system, which rejects this heat to the environment. TCWS transfers heat generated in the Tokamak during nominal pulsed operation - 850 MW at up to 150 C and 4.2 MPa water pressure. Impurities are diffused from in-vessel components and the vacuum vessel by water baking at 200-240 C at up to 4.4 MPa. TCWS is complex because it serves vital functions for four primary clients whose performance is critical to ITER's success and interfaces with more than 20 additional ITER systems. Conceptual design of this one-of-a-kind cooling system has been completed; however, several issues remain that must be resolved before moving to the next stage of the design process. The 2004 baseline design indicated cooling loops that have no fault tolerance for component failures. During plasma operation, each cooling loop relies on a single pump, a single pressurizer, and one heat exchanger. Consequently, failure of any of these would render TCWS inoperable, resulting in plasma shutdown. The application of reliability, availability, maintainability, and inspectability (RAMI) tools during the different stages of TCWS design is crucial for optimization purposes and for maintaining compliance with project requirements. RAMI analysis will indicate appropriate equipment redundancy that provides graceful degradation in the event of an equipment failure. This analysis helps demonstrate that using proven, commercially available equipment is better than using custom-designed equipment with no field experience and lowers specific costs while providing higher reliability. This paper presents a brief description of the TCWS conceptual design and the application of RAMI tools to optimize the design at different stages during the project.

Ferrada, Juan J [ORNL] [ORNL; Reiersen, Wayne T [ORNL] [ORNL

2011-01-01T23:59:59.000Z

348

Using Visualization Process Graphs to Improve Visualization Exploration  

E-Print Network [OSTI]

Using Visualization Process Graphs to Improve Visualization Exploration T. J. Jankun-Kelly1 University, MS 39762, USA. Email: tjk@acm.org Abstract. Visualization exploration is an iterative process, redundant exploration was quickly identified and eliminated. 1 Introduction During the visualization process

Jankun-Kelly, T. J.

349

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

350

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

351

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

352

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

353

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

354

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

355

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

356

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

357

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

358

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

359

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

360

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

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

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

362

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

363

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

364

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

365

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

366

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

367

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

368

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

369

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

370

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

371

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

372

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

373

Purification process  

SciTech Connect (OSTI)

A process for the removal of hydrogen sulphide from gases or liquid hydrocarbons, comprises contacting the gas or liquid hydrocarbon with an aqueous alkaline solution, preferably having a pH value of 8 to 10, comprising (A) an anthraquinone disulphonic acid or a water-soluble sulphonamide thereof (B) a compound of a metal which can exist in at least two valency states and (C) a sequestering agent.

Marshall, A.

1981-02-17T23:59:59.000Z

374

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

375

Combined iterative reconstruction and image-domain decomposition for dual energy CT using total-variation regularization  

SciTech Connect (OSTI)

Purpose: Dual-energy CT (DECT) is being increasingly used for its capability of material decomposition and energy-selective imaging. A generic problem of DECT, however, is that the decomposition process is unstable in the sense that the relative magnitude of decomposed signals is reduced due to signal cancellation while the image noise is accumulating from the two CT images of independent scans. Direct image decomposition, therefore, leads to severe degradation of signal-to-noise ratio on the resultant images. Existing noise suppression techniques are typically implemented in DECT with the procedures of reconstruction and decomposition performed independently, which do not explore the statistical properties of decomposed images during the reconstruction for noise reduction. In this work, the authors propose an iterative approach that combines the reconstruction and the signal decomposition procedures to minimize the DECT image noise without noticeable loss of resolution. Methods: The proposed algorithm is formulated as an optimization problem, which balances the data fidelity and total variation of decomposed images in one framework, and the decomposition step is carried out iteratively together with reconstruction. The noise in the CT images from the proposed algorithm becomes well correlated even though the noise of the raw projections is independent on the two CT scans. Due to this feature, the proposed algorithm avoids noise accumulation during the decomposition process. The authors evaluate the method performance on noise suppression and spatial resolution using phantom studies and compare the algorithm with conventional denoising approaches as well as combined iterative reconstruction methods with different forms of regularization. Results: On the Catphan600 phantom, the proposed method outperforms the existing denoising methods on preserving spatial resolution at the same level of noise suppression, i.e., a reduction of noise standard deviation by one order of magnitude. This improvement is mainly attributed to the high noise correlation in the CT images reconstructed by the proposed algorithm. Iterative reconstruction using different regularization, including quadratic orq-generalized Gaussian Markov random field regularization, achieves similar noise suppression from high noise correlation. However, the proposed TV regularization obtains a better edge preserving performance. Studies of electron density measurement also show that our method reduces the average estimation error from 9.5% to 7.1%. On the anthropomorphic head phantom, the proposed method suppresses the noise standard deviation of the decomposed images by a factor of ?14 without blurring the fine structures in the sinus area. Conclusions: The authors propose a practical method for DECT imaging reconstruction, which combines the image reconstruction and material decomposition into one optimization framework. Compared to the existing approaches, our method achieves a superior performance on DECT imaging with respect to decomposition accuracy, noise reduction, and spatial resolution.

Dong, Xue; Niu, Tianye; 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)

2014-05-15T23:59:59.000Z

376

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

377

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

378

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

379

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

380

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

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

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

382

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

383

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

384

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

385

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

386

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

387

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

388

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

389

Iterative optimizing quantization method for reconstructing three-dimensional images from a limited number of views  

DOE Patents [OSTI]

A three-dimensional image reconstruction method comprises treating the object of interest as a group of elements with a size that is determined by the resolution of the projection data, e.g., as determined by the size of each pixel. One of the projections is used as a reference projection. A fictitious object is arbitrarily defined that is constrained by such reference projection. The method modifies the known structure of the fictitious object by comparing and optimizing its four projections to those of the unknown structure of the real object and continues to iterate until the optimization is limited by the residual sum of background noise. The method is composed of several sub-processes that acquire four projections from the real data and the fictitious object: generate an arbitrary distribution to define the fictitious object, optimize the four projections, generate a new distribution for the fictitious object, and enhance the reconstructed image. The sub-process for the acquisition of the four projections from the input real data is simply the function of acquiring the four projections from the data of the transmitted intensity. The transmitted intensity represents the density distribution, that is, the distribution of absorption coefficients through the object. 5 figs.

Lee, H.R.

1997-11-18T23:59:59.000Z

390

Iterative optimizing quantization method for reconstructing three-dimensional images from a limited number of views  

DOE Patents [OSTI]

A three-dimensional image reconstruction method comprises treating the object of interest as a group of elements with a size that is determined by the resolution of the projection data, e.g., as determined by the size of each pixel. One of the projections is used as a reference projection. A fictitious object is arbitrarily defined that is constrained by such reference projection. The method modifies the known structure of the fictitious object by comparing and optimizing its four projections to those of the unknown structure of the real object and continues to iterate until the optimization is limited by the residual sum of background noise. The method is composed of several sub-processes that acquire four projections from the real data and the fictitious object: generate an arbitrary distribution to define the fictitious object, optimize the four projections, generate a new distribution for the fictitious object, and enhance the reconstructed image. The sub-process for the acquisition of the four projections from the input real data is simply the function of acquiring the four projections from the data of the transmitted intensity. The transmitted intensity represents the density distribution, that is, the distribution of absorption coefficients through the object.

Lee, Heung-Rae (Dublin, CA)

1997-01-01T23:59:59.000Z

391

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

392

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...

393

EIS-0219: F-Canyon Plutonium Solutions  

Broader source: Energy.gov [DOE]

This EIS evaluates the potential environmental impacts of processingthe plutonium solutions to metal form using the F-Canyon and FB-Line facilities at the Savannah River Site.

394

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

395

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

396

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

397

Pervaporation process and assembly  

DOE Patents [OSTI]

The invention is a pervaporation process and pervaporation equipment, using a series of membrane modules, and including inter-module reheating of the feed solution under treatment. The inter-module heating is achieved within the tube or vessel in which the modules are housed, thereby avoiding the need to repeatedly extract the feed solution from the membrane module train.

Wynn, Nicholas P. (Redwood City, CA); Huang, Yu (Palo Alto, CA); Aldajani, Tiem (San Jose, CA); Fulton, Donald A. (Fairfield, CA)

2010-07-20T23:59:59.000Z

398

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

399

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

400

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

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

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

402

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

403

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

404

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

405

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

406

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

407

An Iterative Algorithm for Battery-Aware Task Scheduling on Portable Computing Platforms  

E-Print Network [OSTI]

In this work we consider battery powered portable systems which either have Field Programmable Gate Arrays (FPGA) or voltage and frequency scalable processors as their main processing element. An application is modeled in the form of a precedence task graph at a coarse level of granularity. We assume that for each task in the task graph several unique design-points are available which correspond to different hardware implementations for FPGAs and different voltage-frequency combinations for processors. It is assumed that performance and total power consumption estimates for each design-point are available for any given portable platfrom, including the peripheral components such as memory and display power usage. We present an iterative heuristic algorithm which finds a sequence of tasks along with an appropriate design-point for each task, such that a deadline is met and the amount of battery energy used is as small as possible. A detailed illustrative example along with a case study of a real-world applicati...

Khan, Jawad

2011-01-01T23:59:59.000Z

408

Perturbative Study of Energetic Particle Redistribution by Alfven Eigenmodes in ITER  

SciTech Connect (OSTI)

The modification of particle distributions by magnetohydrodynamic modes is an important topic for magnetically confined plasmas. Low amplitude modes are known to be capable of producing significant modification of injected neutral beam profiles. Flattening of a distribution due to phase mixing in an island or due to portions of phase space becoming stochastic is a process extremely rapid on the time scale of an experiment. In this paper we examine the effect of toroidal Alfven eigenmodes (TAE) and reversed shear Alfven eigenmodes (RSAE) in ITER on alpha particle and injected beam distributions using theoretically predicted mode amplitudes. It is found that for the equilibrium of a hybrid scenario even at ten times the predicted saturation level the modes have negligible effect on these distributions. A strongly reversed shear (or advanced) scenario, having a spectrum of modes that are much more global, is somewhat more susceptible to induced loss due to mode resonance, with alpha particle losses of over one percent with predicted amplitudes and somewhat larger with the assistance of toroidal field ripple. The elevated q profile contributes to stronger TAE (RSAE) drive and more unstable modes. An analysis of the existing mode-particle resonances is carried out to determine which modes are responsible for the profile modification and induced loss. We find that losses are entirely due to resonance with the counter-moving and trapped particle populations, with co-moving passing particles participating in resonances only deep within the plasma and not leading to loss.

N.N. Gorelenkov and R.B. White

2012-10-29T23:59:59.000Z

409

Performance evaluation approach for the supercritical helium cold circulators of ITER  

SciTech Connect (OSTI)

The ITER project design foresees Supercritical Helium (SHe) forced flow cooling for the main cryogenic components, namely, the superconducting (SC) magnets and cryopumps (CP). Therefore, cold circulators have been selected to provide the required SHe mass flow rate to cope with specific operating conditions and technical requirements. Considering the availability impacts of such machines, it has been decided to perform evaluation tests of the cold circulators at operating conditions prior to the series production in order to minimize the project technical risks. A proposal has been conceptualized, evaluated and simulated to perform representative tests of the full scale SHe cold circulators. The objectives of the performance tests include the validation of normal operating condition, transient and off-design operating modes as well as the efficiency measurement. A suitable process and instrumentation diagram of the test valve box (TVB) has been developed to implement the tests at the required thermodynamic conditions. The conceptual engineering design of the TVB has been developed along with the required thermal analysis for the normal operating conditions to support the performance evaluation of the SHe cold circulator.

Vaghela, H.; Sarkar, B.; Bhattacharya, R.; Kapoor, H. [ITER-India, Institute for Plasma Research, Near Indira Bridge, Bhat, Gandhinagar-382428 (India); Chalifour, M.; Chang, H.-S.; Serio, L. [ITER Organization, Route de Vinon sur Verdon - 13115 St Paul Lez Durance (France)

2014-01-29T23:59:59.000Z

410

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

411

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

412

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

413

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

414

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.

415

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

416

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

417

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

418

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

419

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

420

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

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

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

422

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

423

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

424

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

425

Macdonald processes  

E-Print Network [OSTI]

Macdonald processes are probability measures on sequences of partitions defined in terms of nonnegative specializations of the Macdonald symmetric functions and two Macdonald parameters q,t in [0,1). We prove several results about these processes, which include the following. (1) We explicitly evaluate expectations of a rich family of observables for these processes. (2) In the case t=0, we find a Fredholm determinant formula for a q-Laplace transform of the distribution of the last part of the Macdonald-random partition. (3) We introduce Markov dynamics that preserve the class of Macdonald processes and lead to new "integrable" 2d and 1d interacting particle systems. (4) In a large time limit transition, and as q goes to 1, the particles of these systems crystallize on a lattice, and fluctuations around the lattice converge to O'Connell's Whittaker process that describe semi-discrete Brownian directed polymers. (5) This yields a Fredholm determinant for the Laplace transform of the polymer partition function, and taking its asymptotics we prove KPZ universality for the polymer (free energy fluctuation exponent 1/3 and Tracy-Widom GUE limit law). (6) Under intermediate disorder scaling, we recover the Laplace transform of the solution of the KPZ equation with narrow wedge initial data. (7) We provide contour integral formulas for a wide array of polymer moments. (8) This results in a new ansatz for solving quantum many body systems such as the delta Bose gas.

Alexei Borodin; Ivan Corwin

2013-01-06T23:59:59.000Z

426

alkyl carbonate solution: Topics by E-print Network  

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

R. 13 Solution-processed single walled carbon nanotube electrodes for organic thin-film transistors Physics Websites Summary: t Airbrushed single walled carbon nanotube...

427

Robust Waste-to-Value Solution Using Advanced Monitoring and...  

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

Monitoring and Controls Introduction Waste-to-value is a promising and comprehensive wastewater processing solution being pursued by GE that recovers valuable energy and purified...

428

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

429

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

430

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

431

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

432

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

433

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

434

ProPAM: SPI based on Process and Project Alignment Paula Ventura Martins  

E-Print Network [OSTI]

representation is the starting point for process understanding, improvement and communication, project teams development is a creative work with strong co-operation aspects and does not benefit from static process alignment and iterative SPI performed by project team members. Process and project alignment is defined

da Silva, Alberto Rodrigues

435

Automate and accelerate build and release processes IBM Rational Build Forge  

E-Print Network [OSTI]

n n n n n n n Automate and accelerate build and release processes IBM Rational Build Forge in place today Accelerate build and release cycles through iterative develop- ment, parallel processes and efficient use of hardware Improve product quality through consistent, repeatable processes and early

436

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

437

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

438

HEPA filter dissolution process  

DOE Patents [OSTI]

A process is described for dissolution of spent high efficiency particulate air (HEPA) filters and then combining the complexed filter solution with other radioactive wastes prior to calcining the mixed and blended waste feed. The process is an alternate to a prior method of acid leaching the spent filters which is an inefficient method of treating spent HEPA filters for disposal. 4 figures.

Brewer, K.N.; Murphy, J.A.

1994-02-22T23:59:59.000Z

439

Hepa filter dissolution process  

DOE Patents [OSTI]

A process for dissolution of spent high efficiency particulate air (HEPA) filters and then combining the complexed filter solution with other radioactive wastes prior to calcining the mixed and blended waste feed. The process is an alternate to a prior method of acid leaching the spent filters which is an inefficient method of treating spent HEPA filters for disposal.

Brewer, Ken N. (Arco, ID); Murphy, James A. (Idaho Falls, ID)

1994-01-01T23:59:59.000Z

440

Reducing the consumption of anthraquinone disulfonate in stretford solutions  

SciTech Connect (OSTI)

A process for treating a hydrogen sulfide-containing hydrogenated claus process tail gas to convert the hydrogen sulfide to elemental sulfur in which said gas is contacted with an aqueous alkaline solution containing a water-soluble metal vanadate, a water-soluble anthraquinone disulfonate, and a watersoluble, inorganic fluoride, borate, or phosphate complexing agent to yield an effluent gas to reduced sulfur content. The solution is thereafter regenerated by contact with an oxygencontaining gas, elemental sulfur is recovered from the solution, and the regenerated solution is recycled to the gas-contacting step. The complexing agent contained in the solution reduces the chemical consumption of the anthraquinone disulfonate.

Fenton, D.M.; Vaell, R.P.

1982-02-16T23:59:59.000Z

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

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

442

Method for regeneration of electroless nickel plating solution  

SciTech Connect (OSTI)

An electroless nickel(EN)/hypophosphite plating bath is provided employing acetic acid/acetate as a buffer and which is, as a result, capable of perpetual regeneration while avoiding the production of hazardous waste. A regeneration process is provided to process the spent EN plating bath solution. A concentrated starter and replenishment solution is provided for ease of operation of the plating bath. The regeneration process employs a chelating ion exchange system to remove nickel cations from spent EN plating solution. Phosphites are then removed from the solution by precipitation. The nickel cations are removed from the ion exchange system by elution with hypophosphorous acid and the nickel concentration of the eluate adjusted by addition of nickel salt. The treated solution and adjusted eluate are combined, stabilizer added, and the volume of resulting solution reduced by evaporation to form the bath starter and replenishing solution.

Eisenmann, Erhard T. (5423 Vista Sandia, NE., Albuquerque, NM 87111)

1997-01-01T23:59:59.000Z

443

Method for regeneration of electroless nickel plating solution  

SciTech Connect (OSTI)

An electroless nickel(EN)/hypophosphite plating bath is provided employing acetic acid/acetate as a buffer and which is, as a result, capable of perpetual regeneration while avoiding the production of hazardous waste. A regeneration process is provided to process the spent EN plating bath solution. A concentrated starter and replenishment solution is provided for ease of operation of the plating bath. The regeneration process employs a chelating ion exchange system to remove nickel cations from spent EN plating solution. Phosphites are then removed from the solution by precipitation. The nickel cations are removed from the ion exchange system by elution with hypophosphorus acid and the nickel concentration of the eluate adjusted by addition of nickel salt. The treated solution and adjusted eluate are combined, stabilizer added, and the volume of resulting solution reduced by evaporation to form the bath starter and replenishing solution. 1 fig.

Eisenmann, E.T.

1997-03-11T23:59:59.000Z

444

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

445

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

446

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

447

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

448

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

449

Method for preparing salt solutions having desired properties  

DOE Patents [OSTI]

The specification discloses a method for preparing salt solutions which exhibit desired thermodynamic properties. The method enables prediction of the value of the thermodynamic properties for single and multiple salt solutions over a wide range of conditions from activity data and constants which are independent of concentration and temperature. A particular application of the invention is in the control of salt solutions in a process to provide a salt solution which exhibits the desired properties.

Ally, Moonis R. (Oak Ridge, TN); Braunstein, Jerry (Clinton, TN)

1994-01-01T23:59:59.000Z

450

Improved method for extracting lanthanides and actinides from acid solutions  

DOE Patents [OSTI]

A process for the recovery of actinide and lanthanide values from aqueous acidic solutions uses a new series of neutral bi-functional extractants, the alkyl(phenyl)-N,N-dialkylcarbamoylmethylphosphine oxides. The process is suitable for the separation of actinide and lanthanide values from fission product values found together in high-level nuclear reprocessing waste solutions.

Horwitz, E.P.; Kalina, D.G.; Kaplan, L.; Mason, G.W.

1983-07-26T23:59:59.000Z

451

Method for cleaning solution used in nuclear fuel reprocessing  

DOE Patents [OSTI]

Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-n-butyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.

Tallent, O.K.; Crouse, D.J.; Mailen, J.C.

1980-12-17T23:59:59.000Z

452

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

453

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

454

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

455

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

456

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

457

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

458

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

459

Selected methods for the numerical solution of polynomial equations  

E-Print Network [OSTI]

, BZBLXOGBAKH, VZI I APPENDIX ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1. Program Listings and. Data Used . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 29 ~ ~ ~ ~ ~ ~ ~ 3O 31 2. Results of the Method of Newton. 3. Results of the Pseudo-gradient Method. Results of the Method of Ward Z... + iy and i =~1. 1 Newton's Method. P(x + iy) = U(x, y) + iV(x, y) is used. in this approach. Note that U(x, y' ) + iV(x, y ) = 0 if and only if P(z ) = 0, where z = x + iy . 3h the iterative process, 1st U be used to denote the value of (h) U(x, y...

Winkler, Anthony Jerry

1962-01-01T23:59:59.000Z

460

Commercial Lighting Solutions Webtool Peer Review Report, Office Solutions  

SciTech Connect (OSTI)

The Commercial Lighting Solutions (CLS) project directly supports the U.S. Department of Energys Commercial Building Energy Alliance efforts to design high performance buildings. CLS creates energy efficient best practice lighting designs for widespread use, and they are made available to users via an interactive webtool that both educates and guides the end user through the application of the Lighting Solutions. This report summarizes the peer review of the CLS webtool for offices. The methodology for the peer review process included data collection (stakeholder input), analysis of the comments, and organization of the input into categories for prioritization of the comments against a set of criteria. Based on this process, recommendations were developed for the release of version 2.0 of the webtool at the Lightfair conference in Las Vegas in May 2010. The report provides a list of the top ten most significant and relevant improvements that will be made within the webtool for version 2.0 as well as appendices containing the comments and short-term priorities in additional detail. Peer review comments that are considered high priority by the reviewers and the CLS team but cannot be completed for Version 2.0 are listed as long-term recommendations.

Beeson, Tracy A.; Jones, Carol C.

2010-02-01T23:59:59.000Z

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

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

462

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.

463

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...

464

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

465

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

466

Gas treating process and composition  

SciTech Connect (OSTI)

This patent describes a process for the removal of H/sub 2/S from a sour gaseous stream. The process consists of: (a) contacting the sour gaseous stream in a contacting zone with an aqueous reaction solution, at a temperature not greater than about 160{sup 0}C, the reaction solution comprising an effective amount of vanadium V-containing ions to oxidize H/sub 2/S to elemental sulfur and being substantially free of anthraquinone disulfonate, and producing a sweet gas stream and an aqueous solution having a pH of 8-11 and containing sulfur and vanadium IV-containing ions, the reaction solution further comprising an amount of phosphate ions sufficient to provide a molar ratio of phosphate ions to vanadium IV-containing ions produced in solution of at least 0.1; (b) removing sulfur from the aqueous solution, producing an aqueous solution having reduced sulfur content; (c) regenerating aqueous solution having reduced sulfur content in a regenerating zone and producing regenerated reactant in the solution; and (d) returning regenerated solution from step (c) to the contacting zone for use as aqueous reaction solution therein.

Byers, D.L.

1989-06-20T23:59:59.000Z

467

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

468

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

469

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.

470

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

471

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

472

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

473

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

474

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

475

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

476

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

477

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

478

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

479

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.

480

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

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481

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

482

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

483

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"

484

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

485

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.

486

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

487

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

488

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

489

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

490

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

491

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

492

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

493

The ITER Project: International Collaboration to Demonstrate Nuclear Fusion  

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

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

494

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

495

Bayesian soft X-ray tomography using non-stationary Gaussian Processes  

SciTech Connect (OSTI)

In this study, a Bayesian based non-stationary Gaussian Process (GP) method for the inference of soft X-ray emissivity distribution along with its associated uncertainties has been developed. For the investigation of equilibrium condition and fast magnetohydrodynamic behaviors in nuclear fusion plasmas, it is of importance to infer, especially in the plasma center, spatially resolved soft X-ray profiles from a limited number of noisy line integral measurements. For this ill-posed inversion problem, Bayesian probability theory can provide a posterior probability distribution over all possible solutions under given model assumptions. Specifically, the use of a non-stationary GP to model the emission allows the model to adapt to the varying length scales of the underlying diffusion process. In contrast to other conventional methods, the prior regularization is realized in a probability form which enhances the capability of uncertainty analysis, in consequence, scientists who concern the reliability of their results will benefit from it. Under the assumption of normally distributed noise, the posterior distribution evaluated at a discrete number of points becomes a multivariate normal distribution whose mean and covariance are analytically available, making inversions and calculation of uncertainty fast. Additionally, the hyper-parameters embedded in the model assumption can be optimized through a Bayesian Occam's Razor formalism and thereby automatically adjust the model complexity. This method is shown to produce convincing reconstructions and good agreements with independently calculated results from the Maximum Entropy and Equilibrium-Based Iterative Tomography Algorithm methods.

Li, Dong; Svensson, J.; Thomsen, H.; Werner, A.; Wolf, R. [Max Planck Institute for Plasma Physics, Teilinstitut, D-17491 Greifswald (Germany)] [Max Planck Institute for Plasma Physics, Teilinstitut, D-17491 Greifswald (Germany); Medina, F. [Asociacin EURATOM-CIEMAT, Madrid (Spain)] [Asociacin EURATOM-CIEMAT, Madrid (Spain)

2013-08-15T23:59:59.000Z

496

Process for purifying molybdenum  

SciTech Connect (OSTI)

This patent describes a process for purifying molybdenum containing arsenic and phosphorus. The process comprising: adding to an acidic slurry of molybdenum trioxide, a source of magnesium ions in a solid form, with the amount of magnesium and the magnesium ion concentration in the subsequently formed ammonium molybdate solution being sufficient to subsequently form insoluble compounds containing greater than about 80% by weight of the arsenic and greater than about 80% by weight of the phosphorus, and ammonia in an amount sufficient to subsequently dissolve the molybdenum and subsequently form the insoluble compounds, with the source of magnesium ions being added prior to the addition of the ammonia; digesting the resulting ammoniated slurry at a temperature sufficient to dissolve the molybdenum and form an ammonium molybdate solution while the pH is maintained at from bout 9 to about 10 to form a solid containing the insoluble compounds; and separating the solid from the ammonium molybdate solution.

Cheresnowsky, J.

1989-12-05T23:59:59.000Z

497

Actinide recovery process  

DOE Patents [OSTI]

Process for the removal of plutonium polymer and ionic actinides from aqueous solutions by absorption onto a solid extractant loaded on a solid inert support such as polystyrenedivinylbenzene. The absorbed actinides can then be recovered by incineration, by stripping with organic solvents, or by acid digestion. Preferred solid extractants are trioctylphosphine oxide and octylphenyl-N,N-diisobutylcarbamoylmethylphosphine oxide and the like.

Muscatello, Anthony C. (Arvada, CO); Navratil, James D. (Arvada, CO); Saba, Mark T. (Arvada, CO)

1987-07-28T23:59:59.000Z

498

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

499

Using performance assessment for radioactive waste disposal decision making -- implementation of the methodology into the third performance assessment iteration of the Greater Confinement Disposal site  

SciTech Connect (OSTI)

The US Department of Energy is responsible for the disposal of a variety of radioactive wastes. Some of these wastes are prohibited from shallow land burial and also do not meet the waste acceptance criteria for proposed waste repositories at the Waste Isolation Pilot Plant (WIPP) and Yucca Mountain. These have been termed ``special-case`` waste and require an alternative disposal method. From 1984 to 1989, the Department of Energy disposed of a small quantity of special-case transuranic wastes at the Greater Confinement Disposal (GCD) site at the Nevada Test Site. In this paper, an iterative performance assessment is demonstrated as a useful decision making tool in the overall compliance assessment process for waste disposal. The GCD site has been used as the real-site implementation and test of the performance assessment approach. Through the first two performance assessment iterations for the GCD site, and the transition into the third, we demonstrate how the performance assessment methodology uses probabilistic risk concepts to guide affective decisions about site characterization activities and how it can be used as a powerful tool in bringing compliance decisions to closure.

Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States); Baer, T.A. [GRAM, Inc., Albuquerque, NM (United States)

1993-12-31T23:59:59.000Z

500

Process for strontium-82 separation  

DOE Patents [OSTI]

A process for selective separation of strontium-82 and strontium-85 from proton irradiated molybdenum targets comprises dissolving the molybdenum target in a hydrogen peroxide solution to form a first solution containing ions selected from a group consisting of molybdenum, niobium, technetium, selenium, vanadium, arsenic, germanium, zirconium, rubidium, zinc, beryllium, cobalt, iron, manganese, chromium, strontium, and yttrium; passing the solution through a first cationic resin whereby ions selected from a group consisting of zinc, beryllium, cobalt, iron, manganese, chromium, strontium, yttrium a portion of zirconium and a portion of rubidium are selectively absorbed by the first resin; contacting the first resin with an acid solution to strip and remove the absorbed ions from the first cationic exchange resin to form a second solution; evaporating the second solution for a time sufficient to remove substantially all of the acid and water from the solution whereby a residue remains; dissolving the residue in a dilute acid to form a third solution; passing the third solution through a second cationic resin whereby the ions are absorbed by the second resin; contacting the second resin with a dilute sulfuric acid solution whereby the absorbed ions selected from the group consisting of rubidium, zinc, beryllium, cobalt, iron, manganese, chromium and zirconium are selectively removed from the second resin; and contacting the second resin with a dilute acid solution whereby the absorbed strontium ions are selectively removed.

Heaton, Richard C. (Los Alamos, NM); Jamriska, Sr., David J. (Los Alamos, NM); Taylor, Wayne A. (Los Alamos, NM)

1992-01-01T23:59:59.000Z