Sample records for integrated iterative solution

  1. Iterated integrals of superconnections

    E-Print Network [OSTI]

    Igusa, Kiyoshi

    2009-01-01T23:59:59.000Z

    Starting with a Z-graded superconnection on a graded vector bundle over a smooth manifold M, we show how Chen's iterated integration of such a superconnection over smooth simplices in M gives an A-infinity functor if and only if the superconnection is flat. If the graded bundle is trivial, this gives a twisting cochain. Very similar results were obtained by K.T. Chen using similar methods. This paper is intended to explain this from scratch beginning with the definition and basic properties of a connection and ending with an exposition of Chen's "formal connections" and a brief discussion of how this is related to higher Reidemeister torsion.

  2. Iterative solutions of simultaneous equations

    E-Print Network [OSTI]

    Laycock, Guyron Brantley

    1962-01-01T23:59:59.000Z

    ITERATIVE SOLUTIONS OP SIKJLTANEOUS EQUATIONS G~cn Hrantlep I aycock Approved. as to style snd, content by& (Chairman of Committee) E. c. (Head. of Department August 1/62 ACKNOWLEDGEMENT The author wishes to thank Dr. Hi A. Luther for his time sn4.... . . . ~ ~ . . ~ III. JACOBI AND 6AUSS-SEIDEL METHODS I V ~ C ONCLUS I GN ~ ~ ~ a ~ ~ ~ t ~ ~ ~ ~ a ~ 1 ~ ~ ~ ~ ~ ~ 9 ~ . ~ 18 V BIBLIOGRAPHY ~ ~ ~ o ~ ~ t ~ ~ ~ ~ 1 ~ ~ ~ VI ~ APPENDIX ~ ~ o ~ ~ e ~ o ~ ~ o o ~ ~ ~ . 22 Px'ogl am Lisliiixlgs...

  3. ITERATED INTEGRALS OF SUPERCONNECTIONS KIYOSHI IGUSA

    E-Print Network [OSTI]

    Igusa, Kiyoshi

    ITERATED INTEGRALS OF SUPERCONNECTIONS KIYOSHI IGUSA Abstract. Iterated integration of a connection gives the holonomy or parallel transport of the connection. Iterated integration of a superconnection gives something else which we call a "superconnection parallel transport." We ask under what conditions

  4. ITERATED INTEGRALS OF SUPERCONNECTIONS KIYOSHI IGUSA

    E-Print Network [OSTI]

    Igusa, Kiyoshi

    ITERATED INTEGRALS OF SUPERCONNECTIONS KIYOSHI IGUSA Abstract. Starting with a Z-graded superconnection on a graded vector bun- dle over a smooth manifold M, we show how Chen's iterated integration of such a superconnection over smooth simplices in M gives an A functor if and only if the superconnection is flat

  5. ITERATED INTEGRALS OF SUPERCONNECTIONS 0902a KIYOSHI IGUSA

    E-Print Network [OSTI]

    Igusa, Kiyoshi

    ITERATED INTEGRALS OF SUPERCONNECTIONS 0902a KIYOSHI IGUSA Abstract. Iterated integration of a superconnection gives something else which we call a "superconnection parallel transport." We ask under what the superconnection parallel transports give homotopies and higher homotopies of these chain maps. This happens

  6. Iterative algorithm for the volume integral method for magnetostatics problems

    SciTech Connect (OSTI)

    Pasciak, J.E.

    1980-11-01T23:59:59.000Z

    Volume integral methods for solving nonlinear magnetostatics problems are considered in this paper. The integral method is discretized by a Galerkin technique. Estimates are given which show that the linearized problems are well conditioned and hence easily solved using iterative techniques. Comparisons of iterative algorithms with the elimination method of GFUN3D shows that the iterative method gives an order of magnitude improvement in computational time as well as memory requirements for large problems. Computational experiments for a test problem as well as a double layer dipole magnet are given. Error estimates for the linearized problem are also derived.

  7. From Use Cases of the Joint European Torus towards Integrated Commissioning Requirements of the ITER Tokamak

    E-Print Network [OSTI]

    From Use Cases of the Joint European Torus towards Integrated Commissioning Requirements of the ITER Tokamak

  8. Improved parallel solution techniques for the integral transport matrix method

    SciTech Connect (OSTI)

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

    2010-11-23T23:59:59.000Z

    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.

  9. Error Control of Iterative Linear Solvers for Integrated Groundwater Models

    E-Print Network [OSTI]

    Bai, Zhaojun

    gradient method or Generalized Minimum RESidual (GMRES) method, is how to choose the residual tolerance for integrated groundwater models, which are implicitly coupled to another model, such as surface water models the correspondence between the residual error in the preconditioned linear system and the solution error. Using

  10. ITER

    SciTech Connect (OSTI)

    Cowley, Steve

    2005-10-10T23:59:59.000Z

    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.

  11. Iterative Solution of Maxwell's Equations for an Induction Motor

    E-Print Network [OSTI]

    Shayak Bhattacharjee

    2014-07-29T23:59:59.000Z

    In this work we use classical electromagnetism to analyse a three-phase induction motor. We first cast the motor as a boundary value problem involving two phenomenological time-constants. These are derived from the widely used equivalent circuit model of the induction motor. We then use an iterative procedure to evaluate these constants and obtain the motor performance equations. Our results depend only on the geometrical parameters of the motor and can be used to derive precise expressions for the excitation frequency and applied voltage needed to extract maximum performance from a given motor at any rotation speed.

  12. Global integration of the Schr\\"odinger equation: a short iterative scheme within the wave operator formalism using discrete Fourier transforms

    E-Print Network [OSTI]

    Leclerc, Arnaud

    2015-01-01T23:59:59.000Z

    A global solution of the Schr\\"odinger equation for explicitly time-dependent Hamiltonians is derived by integrating the non-linear differential equation associated with the time-dependent wave operator. A fast iterative solution method is proposed in which, however, numerous integrals over time have to be evaluated. This internal work is done using a numerical integrator based on Fast Fourier Transforms (FFT). The case of a transition between two potential wells of a model molecule driven by intense laser pulses is used as an illustrative example. This application reveals some interesting features of the integration technique. Each iteration provides a global approximate solution on grid points regularly distributed over the full time propagation interval. Inside the convergence radius, the complete integration is competitive with standard algorithms, especially when high accuracy is required.

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

    E-Print Network [OSTI]

    Mignotte, Max

    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

  14. Solution characters of iterative coupling between energy simulation and CFD programs

    E-Print Network [OSTI]

    Chen, Qingyan "Yan"

    1 Solution characters of iterative coupling between energy simulation and CFD programs Zhiqiang Energy simulation (ES) and computational fluid dynamics (CFD) provide important and complementary information for building energy and indoor environment designs. A coupled ES and CFD simulation can eliminate

  15. Solution characters of iterative coupling between energy simulation and CFD programs

    E-Print Network [OSTI]

    Zhai, John Z.

    States, building services consume more than one third of the primary energy consumption and twoSolution characters of iterative coupling between energy simulation and CFD programs Zhiqiang Zhaia Massachusetts Avenue, Cambridge, MA 02139-4307, USA b School of Mechanical Engineering, Purdue University, 1288

  16. Integrated modelling of steady-state scenarios and heating and current drive mixes for ITER

    SciTech Connect (OSTI)

    Murakami, Masanori [ORNL; Park, Jin Myung [ORNL; Giruzzi, G. [CEA, IRFM, France; Garcia, J. [CEA Cadarache, St. Paul lex Durance, France; Bonoli, P. T. [Massachusetts Institute of Technology (MIT); Budny, R. V. [Princeton Plasma Physics Laboratory (PPPL); Doyle, E. J. [University of California, Los Angeles; Fukuyama, A. [Kyoto University, Japan; Ferron, J.R. [General Atomics, San Diego; Hayashi, N. [Japan Atomic Energy Agency (JAEA), Naka; Honda, M. [Japan Atomic Energy Agency (JAEA), Naka; Hubbard, A. [MIT Plasma Science & Fusion Center, Cambridge, MA 02139 USA; Hong, R. M. [General Atomics, San Diego; Ide, S. [Japan Atomic Energy Agency (JAEA), Naka; Imbeaux, F. [CEA Cadarache, St. Paul lex Durance, France; Jaeger, Erwin Frederick [ORNL; Jernigan, Thomas C [ORNL; Luce, T.C. [General Atomics, San Diego; Na, Y S [Seoul National University of Technology, Korea; Oikawa, T. [ITER Organization, Saint Paul Lez Durance, France; Osborne, T.H. [General Atomics, San Diego; Parail, V. [Association EURATOM-CCFE, Abingdon, UK; Polevoi, A. [ITER Organization, Saint Paul Lez Durance, France; Prater, R. [General Atomics; Sips, A C C [Max Planck Institute for Plasma Physics, Garching, Germany; Shafer, M. W. [University of Wisconsin, Madison; Snipes, J. A. [ITER Organization, Cadarache, France; St. John, H. E. [ITER Organization, Saint Paul Lez Durance, France; Snyder, P. B. [General Atomics, San Diego; Voitsekhovitch, I [UKAEA Fusion, Culham UK

    2011-01-01T23:59:59.000Z

    Recent progress on ITER steady-state (SS) scenario modelling by the ITPA-IOS group is reviewed. Code-to-code benchmarks as the IOS group's common activities for the two SS scenarios (weak shear scenario and internal transport barrier scenario) are discussed in terms of transport, kinetic profiles, and heating and current drive (CD) sources using various transport codes. Weak magnetic shear scenarios integrate the plasma core and edge by combining a theory-based transport model (GLF23) with scaled experimental boundary profiles. The edge profiles (at normalized radius rho = 0.8-1.0) are adopted from an edge-localized mode-averaged analysis of a DIII-D ITER demonstration discharge. A fully noninductive SS scenario is achieved with fusion gain Q = 4.3, noninductive fraction f(NI) = 100%, bootstrap current fraction f(BS) = 63% and normalized beta beta(N) = 2.7 at plasma current I(p) = 8MA and toroidal field B(T) = 5.3 T using ITER day-1 heating and CD capability. Substantial uncertainties come from outside the radius of setting the boundary conditions (rho = 0.8). The present simulation assumed that beta(N)(rho) at the top of the pedestal (rho = 0.91) is about 25% above the peeling-ballooning threshold. ITER will have a challenge to achieve the boundary, considering different operating conditions (T(e)/T(i) approximate to 1 and density peaking). Overall, the experimentally scaled edge is an optimistic side of the prediction. A number of SS scenarios with different heating and CD mixes in a wide range of conditions were explored by exploiting the weak-shear steady-state solution procedure with the GLF23 transport model and the scaled experimental edge. The results are also presented in the operation space for DT neutron power versus stationary burn pulse duration with assumed poloidal flux availability at the beginning of stationary burn, indicating that the long pulse operation goal (3000s) at I(p) = 9 MA is possible. Source calculations in these simulations have been revised for electron cyclotron current drive including parallel momentum conservation effects and for neutral beam current drive with finite orbit and magnetic pitch effects.

  17. Progress in the Integrated Simulation of Thermal-Hydraulic Operation of the ITER Magnet System

    E-Print Network [OSTI]

    Bagnasco, M; Bessette, D; Marinucci, C

    2010-01-01T23:59:59.000Z

    A new integrated computer code is being developed for the simulations of the overall behavior of the ITER magnet cryo-system. The existing THEA, FLOWER and POWER codes, assembled as modules of a computational environment (Super-Magnet) have been upgraded to perform global simulations of the cooling circuit for the ITER magnet system. The thermal coupling resulting from the generic geometric configurations has been implemented to realize quasi-three-dimensional simulations of the winding pack. In this paper we present details on the model.

  18. Overlapping local/global iteration framework for whole-core transport solution

    SciTech Connect (OSTI)

    Cho, N. Z.; Yuk, S.; Yoo, H. J.; Yun, S. [Korea Advanced Inst. of Science and Technology KAIST, 291 Daehak-ro, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

    2012-07-01T23:59:59.000Z

    In current practice of reactor design analysis, whole-core diffusion nodal method is used in which nodal parameters are provided by single-assembly lattice physics calculation with net current zero boundary condition. Thus, the whole-core solution is not transport, because the inter-assembly transport effect is not incorporated. In this paper, the overlapping local/global iteration framework is described that removes the limitation of the current method. It consists of two-level iterative computations: half-node overlapping local problems embedded in a global problem. The local problem can employ fine-group deterministic or continuous-energy stochastic (Monte Carlo) transport methods, while the global problem is an equivalent coarse-group transport model based on p-CMFD methodology. The method is tested on several highly heterogeneous multi-slab problems with encouraging results. (authors)

  19. Integrating Variable Renewable Energy: Challenges and Solutions

    SciTech Connect (OSTI)

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

    2013-09-01T23:59:59.000Z

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

  20. "Enhancing iterative solution methods for general FEM computations using rigid body modes."

    E-Print Network [OSTI]

    Vuik, Kees

    Structures Geomechanics Enhancing iterative solvers in Diana June 27, 2014 5 #12;Finite elements applications Structures Geomechanics Dams and dikes Enhancing iterative solvers in Diana June 27, 2014 5 #12;Finite elements applications Structures Geomechanics Dams and dikes Tunneling Enhancing iterative solvers in Diana

  1. Guide to Cement-Based Integrated Pavement Solutions

    E-Print Network [OSTI]

    Guide to Cement-Based Integrated Pavement Solutions August 2011 #12;Cement-Based Integrated Pavement Solutions Heavy Industrial Airports Highways Country Roads Arterials Commercial Commercial Residential Recreation LAND USE CEMENT-BASED INTEGRATED PAVEMENT SOLUTIONS 1 2 3 4 5 6 7 8

  2. Remote power -- Integrated, customer oriented solutions

    SciTech Connect (OSTI)

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

    1994-12-31T23:59:59.000Z

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

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

    E-Print Network [OSTI]

    Commer, M.

    2012-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    1996-12-31T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

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

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

    E-Print Network [OSTI]

    Iftikhar Ali; Bilal Chanane; Nadeem A. Malik

    2014-07-31T23:59:59.000Z

    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.

  7. Twin-Screw Extruder and Pellet Accelerator Integration Developments for ITER

    SciTech Connect (OSTI)

    Meitner, Steven J [ORNL; Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Fehling, Dan T [ORNL; Foust, Charles R [ORNL; McGill, James M [ORNL; Rasmussen, David A [ORNL; Maruyama, So [ITER Organization, Cadarache, France

    2011-01-01T23:59:59.000Z

    The ITER pellet injection system consisting of a twinscrew frozen hydrogen isotope extruder, coupled to a combination solenoid actuated pellet cutter and pneumatic pellet accelerator, is under development at the Oak Ridge National Laboratory. A prototype extruder has been built to produce a continuous solid deuterium extrusion and will be integrated with a secondary section, where pellets are cut, chambered, and launched with a single-stage pneumatic accelerator into the plasma through a guide tube. This integrated pellet injection system is designed to provide 5 mm fueling pellets, injected at a rate up to 10 Hz, or 3 mm edge localized mode (ELM) triggering pellets, injected at higher rates up to 20 Hz. The pellet cutter, chamber mechanism, and the solenoid operated pneumatic valve for the accelerator are optimized to provide pellet velocities between 200-300 m/s to ensure high pellet survivability while traversing the inner wall fueling guide tubes, and outer wall ELMpacing guide tubes. This paper outlines the current twin-screwextruder design, pellet accelerator design, and the integrationrequired for both fueling and ELM pacing pellets.

  8. The IBM Health Integration Framework: Accelerating solutions for smarter healthcare

    E-Print Network [OSTI]

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

  9. Review of ITER Physics Issues and Possible Approaches to their Solution

    E-Print Network [OSTI]

    to Reversed Shear qMIN 1.0 - 1. 8 >2.0 qEDGE 3 3.5-5 4-5 Sawteeth Present, Sought Absent, 3/2 mode t p * t R t W G=H89PN/q95 2=0.5-0.4, q95~3.4 G=0.75 Weak Shear High & AT (self regulating) regime > R to ITER ITER Baseline- Conventional Sawtoothing, Elming H-mode Conservative route to 500 MW, 400

  10. IEEE TRANSACTIONS ON COMPUTER-AIDED DESIGN OF INTEGRATED CIRCUITS AND SYSTEMS, VOL. 25, NO. 6, JUNE 2006 1087 SILCA: SPICE-Accurate Iterative Linear-Centric

    E-Print Network [OSTI]

    Shi, C.-J. Richard

    --A new circuit analysis method, named SPICE- accurate iterative linear-centric analysis (SILCA 2006 1087 SILCA: SPICE-Accurate Iterative Linear-Centric Analysis for Efficient Time-Domain Simulation integrated (VLSI) circuits with strong parasitic couplings. SILCA consists of two key linear-centric tech

  11. Integrating Variable Renewable Energy: Challenges and Solutions

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn Other NewsSpin andInterim DataCooling -INTEGRATING

  12. ILP and Iterative LP Solutions for Peak and Average Power Optimization in HLS

    E-Print Network [OSTI]

    Ramanujam, J. "Ram"

    . Ramanujam2 1 Electrical Engineering Dept., Assiut University, Egypt 2 Electrical and Computer Engineering as average power and energy consumptions. As the design problem becomes large, exact solution takes-flow graph (DFG) executes. We define Scheduling for Low Power and Energy (SLoPE) in high-level synthesis

  13. Complete integration of the aligned Newman Tamburino Maxwell solutions

    E-Print Network [OSTI]

    Liselotte De Groote; Norbert Van den Bergh

    2008-04-07T23:59:59.000Z

    We investigate the cylindrical class of Newman Tamburino equations in the presence of an aligned Maxwell field. After obtaining a complete integration of the field equations we look at the possible vacuum limits and we examine the symmetries of the general solution.

  14. Integrating Mobile Agent Technology into an e-Marketplace Solution

    E-Print Network [OSTI]

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

  15. 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

  16. Please cite this article in press as: A. Martin, et al., ITER blanket manifold system: Integration, assembly and maintenance, Fusion Eng. Des. (2014), http://dx.doi.org/10.1016/j.fusengdes.2014.04.013

    E-Print Network [OSTI]

    Raffray, A. Ren

    2014-01-01T23:59:59.000Z

    , assembly and maintenance, Fusion Eng. Des. (2014), http://dx.doi.org/10.1016/j.fusengdes.2014.elsevier.com/locate/fusengdes ITER blanket manifold system: Integration, assembly and maintenance Alex Martina, , George Dellopoulosb failure would prevent ITER operation a maintenance strategy has been planned. 2014 Elsevier B.V. All

  17. Local and global solutions of well-posed integrated Cauchy problems

    E-Print Network [OSTI]

    Miana, Pedro J.

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

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

    SciTech Connect (OSTI)

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

    2014-01-15T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Koteras, J.R.

    1993-07-01T23:59:59.000Z

    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.

  20. Bifurcations of traveling wave solutions for an integrable equation

    SciTech Connect (OSTI)

    Li Jibin [Department of Mathematics, Zhejiang Normal University, Jinhua, Zhejiang 321004 (China) and Kunming University of Science and Technology, Kunming, Yunnan 650093 (China); Qiao Zhijun [Department of Mathematics, University of Texas Pan-American, 1201 West University Drive, Edinburg, Texas 78541 (United States)

    2010-04-15T23:59:59.000Z

    This paper deals with the following equation m{sub t}=(1/2)(1/m{sup k}){sub xxx}-(1/2)(1/m{sup k}){sub x}, which is proposed by Z. J. Qiao [J. Math. Phys. 48, 082701 (2007)] and Qiao and Liu [Chaos, Solitons Fractals 41, 587 (2009)]. By adopting the phase analysis method of planar dynamical systems and the theory of the singular traveling wave systems to the traveling wave solutions of the equation, it is shown that for different k, the equation may have infinitely many solitary wave solutions, periodic wave solutions, kink/antikink wave solutions, cusped solitary wave solutions, and breaking loop solutions. We discuss in a detail the cases of k=-2,-(1/2),(1/2),2, and parametric representations of all possible bounded traveling wave solutions are given in the different (c,g)-parameter regions.

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

    E-Print Network [OSTI]

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

  2. Dual Integrated Appliances as an Energy and Safety Solution for...

    Energy Savers [EERE]

    Building America Technology Solutions for New and Existing Homes: Performance of a Heat Pump Water Heater in the Hot-Humid Climate, Windermere, Florida (Fact Sheet) Space...

  3. Linear scaling solution of the time-dependent self-consistent-field equations with quasi-independent Rayleigh quotient iteration

    SciTech Connect (OSTI)

    Challacombe, Matt [Los Alamos National Laboratory

    2009-01-01T23:59:59.000Z

    An algorithm for solution of the Time-Dependent Self-Consistent-Field (TD-SCF) equations is developed, based on dual solution channels for non-linear optimization of the Tsiper functional [J.Phys.B, 34 L401 (2001)]. This formulation poses the TD-SCF problem as two Rayleigh quotients, coupled weakly through biorthogonality. Convergence rates for the Random Phase Approximation (RPA) are found to be equivalent to the Tamm-Dancoff approximation (TDA). Moreover, the variational nature of the quotient is robust to approximation errors, allowing linear scaling solution to the bulk limit of the RPA matrix-eigenvalue and exchange operator problem for molecular wires with extended conjugation, including polyphenylene vinylene and the (4,3) nanotube.

  4. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelliUS ITER Major

  5. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelliUS ITER

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

    E-Print Network [OSTI]

    Scherrer, Bruno

    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

  7. Numerical solutions to integral equations of the Fredholm type

    E-Print Network [OSTI]

    Pullin, John Henry

    1966-01-01T23:59:59.000Z

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

  8. Wavelet-based integral representation for solutions of the wave equation

    E-Print Network [OSTI]

    M. V. Perel; M. S. Sidorenko

    2008-09-12T23:59:59.000Z

    An integral representation of solutions of the wave equation as a superposition of other solutions of this equation is built. The solutions from a wide class can be used as building blocks for the representation. Considerations are based on mathematical techniques of continuous wavelet analysis. The formulas obtained are justified from the point of view of distribution theory. A comparison of the results with those by G. Kaiser is carried out. Methods of obtaining physical wavelets are discussed.

  9. Way Beyond Widgets: Delivering Integrated Lighting Design in Actionable Solutions

    SciTech Connect (OSTI)

    Myer, Michael; Richman, Eric E.; Jones, Carol C.

    2008-08-17T23:59:59.000Z

    Previously, energy-efficiency strategies for commercial spaces have focused on using efficient equipment without providing specific detailed instructions. Designs by experts in their fields are an energy-efficiency product in its own right. A new national program has developed interactive application-specific lighting designs for widespread use in four major commercial sectors. This paper will describe the technical basis for the solutions, energy efficiency and cost-savings methodology, and installations and measurement/verification to-date. Lighting designs have been developed for five types of retail stores (big box, small box, grocery, specialty market, and pharmacy) and are planned for the office, healthcare, and education sectors as well. Nationally known sustainable lighting designers developed the designs using high-performance commercially available products, daylighting, and lighting controls. Input and peer review was received by stakeholders, including manufacturers, architects, utilities, energy-efficiency program sponsors (EEPS), and end-users (i.e., retailers). An interactive web tool delivers the lighting solutions and analyzes anticipated energy savings using project-specific inputs. The lighting solutions were analyzed against a reference building using the space-by-space method as allowed in the Energy Standard for Buildings Except Low-Rise Residential Buildings (ASHRAE 2004) co-sponsored by the American Society of Heating, Refrigeration, and Air Conditioning Engineers (ASHRAE) and the Illuminating Engineering Society of North America (IESNA). The results showed that the design vignettes ranged from a 9% to 28% reduction in the allowed lighting power density. Detailed control strategies are offered to further reduce the actual kilowatt-hour power consumption. When used together, the lighting design vignettes and control strategies show a modeled decrease in energy consumption (kWh) by 33% to 50% below the baseline design.

  10. Integrated Dynamic Electron Solutions, Inc. | Department of Energy

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov.Energy02.pdf7 OPAMEnergy Innovation inInspectionIntegrated Dynamic Electron

  11. Numerical solutions to integral equations of the Fredholm type

    E-Print Network [OSTI]

    Pullin, John Henry

    1966-01-01T23:59:59.000Z

    %Y ) RETURN AK~SIN(X+Y) RETURN AK~EXP( ABS(X Y)) RETURN AK~(SIN&X-Y })442/&X-Y) RETURN END PROGRAM TO CALCULATE SHIFTED CHEBYSHEV POLYNOMIALS SUBROUT I NE CHES &Me X ~ TM ) DI MENS I QN TM (2D ) IF(M 1)2&3 ~ 2 2 TM(1) = I ~ IF(M 2)4e5 ~ 4 4 TM&2... FUNCTION AK(XeY AN) GO TO &)o2o3)sN 1 AK&I ~ 3 ' +X+Y RETURN 2 AK~SIN&X+Y) RETURN 3 AK~X+Y RETVRN END C THIS FUNCTION CONTAINS THE MAIN FUNCTION OF THE INTEGRAL C EQUATIONS IF IT IS ZERO WE HAVE A HOMOGENEOVS EQUATIONS FUNCTION FOFX(N ~ X) GO...

  12. A time integration scheme for stress - temperature dependent viscoelastic behaviors of isotropic materials

    E-Print Network [OSTI]

    Khan, Kamran-Ahmed

    2009-05-15T23:59:59.000Z

    solutions within a general displacement based FE structural analyses for small deformations and uncoupled thermo-mechanical problems. A previously developed recursive-iterative algorithm for a stress-dependent hereditary integral model which was developed...

  13. Iterative solutions of simultaneous equations

    E-Print Network [OSTI]

    Laycock, Guyron Brantley

    1962-01-01T23:59:59.000Z

    ( )] where 0 gi 1, 1 i - n. Recall that in the e~an- sion of a determinant by cofactors according to the elements of a given col&3an, ii its elements are replaced by the corresponding elements of another column, the result is sero ~ &hns f 121"11 + f 22F...) Rote that ll( 1''' ' ) 1 ( 1' '''n) enl(C] ) ~ ~ 1Q ) e (+] 0 ~ ~ )~n) j9 exi st s ~ appr oaches I (Ail~ ~ "tR ) then one, the Jacobian is non-zero at (+ 1, . . . , () ), It is clear that the product P+ J3 if (wi, . . . , x ) is "near enough...

  14. The first and second monotone integral principles for fundamental solutions of uniformly elliptic equations

    E-Print Network [OSTI]

    Xiao, Jie

    2009-01-01T23:59:59.000Z

    Two optimal monotone integral principles (equivalently for the Laplacian, two sharp iso-weighted-volume inequalities) are established through extending the first and second integral bounds of H. Weinberger for the Green functions (i.e., fundamental solutions) of uniformly elliptic equations in terms of the layer-cake formula, a one-dimensional monotone integral principle, and the isoperimetric and Jenson's inequalities with sharp constants. Surprisingly, a special setting of the first principle can be used to not only verify the low-dimensional P\\'olya conjecture for the principal eigenvalue of the Laplacian but also to characterize the geometry of the Nash inequality for a strong uniform elliptic equation.

  15. US 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItem NotEnergy, science,SpeedingWu,IntelligenceYou are ABOUT US ITER | WHY FUSION? |

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

    E-Print Network [OSTI]

    Liu, Yijun

    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

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

    E-Print Network [OSTI]

    Hoepman, Jaap-Henk

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

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

    E-Print Network [OSTI]

    Hoepman, Jaap-Henk

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

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

    E-Print Network [OSTI]

    Dong Jianping

    2013-01-14T23:59:59.000Z

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

  20. Solutions of TEAM problems 13 and 20 using a volume integral formulation

    SciTech Connect (OSTI)

    Kettunen, L.; Forsman, K. [Tampere Univ. of Technology (Finland); Levine, D.; Gropp, W. [Argonne National Lab., IL (United States)

    1994-10-01T23:59:59.000Z

    Solutions for TEAM benchmark problems 13 and 20, obtained with an h-type volume integral formulation, are presented. Results computed with an increasing number of unknowns are shown in order to study the convergence of the numerical calculations. Some theoretical questions and aspects of parallelism are also highlighted.

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

    E-Print Network [OSTI]

    McNutt, Wayne Eugene

    1952-01-01T23:59:59.000Z

    'IKE FOURIER IRTEORAL AHB ITS USE IN IEE SOLUTION OF GERTAIN BOUNDARY VALVE PRObLERS A Thesis Wayne Eugene McRutt Approved as to style and content by& E. c. a P51RQ 0 e ead of partment or tudent Advisor Kay 1958 TME FOURIRR INTEGRAL...

  2. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Departmentcontributes 75%TokamakITER Magnet

  3. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Departmentcontributes 75%TokamakITER

  4. US ITER | Jobs

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER Quality Assurance,

  5. US ITER | Jobs

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER Quality Assurance,Kevin

  6. US ITER | Jobs

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER Quality

  7. US ITER | Jobs

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelli Kizer

  8. US ITER | Jobs

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelli KizerNicolai

  9. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelli

  10. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelliUS ITERtest

  11. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelliUS ITERtestNew

  12. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelliUS

  13. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER QualityKelliUSLife-size

  14. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITER

  15. What is 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron SpinPrincetonUsing Maps1DOETHEWeeklyTRUDoesmo·men·tumSciTechinITER?

  16. SOLUTIONS

    E-Print Network [OSTI]

    2012-07-04T23:59:59.000Z

    MA 162 - Quiz 5 (20 minutes). SOLUTIONS. The solutions I present are not necessarily the only solutions. As long as you give a correct method of solving a...

  17. Integrability and Boundedness of Local Solutions to Singular and Degenerate Quasilinear Parabolic

    E-Print Network [OSTI]

    O'Leary, Michael

    Equations Mike O'Leary Abstract Integral and supremum estimates are proven for local solutions of de- 1 ) + c5|u|-1 + 2(x, t), AMS Classifications: 35K65, 35B45 Mike O'Leary, Department of Mathematics, Towson University, Towson, MD 21252 moleary@towson.edu #12;2 M. O'Leary (H5) 1 L p p-1 ,loc(T ), (H6) o

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

    SciTech Connect (OSTI)

    Matthew Bruff; Ned Godshall; Karen Evans

    2011-04-30T23:59:59.000Z

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

  19. US 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Departmentcontributes 75% of2014 EIA120

  20. US ITER Moving Forward

    ScienceCinema (OSTI)

    US ITER / ORNL

    2012-03-16T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Not Available

    2012-01-01T23:59:59.000Z

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

  2. 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

  3. Solution

    E-Print Network [OSTI]

    2011-09-09T23:59:59.000Z

    Solution: We're looking for the presale cost of the shirt, so let x be the price of ... The sale price is $10 and we've called the presale price x, so we need to solve.

  4. Solutions

    E-Print Network [OSTI]

    2010-11-29T23:59:59.000Z

    (d) Show that Hlder's inequality is also true for the improper integrals described ... substitution u = up > 0 and v = vq > 0 the inequality that we want to show is...

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

    SciTech Connect (OSTI)

    Botelho, L.C.L.

    1985-03-15T23:59:59.000Z

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

  6. Integration

    E-Print Network [OSTI]

    Koschorke, Albrecht; Musanovic, Emina

    2013-01-01T23:59:59.000Z

    Integration By Albrecht Koschorkeby Emina Musanovic [Integration (from Lat. integrare, toa social unity. Social integration is distinct from systemic

  7. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Departmentcontributes 75% of2014 EIA120ITER

  8. A Short-Distance Integral-Balance Solution to a Strong Subdiffusion Equation: A Weak Power-Law Profile

    E-Print Network [OSTI]

    Jordan Hristov

    2010-12-12T23:59:59.000Z

    The work presents an integral solution of the time-fractional subdiffusion through a preliminary defined profile with unknown coefficients and the concept of penetration layer well known from the heat diffusion The profile satisfies the boundary conditions imposed at the boundary of the boundary layer in a weak form that allows its coefficients to be expressed through the boundary layer depth as unique parameter describing the profile. The technique is demonstrated by a solution of a time fractional subdiffusion equation in rectilinear 1-D conditions

  9. ITER convertible blanket evaluation

    SciTech Connect (OSTI)

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

    1995-09-01T23:59:59.000Z

    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.

  10. 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

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

    E-Print Network [OSTI]

    Pleune, Thomas Todd, 1974-

    1999-01-01T23:59:59.000Z

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

  12. EU signs ITER deal Negotiations on the ITER international nuclear

    E-Print Network [OSTI]

    Korea and the US, the agreement aims to develop a project that will test the feasibility of nuclearEU signs ITER deal Negotiations on the ITER international nuclear fusion project have been on Wednesday reached a final agreement on the ITER project after years of talks. "The completion

  13. Benchmarking ICRF simulations for ITER

    SciTech Connect (OSTI)

    R. V. Budny, L. Berry, R. Bilato, P. Bonoli, M. Brambilla, R.J. Dumont, A. Fukuyama, R. Harvey, E.F. Jaeger, E. Lerche, C.K. Phillips, V. Vdovin, J. Wright, and members of the ITPA-IOS

    2010-09-28T23:59:59.000Z

    Abstract Benchmarking of full-wave solvers for ICRF simulations is performed using plasma profiles and equilibria obtained from integrated self-consistent modeling predictions of four ITER plasmas. One is for a high performance baseline (5.3 T, 15 MA) DT H-mode plasma. The others are for half-field, half-current plasmas of interest for the pre-activation phase with bulk plasma ion species being either hydrogen or He4. The predicted profiles are used by seven groups to predict the ICRF electromagnetic fields and heating profiles. Approximate agreement is achieved for the predicted heating power partitions for the DT and He4 cases. Profiles of the heating powers and electromagnetic fields are compared.

  14. ITER Fusion Energy

    ScienceCinema (OSTI)

    Dr. Norbert Holtkamp

    2010-01-08T23:59:59.000Z

    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.

  15. Regions of influence for two iterative methods

    E-Print Network [OSTI]

    Leifeste, Arlee Ross

    1966-01-01T23:59:59.000Z

    Subject Mathematics REGIONS OF INFLUENCE FOR TWO ITERATIVE METHODS A Thesis By ARLEE ROSS LEIFESTE Approved as to style and content by: (Chairman of Committee) (Head of Department) (Member) (N b )' January 1966 ACKNOWLEDGMENT The author wishes... purpose of the present discussion is to initiate a study of the "regions of influence" of the various solutions of the simul- taneous equations involved. Let the simultaneous functions be denoted and let ( y , y , , y 1 be a point of n...

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

    E-Print Network [OSTI]

    McNutt, Wayne Eugene

    1952-01-01T23:59:59.000Z

    . & . e s, e . . ~ ~ ~ ~ 5 II. Definitions and Stated Theorerns. ~ ~ ~ ~ . ~ ~. . . 3 III. A Proof for the Convergence of the Fourier Integral. 6 IV, Different Forms of the Fourier Integral, . . . . , . 14 V. Fourier and Laplace Transforrnations... & b. 2. xa(a, b) means a & x ~ b. d 3. = is read "is by def1nition". 4. lf +'' kl ) y dy-1 y y+'"+l, 5. L [ f (t) I is read "the Laplace Transform of f (t)". 6. L ( F(s) ) is read "the inverse Laplace Transform of F(s)". Il. IIefinitions...

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

    E-Print Network [OSTI]

    Pike, Ralph W.

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

  18. ITER breeding blanket design

    SciTech Connect (OSTI)

    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

    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.

  19. ITER blanket designs

    SciTech Connect (OSTI)

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

    1994-12-31T23:59:59.000Z

    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.

  20. Neutron cameras for ITER

    SciTech Connect (OSTI)

    Johnson, L.C.; Barnes, C.W.; Batistoni, P. [ITER San Diego Joint Work Site, La Jolla, CA (United States)] [and others

    1998-12-31T23:59:59.000Z

    Neutron cameras with horizontal and vertical views have been designed for ITER, based on systems used on JET and TFTR. The cameras consist of fan-shaped arrays of collimated flight tubes, with suitably chosen detectors situated outside the biological shield. The sight lines view the ITER plasma through slots in the shield blanket and penetrate the vacuum vessel, cryostat, and biological shield through stainless steel windows. This paper analyzes the expected performance of several neutron camera arrangements for ITER. In addition to the reference designs, the authors examine proposed compact cameras, in which neutron fluxes are inferred from {sup 16}N decay gammas in dedicated flowing water loops, and conventional cameras with fewer sight lines and more limited fields of view than in the reference designs. It is shown that the spatial sampling provided by the reference designs is sufficient to satisfy target measurement requirements and that some reduction in field of view may be permissible. The accuracy of measurements with {sup 16}N-based compact cameras is not yet established, and they fail to satisfy requirements for parameter range and time resolution by large margins.

  1. U.S. Plans and Strategy for ITER Blanket Testing

    SciTech Connect (OSTI)

    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

    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.

  2. Information Technology Systems for Fusion Industry and ITER Project

    SciTech Connect (OSTI)

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

    2005-04-15T23:59:59.000Z

    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.

  3. What is ITER

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  4. US ITER | Jobs

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  5. US ITER | About

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  6. US ITER | Media Corner

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  7. US ITER | Media Corner

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  8. US ITER | Media Corner

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  9. US ITER | Media Corner

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  10. US ITER | Media Corner

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  11. US ITER | Media Corner

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  12. US ITER | Media Corner

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  13. US ITER | Media Corner

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  14. US ITER | Media Corner

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  15. US ITER | Media Corner

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

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  16. US ITER | Media Corner

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

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  17. US ITER | Media Corner

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

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  18. Combined Field Integral Equation Based Theory of Characteristic Mode

    E-Print Network [OSTI]

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

    2015-03-04T23:59:59.000Z

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

  19. An exact Lagrangian integral for the Newtonian gravitational field strength

    E-Print Network [OSTI]

    Thomas Buchert

    2006-01-23T23:59:59.000Z

    An exact expression for the gravitational field strength in a self-gravitating dust continuum is derived within the Lagrangian picture of continuum mechanics. From the Euler-Newton system a transport equation for the gravitational field strength is formulated and then integrated along trajectories of continuum elements. The resulting integral solves one of the Lagrangian equations of the corresponding Lagrange-Newton system in general. Relations to known exact solutions without symmetry in Newtonian gravity are discussed. The presented integral may be employed to access the non-perturbative regime of structure formation in Newtonian cosmology, and to apply iterative Lagrangian schemes to solve the Lagrange-Newton system.

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

    E-Print Network [OSTI]

    Graham, Ivan

    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

  1. 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

  2. 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

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

    E-Print Network [OSTI]

    shielding, Tritium containment, vacuum integrity, RH compatibility. #12;A E Costley ITER Diagnostics, 21st distinct measurement systems in total. #12;A E Costley ITER Diagnostics, 21st IAEA 9 of 5 slides HANDLING, Germany THE DESIGN AND IMPLEMENTATIONTHE DESIGN AND IMPLEMENTATION OF DIAGNOSTIC SYSTEMS ON ITEROF

  4. Looking northeast over the ITER construction site

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  5. Bragg x-ray survey spectrometer for ITER

    SciTech Connect (OSTI)

    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

    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.

  6. Project Manager, U.S. ITER INSIDE: ITER Site Progress Washington

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  7. US ITER | About

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  8. US ITER | About

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

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  9. US ITER | About

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

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  10. US ITER | Doing Business

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

    SciTech Connect (OSTI)

    Trcka, Marija; L.M. Hensena, Jan; Wetter, Michael

    2010-06-21T23:59:59.000Z

    Integrated performance simulation of buildings and heating, ventilation and airconditioning (HVAC) systems can help reducing energy consumption and increasing occupant comfort. However, no single building performance simulation (BPS) tool offers suffcient capabilities and flexibilities to analyze integrated building systems and to enable rapid prototyping of innovative building and system technologies. One way to alleviate this problem is to use co-simulation to integrate different BPS tools. Co-simulation approach represents a particular case of simulation scenario where at least two simulators solve coupled differential-algebraic systems of equations and exchange data that couples these equations during the time integration. This article analyzes how co-simulation influences consistency, stability and accuracy of the numerical approximation to the solution. Consistency and zero-stability are studied for a general class of the problem, while a detailed consistency and absolute stability analysis is given for a simple two-body problem. Since the accuracy of the numerical approximation to the solution is reduced in co-simulation, the article concludes by discussing ways for how to improve accuracy.

  12. Multiple solutions of CCD equations for PPP model of benzene

    E-Print Network [OSTI]

    Podeszwa, R; Jankowski, K; Rubiniec, K; Podeszwa, Rafa{\\l}; Stolarczyk, Leszek Z.; Jankowski, Karol; Rubiniec, Krzysztof

    2002-01-01T23:59:59.000Z

    To gain some insight into the structure and physical significance of the multiple solutions to the coupled-cluster doubles (CCD) equations corresponding to the Pariser-Parr-Pople (PPP) model of cyclic polyenes, complete solutions to the CCD equations for the A^{-}_{1g} states of benzene are obtained by means of the homotopy method. By varying the value of the resonance integral beta from -5.0 eV to -0.5 eV, we cover the so-called weakly, moderately, and strongly correlated regimes of the model. For each value of beta 230 CCD solutions are obtained. It turned out, however, that only for a few solutions a correspondence with some physical states can be established. It has also been demonstrated that, unlike for the standard methods of solving CCD equations, some of the multiple solutions to the CCD equations can be attained by means of the iterative process based on Pulay's direct inversion in the iterative subspace (DIIS) approach.

  13. A review of ITER blanket designs

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    2006-07-01T23:59:59.000Z

    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.

  15. ITER | Princeton Plasma Physics Lab

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  16. Travel Requirements - 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin Transition in2,EHSS A-Z Site Map Organization ChartTravelTravel

  17. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Departmentcontributes 75% of2014 EC

  18. US ITER | About

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

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  19. US ITER | About

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

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  20. US ITER | About

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

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  1. US ITER | About

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

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  2. US ITER | About

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

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  3. US ITER | About

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  4. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | DepartmentcontributesShort-Term Accommodations

  5. US ITER | About

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

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  6. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | DepartmentcontributesShort-TermFood Food Oak

  7. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | DepartmentcontributesShort-TermFood Food

  8. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | DepartmentcontributesShort-TermFood FoodMaps

  9. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | DepartmentcontributesShort-TermFood

  10. US ITER | About

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

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  11. US ITER | Doing Business

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

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  12. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITERUT Magnet Lab Advances US

  13. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram |Frank Casella US ITERUT Magnet Lab Advances

  14. Coaxial recess integration of InGaAs edge emitting laser diodes with waveguides on silicon substrates : a complete solution to laser integration on ICs

    E-Print Network [OSTI]

    Famenini, Shaya

    2012-01-01T23:59:59.000Z

    In this thesis, the first demonstration of the full integration of 1.55[mu]m InGaAs/InP edge emitting platelet laser diodes with SiON/SiO2 dielectric waveguides on a silicon substrate is presented. Small footprint laser ...

  15. 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

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

    E-Print Network [OSTI]

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

    2014-01-01T23:59:59.000Z

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

  17. Efficient Solution of the Simplified PN Equations

    SciTech Connect (OSTI)

    Hamilton, Steven P [ORNL; Evans, Thomas M [ORNL

    2015-01-01T23:59:59.000Z

    In this paper we show new solver strategies for the multigroup SPN equations for nuclear reactor analysis. By forming the complete matrix over space, moments, and energy a robust set of solution strategies may be applied. Power iteration, shifted power iteration, Rayleigh quotient iteration, Arnoldi's method, and a generalized Davidson method, each using algebraic and physics-based multigrid preconditioners, have been compared on C5G7 MOX test problem as well as an operational PWR model. Our results show that the most ecient approach is the generalized Davidson method, that is 30{40 times faster than traditional power iteration and 6{10 times faster than Arnoldi's method.

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

    E-Print Network [OSTI]

    Hampshire, Damian

    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

  19. Iterative modelling, a new approach to the inversion of 1-D seismograms

    E-Print Network [OSTI]

    Raskin, Greg Steven

    1987-01-01T23:59:59.000Z

    by correcting the field trace. The plane wave impulse response is decayed by a factor of E" (which need only be approx- imately correct). This corrected impulse response approximates a point source impulse response but neglects differential decay between... schemes . 12 IV ITERATIVE MODELI. LNG 15 A. An iterative modelling procedure B. The initial model C. Smoothing the solution vector D. Parameter removal E. Residual error analysis as a means of parauseter addition . F. Reset ting the parameter...

  20. 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)

    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

    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.

  1. Overview of Recent Developments in Pellet Injection for ITER

    SciTech Connect (OSTI)

    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

    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.

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

    E-Print Network [OSTI]

    Kent, University of

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

  3. A weighted iterative algorithm for neuromagnetic imaging

    SciTech Connect (OSTI)

    Gorodnitsky, I. (Los Alamos National Lab., NM (United States) California Univ., San Diego, La Jolla, CA (United States)); George, J.S.; Schlitt, H.A.; Lewis, P.S. (Los Alamos National Lab., NM (United States))

    1992-01-01T23:59:59.000Z

    The goal of neuromagnetic source reconstruction is high resolution 3-D mapping of the current distribution within the brain. However, the neuromagnetic inverse problem is ill-posed and typically underdetermined. The Moore-Penrose pseudoinverse provides a linear algebraic inverse calculation that simultaneously minimizes chisquare and the Euclidean norm of the component currents. Such minimum norm'' reconstructions tend to produce diffuse and superficial current distributions because voxels nearer the sensor array can account for more power in the data with less current than deeper voxels. We describe an algorithm that overcomes the bias of minimum norm procedures toward superficial solutions by using weights chosen to compensate for the distance dependence of magnetic signal strength. We also apply a Bayesian weighting strategy in an iterative pseudoinverse computation, to address the bias of the linear estimator procedure toward diffuse solutions. This strategy produces a progressively more focal current distribution while accomodating distributed current sources, and appears to effectively reduce the problems associated with the under-determined linear system.

  4. A weighted iterative algorithm for neuromagnetic imaging

    SciTech Connect (OSTI)

    Gorodnitsky, I. [Los Alamos National Lab., NM (United States)]|[California Univ., San Diego, La Jolla, CA (United States); George, J.S.; Schlitt, H.A.; Lewis, P.S. [Los Alamos National Lab., NM (United States)

    1992-09-01T23:59:59.000Z

    The goal of neuromagnetic source reconstruction is high resolution 3-D mapping of the current distribution within the brain. However, the neuromagnetic inverse problem is ill-posed and typically underdetermined. The Moore-Penrose pseudoinverse provides a linear algebraic inverse calculation that simultaneously minimizes chisquare and the Euclidean norm of the component currents. Such ``minimum norm`` reconstructions tend to produce diffuse and superficial current distributions because voxels nearer the sensor array can account for more power in the data with less current than deeper voxels. We describe an algorithm that overcomes the bias of minimum norm procedures toward superficial solutions by using weights chosen to compensate for the distance dependence of magnetic signal strength. We also apply a Bayesian weighting strategy in an iterative pseudoinverse computation, to address the bias of the linear estimator procedure toward diffuse solutions. This strategy produces a progressively more focal current distribution while accomodating distributed current sources, and appears to effectively reduce the problems associated with the under-determined linear system.

  5. Iterative Entanglement Distillation: Approaching full Elimination of Decoherence

    E-Print Network [OSTI]

    Boris Hage; Aiko Samblowski; James DiGuglielmo; Jaromr Fiurek; Roman Schnabel

    2010-07-09T23:59:59.000Z

    The distribution and processing of quantum entanglement form the basis of quantum communication and quantum computing. The realization of the two is difficult because quantum information inherently has a high susceptibility to decoherence, i.e. to uncontrollable information loss to the environment. For entanglement distribution, a proposed solution to this problem is capable of fully eliminating decoherence; namely iterative entanglement distillation. This approach builds on a large number of distillation steps each of which extracts a number of weakly decohered entangled states from a larger number of strongly decohered states. Here, for the first time, we experimentally demonstrate iterative distillation of entanglement. Already distilled entangled states were further improved in a second distillation step and also made available for subsequent steps.Our experiment displays the realization of the building blocks required for an entanglement distillation scheme that can fully eliminate decoherence.

  6. U. S. ITER shield and blanket design activities

    SciTech Connect (OSTI)

    Baker, C.C.

    1989-03-01T23:59:59.000Z

    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/.

  7. Engineering and manufacturing of ITER first mirror mock-ups

    SciTech Connect (OSTI)

    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

    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.

  8. Research at ITER towards DEMO: Specific reactor diagnostic studies to be carried out on ITER

    SciTech Connect (OSTI)

    Krasilnikov, A. V.; Kaschuck, Y. A.; Vershkov, V. A.; Petrov, A. A.; Petrov, V. G.; Tugarinov, S. N. [Institution Project center ITER, Moscow (Russian Federation)

    2014-08-21T23:59:59.000Z

    In ITER diagnostics will operate in the very hard radiation environment of fusion reactor. Extensive technology studies are carried out during development of the ITER diagnostics and procedures of their calibration and remote handling. Results of these studies and practical application of the developed diagnostics on ITER will provide the direct input to DEMO diagnostic development. The list of DEMO measurement requirements and diagnostics will be determined during ITER experiments on the bases of ITER plasma physics results and success of particular diagnostic application in reactor-like ITER plasma. Majority of ITER diagnostic already passed the conceptual design phase and represent the state of the art in fusion plasma diagnostic development. The number of related to DEMO results of ITER diagnostic studies such as design and prototype manufacture of: neutron and ?ray diagnostics, neutral particle analyzers, optical spectroscopy including first mirror protection and cleaning technics, reflectometry, refractometry, tritium retention measurements etc. are discussed.

  9. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC) EnvironmentalGyroSolé(tm)Hydrogen StorageITER

  10. 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

  11. Iterative solution of ordinary differential equations with polynomial coefficients

    E-Print Network [OSTI]

    Forehand, Jimmie Charles Rhea

    1965-01-01T23:59:59.000Z

    + Z b K), (s=2, . . . , r). s ns'n 1 sjj' Given r, the number of 'substitutions" into f, the parameters R, a and s s b are to be determined to obtain an expression for y I which would sj n+1 agree with a Taylor's expansion of y(x ) up to terms... are one-step methods; that is, only the value of y must be known to obtain y from f(x, y). This method n n+1 . 27 consists in setting up y with undetermined parameters as follows: n+1 r n+1 n T s s s=l (1. 1) K =hf(x, y ) 1 n' n s-1 K =hf(x+a h, y...

  12. Stabilized finite element methods with fast iterative solution ...

    E-Print Network [OSTI]

    2003-04-11T23:59:59.000Z

    Computer methods in applied mechanics and engineering. Stabilized finite ... Department of Mathemutics, Purdue Universi@, 1395 Mathematical Science...

  13. Iterative solutions to large sparse finite element equations

    E-Print Network [OSTI]

    Wang, Hongbing

    1995-01-01T23:59:59.000Z

    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...

  14. Iterative Solution of Elliptic Equations with a Small Parameter

    E-Print Network [OSTI]

    Segatti, Antonio

    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

  15. iterative solution of augmented systems arising in interior methods

    E-Print Network [OSTI]

    2005-09-04T23:59:59.000Z

    SE-100 44 Stockholm, Sweden (andersf@kth.se). Research supported by the Swedish Research. Council (VR). Department of Mathematics, University of...

  16. ITER Project Status Fusion Energy Sciences

    E-Print Network [OSTI]

    to capped value) ORNL 100% Tokamak Cooling Water System PPPL 75% Steady State Electrical Network PPPL 14 Project Office April 9, 2014 #12;Major Progress: Construction Site 04/09/14 FESAC/Sauthoff 2 Photo: ITER Organization September 2013 #12;Major Progress: ITER Headquarters Building 04/09/14 FESAC/Sauthoff 3 #12

  17. 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

  18. 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

  19. Iterative Speech Enhancement With Spectral Constraints

    E-Print Network [OSTI]

    Texas at Dallas, University of

    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

  20. 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

  1. Simulations of plasma behavior during pellet injection in ITER

    SciTech Connect (OSTI)

    Klaywittaphat, P., E-mail: thawatchai@siit.tu.ac.th; Onjun, T. [Thammasat University, School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology (Thailand)

    2012-06-15T23:59:59.000Z

    Plasma behavior during pellet injection in ITER is investigated using a 1.5D BALDUR integrated predictive modeling code. In these simulations, the pellet ablation is described using the neutral gas shielding (NGS) model developed by Parks and Turnbull [Phys. Fluids 21, 1735 (1978)]. The NGS pellet ablation model that includes the {nabla}B drift effect is coupled with a plasma core transport model, which is a combination of an MMM95 anomalous transport model and an NCLASS neoclassical transport model. The combination of core transport models, together with pellet model, is used to simulate the time evolution of plasma current, ion and electron temperatures, and density profiles for ITER standard type-I ELMy H-mode discharges during the pellet injection. It is found that the injection of pellet can result in either enhancement or degradation of plasma performance. The {nabla}B drift effect on the pellet deposition is very strong in ITER. The plasma density with high field side pellets, which favorable with the {nabla}B drift effect, is much higher and pellet can penetrate much deeper than that with low field side pellets.

  2. 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...

  3. 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

  4. Project Manager Ned Sauthoff Talks About US 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.70 Hg MercuryProject Final Report:ProjectProjectITER Project

  5. A completely iterative method for the infinite domain electrostatic problem with nonlinear dielectric media

    E-Print Network [OSTI]

    Dayal, Kaushik

    coupling a b s t r a c t We present an iterative method for the solution of the exterior all-space the device over all space, thus leading to an exterior electrostatic problem. In addition to this complexity in revised form 16 June 2011 Accepted 4 July 2011 Available online 20 July 2011 Keywords: Exterior

  6. Damage to nearby divertor components of ITER-like devices during giant ELMs and disruptions

    E-Print Network [OSTI]

    Harilal, S. S.

    Damage to nearby divertor components of ITER-like devices during giant ELMs and disruptions. Fusion 50 (2010) 115004 (7pp) doi:10.1088/0029-5515/50/11/115004 Damage to nearby divertor components. The simulation results of the integrated modelling indicate a significant potential damage of the divertor nearby

  7. ITER UltraScaleScientific Joint Dark Energy Mission ComputingCapability

    E-Print Network [OSTI]

    #12;ITER UltraScaleScientific Joint Dark Energy Mission ComputingCapability Linac Coherent Light eRHIC Fusion Energy Contingency Source Upgrade HFIR Second Cold Source Integrated Beam Experiment IntroductionIntroductionIntroductionIntroductionIntroduction 8 Prioritization Process 9 A Benchmark

  8. 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

  9. ITER Ion Cyclotron Heating and Fueling Systems

    SciTech Connect (OSTI)

    Rasmussen, D.A. [Oak Ridge National Laboratory (United States); Baylor, L.R. [Oak Ridge National Laboratory (United States); Combs, S.K. [Oak Ridge National Laboratory (United States); Fredd, E. [Princeton Plasma Physics Laboratory (United States); Goulding, R.H. [Oak Ridge National Laboratory (United States); Hosea, J. [Princeton Plasma Physics Laboratory (United States); Swain, D.W. [Oak Ridge National Laboratory (United States)

    2005-04-15T23:59:59.000Z

    The ITER burning plasma and advanced operating regimes require robust and reliable heating and current drive and fueling systems. The ITER design documents describe the requirements and reference designs for the ion cyclotron and pellet fueling systems. Development and testing programs are required to optimize, validate and qualify these systems for installation on ITER.The ITER ion cyclotron system offers significant technology challenges. The antenna must operate in a nuclear environment and withstand heat loads and disruption forces beyond present-day designs. It must operate for long pulse lengths and be highly reliable, delivering power to a plasma load with properties that will change throughout the discharge. The ITER ion cyclotron system consists of one eight-strap antenna, eight rf sources (20 MW, 35-65 MHz), associated high-voltage DC power supplies, transmission lines and matching and decoupling components.The ITER fueling system consists of a gas injection system and multiple pellet injectors for edge fueling and deep core fueling. Pellet injection will be the primary ITER fuel delivery system. The fueling requirements will require significant extensions in pellet injector pulse length ({approx}3000 s), throughput (400 torr-L/s,) and reliability. The proposed design is based on a centrifuge accelerator fed by a continuous screw extruder. Inner wall pellet injection with the use of curved guide tubes will be utilized for deep fueling.

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

    E-Print Network [OSTI]

    Trcka, Marija

    2010-01-01T23:59:59.000Z

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

  11. Optical dumps for H-alpha and visible spectroscopy in ITER

    SciTech Connect (OSTI)

    Andreenko, E. N.; Alekseev, A. G.; Gorshkov, A. V.; Orlovskiy, I. I. [NRC Kurchatov Institute, 123182 Moscow (Russian Federation)

    2014-08-21T23:59:59.000Z

    High-reflective Beryllium cover of ITER first wall (R?3060%) causes remarkable increase of divertor stray light component (DSL). Optical dumps are well-known solution for DSL attenuation. In this work few types of optical dumps have been examined both by modeling and experimental studies. Taking into account the limitations, induced by ITER first wall design, OD optimized design has been proposed which could decrease divertor stray light component by 10..100 times depending on incidence angle of light.

  12. 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

  13. Value iteration for (switched) homogeneous systems

    E-Print Network [OSTI]

    Dahleh, Munther A.

    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 ...

  14. Michel Claessens michel.claessens@iter.org

    E-Print Network [OSTI]

    on the manufacturing of critical components, were among the important issues discussed at the eighth meeting. Photos of the Council Meeting can be found at: http://www.iter.org/gallery/pr_2011_06_ic8 Additional

  15. ITERATIVE METHODS FOR NEUTRON TRANSPORT EIGENVALUE PROBLEMS

    E-Print Network [OSTI]

    Graham, Ivan

    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

  16. EQUILIBRIUM RECONSTRUCTION ITERATION FLOW-CHART

    E-Print Network [OSTI]

    EQUILIBRIUM RECONSTRUCTION ITERATION FLOW-CHART SUME AND 0 n GET 1 AND C0 j GET J1 AND 1 n GET 2 the total stored (kinetic + magnetic) energy density #12;TYPICAL FIELD CONFIGURATIONS acuum Field Low Beta

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

    SciTech Connect (OSTI)

    Zhai, Y

    2014-03-03T23:59:59.000Z

    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.

  18. ITER MHD stability analysis. Final report

    SciTech Connect (OSTI)

    Turnbull, A.D.

    1996-05-01T23:59:59.000Z

    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.

  19. Hyperplane arrangements, local system homology and iterated integrals

    E-Print Network [OSTI]

    Kohno, Toshitake

    . The purpose of this article is to review developments concern- ing the homology of a local system0 simplex spanned by the vertices vjk , 0 k p. This simplex defined for Fj0

  20. Augmented Iterations Integrating Neural Activity in Evolutionary Computation for Design

    E-Print Network [OSTI]

    Boyer, Edmond

    , 2011) or the expansion of domotic technologies and human-machine cooperations by controlling external

  1. 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

  2. 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

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

    SciTech Connect (OSTI)

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

    1995-08-01T23:59:59.000Z

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

  4. Parallel computation of multigroup reactivity coefficient using iterative method

    SciTech Connect (OSTI)

    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

    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.

  5. Photo: US ITER/ORNL INSIDE: ITER Site Progress

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Science (SC)IntegratedSpeeding accessPeptoid NanosheetsStudying the Rhizosphere Photo of[FeFe]of

  6. US Contributions to ITER Project

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron Spin TransitionProgram | Departmentcontributes 75% of

  7. AIR: fused Analytical and Iterative Reconstruction method for computed tomography

    E-Print Network [OSTI]

    Yang, Liu; Qi, Sharon X; Gao, Hao

    2013-01-01T23:59:59.000Z

    Purpose: CT image reconstruction techniques have two major categories: analytical reconstruction (AR) method and iterative reconstruction (IR) method. AR reconstructs images through analytical formulas, such as filtered backprojection (FBP) in 2D and Feldkamp-Davis-Kress (FDK) method in 3D, which can be either mathematically exact or approximate. On the other hand, IR is often based on the discrete forward model of X-ray transform and formulated as a minimization problem with some appropriate image regularization method, so that the reconstructed image corresponds to the minimizer of the optimization problem. This work is to investigate the fused analytical and iterative reconstruction (AIR) method. Methods: Based on IR with L1-type image regularization, AIR is formulated with a AR-specific preconditioner in the data fidelity term, which results in the minimal change of the solution algorithm that replaces the adjoint X-ray transform by the filtered X-ray transform. As a proof-of-concept 2D example of AIR, FB...

  8. Integrated Technology Deployment

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  9. US solid breeder blanket design for ITER

    SciTech Connect (OSTI)

    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

    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.

  10. Solid breeder blanket option for the ITER conceptual design

    SciTech Connect (OSTI)

    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

    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.

  11. Plan and Strategy for ITER Blanket Testing in Japan

    SciTech Connect (OSTI)

    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

    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.

  12. Technical Proposal Disclosure Policy - 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over Our InstagramStructureProposedPAGESafety Tag:8,, 20153 To synchronize the

  13. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible forPortsmouth/Paducah47,193.7 348,016.0 336,514.0 350,723.3fact-sheets enroadmappingiter

  14. Development of a Tritium Extruder for ITER Pellet Injection

    SciTech Connect (OSTI)

    M.J. Gouge; P.W. Fisher

    1998-09-01T23:59:59.000Z

    As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development program, Oak Ridge National Laboratory (ORNL) has fabricated a pellet injection system to test the mechanical and thermal properties of extruded tritium. Hydrogenic pellets will be used in ITER to sustain the fusion power in the plasma core and may be crucial in reducing first-wall tritium inventories by a process of "isotopic fueling" in which tritium-rich pellets fuel the burning plasma core and deuterium gas fuels the edge. This repeating single-stage pneumatic pellet injector, called the Tritium-Proof-of-Principle Phase II (TPOP-II) Pellet Injector, has a piston-driven mechanical extruder and is designed to extrude and accelerate hydrogenic pellets sized for the ITER device. The TPOP-II program has the following development goals: evaluate the feasibility of extruding tritium and deuterium-tritium (D-T) mixtures for use in future pellet injection systems; determine the mechanical and thermal properties of tritium and D-T extrusions; integrate, test, and evaluate the extruder in a repeating, single-stage light gas gun that is sized for the ITER application (pellet diameter -7 to 8 mm); evaluate options for recycling propellant and extruder exhaust gas; and evaluate operability and reliability of ITER prototypical fueling systems in an environment of significant tritium inventory that requires secondary and room containment systems. In tests with deuterium feed at ORNL, up to 13 pellets per extrusion have been extruded at rates up to 1 Hz and accelerated to speeds of 1.0 to 1.1 km/s, using hydrogen propellant gas at a supply pressure of 65 bar. Initially, deuterium pellets 7.5 mm in diameter and 11 mm in length were produced-the largest cryogenic pellets produced by the fusion program to date. These pellets represent about a 10% density perturbation to ITER. Subsequently, the extruder nozzle was modified to produce pellets that are almost 7.5-mm right circular cylinders. Tritium and D-T pellets have been produced in experiments at the Los Alamos National Laboratory Tritium Systems Test Assembly. About 38 g of tritium have been utilized in the experiment. The tritium was received in eight batches, six from product containers and two from the Isotope Separation System. Two types of runs were made: those in which the material was only extruded and those in which pellets were produced and fired with deuterium propellant. A total of 36 TZ runs and 28 D-T runs have been made. A total of 36 pure tritium runs and 28 D-T mixture runs were made. Extrusion experiments indicate that both T2 and D-T will require higher extrusion forces than D2 by about a factor of two.

  15. An iterative technique for solving equations of statistical equilibrium

    E-Print Network [OSTI]

    L. B. Lucy

    2001-03-21T23:59:59.000Z

    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.

  16. Symbolic Opportunistic Policy Iteration for Factored-Action MDPs

    E-Print Network [OSTI]

    Iteration (OPI), which is a novel convergent algorithm lying between VI and MPI, that applies policy to converge. This new algorithm, Opportunistic Policy Iteration (OPI), constrains a select subset

  17. Benchmarking ICRF Full-wave Solvers for ITER

    SciTech Connect (OSTI)

    R. V. Budny, L. Berry, R. Bilato, P. Bonoli, M. Brambilla, R. J. Dumont, A. Fukuyama, R. Harvey, E. F. Jaeger, K. Indireshkumar, E. Lerche, D. McCune, C. K. Phillips, V. Vdovin, J. Wright, and members of the ITPA-IOS

    2011-01-06T23:59:59.000Z

    Abstract Benchmarking of full-wave solvers for ICRF simulations is performed using plasma profiles and equilibria obtained from integrated self-consistent modeling predictions of four ITER plasmas. One is for a high performance baseline (5.3 T, 15 MA) DT H-mode. The others are for half-field, half-current plasmas of interest for the pre-activation phase with bulk plasma ion species being either hydrogen or He4. The predicted profiles are used by six full-wave solver groups to simulate the ICRF electromagnetic fields and heating, and by three of these groups to simulate the current-drive. Approximate agreement is achieved for the predicted heating power for the DT and He4 cases. Factor of two disagreements are found for the cases with second harmonic He3 heating in bulk H cases. Approximate agreement is achieved simulating the ICRF current drive.

  18. Chirac calls ITER essential for planet's future

    E-Print Network [OSTI]

    fusion reactor. "Today, our energy consumption has put us in danger. It's mainly based on oil, gasChirac calls ITER essential for planet's future CADARACHE, France, June 30 (AFP) - French President in southern France as vital to the planet's future, praising European solidarity in sealing the deal. "This

  19. 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

  20. Using Iterative Compilation to Reduce Energy Consumption

    E-Print Network [OSTI]

    Gheorghita, Valentin

    or to re- duce power. Most transformations require loop re- structuring. Although a large number.v.gheorghita,h.corporaal,a.a.basten}@tue.nl Keywords: Iterative Compilation, Program Optimization, Energy Consumption, Program Transformation. Abstract. This is emphasized by new demands added to compilers, like reducing static code size, energy consumption or power

  1. AN ALGEBRAIC DESCRIPTION OF ITERATIVE DECODING SCHEMES

    E-Print Network [OSTI]

    Soljanin, Emina

    AN ALGEBRAIC DESCRIPTION OF ITERATIVE DECODING SCHEMES ELKE OFFER AND EMINA SOLJANIN Abstract University of Technology, D- 80290 Munich, Germany, elke@lnt.e-technik.tu-muenchen.de Mathematical Sciences Research Center, Bell Labs, Lucent Technologies, Murray Hill, NJ 07974, USA. emina@lucent.com 1 #12;2 E

  2. Neil Calder neil.calder@iter.org

    E-Print Network [OSTI]

    on the ITER site, financed by the European Union. Approval was also given to for a Test Blanket Module Program to demonstrate the scientific and technological feasibility of fusion power for energy purposes. Fusion plant that is safe and reliable, environmentally responsible and economically viable, with abundant

  3. CONTRACTIVITY IN TURBO ITERATIONS Phillip A. Regalia

    E-Print Network [OSTI]

    Regalia, Phillip A.

    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

  4. US ITER Project Status Fusion Power Associates

    E-Print Network [OSTI]

    .5 Gigajoule stored energy capacity) Central Solenoid The Heartbeat of ITER 12/10/13 FPA/Sauthoff 1,000 tonne assembled and is being prepared for testing Photo: Seco Warwick (wiebodzin. Poland) 11 #12;Toroidal Field Conductor Specs: 18 toroidal field coils are designed to have Total magnetic energy of 41 gigajoules

  5. Michel Claessens michel.claessens@iter.org

    E-Print Network [OSTI]

    . This two-day meeting brought together senior representatives from all seven ITER Members--China-of-a-kind global collaboration. Europe will contribute almost half of the costs of its construction, while the other six Members to this joint international venture (China, India, Japan, the Republic of Korea

  6. Joint News Release ELEVENTH ITER NEGOTIATIONS MEETING

    E-Print Network [OSTI]

    of Science and Technology of China Department of International Co-operation Luo Delong luodl@mail.most.govJoint News Release ELEVENTH ITER NEGOTIATIONS MEETING CHENGDU , CHINA, 24OCTOBER 2005 Delegations from China, European Union, Japan, the Republic of Korea, the Russian Federation and the United States

  7. Application of Asymptotic Iteration Method (AIM) to a Deformed Well Problem

    E-Print Network [OSTI]

    Hakan Ciftci; H. Fatih Kisoglu

    2015-06-23T23:59:59.000Z

    We have used Asymptotic Iteration Method (AIM) for obtaining the eigenvalues of the Schrodinger's equation for a deformed well problem representing trigonometric functions. By solving the problem, we have found that the Schrodinger's equation for the considered potential has quasi-exact solutions. Additionally, we have also calculated the perturbation expansion of energy eigenvalues and found very simple analytical expression of the energy. Finally, we have considered more general cases and obtained energy eigenvalues for arbitrary potential parameters.

  8. Dale M. Meade MFE Plenary Session on ITER Costs

    E-Print Network [OSTI]

    Dale M. Meade MFE Plenary Session on ITER Costs 2002 Fusion Summer Study Snowmass, CO July 9, 2002 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

  9. ITER HEAT REMOVAL SYSTEM SYSTEM & PROCESS CONTROL DESIGN

    E-Print Network [OSTI]

    Raffray, A. René

    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

  10. On the Logic of Iterated Non-prioritised Richard Booth

    E-Print Network [OSTI]

    Booth, Richard

    , 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

  11. A Conditional Logic for Iterated Belief Revision Laura Giordano

    E-Print Network [OSTI]

    Giordano, Laura

    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

  12. Budget Planning Meeting FY 2007 Status of ITER Negotiations

    E-Print Network [OSTI]

    Budget Planning Meeting FY 2007 Status of ITER Negotiations Michael Roberts, Director ITER Preparations of $5M Using FY05 $5M to continue to get ready for MIE project Maintaining U.S. visiting experts Further establishing U.S. ITER Project Office Fulfilling DOE project management requirements

  13. Iterative Water-filling for Gaussian Vector Multiple Access Channels

    E-Print Network [OSTI]

    Li, Tiffany Jing

    Iterative Water-filling for Gaussian Vector Multiple Access Channels W. Yu, W. Rhee, S. Boyd, and J. Cioffi Zhenlei Shen Lehigh University March 29, 2005 Zhenlei Shen (Lehigh) Iterative Water-filling for Gaussian Vector Multiple Access ChannelsMarch 29, 2005 1 / 13 #12;1 Quick Review 2 Iterative Water

  14. ELM heat flux in the ITER divertor

    SciTech Connect (OSTI)

    Leonard, A.W.; Osborne, T.H. [General Atomics, San Diego, CA (United States); Hermann, A.; Suttrop, W. [Max Planck Inst. fuer Plasmaphysics (Germany); Itami, K. [Japan Atomic Energy Research Inst. (Japan); Lingertat, J. [JET Joint Undertaking, Abingdon (United Kingdom); Loarte, A. [Next European Torus, Garching (Germany)

    1998-07-01T23:59:59.000Z

    Edge-Localized-Modes (ELMs) have the potential to produce unacceptable levels of erosion of the ITER divertor. Ablation of the carbon divertor target will occur if the surface temperature rises above about 2,500 C. Because a large number of ELMs, {ge}1000, are expected in each discharge it is important that the surface temperature rise due to an individual ELM remain below this threshold. Calculations that have been carried out for the ITER carbon divertor target indicate ablation will occur for ELM energy {ge}0.5MJ/m{sup 2} if it is deposited in 0.1 ms, or 1.2 MJ/m{sup 2} if the deposition time is 1.0 ms. Since {Delta}T{proportional_to}Q{Delta}t{sup {minus}1/2}, an ablation threshold can be estimated at Q{Delta}t{sup {minus}1/2}{approx}45 MJm{sup {minus}2} s{sup {minus}1/2} where Q is the divertor ELM energy density in J-m{sup {minus}2} and {Delta}t is the time in seconds for that deposition. If a significant fraction of ELMs exceed this threshold then an unacceptable level of erosion may take place. The ablation parameter in ITER can be determined by scaling four factors from present experiments: the ELM energy loss from the core plasma, the fraction of ELM energy deposited on the divertor target, the area of the ELM profile onto the target, and the time for the ELM deposition. ELM data from JET, ASDEX-Upgrade, JT-60U, DIII-D and Compass-D have been assembled by the ITER Divertor Modeling and Database expert group into a database for the purpose of predicting these factors for ELMs in the ITER divertor.

  15. 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

  16. Approaches to confined alpha diagnostics on ITER

    SciTech Connect (OSTI)

    Fisher, R.K. [General Atomics, PO Box 85608, San Diego, California 92186-5608 (United States)

    2004-10-01T23:59:59.000Z

    Three approaches to obtain information on the confined fast alphas in the International Thermonuclear Experimental Reactor (ITER) are proposed. The first technique measures the energetic charge exchange (CX) neutrals that result from the alpha collision-induced knock-on fuel ion tails undergoing electron capture on the MeV D neutral beams planned for heating and current drive. The second technique measures the energetic knock-on neutron tail due to alphas using the lengths of the proton recoil tracks produced by neutron collisions in nuclear emulsions. The range of the 14 to 20 MeV recoil protons increases by {approx}140 {mu}m per MeV. The third approach would measure the CX helium neutrals resulting from confined alphas capturing two electrons in the ablation cloud surrounding a dense gas jet that has been proposed for disruption mitigation in ITER.

  17. Thermomechanical analysis of the ITER breeding blanket

    SciTech Connect (OSTI)

    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

    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.

  18. Main challenges for ITER optical diagnostics

    SciTech Connect (OSTI)

    Vukolov, K. Yu.; Orlovskiy, I. I.; Alekseev, A. G.; Borisov, A. A.; Andreenko, E. N.; Kukushkin, A. B.; Lisitsa, V. S.; Neverov, V. S. [Tokamak Physics Institute, NRC Kurchatov Institute, 123182 Moscow (Russian Federation)

    2014-08-21T23:59:59.000Z

    The review is made of the problems of ITER optical diagnostics. Most of these problems will be related to the intensive neutron radiation from hot plasma. At a high level of radiation loads the most types of materials gradually change their properties. This effect is most critical for optical diagnostics because of degradation of optical glasses and mirrors. The degradation of mirrors, that collect the light from plasma, basically will be induced by impurity deposition and (or) sputtering by charge exchange atoms. Main attention is paid to the search of glasses for vacuum windows and achromatic lens which are stable under ITER irradiation conditions. The last results of irradiation tests in nuclear reactor of candidate silica glasses KU-1, KS-4V and TF 200 are presented. An additional problem is discussed that deals with the stray light produced by multiple reflections from the first wall of the intense light emitted in the divertor plasma.

  19. Development of structural design criteria for ITER.

    SciTech Connect (OSTI)

    Majumdar, S.

    1998-06-22T23:59:59.000Z

    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.

  20. Disruptions, loads, and dynamic response of ITER

    SciTech Connect (OSTI)

    Nelson, B.; Riemer, B.; Sayer, R.; Strickler, D. [Oak Ridge National Lab., TN (United States); Barabaschi, P.; Ioki, K.; Johnson, G.; Shimizu, K.; Williamson, D. [Max-Planck-Institut fuer Plasmaphysik, Garching (Germany). International Thermonuclear Experimental Reactor (ITER) Team

    1995-12-31T23:59:59.000Z

    Plasma disruptions and the resulting electromagnetic loads are critical to the design of the vacuum vessel and in-vessel components of the International Thermonuclear Experimental Reactor (ITER). This paper describes the status of plasma disruption simulations and related analysis, including the dynamic response of the vacuum vessel and in-vessel components, stresses and deflections in the vacuum vessel, and reaction loads in the support structures.

  1. US Demo test blankets in ITER

    SciTech Connect (OSTI)

    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

    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.

  2. Automated structure solution with the PHENIX suite

    SciTech Connect (OSTI)

    Terwilliger, Thomas C [Los Alamos National Laboratory; Zwart, Peter H [LBNL; Afonine, Pavel V [LBNL; Grosse - Kunstleve, Ralf W [LBNL

    2008-01-01T23:59:59.000Z

    Significant time and effort are often required to solve and complete a macromolecular crystal structure. The development of automated computational methods for the analysis, solution, and completion of crystallographic structures has the potential to produce minimally biased models in a short time without the need for manual intervention. The PHENIX software suite is a highly automated system for macromolecular structure determination that can rapidly arrive at an initial partial model of a structure without significant human intervention, given moderate resolution, and good quality data. This achievement has been made possible by the development of new algorithms for structure determination, maximum-likelihood molecular replacement (PHASER), heavy-atom search (HySS), template- and pattern-based automated model-building (RESOLVE, TEXTAL), automated macromolecular refinement (phenix. refine), and iterative model-building, density modification and refinement that can operate at moderate resolution (RESOLVE, AutoBuild). These algorithms are based on a highly integrated and comprehensive set of crystallographic libraries that have been built and made available to the community. The algorithms are tightly linked and made easily accessible to users through the PHENIX Wizards and the PHENIX GUI.

  3. Automated Structure Solution with the PHENIX Suite

    SciTech Connect (OSTI)

    Zwart, Peter H.; Zwart, Peter H.; Afonine, Pavel; Grosse-Kunstleve, Ralf W.; Hung, Li-Wei; Ioerger, Tom R.; McCoy, A.J.; McKee, Eric; Moriarty, Nigel; Read, Randy J.; Sacchettini, James C.; Sauter, Nicholas K.; Storoni, L.C.; Terwilliger, Tomas C.; Adams, Paul D.

    2008-06-09T23:59:59.000Z

    Significant time and effort are often required to solve and complete a macromolecular crystal structure. The development of automated computational methods for the analysis, solution and completion of crystallographic structures has the potential to produce minimally biased models in a short time without the need for manual intervention. The PHENIX software suite is a highly automated system for macromolecular structure determination that can rapidly arrive at an initial partial model of a structure without significant human intervention, given moderate resolution and good quality data. This achievement has been made possible by the development of new algorithms for structure determination, maximum-likelihood molecular replacement (PHASER), heavy-atom search (HySS), template and pattern-based automated model-building (RESOLVE, TEXTAL), automated macromolecular refinement (phenix.refine), and iterative model-building, density modification and refinement that can operate at moderate resolution (RESOLVE, AutoBuild). These algorithms are based on a highly integrated and comprehensive set of crystallographic libraries that have been built and made available to the community. The algorithms are tightly linked and made easily accessible to users through the PHENIX Wizards and the PHENIX GUI.

  4. Code of a Tokamak Fusion Energy Facility ITER

    SciTech Connect (OSTI)

    Yasuhide Asada [Central Research Institute of Electric Power Industry - CRIEPI (Japan); Kenzo Miya [Keio University (Japan); Kazuhiko Hada; Eisuke Tada [Japan Atomic Energy Research Institute (Japan)

    2002-07-01T23:59:59.000Z

    The technical structural code for ITER (International Thermonuclear Experimental Fusion Reactor) and, as more generic applications, for D-T burning fusion power facilities (hereafter, Fusion Code) should be innovative because of their quite different features of safety and mechanical components from nuclear fission reactors, and the necessity of introducing several new fabrication and examination technologies. Introduction of such newly developed technologies as inspection-free automatic welding into the Fusion Code is rationalized by a pilot application of a new code concept of {sup s}ystem-based code for integrity{sup .} The code concept means an integration of element technical items necessary for construction, operation and maintenance of mechanical components of fusion power facilities into a single system to attain an optimization of the total margin of these components. Unique and innovative items of the Fusion Code are typically as follows: - Use of non-metals; - Cryogenic application; - New design margins on allowable stresses, and other new design rules; - Use of inspection-free automatic welding, and other newly developed fabrication technologies; - Graded approach of quality assurance standard to cover radiological safety-system components as well as non-safety-system components; - Consideration on replacement components. (authors)

  5. An algorithm for enforcement of contact constraints in quasistatic applications using matrix-free solution algorithms

    SciTech Connect (OSTI)

    Heinstein, M.W. [Sandia National Labs., Albuquerque, NM (United States). Engineering Mechanics and Material Modeling Dept.

    1997-10-01T23:59:59.000Z

    A contact enforcement algorithm has been developed for matrix-free quasistatic finite element techniques. Matrix-free (iterative) solution algorithms such as nonlinear Conjugate Gradients (CG) and Dynamic Relaxation (DR) are distinctive in that the number of iterations required for convergence is typically of the same order as the number of degrees of freedom of the model. From iteration to iteration the contact normal and tangential forces vary significantly making contact constraint satisfaction tenuous. Furthermore, global determination and enforcement of the contact constraints every iteration could be questioned on the grounds of efficiency. This work addresses this situation by introducing an intermediate iteration for treating the active gap constraint and at the same time exactly (kinematically) enforcing the linearized gap rate constraint for both frictionless and frictional response.

  6. Iterative-build OMIT maps: map improvement by iterative model building and refinement without model bias

    SciTech Connect (OSTI)

    Terwilliger, Thomas C., E-mail: terwilliger@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Grosse-Kunstleve, Ralf W.; Afonine, Pavel V.; Moriarty, Nigel W.; Adams, Paul D. [Lawrence Berkeley National Laboratory, One Cyclotron Road, Building 64R0121, Berkeley, CA 94720 (United States); Read, Randy J. [Department of Haematology, University of Cambridge, Cambridge CB2 0XY (United Kingdom); Zwart, Peter H. [Lawrence Berkeley National Laboratory, One Cyclotron Road, Building 64R0121, Berkeley, CA 94720 (United States); Hung, Li-Wei [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

    2008-05-01T23:59:59.000Z

    An OMIT procedure is presented that has the benefits of iterative model building density modification and refinement yet is essentially unbiased by the atomic model that is built. A procedure for carrying out iterative model building, density modification and refinement is presented in which the density in an OMIT region is essentially unbiased by an atomic model. Density from a set of overlapping OMIT regions can be combined to create a composite iterative-build OMIT map that is everywhere unbiased by an atomic model but also everywhere benefiting from the model-based information present elsewhere in the unit cell. The procedure may have applications in the validation of specific features in atomic models as well as in overall model validation. The procedure is demonstrated with a molecular-replacement structure and with an experimentally phased structure and a variation on the method is demonstrated by removing model bias from a structure from the Protein Data Bank.

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

    SciTech Connect (OSTI)

    Baker, C.C.

    1988-08-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2007-04-30T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1990-09-01T23:59:59.000Z

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

  10. p-points in iterated forcing extensions

    E-Print Network [OSTI]

    Roitman, Judith A.

    1978-05-03T23:59:59.000Z

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

  11. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del SolStrengthening aTurbulence may bedieselsummer gasoline price0 UPCNational ITER

  12. 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

  13. Linearized Constraints in the Connection Representation: Hamilton-Jacobi Solution

    E-Print Network [OSTI]

    J. N. Goldberg; D. C. Robinson

    1994-05-11T23:59:59.000Z

    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.

  14. Diverse Power Iteration Embeddings and Its Applications

    SciTech Connect (OSTI)

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

    2014-12-14T23:59:59.000Z

    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.

  15. Twisted symmetries and integrable systems

    E-Print Network [OSTI]

    G. Cicogna; G. Gaeta

    2010-02-07T23:59:59.000Z

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

  16. 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. Pacher, G. Pacher, R. Tivey, M. Sugihara, JCT and HTs #12;San Diego; 01.05.2001 Power and Particle to pump #12;San Diego; 01.05.2001 Power and Particle Exhaust in ITER Slide 3 by G. Janeschitz. ITER

  17. Properties of Iterated Multiple Belief Revision Dongmo Zhang

    E-Print Network [OSTI]

    Zhang, Dongmo

    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

  18. Iterated Belief Revision and Conditional Logic Laura Giordano

    E-Print Network [OSTI]

    Torino, Università di

    /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

  19. BLIND ITERATIVE RESTORATION OF IMAGES WITH SPATIALLY-VARYING BLUR

    E-Print Network [OSTI]

    Bardsley, John

    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

  20. Japan, EU reach basic agreement over ITER The Yomiuri Shimbun

    E-Print Network [OSTI]

    Japan, EU reach basic agreement over ITER The Yomiuri Shimbun The government and the European Union to the unsuccessful candidate country. Japan and France, the EU's candidate, have been bidding to host the facility bidder's country. The ITER project participants--Japan, China, the EU, Russia, South Korea and the United

  1. Proving termination by policy iteration Damien Masse1

    E-Print Network [OSTI]

    Paris-Sud XI, Universit de

    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

  2. Fractional Variational Iteration Method for Fractional Nonlinear Differential Equations

    E-Print Network [OSTI]

    Guo-cheng Wu

    2010-07-12T23:59:59.000Z

    Recently, fractional differential equations have been investigated via the famous variational iteration method. However, all the previous works avoid the term of fractional derivative and handle them as a restricted variation. In order to overcome such shortcomings, a fractional variational iteration method is proposed. The Lagrange multipliers can be identified explicitly based on fractional variational theory.

  3. 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

  4. A Turbo Iteration Algorithm In 16QAM Hierarchical Modulation

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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

  5. TRANSP Tests Of TGLF and Predictions For ITER

    SciTech Connect (OSTI)

    none,; Budny, Robert; Yuan, Xingqiu

    2014-02-26T23:59:59.000Z

    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.

  6. Final Report on ITER Task Agreement 81-10

    SciTech Connect (OSTI)

    Brad J. Merrill

    2009-01-01T23:59:59.000Z

    An International Thermonuclear Experimental Reactor (ITER) Implementing Task Agreement (ITA) on Magnet Safety was established between the ITER International Organization (IO) and the Idaho National Laboratory (INL) Fusion Safety Program (FSP) during calendar year 2004. The objectives of this ITA were to add new capabilities to the MAGARC code and to use this updated version of MAGARC to analyze unmitigated superconductor quench events for both poloidal field (PF) and toroidal field (TF) coils of the ITER design. This report documents the completion of the work scope for this ITA. Based on the results obtained for this ITA, an unmitigated quench event in an ITER larger PF coil does not appear to be as severe an accident as in an ITER TF coil.

  7. R&D activities on RF contacts for the ITER ion cyclotron resonance heating launcher

    E-Print Network [OSTI]

    Hillairet, Julien; Bamber, Rob; Beaumont, Bertrand; Bernard, Jean-Michel; Delaplanche, Jean-Marc; Durodi, Frdric; Lamalle, Philippe; Lombard, Gilles; Nicholls, Keith; Shannon, Mark; Vulliez, Karl; Cantone, Vincent; Hatchressian, Jean-Claude; Lebourg, Philippe; Martinez, Andr; Mollard, Patrick; Mouyon, David; Pagano, Marco; Patterlini, Jean-Claude; Soler, Bernard; Thouvenin, Didier; Toulouse, Lionel; Verger, Jean-Marc; Vigne, Terence; Volpe, Robert

    2015-01-01T23:59:59.000Z

    Embedded RF contacts are integrated within the ITER ICRH launcher to allow assembling, sliding and to lower the thermo-mechanical stress. They have to withstand a peak RF current up to 2.5 kA at 55 MHz in steady-state conditions, in the vacuum environment of themachine.The contacts have to sustain a temperature up to 250{\\textdegree}Cduring several days in baking operations and have to be reliable during the whole life of the launcher without degradation. The RF contacts are critical components for the launcher performance and intensive R&D is therefore required, since no RF contactshave so far been qualified at these specifications. In order to test and validate the anticipated RF contacts in operational conditions, CEA has prepared a test platform consisting of a steady-state vacuum pumped RF resonator. In collaboration with ITER Organization and the CYCLE consortium (CYclotronCLuster for Europe), an R&D program has been conducted to develop RF contacts that meet the ITER ICRH launcher specification...

  8. Recent progress on lower hybrid current drive and implications for ITER

    E-Print Network [OSTI]

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

    2015-01-01T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2005-05-15T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

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

    2007-01-08T23:59:59.000Z

    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.

  11. Iterative Algorithms for Ptychographic Phase Retrieval

    E-Print Network [OSTI]

    Yang, Chao

    2011-01-01T23:59:59.000Z

    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

  12. INTEGRATING GEOLOGIC AND GEOPHYSICAL DATA THROUGH

    E-Print Network [OSTI]

    Oldenburg, Douglas W.

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

  13. Iterative build OMIT maps: Map improvement by iterative model-building and refinement without model bias

    SciTech Connect (OSTI)

    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; Terwilliger, Thomas; Terwilliger, T.C.; Grosse-Kunstleve, Ralf Wilhelm; Afonine, P.V.; Moriarty, N.W.; Zwart, P.H.; Hung, L.-W.; Read, R.J.; Adams, P.D.

    2008-02-12T23:59:59.000Z

    A procedure for carrying out iterative model-building, density modification and refinement is presented in which the density in an OMIT region is essentially unbiased by an atomic model. Density from a set of overlapping OMIT regions can be combined to create a composite 'Iterative-Build' OMIT map that is everywhere unbiased by an atomic model but also everywhere benefiting from the model-based information present elsewhere in the unit cell. The procedure may have applications in the validation of specific features in atomic models as well as in overall model validation. The procedure is demonstrated with a molecular replacement structure and with an experimentally-phased structure, and a variation on the method is demonstrated by removing model bias from a structure from the Protein Data Bank.

  14. ITER Central Solenoid Coil Insulation Qualification

    SciTech Connect (OSTI)

    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

    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.

  15. ITER L-Mode Confinement Database

    SciTech Connect (OSTI)

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

    1997-10-01T23:59:59.000Z

    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.

  16. ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION

    SciTech Connect (OSTI)

    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

    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.

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

    E-Print Network [OSTI]

    Heffron, Timothy Paul

    2005-01-01T23:59:59.000Z

    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 ...

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

    E-Print Network [OSTI]

    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

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

  19. Nuclear Forensic Inferences Using Iterative Multidimensional Statistics

    SciTech Connect (OSTI)

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

    2009-06-09T23:59:59.000Z

    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.

  20. Steady-state solution methods for open quantum optical systems

    E-Print Network [OSTI]

    Nation, P D

    2015-01-01T23:59:59.000Z

    We discuss the numerical solution methods available when solving for the steady-state density matrix of a time-independent open quantum optical system, where the system operators are expressed in a suitable basis representation as sparse matrices. In particular, we focus on the difficulties posed by the non-Hermitian structure of the Lindblad super operator, and the numerical techniques designed to mitigate these pitfalls. In addition, we introduce a doubly iterative inverse-power method that can give reduced memory and runtime requirements in situations where other iterative methods are limited due to poor bandwidth and profile reduction. The relevant methods are demonstrated on several prototypical quantum optical systems where it is found that iterative methods based on iLU factorization using reverse Cuthill-Mckee ordering tend to outperform other solution techniques in terms of both memory consumption and runtime as the size of the underlying Hilbert space increases. For eigenvalue solving, Krylov iterat...

  1. Iterative Decoding and Turbo Equalization: The Z-Crease Phenomenon

    E-Print Network [OSTI]

    Jing Li; Kai Xie

    2013-06-03T23:59:59.000Z

    Iterative probabilistic inference, popularly dubbed the soft-iterative paradigm, has found great use in a wide range of communication applications, including turbo decoding and turbo equalization. The classic approach of analyzing the iterative approach inevitably use the statistical and information-theoretical tools that bear ensemble-average flavors. This paper consider the per-block error rate performance, and analyzes it using nonlinear dynamical theory. By modeling the iterative processor as a nonlinear dynamical system, we report a universal "Z-crease phenomenon:" the zig-zag or up-and-down fluctuation -- rather than the monotonic decrease -- of the per-block errors, as the number of iteration increases. Using the turbo decoder as an example, we also report several interesting motion phenomenons which were not previously reported, and which appear to correspond well with the notion of "pseudo codewords" and "stopping/trapping sets." We further propose a heuristic stopping criterion to control Z-crease and identify the best iteration. Our stopping criterion is most useful for controlling the worst-case per-block errors, and helps to significantly reduce the average-iteration numbers.

  2. Demonstration of ITER Operational Scenarios on DIII-D

    SciTech Connect (OSTI)

    Doyle, E J; Budny, R V; DeBoo, J C; Ferron, J R; Jackson, G L; Luce, T C; Murakami, M; Osborne, T H; Park, J; Politzer, P A; Reimerdes, H; Casper, T A; Challis, C D; Groebner, R J; Holcomb, C T; Hyatt, A W; La Haye, R J; McKee, G R; Petrie, T W; Petty, C C; Rhodes, T L; Shafer, M W; Snyder, P B; Strait, E J; Wade, M R; Wang, G; West, W P; Zeng, L

    2008-10-13T23:59:59.000Z

    The DIII-D program has recently initiated an effort to provide suitably scaled experimental evaluations of four primary ITER operational scenarios. New and unique features of this work are that the plasmas incorporate essential features of the ITER scenarios and anticipated operating characteristics; e.g., the plasma cross-section, aspect ratio and value of I/aB of the DIII-D discharges match the ITER design, with size reduced by a factor of 3.7. Key aspects of all four scenarios, such as target values for {beta}{sub N} and H{sub 98}, have been replicated successfully on DIII-D, providing an improved and unified physics basis for transport and stability modeling, as well as for performance extrapolation to ITER. In all four scenarios normalized performance equals or closely approaches that required to realize the physics and technology goals of ITER, and projections of the DIII-D discharges are consistent with ITER achieving its goals of {ge} 400 MW of fusion power production and Q {ge} 10. These studies also address many of the key physics issues related to the ITER design, including the L-H transition power threshold, the size of ELMs, pedestal parameter scaling, the impact of tearing modes on confinement and disruptivity, beta limits and the required capabilities of the plasma control system. An example of direct influence on the ITER design from this work is a modification of the specified operating range in internal inductance at 15 MA for the poloidal field coil set, based on observations that the measured inductance in the baseline scenario case lay outside the original ITER specification.

  3. Shattered Pellet Disruption Mitigation Technology Development for ITER

    SciTech Connect (OSTI)

    Baylor, Larry R [ORNL; Combs, Stephen Kirk [ORNL; Jernigan, T. C. [Oak Ridge National Laboratory (ORNL); Meitner, Steven J [ORNL; Edgemon, Timothy D [ORNL; Parks, P. B. [General Atomics; Commaux, Nicolas JC [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; Caughman, John B [ORNL; Rasmussen, David A [ORNL

    2010-01-01T23:59:59.000Z

    The mitigation of first wall thermal and mechanical loads and damage from runaway electrons during disruptions are critical for successful long term operation of ITER. Disruption mitigation tools based on shattered pellet injection are being developed at Oak Ridge National Laboratory that can be employed on ITER to provide the necessary mitigation of thermal and mechanical loads from disruptions as well as provide collisional damping to inhibit the formation of runaway electrons . Here we present progress on the development of the technology to provide reliable disruption mitigation with large shattered cryogenic pellets. An example of how this concept can be employed on ITER is discussed.

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

    SciTech Connect (OSTI)

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

    2013-07-01T23:59:59.000Z

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

  5. Implementation of an iterative matching scheme for the Kapchinskij-Vladimirskij equations in the WARP code

    SciTech Connect (OSTI)

    Chilton, Sven; Chilton, Sven H.

    2008-07-01T23:59:59.000Z

    The WARP code is a robust electrostatic particle-in-cell simulation package used to model charged particle beams with strong space-charge forces. A fundamental operation associated with seeding detailed simulations of a beam transport channel is to generate initial conditions where the beam distribution is matched to the structure of a periodic focusing lattice. This is done by solving for periodic, matched solutions to a coupled set of ODEs called the Kapchinskij-Vladimirskij (KV) envelope equations, which describe the evolution of low-order beam moments subject to applied lattice focusing, space-charge defocusing, and thermal defocusing forces. Recently, an iterative numerical method was developed (Lund, Chilton, and Lee, Efficient computation of matched solutions to the KV envelope equations for periodic focusing lattices, Physical Review Special Topics-Accelerators and Beams 9, 064201 2006) to generate matching conditions in a highly flexible, convergent, and fail-safe manner. This method is extended and implemented in the WARP code as a Python package to vastly ease the setup of detailed simulations. In particular, the Python package accommodates any linear applied lattice focusing functions without skew coupling, and a more general set of beam parameter specifications than its predecessor. Lattice strength iteration tools were added to facilitate the implementation of problems with specific applied focusing strengths.

  6. Assessing the Power Requirements for Sawtooth Control in ITER Through Modelling and Joint Experiments

    E-Print Network [OSTI]

    Assessing the Power Requirements for Sawtooth Control in ITER Through Modelling and Joint Experiments

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

    E-Print Network [OSTI]

    Carmignani, B

    2005-01-01T23:59:59.000Z

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

  8. 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

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

    E-Print Network [OSTI]

    scale plasma physics research. First and foremost, experiments in ITER will explore ``controlled ignition

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

    E-Print Network [OSTI]

    Abdou, Mohamed

    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

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

    E-Print Network [OSTI]

    Andr Gsponer; Jean-pierre Hurni

    2004-01-01T23:59:59.000Z

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

  12. Exhibit 9RDF Technical Data -ITER UT-B Contracts Div Page 1 of 5

    E-Print Network [OSTI]

    Pennycook, Steve

    Exhibit 9RDF ­ Technical Data - ITER UT-B Contracts Div Sept 2009 Page 1 of 5 ex9rdf-ITER-sept09.doc Exhibit 9RDF-ITER Ref: DEAR 970.5227-1 TECHNICAL DATA ­ ITER (Sept 2009) 1. Rights in Data; (ii) Unlimited rights in Technical Data and Computer Software specifically used in the performa

  13. Plans for U.S. Contributions to ITER

    E-Print Network [OSTI]

    Physics Laboratory (New Jersey) Electric Power Systems Diagnostics Savannah River National Laboratory, but co-located U.S. ITER / Sauthoff Slide 4 #12;Oak Ridge National Laboratory (Tennessee), host lab

  14. Evolution of Deixis: Personal Pronouns in an Iterated Learning Experiment

    E-Print Network [OSTI]

    Komorowska, Krystyna

    2012-11-28T23:59:59.000Z

    To date, empirical research on language evolution has been based on entirely non-deictic languages. This study presents an experiment using the Iterated Learning Model to establish in what way deixis may affect process of language transmission...

  15. Revisiting Stopping Rules for Iterative Methods used in Emission Tomography

    E-Print Network [OSTI]

    Renaut, Rosemary

    Stopping Rules for Iterative Methods used in Emission Tomography Hongbin Guo,a, Rosemary A Renautb a Insta.guo@gmail.com (Hongbin Guo) Preprint submitted to Computerized Medical Imaging and Graphics September 28, 2010

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

    SciTech Connect (OSTI)

    Saad, Yousef

    2014-01-16T23:59:59.000Z

    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.

  17. Experimental Study of Pellet Delivery to the ITER Inner Wall through a Curved Guide Tube at Steady-State Pressure

    SciTech Connect (OSTI)

    Combs, Stephen Kirk [ORNL; Baylor, Larry R [ORNL; Caughman, John B [ORNL; Fehling, Dan T [ORNL; Foust, Charles R [ORNL; Maruyama, S. [ITER International Team, Garching, Germany; McGill, James M [ORNL; Rasmussen, David A [ORNL

    2006-01-01T23:59:59.000Z

    Injection of solid hydrogen pellets from the magnetic high-field side will be the primary technique for depositing fuel particles into the core of International Thermonuclear Experimental Reactor (ITER) burning plasmas. This injection scheme will require the use of a curved guide tube to route the pellets from the acceleration device, under the divertor, and to the inside wall launch location. In an initial series of pellet tests in support of ITER, single 5.3-mm-diam cylindrical D2 pellets were shot through a mock-up of the planned ITER curved guide tube. Those data showed that the pellet speed had to be limited to ?300 m/s for reliable delivery of intact pellets. Also, microwave cavity mass detectors located upstream and downstream of the test tube indicated that ?10% of the pellet mass was lost in the guide tube at 300 m/s. The tube base pressure for that test series was ?10-4 torr. However, for steady-state pellet fueling on ITER, the guide tube will operate at an elevated pressure due to the pellet erosion in the tube. Assuming the present design values for ITER pellet fueling rates/vacuum pumping and a 10% pellet mass loss during flight in the tube, calculations suggest a steadystate operating pressure in the range of 10-20 torr. Thus, experiments to ascertain the pellet integrity and mass loss under these conditions have been carried out. Also, some limited test data were collected at a tube pressure of ?100 torr. No significant detrimental effects have been observed at the higher tube pressures. The new test results are presented and compared to the baseline data previously reported.

  18. Electrostatic Dust Detection and Removal for ITER

    SciTech Connect (OSTI)

    C.H. Skinner; A. Campos; H. Kugel; J. Leisure; A.L. Roquemore; S. Wagner

    2008-09-01T23:59:59.000Z

    We present some recent results on two innovative applications of microelectronics technology to dust inventory measurement and dust removal in ITER. A novel device to detect the settling of dust particles on a remote surface has been developed in the laboratory. A circuit board with a grid of two interlocking conductive traces with 25 ?m spacing is biased to 30 50 V. Carbon particles landing on the energized grid create a transient short circuit. The current flowing through the short circuit creates a voltage pulse that is recorded by standard nuclear counting electronics and the total number of counts is related to the mass of dust impinging on the grid. The particles typically vaporize in a few seconds restoring the previous voltage standoff. Experience on NSTX however, showed that in a tokamak environment it was still possible for large particles or fibers to remain on the grid causing a long term short circuit. We report on the development of a gas puff system that uses helium to clear such particles. Experiments with varying nozzle designs, backing pressures, puff durations, and exit flow orientations have given an optimal configuration that effectively removes particles from an area up to 25 cm with a single nozzle. In a separate experiment we are developing an advanced circuit grid of three interlocking traces that can generate a miniature electrostatic traveling wave for transporting dust to a suitable exit port. We have fabricated such a 3-pole circuit board with 25 micron insulated traces that operates with voltages up to 200 V. Recent results showed motion of dust particles with the application of only 50 V bias voltage. Such a device could potentially remove dust continuously without dedicated interventions and without loss of machine availability for plasma operations.

  19. ITER Physics and Exploring Magnetically-Confined

    E-Print Network [OSTI]

    with Early Integration of Physics and Technology Ned Sauthoff April 4, 2005 #12;Plasma self-heating D+ + T+ 4He++ (3.5 MeV) + n0 (14.1 MeV) Key Science Topics of Burning Plasmas: Self-heating and self: low- *, low- *, isotopic- 's, self-heated/self-organized, low rotation MHD is not a fundamental

  20. Development and Integration Issues and Solutions

    E-Print Network [OSTI]

    V S ubestacin de distribucin Qualified consumers Outages Ancillary Services Spanish Electrical System of lines and 60000 MW of transforming capacity FREE- FLOAT 80% SEPI: Spanish Stated Owned Holding Company demand Spanish peak demands 45 GW and offpeak demands of 1925 GW. Maximum demand 41318 MW 13:26 h 19

  1. Numerical solution of the inversion integral

    E-Print Network [OSTI]

    Bradford, Halley Oren

    1964-01-01T23:59:59.000Z

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

  2. INTEGRATED SOLUTIONS FROM NATURE PUBLISHING GROUP

    E-Print Network [OSTI]

    Cai, Long

    8765 India T: +91 12 4288 1057 Greater China/Singapore T: +852 2811 7191 Middle East T: +44 (0)20 7843 4015 Japan T: +81 3 3267 8765 India T: +91 12 4288 1057 Greater China/Singapore T: +852 2811 7191 Middle East T: +44 (0)20 7843 4922 E-mail: natureevents@nature.com Academia 70% Corporate 14% Gov

  3. Integrated Energy Solutions LLC | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation, search OpenEIHesperia,IDGWPIndiantown,Innoferm GmbHCaltech CenterArea,

  4. 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]

    Raffray, A. René

    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

  5. Noncommutative integrable systems and quasideterminants

    SciTech Connect (OSTI)

    Hamanaka, Masashi [Department of Mathematics, Nagoya University, Chikusa-ku, Nagoya, 464-8602 (Japan)

    2010-03-08T23:59:59.000Z

    We discuss extension of soliton theories and integrable systems into noncommutative spaces. In the framework of noncommutative integrable hierarchy, we give infinite conserved quantities and exact soliton solutions for many noncommutative integrable equations, which are represented in terms of Strachan's products and quasi-determinants, respectively. We also present a relation to an noncommutative anti-self-dual Yang-Mills equation, and make comments on how 'integrability' should be considered in noncommutative spaces.

  6. ITER physics design guidelines at high aspect ratio

    SciTech Connect (OSTI)

    Uckan, N.A.

    1991-01-01T23:59:59.000Z

    The physics requirements for ITER design are formulated in a set of physics design guidelines. These guidelines, established by the ITER Physics Group during the Conceptual Design Activity (CDA, 1988--90), were based on credible extrapolations of the tokamak physics database as assessed during the CDA, and defined a class of tokamak designs (with plasma current I {approximately}20 MA and aspect ratio A {approximately}2.5--3.5) that meet the ITER objectives. Recent US studies have indicated that there may be significant benefits if the ITER-CDA design point is moved from the low aspect ratio, high current baseline (A = 2.79, I = 22 MA) to a high aspect ratio machine at A {approximately}4, I {approximately}15 MA, especially regarding steady-state, technology-testing performance. To adequately assess the physics and technology testing capability of higher aspect ratio design options, several changes are proposed to the original ITER guidelines to reflect the latest (although limited) developments in physics understanding at higher aspect ratios. The critical issues for higher aspect ratio design options are the uncertainty in scaling of confinement with aspect ratio, the variation of vertical stability with elongation and aspect ratio, plasma shaping requirements, ability to control and maintain plasma current and q-profiles for MHD stability (and volt-second consumption), access for current drive, restrictions on field ripple and divertor plate incident angles, etc. 5 refs., 1 tab.

  7. Accelerated Lambda Iteration in Rapidly Expanding Envelopes

    E-Print Network [OSTI]

    P. Hoeflich

    2002-07-04T23:59:59.000Z

    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.

  8. Project Management Plan Solution Stabilization

    SciTech Connect (OSTI)

    SATO, P.K.

    1999-08-31T23:59:59.000Z

    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.

  9. Description of the prototype diagnostic residual gas analyzer for ITER

    SciTech Connect (OSTI)

    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

    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.

  10. Diamond neutral particle spectrometer for fusion reactor ITER

    SciTech Connect (OSTI)

    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

    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.

  11. The influence of an ITER-like wall on disruptions at JET

    SciTech Connect (OSTI)

    Vries, P. C. de, E-mail: Peter.de.Vries@jet.efda.org; Hogeweij, G. M. D. [FOM institute DIFFER, EURATOM association, P.O. Box 1207, Nieuwegein (Netherlands)] [FOM institute DIFFER, EURATOM association, P.O. Box 1207, Nieuwegein (Netherlands); Baruzzo, M.; Murari, A. [Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4, 35127 Padova (Italy)] [Consorzio RFX, EURATOM-ENEA Association, Corso Stati Uniti 4, 35127 Padova (Italy); Jachmich, S. [ERM/KMS, Association EURATOM-Belgian State, B-1000 Brussels, Brussels (Belgium)] [ERM/KMS, Association EURATOM-Belgian State, B-1000 Brussels, Brussels (Belgium); Joffrin, E.; Reux, C. [IRFM-CEA, Centre de Cadarache, 13108 Sant-Paul-lez-Durance (France)] [IRFM-CEA, Centre de Cadarache, 13108 Sant-Paul-lez-Durance (France); Lomas, P. J.; Matthews, G. F. [CCFE/Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)] [CCFE/Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Nunes, I. [Associao EURATOM-IST, Instituto de Plasmas e Fuso Nuclear, 1049-001 Lisboa (Portugal)] [Associao EURATOM-IST, Instituto de Plasmas e Fuso Nuclear, 1049-001 Lisboa (Portugal); Ptterich, T. [Max-Planck-Institut fr Plasmaphysik, EURATOM Association, 85748 Garching (Germany)] [Max-Planck-Institut fr Plasmaphysik, EURATOM Association, 85748 Garching (Germany); Vega, J. [Asociacin EURATOM/CIEMAT para Fusin, Madrid (Spain) [Asociacin EURATOM/CIEMAT para Fusin, Madrid (Spain); JET-EFDA Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Collaboration: JET-EFDA Contributors

    2014-05-15T23:59:59.000Z

    In order to preserve the integrity of large tokamaks such as ITER, the number of disruptions has to be limited. JET has operated previously with a low frequency of disruptions (i.e., disruption rate) of 3.4% [P. C. de Vries et al., Nucl. Fusion 51, 053018 (2011)]. The start of operations with the new full-metal ITER-like wall at JET showed a marked rise in the disruption rate to 10%. A full survey was carried out to identify the root causes, the chain-of-events and classifying each disruption, similar to a previous analysis for carbon-wall operations. It showed the improvements made to avoid various disruption classes, but also indicated those disruption types responsible for the enhanced disruption rate. The latter can be mainly attributed to disruptions due to too high core radiation but also due to density control issues and error field locked modes. Detailed technical and physics understanding of disruption causes is essential for devising optimized strategies to avoid or mitigate these events.

  12. Testability of non-autonomous two dimensional iterative logic array

    E-Print Network [OSTI]

    Nagumo, Hideo

    1991-01-01T23:59:59.000Z

    ' SCIENCE August III91 Major Subject: Electrical Engineering TESTABILITY OF NON-AUTONOMOUS T'A'0 DIMENSIONAL ITERATIVE LOGIC ARRAY A Thesis by HIDEO NAGUMO Approved as to style and content by: . . ed~ I(aran L. watson (Chair of Committee) Mi Lu... (Member) William G. Bliss (Member) Donald K. Friesen (Member) Jo Howze (Head of Department) August 1991 ABSTRACT Testability of i%on-Autonomous Two-Dimensional Iterative Logic Array. (August 1991) Hideo iX'agumo, B. S. , Shinshu University...

  13. STELLOPT Modeling of the 3D Diagnostic Response in ITER

    SciTech Connect (OSTI)

    Lazerson, Samuel A

    2013-05-07T23:59:59.000Z

    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.

  14. Iterative methods for solving nonlinear problems of nuclear reactor criticality

    SciTech Connect (OSTI)

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

    2012-12-15T23:59:59.000Z

    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.

  15. PPPL--2702 Power Radiated from 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's Possible for RenewableSpeedingBiomass and4/26/11:Tel.:162Physics|station |PhysicsPPPL'sorigin702

  16. Required Coordination with ITER Logistical Services Provider

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection Technical s o Freiberge s 3 % A PB 2 7 7 2 x>16

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

    SciTech Connect (OSTI)

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

    1999-04-01T23:59:59.000Z

    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.

  18. Steady-state solution methods for open quantum optical systems

    E-Print Network [OSTI]

    P. D. Nation

    2015-04-25T23:59:59.000Z

    We discuss the numerical solution methods available when solving for the steady-state density matrix of a time-independent open quantum optical system, where the system operators are expressed in a suitable basis representation as sparse matrices. In particular, we focus on the difficulties posed by the non-Hermitian structure of the Lindblad super operator, and the numerical techniques designed to mitigate these pitfalls. In addition, we introduce a doubly iterative inverse-power method that can give reduced memory and runtime requirements in situations where other iterative methods are limited due to poor bandwidth and profile reduction. The relevant methods are demonstrated on several prototypical quantum optical systems where it is found that iterative methods based on iLU factorization using reverse Cuthill-Mckee ordering tend to outperform other solution techniques in terms of both memory consumption and runtime as the size of the underlying Hilbert space increases. For eigenvalue solving, Krylov iterations using the stabilized bi-conjugate gradient method outperform generalized minimal residual methods. In contrast, minimal residual methods work best for solvers based on direct LU decomposition. This work serves as a guide for solving the steady-state density matrix of an arbitrary quantum optical system, and points to several avenues of future research that will extend the applicability of these classical algorithms in absence of a quantum computer.

  19. 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

  20. 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

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

    E-Print Network [OSTI]

    . INTRODUCTION The ITER plasma will provide a unique opportunity for reactor-scale plasma physics research. First

  2. Exhibit 9 Technical Data ITER UT-B Contracts Div Page 1 of 5

    E-Print Network [OSTI]

    Pennycook, Steve

    Exhibit 9 ­ Technical Data ­ ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9-ITER-june11.doc Exhibit 9 ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt.V, 52.227-16 TECHNICAL DATA - ITER (June, or statements, regardless of the media in which recorded, that allow or cause a computer to perform a specific

  3. Iterative Detection and Channel Estimation for Thomas Zemen

    E-Print Network [OSTI]

    Müller, Ralf R.

    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

  4. Iterative Detection and Channel Estimation for Thomas Zemen

    E-Print Network [OSTI]

    Zemen, Thomas

    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

  5. PUBLISHED VERSION RF contact development for the ITER ICRH antenna

    E-Print Network [OSTI]

    Cyclotron (IC) antenna design, ITER Organization requested qualification tests on sliding Radio contacts in relevant conditions (2.25kA @ 62.5MHz, vacuum pressure detailed with RF power tests for long shot duration (1000s) under vacuum and extensive sliding tests

  6. 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

  7. AND THEIR PREDICTIONS FOR ITER D. R. MIKKELSEN

    E-Print Network [OSTI]

    Hammett, Greg

    15) Chalmers University of Technology, Gteborg, Sweden Abstract A number of proposed tokamak thermal transport models for several reasons. Firstly, to enhance our confidence in extrapolations of energy range of existing tokamak data. This has led to the development of the ITER Profile Database [2] which

  8. Fusion project decision delayed ITER -NUCLEAR FUSION PROJECT

    E-Print Network [OSTI]

    -free energy - but the reactor will take 10 years to build. Pros and cons Member countries of the International research facility and a more moderate climate. Iter consortium European Union United States Russia China the decision is highly political, involving huge amounts of horse-trading behind the scenes. Delegates were

  9. 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

  10. 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

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

    SciTech Connect (OSTI)

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

    1996-12-01T23:59:59.000Z

    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.

  12. Edge-Localized Iterative Reconstruction for Computed Tomography

    E-Print Network [OSTI]

    1 Edge-Localized Iterative Reconstruction for Computed Tomography Zhou Yu Student Member, IEEE) can greatly improve the quality of computed tomography (CT) images. In particular, MBR can recover at significantly reduced computational cost. Index Terms--Computed tomography, model based reconstruc- tion

  13. Edge-Localized Iterative Reconstruction for Computed Tomography

    E-Print Network [OSTI]

    Edge-Localized Iterative Reconstruction for Computed Tomography Zhou Yu Student Member, IEEE, Jean the quality of computed tomography (CT) images. In particular, MBR can recover fine details and small features reduced computational cost. Index Terms--Computed tomography, model based reconstruc- tion, coordinate

  14. Moldable Parallel Job Scheduling Using Job Efficiency: An Iterative Approach

    E-Print Network [OSTI]

    Feitelson, Dror

    Moldable Parallel Job Scheduling Using Job Efficiency: An Iterative Approach Gerald Sabin, Matthew OH 43201, USA, {sabin, langma, saday}@cse.ohio-state.edu Abstract. Currently, job schedulers require "rigid" job submissions from users, who must specify a particular number of processors for each paral

  15. ITERATIVE TOTAL VARIATION REGULARIZATION WITH NON-QUADRATIC FIDELITY

    E-Print Network [OSTI]

    Burger, Martin

    , AND STANLEY J. OSHER Abstract. A generalized iterative regularization procedure based on the total variation still eliminate high-frequency noise. However, the ROF model (1.1) has certain limitations. Meyer has with the norm ||w|| = inf g,w= g ess sup x |g(x)| , Meyer provided arguments in favour of considering elements

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

    SciTech Connect (OSTI)

    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

    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.

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

    E-Print Network [OSTI]

    Heckrotte, Robert Platt

    1964-01-01T23:59:59.000Z

    OF THE I ECKNGRK PO( YNONIAL SUBROUTINE DIFEQ DINENSI 0}{ A(20o20) oX(20 ) oP(20 ~ 20) ~ C{20) oW{ 20) C 0)(NON A o X o P o C o N o K o ){ o NUN DINENS ION U(20) o V{20 } o Y(20) o2(20) oD {20) CONNON U o V o Y o Z o D o t AURA DINENS ION 0 (10) QQ...~loN 36 2{ 1)~tYt I)~fo){o(lo/Xt 1)~SINF{X{1 ))i'COSF(X( I)) I ~ ) QQ TO 26 4 DQ 38 foo)oN 3S Z(1 ) ~I o+ 1 Y( I )~I ~ )442 CQ TO 26 5 DO 40 I~I ~ N 40 Z{ I ) a(~1 or'4 ~ )4SQRTF {4o (Y{ I )+1 ~ )4{}2) QQ TO 26 6 DO 42 l&io6 42 Zt I )&X( I )+Yt I...

  18. ITERATIVE SOLUTION OF A COUPLED MIXED AND STANDARD GALERKIN DISCRETIZATION METHOD FOR

    E-Print Network [OSTI]

    Pasciak, Joseph

    .S. Department of Energy by Lawrence Livermore National Laboratory under Contract W-7405-Eng-48. 1 #12; 2 RAYTCHO

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

    E-Print Network [OSTI]

    Grossmann, Ignacio E.

    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

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

    E-Print Network [OSTI]

    Um, E.S.

    2013-01-01T23:59:59.000Z

    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

  1. 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

  2. ASSESSMENT OF THE DCLL TBM THERMOSTRUCTURAL RESPONSE BASED ON ITER DESIGN CRITERIA

    E-Print Network [OSTI]

    Ghoniem, Nasr M.

    codes (e.g., ASME Code4 and RCC-MR5 ). A detailed thermo-structural analysis of the DCLL TBM as safety important ITER components, they must fulfill all required ITER codes and standards for reliable performance under ITER normal operating conditions. II. DESIGN CODE PURPOSE The primary purpose of structural

  3. 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

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

    E-Print Network [OSTI]

    Holst, Michael J.

    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

  5. On the Strategy and Requirements for Neutronics Testing in ITER

    SciTech Connect (OSTI)

    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

    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.

  6. Senate panel orders US withdrawal from ITER Appropriators cite rising costs and mismanagement for terminating US participation in ITER, but

    E-Print Network [OSTI]

    for terminating US participation in ITER, but House spending bill would increase funding above administration is stifling research, science board warns Senate appropriators approved a bill last week that would order by the subcommittee on energy and water development, would allow just $75 million to pay for contracts that have

  7. Information-theoretic discrepancy based iterative reconstructions (IDIR) for polychromatic x-ray tomography

    SciTech Connect (OSTI)

    Jang, Kwang Eun; Lee, Jongha; Sung, Younghun; Lee, SeongDeok [Advanced Media Laboratory, Samsung Advanced Institute of Technology (SAIT), San 14, Nongseo Dong, Giheung Gu, Yongin, Gyeonggi 446-712 (Korea, Republic of)] [Advanced Media Laboratory, Samsung Advanced Institute of Technology (SAIT), San 14, Nongseo Dong, Giheung Gu, Yongin, Gyeonggi 446-712 (Korea, Republic of)

    2013-09-15T23:59:59.000Z

    Purpose: X-ray photons generated from a typical x-ray source for clinical applications exhibit a broad range of wavelengths, and the interactions between individual particles and biological substances depend on particles' energy levels. Most existing reconstruction methods for transmission tomography, however, neglect this polychromatic nature of measurements and rely on the monochromatic approximation. In this study, we developed a new family of iterative methods that incorporates the exact polychromatic model into tomographic image recovery, which improves the accuracy and quality of reconstruction.Methods: The generalized information-theoretic discrepancy (GID) was employed as a new metric for quantifying the distance between the measured and synthetic data. By using special features of the GID, the objective function for polychromatic reconstruction which contains a double integral over the wavelength and the trajectory of incident x-rays was simplified to a paraboloidal form without using the monochromatic approximation. More specifically, the original GID was replaced with a surrogate function with two auxiliary, energy-dependent variables. Subsequently, the alternating minimization technique was applied to solve the double minimization problem. Based on the optimization transfer principle, the objective function was further simplified to the paraboloidal equation, which leads to a closed-form update formula. Numerical experiments on the beam-hardening correction and material-selective reconstruction were conducted to compare and assess the performance of conventional methods and the proposed algorithms.Results: The authors found that the GID determines the distance between its two arguments in a flexible manner. In this study, three groups of GIDs with distinct data representations were considered. The authors demonstrated that one type of GIDs that comprises raw data can be viewed as an extension of existing statistical reconstructions; under a particular condition, the GID is equivalent to the Poisson log-likelihood function. The newly proposed GIDs of the other two categories consist of log-transformed measurements, which have the advantage of imposing linearized penalties over multiple discrepancies. For all proposed variants of the GID, the aforementioned strategy was used to obtain a closed-form update equation. Even though it is based on the exact polychromatic model, the derived algorithm bears a structural resemblance to conventional methods based on the monochromatic approximation. The authors named the proposed approach as information-theoretic discrepancy based iterative reconstructions (IDIR). In numerical experiments, IDIR with raw data converged faster than previously known statistical reconstruction methods. IDIR with log-transformed data exhibited superior reconstruction quality and faster convergence speed compared with conventional methods and their variants.Conclusions: The authors' new framework for tomographic reconstruction allows iterative inversion of the polychromatic data model. The primary departure from the traditional iterative reconstruction was the employment of the GID as a new metric for quantifying the inconsistency between the measured and synthetic data. The proposed methods outperformed not only conventional methods based on the monochromatic approximation but also those based on the polychromatic model. The authors have observed that the GID is a very flexible means to design an objective function for iterative reconstructions. Hence, the authors expect that the proposed IDIR framework will also be applicable to other challenging tasks.

  8. Dynamic simulation of a proposed ITER tritium processing system

    SciTech Connect (OSTI)

    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

    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.

  9. An Overview of US ITER Test Blanket Module Program

    SciTech Connect (OSTI)

    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

    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.

  10. Krylov subspace iteration for eigenvalue response matrix calculations

    SciTech Connect (OSTI)

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

    2012-07-01T23:59:59.000Z

    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)

  11. Water-cooled solid-breeder blanket concept for ITER

    SciTech Connect (OSTI)

    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

    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.

  12. Pellet Fueling and Control of Burning Plasmas in ITER

    SciTech Connect (OSTI)

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

    2007-01-01T23:59:59.000Z

    Pellet injection from the inner wall is planned for use on ITER as the primary core fueling system since gas fueling is expected to be highly inefficient in burning plasmas. Tests of the inner wall guide tube have shown that 5mm pellets with up to 300 m/s speeds can survive intact and provide the necessary core fueling rate. Modeling and extrapolation of the inner wall pellet injection experiments from today's smaller tokamaks leads to the prediction that this method will provide efficient core fueling beyond the pedestal region. Using pellets for triggering of frequent small edge localized modes is an attractive additional benefit that the pellet injection system can provide. A description of the ITER pellet injection system capabilities for fueling and ELM triggering are presented and performance expectations and fusion power control aspects are discussed.

  13. Atomic Physics in the Quest for Fusion Energy and ITER

    SciTech Connect (OSTI)

    Charles H. Skinner

    2008-02-27T23:59:59.000Z

    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.

  14. 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

  15. Qualification of the Joints for the ITER Central Solenoid

    SciTech Connect (OSTI)

    Martovetsky, N; Berryhill, A; Kenney, S

    2011-09-01T23:59:59.000Z

    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.

  16. Progress and present status of ITER cryoline system

    SciTech Connect (OSTI)

    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

    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.

  17. Water-cooled solid-breeder concept for ITER

    SciTech Connect (OSTI)

    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

    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.

  18. Final Report - Modeling Results For the ITER Cryogenic Fore Pump

    SciTech Connect (OSTI)

    Pfotenhauer, John M; Zhang, Dongsheng

    2014-03-31T23:59:59.000Z

    A numerical model characterizing the operation of a cryogenic fore-pump (CFP) for ITER has been developed at the University of Wisconsin Madison during the period from March 15, 2011 through June 30, 2014. The purpose of the ITER-CFP is to separate hydrogen isotopes from helium gas, both making up the exhaust components from the ITER reactor. The model explicitly determines the amount of hydrogen that is captured by the supercritical-helium-cooled pump as a function of the inlet temperature of the supercritical helium, its flow rate, and the inlet conditions of the hydrogen gas flow. Furthermore the model computes the location and amount of hydrogen captured in the pump as a function of time. Throughout the models development, and as a calibration check for its results, it has been extensively compared with the measurements of a CFP prototype tested at Oak Ridge National Lab. The results of the model demonstrate that the quantity of captured hydrogen is very sensitive to the inlet temperature of the helium coolant on the outside of the cryopump. Furthermore, the model can be utilized to refine those tests, and suggests methods that could be incorporated in the testing to enhance the usefulness of the measured data.

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

    SciTech Connect (OSTI)

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

    1999-09-01T23:59:59.000Z

    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.

  20. Impacts of pellets injected from the low-field side on plasma in ITER

    SciTech Connect (OSTI)

    Wisitsorasak, A. [Mahidol University, Faculty of Science (Thailand); Onjun, T. [Thammasat University, School of Manufacturing Systems and Mechanical Engineering, Sirindhorn International Institute of Technology (Thailand)

    2011-01-15T23:59:59.000Z

    Impacts of pellets injected from the low-field side (LFS) on plasma in ITER are investigated using the 1.5D BALDUR integrated predictive modeling code. In these simulations, the pellet ablation is described using the neutral gas shielding (NGS) model. The pellet ablation model is coupled with the plasma core transport model, which is a combination of the MMM95 anomalous transport model and NCLASS neoclassical transport model. The boundary conditions are assumed to be at the top of the pedestal, in which the pedestal parameters are predicted using a pedestal model based on the theoretical-based pedestal width scaling (either magnetic and flow shear stabilization width scaling, or flow shear stabilization width scaling, or normalized poloidal pressure width scaling) and the infinite-n ballooning mode pressure gradient limit. These pedestal models depend sensitively on the density at the top of the pedestal, which can be strongly influenced by the injection of pellets. The combination of the MMM95 and NCLASS models, together with the pedestal and NGS models, is used to simulate the time evolution of the plasma current, ion and electron temperatures, and density profiles for ITER standard type-I ELMy H-mode discharges during the injection of LFS pellets. It is found that the injection of pellets results in a complicated plasma scenario, especially in the outer region of the plasma and the plasma conditions at the boundary in which the pellet has an impact on increasing the plasma edge density, but reducing the plasma edge temperature. The LFS pellet has a stronger impact on the edge as compared to the center. For fusion performance, the pellet can result in either enhancement or degradation, depending sensitively on the pellet parameters; such as the pellet size, pellet velocity, and pellet frequency. For example, when a series of deuterium pellets with a size of 0.5 cm, velocity of 1 km/s, and frequency of 2 Hz are injected into the ITER plasma from the LFS, the plasma performance, evaluated in terms of Q{sub fusion}, can increase to 72% of that before the use of pellets. It is also found that the injection of pellets results in an increase in the ion and electron densities, but does not enhance the central plasma density. On the other hand, it results in the formation of another peak of the plasma density in the outer region near the plasma edge. The formation of the density peak results in the reduction of plasma transports near the edge by decreasing the contributions of ion-temperature-gradient and trapped electron modes, as well as kinetic ballooning modes.

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

    E-Print Network [OSTI]

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

    2001-01-08T23:59:59.000Z

    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.

  2. A new nonlinear solution method for phase-change problems

    SciTech Connect (OSTI)

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

    1999-06-01T23:59:59.000Z

    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.

  3. Iterative reconstruction using a Monte Carlo based system transfer matrix for dedicated breast positron emission tomography

    SciTech Connect (OSTI)

    Saha, Krishnendu [Ohio Medical Physics Consulting, Dublin, Ohio 43017 (United States); Straus, Kenneth J.; Glick, Stephen J. [Department of Radiology, University of Massachusetts Medical School, Worcester, Massachusetts 01655 (United States); Chen, Yu. [Department of Radiation Oncology, Columbia University, New York, New York 10032 (United States)

    2014-08-28T23:59:59.000Z

    To maximize sensitivity, it is desirable that ring Positron Emission Tomography (PET) systems dedicated for imaging the breast have a small bore. Unfortunately, due to parallax error this causes substantial degradation in spatial resolution for objects near the periphery of the breast. In this work, a framework for computing and incorporating an accurate system matrix into iterative reconstruction is presented in an effort to reduce spatial resolution degradation towards the periphery of the breast. The GATE Monte Carlo Simulation software was utilized to accurately model the system matrix for a breast PET system. A strategy for increasing the count statistics in the system matrix computation and for reducing the system element storage space was used by calculating only a subset of matrix elements and then estimating the rest of the elements by using the geometric symmetry of the cylindrical scanner. To implement this strategy, polar voxel basis functions were used to represent the object, resulting in a block-circulant system matrix. Simulation studies using a breast PET scanner model with ring geometry demonstrated improved contrast at 45% reduced noise level and 1.5 to 3 times resolution performance improvement when compared to MLEM reconstruction using a simple line-integral model. The GATE based system matrix reconstruction technique promises to improve resolution and noise performance and reduce image distortion at FOV periphery compared to line-integral based system matrix reconstruction.

  4. Grid Integration

    SciTech Connect (OSTI)

    Not Available

    2008-09-01T23:59:59.000Z

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

  5. Applying Quadrature Rules with Multiple Nodes to Solving Integral Equations

    SciTech Connect (OSTI)

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

    2008-09-01T23:59:59.000Z

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

  6. An Iterative Approach to Comprehensive Performance Evaluation of Integrated Services Networks \\Lambda

    E-Print Network [OSTI]

    is supported in part by ONR and DARPA under contract N00014­91­C­0195 to Honeywell and Computer Science Research Projects Agency, ONR, the U.S. Government or Honeywell. cial to the overall performance

  7. Evolution integrals

    E-Print Network [OSTI]

    Rocco Duvenhage

    2006-05-24T23:59:59.000Z

    A framework analogous to path integrals in quantum physics is set up for abstract dynamical systems in a W*-algebraic setting. We consider spaces of evolutions, defined in a specific way, of a W*-algebra A as an analogue of spaces of classical paths, and show how integrals over such spaces, which we call ``evolution integrals'', lead to dynamics in a Hilbert space on a ``higher level'' which is viewed as an analogue of quantum dynamics obtained from path integrals. The measures with respect to which these integrals are performed are projection valued.

  8. Assessment of CONTAIN and MELCOR for performing LOCA and LOVA analyses in ITER

    SciTech Connect (OSTI)

    Merrill, B.J.; Hagrman, D.L.; Gaeta, M.J.; Petti, D.A.

    1994-09-01T23:59:59.000Z

    This report describes the results of an assessment of the CONTAIN and MELCOR computer codes for ITER LOCA and LOVA applications. As part of the assessment, the results of running a test problem that describes an ITER LOCA are presented. It is concluded that the MELCOR code should be the preferred code for ITER severe accident thermal hydraulic analyses. This code will require the least modification to be appropriate for calculating thermal hydraulic behavior in ITER relevant conditions that include vacuum, cryogenics, ITER temperatures, and the presence of a liquid metal test module. The assessment of the aerosol transport models in these codes concludes that several modifications would have to be made to CONTAIN and/or MELCOR to make them applicable to the aerosol transport part of severe accident analysis in ITER.

  9. Multiple solutions of coupled-cluster equations for PPP model of [10]annulene

    E-Print Network [OSTI]

    Podeszwa, R

    2002-01-01T23:59:59.000Z

    Multiple (real) solutions of the CC equations (corresponding to the CCD, ACP and ACPQ methods) are studied for the PPP model of [10]annulene, C_{10}H_{10}. The long-range electrostatic interactions are represented either by the Mataga--Nishimoto potential, or Pople's R^{-1} potential. The multiple solutions are obtained in a quasi-random manner, by generating a pool of starting amplitudes and applying a standard CC iterative procedure combined with Pulay's DIIS method. Several unexpected features of these solutions are uncovered, including the switching between two CCD solutions when moving between the weakly and strongly correlated regime of the PPP model with Pople's potential.

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

    SciTech Connect (OSTI)

    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

    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.

  11. 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 vessel. Another possible technique to mitigate tritium accumulation in these codeposited surfaces

  12. US ITER is a strong contributor in plan to enhance international...

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

    to housing the extensive diagnostic systems that will be installed on the ITER tokamak. (Photo by Elle StarkmanPPPL Office of Communications) PPPL's Russell Feder, left,...

  13. Application of the Asymptotic Iteration Method to a Perturbed Coulomb Model

    E-Print Network [OSTI]

    Paolo Amore; Francisco M. Fernandez

    2006-04-17T23:59:59.000Z

    We show that the asymptotic iteration method converges and yields accurate energies for a perturbed Coulomb model. We also discuss alternative perturbation approaches to that model.

  14. 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...

  15. The impact of ELMs on the ITER divertor

    SciTech Connect (OSTI)

    Leonard, A.W.; Osborne, T.H.; Suttrop, W. [General Atomics, San Diego, CA (United States); Hermann, A. [Max Planck Inst. fuer Plasmaphysics, Garching (Germany); Itami, K. [Japan Atomic Energy Research Inst. (Japan); Lingertat, J. [JET Joint Undertaking, Abingdon (United Kingdom); Loarte, A. [Next European Torus, Garching (Germany)

    1998-07-01T23:59:59.000Z

    Edge-Localized-Modes (ELMs) are expected to present a significant transient flux of energy and particles to the ITER divertor. The threshold for ablation of the graphite target will be reached if the ELM transient exceeds Q/t{sup 1/2} {approximately} 45 MJ-m{sup {minus}2}-s{sup {minus}1/2} where Q is the ELM deposition energy density and t is the ELM deposition time. The ablation parameter in ITER can be determined by scaling four factors from present experiments: the ELM energy loss from the core plasma, the fraction of ELM energy deposited on the divertor target, the area of the ELM profile onto the target, and finally the time for the ELM deposition. Review of the ELM energy loss of Type 1 ELM data suggests an ITER ELM energy loss of 2--6% of the stored energy or 25--80 MJ. The fraction of heating power crossing the separatrix due to ELMs is nearly constant (20--40%) resulting in an inverse relationship between ELM amplitude and frequency. Measurements on DIII-D and ASDEX-Upgrade indicate that 50--80% of the ELM energy is deposited on the target. There is currently no evidence for a large fraction of the ELM energy being dissipated through radiation. Profiles of the ELM heat flux are typically 1--2 times the width of steady heat flux between ELMs, with the ELM amplitude usually larger on the inboard target. The ELM deposition time varies from about 0.1 ms in JET to as high as 1.0 ms in ASDEX-Upgrade and DIII-D. The ELM deposition time for ITER will depend upon the level of conductive versus convective transport determined by the ratio of energy to particles released by the ELM. Preliminary analysis suggests that large Type 1 ELMs for low recycling H-mode may exceed the ablation parameter by a factor of 5. Promising regimes with smaller ELMS have been found at other edge operational regimes, including high density with gas puffing, use of rf heating and operation with Type 3 ELMs.

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

    SciTech Connect (OSTI)

    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

    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.

  17. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742EnergyOnItemResearch >Internship Program TheSite Map Site Map Home PageSurvey Forms AllITER

  18. AdS String: Classical Solutions and Moduli Dynamics

    E-Print Network [OSTI]

    Antal Jevicki; Kewang Jin

    2010-01-29T23:59:59.000Z

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

  19. Insolation integrator

    DOE Patents [OSTI]

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

    1980-01-01T23:59:59.000Z

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

  20. Modeling results for the ITER cryogenic fore pump

    SciTech Connect (OSTI)

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

    2014-01-29T23:59:59.000Z

    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.

  1. Assessment Of An Oblique ECE Diagnostic For ITER

    SciTech Connect (OSTI)

    Gary Taylor and Robert W. Harvey

    2009-07-15T23:59:59.000Z

    A systematic disagreement between the electron temperature measured by electron cyclotron emission (TECE) and laser Thomson scattering (TTS), that increases with TECE, is observed in JET and TFTR plasmas, such that TECE ~ 1.2 TTS when TECE ~ 10 keV. The disagreement is consistent with a non-Maxwellian distortion in the bulk electron momentum distribution. ITER is projected to operate with Te(0) ~ 20-40 keV so the disagreement between TECE and TTS could be > 50%, with significant physics implications. The GENRAY ray tracing code predicts that a two-view ECE system, with perpendicular and moderately oblique viewing antennas, would be sufficient to reconstruct a two-temperature bulk distribution. If the electron momentum distribution remains Maxwellian the moderately oblique view could still be used to measure Te(R). A viewing dump will not be required for the oblique view and plasma refraction will be minimal. The oblique view has a similar radial resolution to the perpendicular view, but with some reduction in radial coverage. Oblique viewing angles of up to 20o can be implemented without a major revision to the front end of the existing ITER ECE diagnostic design.

  2. Chevron beam dump for ITER edge Thomson scattering system

    SciTech Connect (OSTI)

    Yatsuka, E.; Hatae, T.; Bassan, M.; Itami, K. [Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan)] [Japan Atomic Energy Agency, 801-1 Mukoyama, Naka, Ibaraki 311-0193 (Japan); Vayakis, G. [ITER Organization, 13115 St Paul Lez Durance Cedex (France)] [ITER Organization, 13115 St Paul Lez Durance Cedex (France)

    2013-10-15T23:59:59.000Z

    This paper contains the design of the beam dump for the ITER edge Thomson scattering system and mainly concerns its lifetime under the harsh thermal and electromagnetic loads as well as tight space allocation. The lifetime was estimated from the multi-pulse laser-induced damage threshold. In order to extend its lifetime, the structure of the beam dump was optimized. A number of bent sheets aligned parallel in the beam dump form a shape called a chevron which enables it to avoid the concentration of the incident laser pulse energy. The chevron beam dump is expected to withstand thermal loads due to nuclear heating, radiation from the plasma, and numerous incident laser pulses throughout the entire ITER project with a reasonable margin for the peak factor of the beam profile. Structural analysis was also carried out in case of electromagnetic loads during a disruption. Moreover, detailed issues for more accurate assessments of the beam dump's lifetime are clarified. Variation of the bi-directional reflection distribution function (BRDF) due to erosion by or contamination of neutral particles derived from the plasma is one of the most critical issues that needs to be resolved. In this paper, the BRDF was assumed, and the total amount of stray light and the absorbed laser energy profile on the beam dump were evaluated.

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

    SciTech Connect (OSTI)

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

    1996-12-31T23:59:59.000Z

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

  4. Iterative image-domain decomposition for dual-energy CT

    SciTech Connect (OSTI)

    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

    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.

  5. Copper wafer bonding in three-dimensional integration

    E-Print Network [OSTI]

    Chen, Kuan-Neng, 1974-

    2005-01-01T23:59:59.000Z

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

  6. Notice of Intent to Issue Funding Opportunity for Integrated...

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

    integrate these solutions into PV power plants. SHINES projects can also focus on demand response and load management to achieve target metrics. These projects will...

  7. 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

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

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    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

  9. PARSMI, a parallel revised simplex algorithm incorporating minor iterations and Devex pricing

    E-Print Network [OSTI]

    Hall, Julian

    PARSMI, a parallel revised simplex algorithm incorporating minor iterations and Devex pricing J, a parallel revised simplex algorithm incorporating minor iterations and Devex pricing J. A. J. Hall and K. I linear programming problems using the re- vised simplex method, two common variants are the incorporation

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

    E-Print Network [OSTI]

    Toint, Philippe

    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

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

    E-Print Network [OSTI]

    Raffray, A. René

    , 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

  12. Brussels, 1 April 2006 ITER Project on Track Top Management Team

    E-Print Network [OSTI]

    IP/06/418 Brussels, 1 April 2006 ITER Project on Track Top Management Team Identified Union, India, Japan, Korea, China, Russia and USA), identified the top management team that will manage-General in November 2005, the top management team of the prospective ITER Organization is now complete. The Tokyo

  13. 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

  14. S12.9Constrained Iterative Speech Enhance with Application to

    E-Print Network [OSTI]

    Texas at Dallas, University of

    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

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

    E-Print Network [OSTI]

    Raffray, A. Ren

    Angeles, CA 90066 Introduction For an ITER ceramic breeding blanket, the breeder temperature must be kept the coolant and solid breeder to allow their operating temperatures to be optimized for ITER.[11 This thermal%) is desired to increase the tritium production in the blanket. The proposed concept also provides operational

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

    E-Print Network [OSTI]

    Abdou, Mohamed

    2006-01-01T23:59:59.000Z

    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

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

    E-Print Network [OSTI]

    Raffray, A. Ren

    1999-01-01T23:59:59.000Z

    breeding blanket with a lithium ceramic as breeder material and beryllium as neutron multiplierFusion Engineering and Design 46 (1999) 177183 ITER reference breeding blanket design M. Ferrari a The ITER reference breeding blanket design is water-cooled and is characterised by the use of the neutronic

  18. CONCURRENT ENGINEERING: Research and Applications Overcoming the 90% Syndrome: Iteration Management

    E-Print Network [OSTI]

    Ford, David N.

    CONCURRENT ENGINEERING: Research and Applications Overcoming the 90% Syndrome: Iteration Management in Concurrent Development Projects David N. Ford1,* and John D. Sterman2 1 Department of Civil Engineering to unanticipated problems and perturbations. Key Words: concurrent development, concurrent engineering, iteration

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

    E-Print Network [OSTI]

    1 The European Joint Undertaking for ITER and the Development of Fusion Energy (Fusion for Energy Agreement Last meeting of negotiators took place in Jeju, China in November 2005 Meeting of legal experts in Barcelona last week resolved most remaining issues #12;3 Tentative ITER Timetable Political

  20. 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

  1. 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

  2. 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

  3. 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

  4. Visions for data management and remote collaboration for ITER M. Greenwald1

    E-Print Network [OSTI]

    Greenwald, Martin

    Visions for data management and remote collaboration for ITER M. Greenwald1 D. Schissel2 J. R Introduction This paper outlines a vision for data management and remote collaboration systems for ITER scales, leading to requirements for efficient browsing of very long data records and the ability

  5. Fourier-Based Forward and Back-Projectors for Iterative Image Reconstruction

    E-Print Network [OSTI]

    Fessler, Jeffrey A.

    Fourier-Based Forward and Back-Projectors for Iterative Image Reconstruction Samuel Matej, Jeffrey. Fourier-Based Projectors B. Non-Uniform Fast Fourier Transform C. Fourier-Based Iterative Reconstruction D. Fourier-based forward and back-projection methods have the potential to considerably reduce

  6. Dual-dictionary learning-based iterative image reconstruction for spectral computed tomography application

    E-Print Network [OSTI]

    Wang, Ge

    Dual-dictionary learning-based iterative image reconstruction for spectral computed tomography-based iterative image reconstruction for spectral computed tomography application Bo Zhao1 , Huanjun Ding1 , Yang discriminating photon-counting detectors, such as cadmiumzinctelluride (CZT), in spectral computed tomography

  7. 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

  8. An Optical Programmable Network Architecture Supporting Iterative Multicast for Data-intensive Applications

    E-Print Network [OSTI]

    Ng, T. S. Eugene

    An Optical Programmable Network Architecture Supporting Iterative Multicast for Data. Bergman1 1 Department of Electrical Engineering, Columbia University, 500 West 120th Street, New York, New.edu Abstract--We present an optical programmable network architecture to enable agile and efficient iterative

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

    E-Print Network [OSTI]

    Wang, Desheng

    grid equation systems and an efficient method for inverting a map by computing isoA 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

  10. Current control in ITER steady state plasmas with neutral beam steering R. V. Budnya

    E-Print Network [OSTI]

    Budny, Robert

    . The heating and current drive systems for ITER plasmas are being designed. The primary systems being for ITER steady state plasmas are specified. Current drive by negative ion neutral beam injection, lower-hybrid as the ratio of the DT fusion and the external heating powers PDT/Pext 5 for durations of up to 3000 s

  11. Development of iteration strategies for a practical implementation of a higher order transverse leakage approximation

    SciTech Connect (OSTI)

    Prinsloo, R. H.; Tomasevic, D. I. [Necsa, PO Box 582, Pretoria, 0001 (South Africa)

    2012-07-01T23:59:59.000Z

    Transverse integrated nodal diffusion methods currently represent the standard in full core neutronic simulation. The primary shortcoming in this approach is the utilization of the quadratic transverse leakage approximation. This approach, although proven to work well for typical LWR problems, is not consistent with the formulation of nodal methods and can cause accuracy and convergence problems. In previous work, an improved, consistent quadratic leakage approximation was formulated, which derived from the class of higher order nodal methods developed some years ago. In this paper a number of iteration schemes are developed around this consistent quadratic leakage approximation which yield accurate node average results in much improved calculational times. The developed consistent leakage approximation is extended in this work via a number of numerical schemes, the most promising of which results from utilizing the consistent leakage approximation as a correction method to the standard quadratic leakage approximation. Numerical results are demonstrated on a set of benchmark problems, such as the 3D IAEA LWR and MOX C5 problems. (authors)

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

    SciTech Connect (OSTI)

    NONE

    1998-12-31T23:59:59.000Z

    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.

  13. Nebraska Statewide Wind Integration Study: Executive Summary

    SciTech Connect (OSTI)

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

    2010-03-01T23:59:59.000Z

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

  14. Integrated Brush Management Systems for Texas

    E-Print Network [OSTI]

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

    2001-01-04T23:59:59.000Z

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

  15. ITERATIVE REPAIR PLANNING FOR SPACECRAFT OPERATIONS USING THE ASPEN SYSTEM Gregg Rabideau, Russell Knight, Steve Chien, Alex Fukunaga, Anita Govindjee

    E-Print Network [OSTI]

    Schaffer, Steven

    ITERATIVE REPAIR PLANNING FOR SPACECRAFT OPERATIONS USING THE ASPEN SYSTEM Gregg Rabideau, Russell and Planning Environment (ASPEN). ASPEN encodes complex spacecraft knowledge of operability constraints, flight generation of low level spacecraft sequences. Using a technique called iterative repair, ASPEN classifies

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

    SciTech Connect (OSTI)

    Hunt, S.; Schur, A.

    1991-09-01T23:59:59.000Z

    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.

  17. 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

  18. Coupling between JET Pedestal ne-Te and Outer Target Plate Recycling: Consequences for JET ITER-Like-Wall Operation

    E-Print Network [OSTI]

    Coupling between JET Pedestal ne-Te and Outer Target Plate Recycling: Consequences for JET ITER-Like-Wall Operation

  19. Simulation of MGI Efficiency for Plasma Energy Conversion into Ar Radiation in JET and Implications for ITER

    E-Print Network [OSTI]

    Simulation of MGI Efficiency for Plasma Energy Conversion into Ar Radiation in JET and Implications for ITER

  20. Modelling of Melt Damage of Tungsten Armour under Multiple Transients Expected in ITER and Validations Against JET-ILW Experiments

    E-Print Network [OSTI]

    Modelling of Melt Damage of Tungsten Armour under Multiple Transients Expected in ITER and Validations Against JET-ILW Experiments

  1. 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

  2. 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

  3. 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

  4. Occupational Radiation Exposure Analysis of US ITER DCLL TBM

    SciTech Connect (OSTI)

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

    2007-08-01T23:59:59.000Z

    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.

  5. DESIGN OF THE ITER IN-VESSEL COILS

    SciTech Connect (OSTI)

    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

    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.

  6. Status of ITER neutral beam cell remote handling system

    E-Print Network [OSTI]

    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

    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.

  7. Iterative methods for solving the pressure problem at multiphase filtration

    E-Print Network [OSTI]

    Vabishchevich, P

    2011-01-01T23:59:59.000Z

    Applied problems of oil and gas recovery are studied numerically using the mathematical models of multiphase fluid flows in porous media. The basic model includes the continuity equations and the Darcy laws for each phase, as well as the algebraic expression for the sum of saturations. Primary computational algorithms are implemented for such problems using the pressure equation. In this paper, we highlight the basic properties of the pressure problem and discuss the necessity of their fulfillment at the discrete level. The resulting elliptic problem for the pressure equation is characterized by a non-selfadjoint operator. Possibilities of approximate solving the elliptic problem are considered using the iterative methods. Special attention is given to the numerical algorithms for calculating the pressure on parallel computers.

  8. Iterative methods for dose reduction and image enhancement in tomography

    DOE Patents [OSTI]

    Miao, Jianwei; Fahimian, Benjamin Pooya

    2012-09-18T23:59:59.000Z

    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.

  9. Simulations of Alpha Wall Load in ITER. Final report

    SciTech Connect (OSTI)

    Carlsson, Johan

    2010-10-20T23:59:59.000Z

    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.

  10. Development of the bus joint for the ITER Central Solenoid

    SciTech Connect (OSTI)

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

    2013-01-01T23:59:59.000Z

    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.

  11. Power Transmission From The ITER Model Negative Ion Source

    SciTech Connect (OSTI)

    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

    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.

  12. Path Integration on Darboux Spaces

    E-Print Network [OSTI]

    Christian Grosche

    2005-07-20T23:59:59.000Z

    In this paper the Feynman path integral technique is applied to two-dimensional spaces of non-constant curvature: these spaces are called Darboux spaces $\\DI$--$\\DIV$. We start each consideration in terms of the metric and then analyze the quantum theory in the separable coordinate systems. The path integral in each case is formulated and then solved in the majority of cases, the exceptions being quartic oscillators where no closed solution is known. The required ingredients are the path integral solutions of the linear potential, the harmonic oscillator, the radial harmonic oscillator, the modified P\\"oschl--Teller potential, and for spheroidal wave-functions, respectively. The basic path integral solutions, which appear here in a complicated way, have been developed in recent work and are known. The final solutions are represented in terms of the corresponding Green's functions and the expansions into the wave-functions, respectively. We also sketch some limiting cases of the Darboux spaces, where spaces of constant negative and zero curvature emerge.

  13. 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

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

    E-Print Network [OSTI]

    Pennycook, Steve

    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

  15. Exhibit 1B Patent Rights Acquisition by the Government ITER UT-B Contracts Div Page 1 of 6

    E-Print Network [OSTI]

    Pennycook, Steve

    Exhibit 1B Patent Rights Acquisition by the Government ITER UT-B Contracts Div March 2007 Page 1 of 6 ex1b-ITER-mar07.doc Exhibit 1B ITER Ref: DEAR 952.227-13 PATENT RIGHTS - ACQUISITION or discovery which is or may be patentable or otherwise protectable under title 35 of the United States Code

  16. Pellet fueling technology development leading to efficient fueling of ITER burning plasmas

    SciTech Connect (OSTI)

    Baylor, L.R.; Combs, S.K.; Jernigan, T.C.; Houlberg, W.A.; Owen, L.W.; Rasmussen, D.A.; Maruyama, S.; Parks, P.B. [Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6169 (United States)

    2005-05-15T23:59:59.000Z

    Pellet injection is the primary fueling technique planned for core fueling of ITER [ITER Technical Basis 2002 ITER EDA Documentation Series (Vienna: IAEA)] burning plasmas. Efficient core plasma fueling with deuterium and tritium D-T is a requirement for achieving high fusion gain and it cannot be achieved with gas fueling. 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. Modeling of the fueling deposition from inner wall pellet injection using the Parks ExB drift model indicates that pellets have the capability to fuel well inside the separatrix. Gas fueling calculations show very poor neutral penetration due to the high density and wide scrape off layer. Isotopically mixed D-T pellets can provide efficient tritium fueling that will minimize tritium wall loading when compared to gas puffing. Currently the performance of the ITER inner wall guide tube design is under test with initial results indicating that pellet speeds in excess of 300 m/s will lead to fragmented pellets. The ITER pellet injection technology requirements and remaining development issues are discussed along with a plan to reach the design goal for employment on ITER.

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

    SciTech Connect (OSTI)

    Francesca M. Poli and Charles Kessel

    2012-12-03T23:59:59.000Z

    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.

  18. Certifying Solutions to Permutation Group Problems

    E-Print Network [OSTI]

    Sorge, Volker

    the integration of permutation group algorithms with proof planning. We consider eight basic questions arising planning. We consider eight basic questions arising in computational permutation group theory, for whichCertifying Solutions to Permutation Group Problems Arjeh Cohen 1 , Scott H. Murray 1#3; , Martin

  19. Certifying Solutions to Permutation Group Problems

    E-Print Network [OSTI]

    Murray, Scott H.

    of permutation group algorithms with proof planning. We consider eight basic questions arising in com- putational the integration of permutation group algorithms from computer algebra with proof planning. We consider eight basicCertifying Solutions to Permutation Group Problems Arjeh Cohen1 , Scott H. Murray1, , Martin Pollet

  20. An adaptive iterative method for solving stochastic PDEs

    E-Print Network [OSTI]

    Hackbusch, Wolfgang

    and memory compared to many state-of-the-art stochastic intrusive and non-intrusive methods. 1 #12; A new intrusive approach for constructing low-rank solutions to stochastic partial dif- ferential

  1. The A_infty de Rham theorem and integration of representations up to homotopy

    E-Print Network [OSTI]

    Abad, Camilo Arias

    2010-01-01T23:59:59.000Z

    We use Chen's iterated integrals to integrate representations up to homotopy. That is, we construct an A_infty functor from the representations up to homotopy of a Lie algebroid to those of its infinity groupoid. This construction extends the usual integration of representations in Lie theory. We discuss several examples including Lie algebras and Poisson manifolds. The construction is based on an A_infty version of de Rham's theorem due to Gugenheim. The integration procedure we explain here amounts to extending the construction of parallel transport for superconnections, introduced by Igusa and Block-Smith, to the case of certain differential graded manifolds.

  2. Smart Grid Integration Laboratory

    SciTech Connect (OSTI)

    Wade Troxell

    2011-09-30T23:59:59.000Z

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

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

    E-Print Network [OSTI]

    2009-07-15T23:59:59.000Z

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

  4. Enabling rapid iterative model design within the laboratory environment

    E-Print Network [OSTI]

    Clayton, Thomas F.

    2009-01-01T23:59:59.000Z

    This thesis presents a proof of concept study for the better integration of the electrophysiological and modelling aspects of neuroscience. Members of these two sub-disciplines collaborate regularly, but due to differing ...

  5. Numerical integration of variational equations

    E-Print Network [OSTI]

    Ch. Skokos; E. Gerlach

    2010-09-29T23:59:59.000Z

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

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

    E-Print Network [OSTI]

    Temkin, Richard J.

    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 ...

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

    E-Print Network [OSTI]

    Tamma, Raja Venkatesh

    2004-09-30T23:59:59.000Z

    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...

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

    SciTech Connect (OSTI)

    Not Available

    1991-01-01T23:59:59.000Z

    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)

  9. Tritium inventory control in ITER Charles Skinner with key contributions from

    E-Print Network [OSTI]

    Princeton Plasma Physics Laboratory

    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

  10. ITERATIVE NEAR-FIELD (INF) PRECONDITIONER FOR THE MULTILEVEL FAST MULTIPOLE ALGORITHM

    E-Print Network [OSTI]

    Grel, Levent

    ITERATIVE NEAR-FIELD (INF) PRECONDITIONER FOR THE MULTILEVEL FAST MULTIPOLE ALGORITHM LEVENT G in computa- tional electromagnetics using the multilevel fast multipole algorithm (MLFMA), preconditioners multipole method (FMM), multilevel fast multipole algorithm (MLFMA), sparse approximate inverse

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

    E-Print Network [OSTI]

    the best working and living conditions. The EU Delegation also informed that the Spanish Secretary of State to personally re-iterate the firm commitment of all layers of Spanish government and society to the success

  12. 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

  13. Performance of Closed Form and Iterative MU-MIMO Precoders for Different Broadcast

    E-Print Network [OSTI]

    Gesbert, David

    in improving both reliability and capacity of the system. Some theoretical analysis of the capacity, and Hassibi) algorithm proposed in [12] as it is an iterative algorithm for MU-MISO sumrate maximization based

  14. 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 trademarks and trademarks of the Reuters group of companies around the world. Close This Window 12/2/05 4

  15. Iterative receivers for OFDM systems with dispersive fading and frequency offset

    E-Print Network [OSTI]

    Liu, Hui

    2004-09-30T23:59:59.000Z

    The presence of dispersive fading and inter-carrier interference (ICI) constitute the major impediment to reliable communications in orthogonal frequency-division multiplexing (OFDM) systems. Recently iterative (``Turbo'') processing techniques...

  16. An assessment of the base blanket for ITER

    SciTech Connect (OSTI)

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

    1991-01-01T23:59:59.000Z

    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.

  17. Helium-cooled solid breeder blanket for ITER

    SciTech Connect (OSTI)

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

    1989-03-01T23:59:59.000Z

    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.

  18. An Overview of the US DCLL ITER-TBM Program

    SciTech Connect (OSTI)

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

    2010-12-01T23:59:59.000Z

    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.

  19. An overview of the US DCLL ITER-TBM program

    SciTech Connect (OSTI)

    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

    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.

  20. An Overview of the US DCLL ITER TBM Program

    SciTech Connect (OSTI)

    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

    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.

  1. An assessment of the base blanket for ITER

    SciTech Connect (OSTI)

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

    1991-12-31T23:59:59.000Z

    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.

  2. Status of the Design of the ITER ECE Diagnostic

    SciTech Connect (OSTI)

    Taylor, Gary [PPPL

    2014-04-01T23:59:59.000Z

    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.

  3. Development of the Long Pulse Negative Ion Source for ITER

    SciTech Connect (OSTI)

    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

    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.

  4. 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

  5. Qualification of the US made conductors for ITER TF magnet system

    SciTech Connect (OSTI)

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

    2009-10-08T23:59:59.000Z

    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.

  6. Exact solutions of Deformed Schrodinger Equation with a class of non central physical potentials

    E-Print Network [OSTI]

    M. Chabab; A. El Batoul; M. Oulne

    2015-06-20T23:59:59.000Z

    In this paper we present exact solutions of Schrodinger equation (SE) for a class of non central physical potentials within the formalism of position-dependent effective mass. The energy eigenvalues and eigenfunctions of the bound-states for the Schrodinger equation are obtained analytically by means of asymptotic iteration method (AIM) and easily calculated through a new generalized decomposition of the effective potential allowing easy separation of the coordinates. Our results are in excellent agreement with other works in the literature.

  7. Integrable cases of gravitating static isothermal fluid spheres

    E-Print Network [OSTI]

    B. V. Ivanov

    2001-07-17T23:59:59.000Z

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

  8. Integrative Bioengineering Institute

    SciTech Connect (OSTI)

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

    2009-01-09T23:59:59.000Z

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

  9. Computation of Contour Integrals on ${\\cal M}_{0,n}$

    E-Print Network [OSTI]

    Cachazo, Freddy

    2015-01-01T23:59:59.000Z

    Contour integrals of rational functions over ${\\cal M}_{0,n}$, the moduli space of $n$-punctured spheres, have recently appeared at the core of the tree-level S-matrix of massless particles in arbitrary dimensions. The contour is determined by the critical points of a certain Morse function on ${\\cal M}_{0,n}$. The integrand is a general rational function of the puncture locations with poles of arbitrary order as two punctures coincide. In this note we provide an algorithm for the analytic computation of any such integral. The algorithm uses three ingredients: an operation we call general KLT, Petersen's theorem applied to the existence of a 2-factor in any 4-regular graph and Hamiltonian decompositions of certain 4-regular graphs. The procedure is iterative and reduces the computation of a general integral to that of simple building blocks. These are integrals which compute double-color-ordered partial amplitudes in a bi-adjoint cubic scalar theory.

  10. Design of fast tuning elements for the ITER ICH system

    SciTech Connect (OSTI)

    Swain, D.W.; Goulding, R.H.

    1996-05-01T23:59:59.000Z

    The coupling between the ion cyclotron (IC) antenna and the ITER plasma (as expressed by the load resistance the antenna sees) will experience relatively fast variations due to plasma edge profile modifications. If uncompensated, these will cause an increase in the amount of power reflected back to the transmitter and ultimately a decrease in the amount of radio frequency (rf) power to the plasma caused by protective suppression of the amount of rf power generated by the transmitter. The goals of this task were to study several alternate designs for a tuning and matching (T&M) system and to recommend some research and development (R&D) tasks that could be carried out to test some of the most promising concepts. Analyses of five different T&M configurations are presented in this report. They each have different advantages and disadvantages, and the choice among them must be made depending on the requirements for the IC system. Several general conclusions emerge from our study: The use of a hybrid splitter as a passive reflected-power dump [``edge localized mode (ELM)-dump``] appears very promising; this configuration will protect the rf power sources from reflected power during changes in plasma loading due to plasma motion or profile changes (e.g., ELM- induced changes in the plasma scrape-off region) and requires no active control of the rf system. Trade-offs between simplicity of design and capability of the system must be made. Simple system designs with few components near the antenna either have high voltages over considerable distances of transmission lines, or they are not easily tuned to operate at different frequencies. Designs using frequency shifts and/or fast tuning elements can provide fast matching over a wide range of plasma loading; however, the designs studied here require components near the antenna, complicating assembly and maintenance. Capacitor-tuned resonant systems may offer a good compromise.

  11. Helium-cooled lithiuim compound suspension blanket concept for ITER

    SciTech Connect (OSTI)

    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

    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.

  12. Volumetric quantification of lung nodules in CT with iterative reconstruction (ASiR and MBIR)

    SciTech Connect (OSTI)

    Chen, Baiyu [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 and Carl E. Ravin Advanced Imaging Laboratories, Duke University, Durham, North Carolina 27705 (United States)] [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 and Carl E. Ravin Advanced Imaging Laboratories, Duke University, Durham, North Carolina 27705 (United States); Barnhart, Huiman [Department of Biostatistics and Bioinformatics, Duke University, Durham, North Carolina 27705 (United States)] [Department of Biostatistics and Bioinformatics, Duke University, Durham, North Carolina 27705 (United States); Richard, Samuel [Carl E. Ravin Advanced Imaging Laboratories, Duke University, Durham, North Carolina 27705 and Department of Radiology, Duke University, Durham, North Carolina 27705 (United States)] [Carl E. Ravin Advanced Imaging Laboratories, Duke University, Durham, North Carolina 27705 and Department of Radiology, Duke University, Durham, North Carolina 27705 (United States); Robins, Marthony [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States)] [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States); Colsher, James [Department of Radiology, Duke University, Durham, North Carolina 27705 (United States)] [Department of Radiology, Duke University, Durham, North Carolina 27705 (United States); Samei, Ehsan [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States) [Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States); Carl E. Ravin Advanced Imaging Laboratories, Duke University, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University, Durham, North Carolina 27705 (United States); Department of Physics, Department of Biomedical Engineering, and Department of Electronic and Computer Engineering, Duke University, Durham, North Carolina 27705 (United States)

    2013-11-15T23:59:59.000Z

    Purpose: Volume quantifications of lung nodules with multidetector computed tomography (CT) images provide useful information for monitoring nodule developments. The accuracy and precision of the volume quantification, however, can be impacted by imaging and reconstruction parameters. This study aimed to investigate the impact of iterative reconstruction algorithms on the accuracy and precision of volume quantification with dose and slice thickness as additional variables.Methods: Repeated CT images were acquired from an anthropomorphic chest phantom with synthetic nodules (9.5 and 4.8 mm) at six dose levels, and reconstructed with three reconstruction algorithms [filtered backprojection (FBP), adaptive statistical iterative reconstruction (ASiR), and model based iterative reconstruction (MBIR)] into three slice thicknesses. The nodule volumes were measured with two clinical software (A: Lung VCAR, B: iNtuition), and analyzed for accuracy and precision.Results: Precision was found to be generally comparable between FBP and iterative reconstruction with no statistically significant difference noted for different dose levels, slice thickness, and segmentation software. Accuracy was found to be more variable. For large nodules, the accuracy was significantly different between ASiR and FBP for all slice thicknesses with both software, and significantly different between MBIR and FBP for 0.625 mm slice thickness with Software A and for all slice thicknesses with Software B. For small nodules, the accuracy was more similar between FBP and iterative reconstruction, with the exception of ASIR vs FBP at 1.25 mm with Software A and MBIR vs FBP at 0.625 mm with Software A.Conclusions: The systematic difference between the accuracy of FBP and iterative reconstructions highlights the importance of extending current segmentation software to accommodate the image characteristics of iterative reconstructions. In addition, a calibration process may help reduce the dependency of accuracy on reconstruction algorithms, such that volumes quantified from scans of different reconstruction algorithms can be compared. The little difference found between the precision of FBP and iterative reconstructions could be a result of both iterative reconstruction's diminished noise reduction at the edge of the nodules as well as the loss of resolution at high noise levels with iterative reconstruction. The findings do not rule out potential advantage of IR that might be evident in a study that uses a larger number of nodules or repeated scans.

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

    SciTech Connect (OSTI)

    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

    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.

  14. Lightweight Steel Solutions for Automotive Industry

    SciTech Connect (OSTI)

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

    2010-06-15T23:59:59.000Z

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

  15. A high level meeting between the ITER Participants today in Vienna issued the following press release: "Common Message from the 5th Preparatory Meeting for ITER Decision Making

    E-Print Network [OSTI]

    th November 2005) High level negotiators from China, European Union, Japan, the Republic of Korea is currently Ambassador of Japan to Croatia, is a graduate Nuclear Engineer and has extensive experience ITER Agreement and completion of the Negotiations. Conclusion With the progress made in the Parties

  16. A Comparison of Some Iterative Methods in Scientific Shawn Sickel

    E-Print Network [OSTI]

    Yeung, Man-Chung

    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

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

    SciTech Connect (OSTI)

    NONE

    1995-12-01T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Perry, Richard Allan

    1970-01-01T23:59:59.000Z

    Scientific Re t. MW-64, McGill University, Montreal, Canada, 65 pp. 20 APPEIIDIX IMPLICIT REAL sB (4 H ~ 0 Zl RE4LSB Lttl ~ Ny IR t I I ~ I C v KX ~ LZ ~ LT DIMFNS ION IC(401 PC(40), BIN(40) 1(31 ~ DES(3) F 81(3) t82(3) tE(3) ~ DPS(3 TB = 3 ~ 010... ) Ts = TQ(K) - 273. 0 Es(KI = 6. 11 s ( 10. 0ss( 7. SsTS / ( DES(K) = Es(KI S ( 7. 5SG/((Tst237 1(. 43429) Bl(KI = L / ( RV s TQ(KI ) BZ&KI = L / ( CP sTQ(KI ) E(KI = DEXP( 81(K) s rf'L&KI ) ? ( DPS(KI = -PQ 4 ( PIN(K)SS2. 5) S 3 AP(KI = -C...

  19. NREL: Energy Systems Integration - Energy Systems Integration...

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

    Printable Version Energy Systems Integration Facility Newsroom The Energy Systems Integration Facility (ESIF) will be one of the only megawatt-scale test facilities in the United...

  20. Analytical solutions to matrix diffusion problems

    SciTech Connect (OSTI)

    Keklinen, Pekka, E-mail: pekka.kekalainen@helsinki.fi [Laboratory of Radiochemistry, Department of Chemistry, P.O. Box 55, FIN-00014 University of Helsinki (Finland)

    2014-10-06T23:59:59.000Z

    We report an analytical method to solve in a few cases of practical interest the equations which have traditionally been proposed for the matrix diffusion problem. In matrix diffusion, elements dissolved in ground water can penetrate the porous rock surronuding the advective flow paths. In the context of radioactive waste repositories this phenomenon provides a mechanism by which the area of rock surface in contact with advecting elements is greatly enhanced, and can thus be an important delay mechanism. The cases solved are relevant for laboratory as well for in situ experiments. Solutions are given as integral representations well suited for easy numerical solution.

  1. Solution deposition assembly

    DOE Patents [OSTI]

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

    2014-01-21T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    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.

  3. Integrated Building Management System (IBMS)

    SciTech Connect (OSTI)

    Anita Lewis

    2012-07-01T23:59:59.000Z

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

  4. Solution to Quiz 5

    E-Print Network [OSTI]

    jeffb_000

    2013-12-02T23:59:59.000Z

    Nov 19, 2013 ... Calculate the total transaction costs incurred by Patrick and Eric combined. Solution: Ask Price = 30. Bid Ask Spread = 0.50 = Ask Price - Bid...

  5. Mixed oxide solid solutions

    DOE Patents [OSTI]

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

    2003-01-01T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Turner, S. C.

    1998-01-01T23:59:59.000Z

    marketplace. STANDARDS Building codes typically establish required minimums for ventilation and some other IAQ- related elements of performance contracts. k addition, widely accepted industry standards are often referenced in building codes, and become... for accomplishing that work. Often, establishing a clearer basis for performance expectations with respect to JAQ is complicated by the age of a facility or the capacity of its existing heating, ventilating, and air conditioning WAC) systems. Buildings...

  7. Integrated Dynamic Electron Solutions, Inc. | Department of Energy

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

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

  8. STATEMENT OF CONSIDERATIONS REQUEST BY GED INTEGRATED SOLUTIONS...

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

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

  9. Integrating Security Solutions to Support nanoCMOS Electronics Research

    E-Print Network [OSTI]

    Sinnott, R.O.

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

  10. Geometric Integration: Numerical Solution of Differential Equations on Manifolds

    E-Print Network [OSTI]

    Burton, Geoffrey R.

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

  11. Comprehensive Solutions for Integration of Solar Resources into Grid

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the YouTube platformBuildingCoalComplex Flow Workshop Report January 17-18,51429Operations |

  12. Demonstrating & Deploying Integrated Retrofit Technologies & Solutions

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:Revised Finding of No53197 This workDayton:|Electricity

  13. Demonstrating and Deploying Integrated Retrofit Technologies and Solutions

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page onYouTube YouTube Note: Since the YouTube| DepartmentStatement Delphi Statement From October, 2008, a statement onAct-

  14. Integrated Dynamic Electron Solutions, Inc. | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferApril 1, 1999 Inspection of SelectedIG-1CONFERENCE ofLandfill Gas to7AC

  15. Integrated Dynamic Electron Solutions, Inc. | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferApril 1, 1999 Inspection of SelectedIG-1CONFERENCE ofLandfill Gas

  16. Integrated Dynamic Electron Solutions, Inc. | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferApril 1, 1999 Inspection of SelectedIG-1CONFERENCE ofLandfill GasTrakLok

  17. Integrated Dynamic Electron Solutions, Inc. | Department of Energy

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy ChinaofSchaeferApril 1, 1999 Inspection of SelectedIG-1CONFERENCE ofLandfill GasTrakLok333

  18. Dispersant solutions for dispersing hydrocarbons

    DOE Patents [OSTI]

    Tyndall, Richard L. (Clinton, TN)

    1997-01-01T23:59:59.000Z

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

  19. Dispersant solutions for dispersing hydrocarbons

    DOE Patents [OSTI]

    Tyndall, R.L.

    1997-03-11T23:59:59.000Z

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

  20. Evolution of smooth shapes and integrable systems

    E-Print Network [OSTI]

    Irina Markina; Alexander Vasil'ev

    2011-11-05T23:59:59.000Z

    We consider a homotopic evolution in the space of smooth shapes starting from the unit circle. Based on the Loewner-Kufarev equation we give a Hamiltonian formulation of this evolution and provide conservation laws. The symmetries of the evolution are given by the Virasoro algebra. The `positive' Virasoro generators span the holomorphic part of the complexified vector bundle over the space of conformal embeddings of the unit disk into the complex plane and smooth on the boundary. In the covariant formulation they are conserved along the Hamiltonian flow. The `negative' Virasoro generators can be recovered by an iterative method making use of the canonical Poisson structure. We study an embedding of the Loewner-Kufarev trajectories into the Segal-Wilson Grassmannian, construct the tau-function, the Baker-Akhiezer function, and finally, give a class of solutions to the KP equation.