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1

ITER  

SciTech Connect (OSTI)

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

Cowley, Steve

2005-10-10T23:59:59.000Z

2

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

E-Print Network [OSTI]

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

Hampshire, Damian

3

Dynamic Planning and control Methodology : understanding and managing iterative error and change cycles in large-scale concurrent design and construction projects  

E-Print Network [OSTI]

Construction projects are uncertain and complex in nature. One of the major driving forces that may account for these characteristics is iterative cycles caused by errors and changes. Errors and changes worsen project ...

Lee, Sang Hyun, 1973-

2006-01-01T23:59:59.000Z

4

Iterative uncertainty reduction via Monte Carlo simulation : a streamlined life cycle assessment case study  

E-Print Network [OSTI]

Life cycle assessment (LCA) is one methodology for assessing a product's impact on the environment. LCA has grown in popularity recently as consumers and governments request more information concerning the environmental ...

Bolin, Christopher E. (Christopher Eric)

2013-01-01T23:59:59.000Z

5

Cytosolic High Km 5 -Nucleotidase and 5 (3 )-Deoxyribonucleotidase in Substrate Cycles Involved in Nucleotide Metabolism*  

E-Print Network [OSTI]

in Nucleotide Metabolism* Received for publication, August 21, 2000, and in revised form, November 14, 2000 that the hkm-NT is not involved in the regulation of deoxyribo- nucleotide pools but affects IMP and GTP pools. dNT-1, instead, appears to be the catabolic arm of substrate cycles regulating pyrimidine nucleotide

Bianchi, Vera

6

Elementary Act of Consciousness or Cycle of Mind, involving Distant and Nonlocal Interaction  

E-Print Network [OSTI]

Each macroscopic process can be subdivided on the quantum and classical stages. Particularly, the quantum stages of Cycle of Mind involves:1) the stimulation of dynamic correlation between water clusters in the same and remote microtubules (MTs) in state of mesoscopic Bose condensation (mBC) by phonons (acoustic waves) and by librational IR photons (electromagnetic-EM waves) distant exchange; 2) the transition from distant EM interaction between remote MTs to nonlocal quantum interaction, induced by IR photons exchange between clusters, the clusters Virtual Replicas multiplication (VRM) and virtual guides (VirG) formation between elementary particles of remote coherent water molecules. This process represents transition from mesoscopic Bose condensation to macroscopic nonuniform semi-virtual Bose condensation (VirBC) (Kaivarainen, 2006, http://arxiv.org/abs/physics/0207027); 3) the collapsing of corresponding macroscopic wave function, as a result of the optical bistability of the entangled water clusters and their disassembly due to librational photons pumping, shifting clusters to less stable state; 4) turning the clusterphilic interaction between water clusters in the open state of cavities between alpha and beta tubulins to hydrophobic one and the in-phase shift of these cavities to the closed state due to clusters disassembly (Kaivarainen, http://arxiv.org/abs/physics/0102086). The classical stages of our Hierarchic model of elementary act of Cycle of Mind are analyzed in detail.

Alex Kaivarainen

2007-09-11T23:59:59.000Z

7

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

E-Print Network [OSTI]

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

Scherrer, Bruno

8

ITER Project  

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

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9

US ITER Moving Forward  

ScienceCinema (OSTI)

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

US ITER / ORNL

2012-03-16T23:59:59.000Z

10

ECRH System For ITER  

SciTech Connect (OSTI)

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

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

2009-11-26T23:59:59.000Z

11

ITER MHD stability analysis. Final report  

SciTech Connect (OSTI)

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

Turnbull, A.D.

1996-05-01T23:59:59.000Z

12

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

13

ITER convertible blanket evaluation  

SciTech Connect (OSTI)

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

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

1995-09-01T23:59:59.000Z

14

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

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)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News

18

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News7

19

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News78

20

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6 News789

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


21

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUSUS ITER6

22

US ITER | Media Corner  

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

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23

The physics role of ITER  

SciTech Connect (OSTI)

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

Rutherford, P.H.

1997-04-01T23:59:59.000Z

24

ITER Fusion Energy  

ScienceCinema (OSTI)

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

Dr. Norbert Holtkamp

2010-01-08T23:59:59.000Z

25

U.S. Plans and Strategy for ITER Blanket Testing  

SciTech Connect (OSTI)

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

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

2005-04-15T23:59:59.000Z

26

ITER risk workshop participant guide  

SciTech Connect (OSTI)

The goal of planning risk management is to make everyone involved in a program aware that risk should be a consideration in the design, development, and fielding of a system. Risk planning is a tool to assess and mitigate events that might adversely impact the program. Therefore, risk management increases the probability/likelihood of program success and can help to avoid program crisis management and improve problem solving by managing risk early in the acquisition cycle.

Medina, Patricia [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

27

ITER breeding blanket design  

SciTech Connect (OSTI)

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

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

1995-12-31T23:59:59.000Z

28

US ITER | Media Corner  

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

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29

US ITER | Media Corner  

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

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30

US ITER | Media Corner  

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

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31

US ITER | Media Corner  

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

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32

ITER blanket designs  

SciTech Connect (OSTI)

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

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

1994-12-31T23:59:59.000Z

33

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

SciTech Connect (OSTI)

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

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

1992-12-01T23:59:59.000Z

34

US ITER | About  

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

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35

US ITER | Media Corner  

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

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36

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnet requiresUS

37

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's Fusion

38

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's FusionUS

39

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's central magnetORNL's

40

US ITER | Media Corner  

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

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While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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41

US ITER | Media Corner  

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

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42

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sectorlong version) The0 -ITER's centralNewUS Production

43

US ITER | Media Corner  

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

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44

What is ITER  

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

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45

US ITER | About  

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

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46

US ITER | About  

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

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47

US ITER | About  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. CrudeElectronPelletIonITER

48

US ITER | Media Corner  

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

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49

US ITER | Media Corner  

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

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50

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER MajorIntest

51

US ITER | Media Corner  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy ConferenceKelli KizerUS ITER

52

ITER CENTRAL SOLENOID COIL INSULATION QUALIFICATION  

SciTech Connect (OSTI)

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

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

2009-06-11T23:59:59.000Z

53

ITER Central Solenoid Coil Insulation Qualification  

SciTech Connect (OSTI)

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

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

2010-01-01T23:59:59.000Z

54

Dynamic simulation of a proposed ITER tritium processing system  

SciTech Connect (OSTI)

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

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

1995-10-01T23:59:59.000Z

55

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

56

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

57

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

58

ITER Diagnostic First Wal  

SciTech Connect (OSTI)

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

G. Douglas Loesser, et. al.

2012-09-21T23:59:59.000Z

59

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

60

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

E-Print Network [OSTI]

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

Hampshire, Damian

Note: This page contains sample records for the topic "involves iterative cycling" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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61

Michel Claessens michel.claessens@iter.org  

E-Print Network [OSTI]

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

62

Parent Involvement  

E-Print Network [OSTI]

To be successful, a 4-H program must have parent involvement. Although 4-H leaders and Extension agents may interest young people in becoming members, they need the parents' goodwill and support to keep them interested, enthusiastic and active. Here...

Howard, Jeff W.

2005-05-10T23:59:59.000Z

63

Nuclear Forensic Inferences Using Iterative Multidimensional Statistics  

SciTech Connect (OSTI)

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

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

2009-06-09T23:59:59.000Z

64

Advanced thermochemical hydrogen cycles  

SciTech Connect (OSTI)

The overall objective of this program is to contribute to the development of practical thermochemical cycles for the production of hydrogen from water. Specific goals are: investigate and evaluate the technical and economic viability of thermochemical cycles as an advanced technology for producing hydrogen from water; investigate and evaluate the engineering principles involved in interfacing individual thermochemical cycles with the different thermal energy sources (high temperature fission, solar, and fusion); and conduct a continuing research and development effort to evaluate the use of solid sulfates, oxides and other compounds as potentially advanced cycles and as alternates to H/sub 2/SO/sub 4/ based cycles. Basic thermochemistry studies have been completed for two different steps in the decomposition of bismuth sulfate. Two different bismuth sulfate cycles have been defined for different sulfuric acid strengths. The eventual best cycle will depend on energy required to form sulfuric acid at different concentrations. A solids decomposition facility has been constructed and practical studies of solid decompositions are being conducted. The facility includes a rotary kiln system and a dual-particle fluidized bed system. Evaluation of different types of cycles for coupling with different heat sources is continuing.

Hollabaugh, C.M.; Bowman, M.G.

1981-01-01T23:59:59.000Z

65

On the Strategy and Requirements for Neutronics Testing in ITER  

SciTech Connect (OSTI)

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

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

2005-05-15T23:59:59.000Z

66

Qualification of the Joints for the ITER Central Solenoid  

SciTech Connect (OSTI)

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

Martovetsky, N; Berryhill, A; Kenney, S

2011-09-01T23:59:59.000Z

67

ITER | Princeton Plasma Physics Lab  

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68

US ITER Moving Forward Video  

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

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69

Princeton Plasma Physics Lab - ITER  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FOR Primary Author Last Nameenergyiter ITER is a

70

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

71

Graph Kernels Based on Relevant Patterns and Cycle Information for Chemoinformatics  

E-Print Network [OSTI]

by combining relevant cycles and newly discovered cycles. Horv´ath showed that a low number of iterationsGraph Kernels Based on Relevant Patterns and Cycle Information for Chemoinformatics Benoit Ga of view, graph kernels provide a nice framework for combining these two fields. We present in this paper

Boyer, Edmond

72

Iterative multiuser detection techniques for CDMA systems  

E-Print Network [OSTI]

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

Du, Xuechao

2012-06-07T23:59:59.000Z

73

Iterative Speech Enhancement With Spectral Constraints  

E-Print Network [OSTI]

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

Texas at Dallas, University of

74

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

75

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

76

ITER11/3/04 Y. Shimomura  

E-Print Network [OSTI]

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

77

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

78

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

79

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...

80

Value iteration for (switched) homogeneous systems  

E-Print Network [OSTI]

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

Dahleh, Munther A.

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


81

ITERATIVE METHODS FOR NEUTRON TRANSPORT EIGENVALUE PROBLEMS  

E-Print Network [OSTI]

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

Graham, Ivan

82

Iterated maps for clarinet-like systems  

E-Print Network [OSTI]

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

Pierre-Andr Taillard; Jean Kergomard; Franck Lalo

2010-05-31T23:59:59.000Z

83

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

84

CHINA SPALLATION NEUTRON SOURCE PROJECT: DESIGN ITERATIONS AND R AND D STATUS.  

SciTech Connect (OSTI)

The China Spallation Neutron Source (CSNS) is an accelerator based high power project currently under preparation in China. The accelerator complex is based on an H{sup -} linear accelerator and a rapid cycling proton synchrotron. During the past year, the design of most accelerator systems went through major iterations, and initial research and developments were started on the prototyping of several key components. This paper summarizes major activities of the past year.

WEI,J.

2006-09-21T23:59:59.000Z

85

Cycle cover with short cycles Nicole Immorlica  

E-Print Network [OSTI]

Introduction Given a graph and a subset of marked elements (nodes, edges, or some combination thereof), a cycleCycle cover with short cycles Nicole Immorlica£ Mohammad Mahdian£ Vahab S. Mirrokni£ Abstract Cycle for variants of cycle covering problems which bound the size and/or length of the covering cycles

Immorlica, Nicole

86

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

87

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

E-Print Network [OSTI]

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

88

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

89

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

E-Print Network [OSTI]

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

90

M. Bahrami ENSC 461 (S 11) Carnot Cycle 1 Power Cycles  

E-Print Network [OSTI]

adiabatically through the turbine and work is developed. The steam temperature decreases from TH to TL 2-3: Two represent the net work of the idealized cycle. Remember that an ideal power cycle does not involve any a simple vapor power plant. Fig. 2-2: Carnot vapor cycle. 1-2: The steam exiting the boiler expands

Bahrami, Majid

91

US solid breeder blanket design for ITER  

SciTech Connect (OSTI)

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

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

1990-09-01T23:59:59.000Z

92

Beyond ITER: Neutral beams for DEMO  

E-Print Network [OSTI]

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

McAdams, R

2013-01-01T23:59:59.000Z

93

Plan and Strategy for ITER Blanket Testing in Japan  

SciTech Connect (OSTI)

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

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

2005-05-15T23:59:59.000Z

94

Michel Claessens michel.claessens@iter.org  

E-Print Network [OSTI]

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

95

ITER Project Status Fusion Energy Sciences  

E-Print Network [OSTI]

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

96

CONTRACTIVITY IN TURBO ITERATIONS Phillip A. Regalia  

E-Print Network [OSTI]

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

Regalia, Phillip A.

97

Limited View Angle Iterative CT Reconstruction  

E-Print Network [OSTI]

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

98

Funding for nuclear fusion Expensive Iteration  

E-Print Network [OSTI]

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

99

Bold Step by the World to Fusion Energy: ITER  

E-Print Network [OSTI]

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

100

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

E-Print Network [OSTI]

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

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


101

ITER HEAT REMOVAL SYSTEM SYSTEM & PROCESS CONTROL DESIGN  

E-Print Network [OSTI]

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

Raffray, A. René

102

On the Logic of Iterated Non-prioritised Richard Booth  

E-Print Network [OSTI]

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

Booth, Richard

103

A Conditional Logic for Iterated Belief Revision Laura Giordano  

E-Print Network [OSTI]

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

Giordano, Laura

104

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

105

Introduction The complex life cycle of holometabolous insects involves  

E-Print Network [OSTI]

in the larval fat body, a single-cell thick tissue composed of fat cells. These larval fat cells serve.R.A. and D.K.H., unpublished data). Larvae must therefore acquire enough nutrients not only to fuel by the adult. The unusual developmental history of the larval fat body complicates our understanding of its

Ahmad, Sajjad

106

Commitment to Public Involvement  

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

Create a Sustainable Future Commitment to Public Involvement Commitment to Public Involvement LANL is commited to our neighbors August 1, 2013 Lab Director McMillan talks with...

107

Development of structural design criteria for ITER.  

SciTech Connect (OSTI)

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

Majumdar, S.

1998-06-22T23:59:59.000Z

108

Thermomechanical analysis of the ITER breeding blanket  

SciTech Connect (OSTI)

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

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

1997-03-01T23:59:59.000Z

109

Analysis of supercritical CO{sub 2} cycle control strategies and dynamic response for Generation IV Reactors.  

SciTech Connect (OSTI)

The analysis of specific control strategies and dynamic behavior of the supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle has been extended to the two reactor types selected for continued development under the Generation IV Nuclear Energy Systems Initiative; namely, the Very High Temperature Reactor (VHTR) and the Sodium-Cooled Fast Reactor (SFR). Direct application of the standard S-CO{sub 2} recompression cycle to the VHTR was found to be challenging because of the mismatch in the temperature drop of the He gaseous reactor coolant through the He-to-CO{sub 2} reactor heat exchanger (RHX) versus the temperature rise of the CO{sub 2} through the RHX. The reference VHTR features a large temperature drop of 450 C between the assumed core outlet and inlet temperatures of 850 and 400 C, respectively. This large temperature difference is an essential feature of the VHTR enabling a lower He flow rate reducing the required core velocities and pressure drop. In contrast, the standard recompression S-CO{sub 2} cycle wants to operate with a temperature rise through the RHX of about 150 C reflecting the temperature drop as the CO{sub 2} expands from 20 MPa to 7.4 MPa in the turbine and the fact that the cycle is highly recuperated such that the CO{sub 2} entering the RHX is effectively preheated. Because of this mismatch, direct application of the standard recompression cycle results in a relatively poor cycle efficiency of 44.9%. However, two approaches have been identified by which the S-CO{sub 2} cycle can be successfully adapted to the VHTR and the benefits of the S-CO{sub 2} cycle, especially a significant gain in cycle efficiency, can be realized. The first approach involves the use of three separate cascaded S-CO{sub 2} cycles. Each S-CO{sub 2} cycle is coupled to the VHTR through its own He-to-CO{sub 2} RHX in which the He temperature is reduced by 150 C. The three respective cycles have efficiencies of 54, 50, and 44%, respectively, resulting in a net cycle efficiency of 49.3 %. The other approach involves reducing the minimum cycle pressure significantly below the critical pressure such that the temperature drop in the turbine is increased while the minimum cycle temperature is maintained above the critical temperature to prevent the formation of a liquid phase. The latter approach also involves the addition of a precooler and a third compressor before the main compressor to retain the benefits of compression near the critical point with the main compressor. For a minimum cycle pressure of 1 MPa, a cycle efficiency of 49.5% is achieved. Either approach opens up the door to applying the SCO{sub 2} cycle to the VHTR. In contrast, the SFR system typically has a core outlet-inlet temperature difference of about 150 C such that the standard recompression cycle is ideally suited for direct application to the SFR. The ANL Plant Dynamics Code has been modified for application to the VHTR and SFR when the reactor side dynamic behavior is calculated with another system level computer code such as SAS4A/SYSSYS-1 in the SFR case. The key modification involves modeling heat exchange in the RHX, accepting time dependent tabular input from the reactor code, and generating time dependent tabular input to the reactor code such that both the reactor and S-CO{sub 2} cycle sides can be calculated in a convergent iterative scheme. This approach retains the modeling benefits provided by the detailed reactor system level code and can be applied to any reactor system type incorporating a S-CO{sub 2} cycle. This approach was applied to the particular calculation of a scram scenario for a SFR in which the main and intermediate sodium pumps are not tripped and the generator is not disconnected from the electrical grid in order to enhance heat removal from the reactor system thereby enhancing the cooldown rate of the Na-to-CO{sub 2} RHX. The reactor side is calculated with SAS4A/SASSYS-1 while the S-CO{sub 2} cycle is calculated with the Plant Dynamics Code with a number of iterations over a timescale of 500 seconds. It is found that the RHX u

Moisseytsev, A.; Sienicki, J. J. (Nuclear Engineering Division)

2011-04-12T23:59:59.000Z

110

ITER Physics and Exploring Magnetically-Confined  

E-Print Network [OSTI]

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

111

US Demo test blankets in ITER  

SciTech Connect (OSTI)

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

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

1996-12-31T23:59:59.000Z

112

Simple ocean carbon cycle models  

SciTech Connect (OSTI)

Simple ocean carbon cycle models can be used to calculate the rate at which the oceans are likely to absorb CO{sub 2} from the atmosphere. For problems involving steady-state ocean circulation, well calibrated ocean models produce results that are very similar to results obtained using general circulation models. Hence, simple ocean carbon cycle models may be appropriate for use in studies in which the time or expense of running large scale general circulation models would be prohibitive. Simple ocean models have the advantage of being based on a small number of explicit assumptions. The simplicity of these ocean models facilitates the understanding of model results.

Caldeira, K. [Lawrence Livermore National Lab., CA (United States); Hoffert, M.I. [New York Univ., NY (United States). Dept. of Earth System Sciences; Siegenthaler, U. [Bern Univ. (Switzerland). Inst. fuer Physik

1994-02-01T23:59:59.000Z

113

Cycle Track Lessons Learned  

E-Print Network [OSTI]

Cycle Track Lessons Learned #12;Presentation Overview · Bicycling trends · Cycle track lessons learned · What is a "Cycle track"? · Essential design elements of cycle tracks Separation Width Crossing driveways & low-volume streets Signalized intersections #12;Trend in kilometers cycled per year

Bertini, Robert L.

114

Cell cycle nucleic acids, polypeptides and uses thereof  

DOE Patents [OSTI]

The invention provides isolated nucleic acids and their encoded proteins that are involved in cell cycle regulation. The invention further provides recombinant expression cassettes, host cells, transgenic plants, and antibody compositions. The present invention provides methods and compositions relating to altering cell cycle protein content, cell cycle progression, cell number and/or composition of plants.

Gordon-Kamm, William J. (Urbandale, IA); Lowe, Keith S. (Johnston, IA); Larkins, Brian A. (Tucson, AZ); Dilkes, Brian R. (Tucson, AZ); Sun, Yuejin (Westfield, IN)

2007-08-14T23:59:59.000Z

115

Development and test of the ITER conductor joints  

SciTech Connect (OSTI)

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

Martovetsky, N., LLNL

1998-05-14T23:59:59.000Z

116

Variational Iteration Method for Image Restoration  

E-Print Network [OSTI]

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

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

2010-01-01T23:59:59.000Z

117

US ITER toroidal field coil conductor produc  

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

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

118

p-points in iterated forcing extensions  

E-Print Network [OSTI]

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

Roitman, Judith A.

1978-05-03T23:59:59.000Z

119

Heavy Truck Duty Cycle (HTDC) Project The Heavy Truck Duty Cycle (HTDC)  

E-Print Network [OSTI]

data from trucks operating in long-haul operations. The research program was designed to be conductedHeavy Truck Duty Cycle (HTDC) Project OVERVIEW The Heavy Truck Duty Cycle (HTDC) Project. The project involves efforts to collect, analyze and archive data and information related to class -8 truck

120

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

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


121

A review of ITER blanket designs  

SciTech Connect (OSTI)

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

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

1994-11-01T23:59:59.000Z

122

Diverse Power Iteration Embeddings and Its Applications  

SciTech Connect (OSTI)

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

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

2014-12-14T23:59:59.000Z

123

Involvement and Communication Committee.  

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

Public Involvement and Communication Committee Chair 1 : Liz Mattson 4 , Alternate Vice Chair 1 : Ken Niles 4 , Member Committee Members 2 : Shelley Cimon Peggy Maze Johnson Rob...

124

Proving termination by policy iteration Damien Masse1  

E-Print Network [OSTI]

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

Paris-Sud XI, Universit de

125

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

126

A Turbo Iteration Algorithm In 16QAM Hierarchical Modulation  

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

127

Properties of Iterated Multiple Belief Revision Dongmo Zhang  

E-Print Network [OSTI]

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

Zhang, Dongmo

128

Iterated Belief Revision and Conditional Logic Laura Giordano  

E-Print Network [OSTI]

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

Torino, Università di

129

BLIND ITERATIVE RESTORATION OF IMAGES WITH SPATIALLY-VARYING BLUR  

E-Print Network [OSTI]

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

Bardsley, John

130

Nested Loop Algorithm for Parallel Model Based Iterative Reconstruction  

E-Print Network [OSTI]

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

131

Accelerated Iterative Method for Solving Steady Solutions of Linearized Atmospheric Models  

E-Print Network [OSTI]

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

Watanabe, Masahiro

132

ITER L-Mode Confinement Database  

SciTech Connect (OSTI)

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

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

1997-10-01T23:59:59.000Z

133

Combined Cycle Cogeneration at NALCO Chemical  

E-Print Network [OSTI]

centrifugal chilling capacity expansion were integrated into the model. The gas turbine selection procedure is out lined. Bid evaulation procedure involved a life cycle cost comparison wherein the bid specification responses for each model turbine were... ~ STEAM USE - LB/HR Figure 1 ? NALCO CHEMICAL COMPANY, NAPERVILLE FACILITIES STEAM USE PROFILE Cogeneration Approach Three modes of cogeneration are typically available. These are steam cycle, gas turbine, and reciprocating engine. Preliminary...

Thunem, C. B.; Jacobs, K. W.; Hanzel, W.

134

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

E-Print Network [OSTI]

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

135

Radioactivity measurements of ITER materials using TFTR D-T neutron field  

SciTech Connect (OSTI)

TFTR successfully initiated trace tritium plasma experiments in mid-November 1993. During the coming year, the TFTR plasma tritium fraction is scheduled to be increased to at least 50%. The availability of larger amounts of D-T fusion neutrons in the high power D-T plasma phase of TFTR provides an useful opportunity to directly measure D-T neutron induced radioactivity in a realistic tokamak-environment in materials of vital interest to ITER. These measurements are invaluable for characterizing short and long lived radioactivity in various ITER candidate materials, for validating complex neutron transport calculations, and for meeting fusion reactor licensing requirements. The radioactivity measurements at TFTR will involve potential ITER materials that include stainless steel 316, vanadium-alloy, copper, iron, nickel, chromium, vanadium, titanium, manganese, cobalt, molybdenum, zinc, niobium, zirconium, tungsten, lead, tin, silicon, etc. Small samples of these materials will be irradiated in varying neutron energy spectra at the vacuum vessel first wall. These irradiated samples will then be counted for {gamma}-radioactivity at different cooling times to get extensive information on as many {gamma}-emitting radioactive products as feasible.

Kumar, A.; Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Kugel, H.W. [Princeton Univ., NJ (United States)] [and others

1994-12-31T23:59:59.000Z

136

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

E-Print Network [OSTI]

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

Heffron, Timothy Paul

2005-01-01T23:59:59.000Z

137

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

E-Print Network [OSTI]

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

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

2008-01-01T23:59:59.000Z

138

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECN/NEA activities reports; not reflect any one single source but frequently represent a consolidation/combination of information.

Leigh, I.W.; Patridge, M.D.

1991-05-01T23:59:59.000Z

139

Information Technology Systems for Fusion Industry and ITER Project  

SciTech Connect (OSTI)

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

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

2005-04-15T23:59:59.000Z

140

Power Plant Cycling Costs  

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

(say, a trip) and such factors are not fully captured in this dataset. 9. Older combined cycle units were a step change in lower operating costs due to cycling...

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


141

Edgeworth cycles revisited  

E-Print Network [OSTI]

Some gasoline markets exhibit remarkable price cycles, where price spikes are followed by a series of small price declines: a pattern consistent with a model of Edgeworth cycles described by Maskin and Tirole. We extend ...

Doyle, Joseph J.

142

Photovoltaics Life Cycle Analysis  

E-Print Network [OSTI]

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

143

mathematics single cycle  

E-Print Network [OSTI]

47 mathematics education single cycle master's study programme #12;48 single cycle master's study program in Mathematics Education #12;49 single cycle master's study program in Mathematics Education MATHEMATICS EDUCATION The program is in tune with the principles of the Bologna Declaration. · Academic title

?umer, Slobodan

144

Cycle to Cycle Manufacturing Process Control  

E-Print Network [OSTI]

Most manufacturing processes produce parts that can only be correctly measured after the process cycle has been completed. Even if in-process measurement and control is possible, it is often too expensive or complex to ...

Hardt, David E.

145

Importance of life cycle assessment  

SciTech Connect (OSTI)

The paper presents Life Cycle Assessment (LCA) as a tool to assist the waste professional with integrated waste management. LCA can be the connection between the waste professional and designer/producer to permit the waste professional to encourage the design of products so material recovery is most efficient and markets can be better predicted. The waste professional can better monitor the involvement of the consumer in waste management by using LCA and looking upstream at how the consumer actually reacts to products and packaging. LCA can also help the waste professional better understand the waste stream.

Bridges, J.S.

1994-06-16T23:59:59.000Z

146

Circadian Clock Genes Contribute to the Regulation of Hair Follicle Cycling  

E-Print Network [OSTI]

characterization of a new hair keratin-associated protein (neurturin: involvement in hair cycle control. Am J PatholPaus R (2001) Controls of hair follicle cycling. Physiol Rev

2009-01-01T23:59:59.000Z

147

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

E-Print Network [OSTI]

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

Raffray, A. René

148

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

E-Print Network [OSTI]

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

Abdou, Mohamed

149

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

E-Print Network [OSTI]

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

Andr Gsponer; Jean-pierre Hurni

2004-01-01T23:59:59.000Z

150

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

151

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

E-Print Network [OSTI]

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

Carmignani, B

2005-01-01T23:59:59.000Z

152

Dale M. Meade MFE Plenary Session on ITER Costs  

E-Print Network [OSTI]

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

153

Visible and Infrared Optical Design for the ITER Upper Ports  

SciTech Connect (OSTI)

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

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

2007-03-01T23:59:59.000Z

154

DIII-D Research in Support of ITER  

SciTech Connect (OSTI)

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

Strait, E

2008-10-14T23:59:59.000Z

155

Stirling-cycle refrigerator  

SciTech Connect (OSTI)

A Stirling-cycle refrigerator comprises a plurality of Stirling-cycle refrigerator units each having a displacer defining an expansion chamber, a piston defining a compression chamber, and a circuit including a heater and a cooler and interconnecting the expansion chamber and the compression chamber, and a heat exchanger shared by the circuits and disposed between the coolers and the heaters for effecting heat exchange between working gases in the circuits. The heat exchanger may comprise a countercurrent heat exchanger, and the Stirling-cycle refrigerator units are operated in cycles which are 180/sup 0/ out of phase with each other.

Nakamura, K.

1985-06-11T23:59:59.000Z

156

Negative Ion Based Heating and Diagnostic Neutral Beams for ITER  

SciTech Connect (OSTI)

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

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

2008-04-07T23:59:59.000Z

157

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

E-Print Network [OSTI]

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

Raffray, A. René

158

ASI Student Involvement Outcomes ASI Student Involvement Outcomes  

E-Print Network [OSTI]

ASI Student Involvement Outcomes ASI Student Involvement Outcomes A student involved in the activities, programs, and services of the Associated Students, CSUF, Inc. develops and demonstrates achievement in the following (adopted from the University of Minnesota Student Success Outcomes

de Lijser, Peter

159

Power Plant Cycling Costs  

SciTech Connect (OSTI)

This report provides a detailed review of the most up to date data available on power plant cycling costs. The primary objective of this report is to increase awareness of power plant cycling cost, the use of these costs in renewable integration studies and to stimulate debate between policymakers, system dispatchers, plant personnel and power utilities.

Kumar, N.; Besuner, P.; Lefton, S.; Agan, D.; Hilleman, D.

2012-07-01T23:59:59.000Z

160

Life Cycle Cost Estimate  

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

Life-cycle costs (LCCs) are all the anticipated costs associated with a project or program alternative throughout its life. This includes costs from pre-operations through operations or to the end of the alternative.This chapter discusses life cycle costs and the role they play in planning.

1997-03-28T23:59:59.000Z

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


161

Advanced Fuel Cycles Activities in IAEA  

SciTech Connect (OSTI)

Considerable scientific and technical progress in many areas of Partitioning and Transmutation (P and T) has been recognized as probable answers to ever-growing issues threatening sustainability, environmental protection and non-proliferation. These recent global developments such as Russian initiative on Global Nuclear Infrastructure-International Fuel Centre and the US initiative on Global Nuclear Energy Partnership (GNEP) have made advanced fuel cycles as one of the decisive influencing factor for the future growth of nuclear energy. International Atomic Energy Agency has initiated the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) with overall objective of bringing together technology holders and technology users to consider jointly the international and national actions required achieving desired innovations in nuclear reactors and fuel cycles. One of the interesting common features of these initiatives (INPRO, GNEP and GNI-IFC) is closed fast reactor fuel cycles and proliferation resistance. Any fuel cycle that integrate P and T into it is also known as 'Advanced Fuel Cycle' (AFC) that could achieve reduction of plutonium and Minor Actinide (MA) elements (namely Am, Np, Cm, etc.). In this regard, some Member States are also evaluating alternative concepts involving the use of thorium fuel cycle, inert-matrix fuel or coated particle fuel. Development of 'fast reactors with closed fuel cycles' would be the most essential step for implementation of P and T. The scale of realization of any AFC depends on the maturity of the development of all these elemental technologies such as recycling MA, Pu as well as reprocessed uranium. In accordance with the objectives of the Agency, the programme B entitled 'Nuclear Fuel cycle technologies and materials' initiated several activities aiming to strengthen the capabilities of interested Member States for policy making, strategic planning, technology development and implementation of safe, reliable, economically efficient, proliferation resistant, environmentally sound and secure nuclear fuel cycle programmes. The paper describes some on-going IAEA activities in the area of: MA-fuel and target, thorium fuel cycle, coated particle fuel, MA-property database, inert matrix fuels, liquid metal cooled fast reactor fuels and fuel cycles, management of reprocessed uranium and proliferation resistance in fuel cycle. (authors)

Nawada, H.P.; Ganguly, C. [Nuclear Fuel Cycle and Materials Section, Division of Nuclear Fuel Cycle and Waste Technology, Department of Nuclear Energy, International Atomic Energy Agency, Vienna (Austria)

2007-07-01T23:59:59.000Z

162

Description of the prototype diagnostic residual gas analyzer for ITER  

SciTech Connect (OSTI)

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

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

2014-11-15T23:59:59.000Z

163

Diamond neutral particle spectrometer for fusion reactor ITER  

SciTech Connect (OSTI)

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

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

2014-08-21T23:59:59.000Z

164

STELLOPT Modeling of the 3D Diagnostic Response in ITER  

SciTech Connect (OSTI)

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

Lazerson, Samuel A

2013-05-07T23:59:59.000Z

165

Iterative methods for solving nonlinear problems of nuclear reactor criticality  

SciTech Connect (OSTI)

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

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

2012-12-15T23:59:59.000Z

166

Iterative reconstruction of the detector response for medical gamma cameras  

E-Print Network [OSTI]

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

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

2015-01-01T23:59:59.000Z

167

Bragg x-ray survey spectrometer for ITER  

SciTech Connect (OSTI)

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

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

2012-10-15T23:59:59.000Z

168

Fusion Materials Science and Technology Research Needs: Now and During the ITER era  

SciTech Connect (OSTI)

The plasma facing components, first wall and blanket systems of future tokamak-based fusion power plants arguably represent the single greatest materials engineering challenge of all time. Indeed, the United States National Academy of Engineering has recently ranked the quest for fusion as one of the top grand challenges for engineering in the 21st Century. These challenges are even more pronounced by the lack of experimental testing facilities that replicate the extreme operating environment involving simultaneous high heat and particle fluxes, large time varying stresses, corrosive chemical environments, and large fluxes of 14-MeV peaked fusion neutrons. This paper will review, and attempt to prioritize, the materials research and development challenges facing fusion nuclear science and technology into the ITER era and beyond to DEMO. In particular, the presentation will highlight the materials degradation mechanisms we anticipate to occur in the fusion environment, the temperature- displacement goals for fusion materials and plasma facing components and the near and long-term materials challenges required for both ITER, a fusion nuclear science facility and longer term ultimately DEMO.

Wirth, Brian D.; Kurtz, Richard J.; Snead, Lance L.

2013-09-30T23:59:59.000Z

169

Cell Cycle . Author manuscript Cell cycle regulators in the control of metabolism  

E-Print Network [OSTI]

secretion. There is enough evidence to indicateATP that the CDK4-pRB-E2F1 regulatory pathway is involved ; metabolism ; Energy Metabolism ; physiology ; Homeostasis ; physiology ; Humans ; Lipid Metabolism cycle regulators in lipids and adipocytes metabolism Lipids metabolism not only consists on lipid

Paris-Sud XI, Université de

170

Cycle isolation monitoring  

SciTech Connect (OSTI)

There are many factors to monitor in power plants, but one that is frequently overlooked is cycle isolation. Often this is an area where plant personnel can find 'low hanging fruit' with great return on investment, especially high energy valve leakage. This type of leakage leads to increased heat rate, potential valve damage and lost generation. The fundamental question to ask is 'What is 100 Btu/kW-hr of heat rate worth to your plant? On a 600 MW coal-fired power plant, a 1% leakage can lead to an 81 Btu/kW-hr impact on the main steam cycle and a 64 Btu/kW-hr impact on the hot reheat cycle. The article gives advice on methods to assist in detecting leaking valves and to monitor cycle isolation. A software product, TP. Plus-CIM was designed to estimate flow rates of potentially leaking valves.

Svensen, L.M. III; Zeigler, J.R.; Todd, F.D.; Alder, G.C. [Santee Copper, Moncks Corner, SC (United States)

2009-07-15T23:59:59.000Z

171

Malone cycle refrigerator development  

SciTech Connect (OSTI)

This paper describes the progress made in demonstrating a Malone Cycle Refrigerator/Freezer. The Malone cycle is similar to the Stirling cycle but uses a supercritical fluid in place of real gas. In the approach, solid-metal diaphragms are used to seal and sweep the working volumes against the high working fluid pressures required in Malone cycle machines. This feature eliminates the friction and leakage that accounted for nearly half the losses in the best piston-defined Malone cycle machines built to date. The authors successfully built a Malone cycle refrigerator that: (1) used CO{sub 2} as the working fluid, (2) operated at pressures up to 19.3 Mpa (2,800 psi), (3) achieved a cold end metal temperatures of {minus}29 C ({minus}20 F), and (4) produced over 400 Watts of cooling at near ambient temperatures. The critical diaphragm components operated flawlessly throughout characterization and performance testing, supporting the conclusion of high reliability based on analysis of fatigue date and actual strain measurements.

Shimko, M.A.; Crowley, C.J.

1999-07-01T23:59:59.000Z

172

A Coupled Quantum Otto Cycle  

E-Print Network [OSTI]

We study the 1-d isotropic Heisenberg model of two spin-1/2 systems as a quantum heat engine. The engine undergoes a four-step Otto cycle where the two adiabatic branches involve changing the external magnetic field at a fixed value of the coupling constant. We find conditions for the engine efficiency to be higher than the uncoupled model; in particular, we find an upper bound which is tighter than the Carnot bound. A new domain of parameter values is pointed out which was not feasible in the interaction-free model. Locally, each spin seems to effect the flow of heat in a direction opposite to the global temperature gradient. This seeming contradiction to the second law can be resolved in terms of local effective temperature of the spins.

George Thomas; Ramandeep S. Johal

2010-11-03T23:59:59.000Z

173

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

174

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

175

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

E-Print Network [OSTI]

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

176

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

Leigh, I.W.

1992-05-01T23:59:59.000Z

177

International nuclear fuel cycle fact book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source or information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

Leigh, I.W.

1988-01-01T23:59:59.000Z

178

International Nuclear Fuel Cycle Fact Book  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops, etc. The data listed do not reflect any one single source but frequently represent a consolidation/combination of information.

Leigh, I W; Mitchell, S J

1990-01-01T23:59:59.000Z

179

Soil metagenomics and carbon cycling  

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

Soil metagenomics and carbon cycling Soil metagenomics and carbon cycling Establishing a foundational understanding of the microbial and ecosystem factors that control carbon...

180

A Transport Synthetic Acceleration method for transport iterations  

E-Print Network [OSTI]

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

Ramone, Gilles Lionel

1996-01-01T23:59:59.000Z

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


181

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

182

Overview of Recent Developments in Pellet Injection for ITER  

SciTech Connect (OSTI)

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

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

2012-01-01T23:59:59.000Z

183

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

SciTech Connect (OSTI)

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

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

1996-12-01T23:59:59.000Z

184

Plans for U.S. Contributions to ITER  

E-Print Network [OSTI]

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

185

Iterative Detection and Channel Estimation for Thomas Zemen  

E-Print Network [OSTI]

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

Müller, Ralf R.

186

Iterative Detection and Channel Estimation for Thomas Zemen  

E-Print Network [OSTI]

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

Zemen, Thomas

187

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

188

About the Limiting Behaviour of Iterated Robust Morphological Operators  

E-Print Network [OSTI]

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

Van Horebeek, Johan

189

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

E-Print Network [OSTI]

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

Wickerhauser, M. Victor

190

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

E-Print Network [OSTI]

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

Mueller, Klaus

191

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

E-Print Network [OSTI]

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

2014-10-15T23:59:59.000Z

192

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

193

Error Control of Iterative Linear Solvers for Integrated Groundwater Models  

E-Print Network [OSTI]

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

Bai, Zhaojun

194

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

E-Print Network [OSTI]

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

195

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

E-Print Network [OSTI]

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

Holst, Michael J.

196

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

E-Print Network [OSTI]

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

Torres-Verdín, Carlos

197

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT  

E-Print Network [OSTI]

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

198

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

E-Print Network [OSTI]

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

Zonca, Fulvio

199

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

E-Print Network [OSTI]

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

Abdou, Mohamed

200

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

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


201

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

E-Print Network [OSTI]

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

202

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

203

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

204

Helium process cycle  

DOE Patents [OSTI]

A unique process cycle and apparatus design separates the consumer (cryogenic) load return flow from most of the recycle return flow of a refrigerator and/or liquefier process cycle. The refrigerator and/or liquefier process recycle return flow is recompressed by a multi-stage compressor set and the consumer load return flow is recompressed by an independent consumer load compressor set that maintains a desirable constant suction pressure using a consumer load bypass control valve and the consumer load return pressure control valve that controls the consumer load compressor's suction pressure. The discharge pressure of this consumer load compressor is thereby allowed to float at the intermediate pressure in between the first and second stage recycle compressor sets. Utilizing the unique gas management valve regulation, the unique process cycle and apparatus design in which the consumer load return flow is separate from the recycle return flow, the pressure ratios of each recycle compressor stage and all main pressures associated with the recycle return flow are allowed to vary naturally, thus providing a naturally regulated and balanced floating pressure process cycle that maintains optimal efficiency at design and off-design process cycle capacity and conditions automatically.

Ganni, Venkatarao (Yorktown, VA)

2008-08-12T23:59:59.000Z

205

Helium process cycle  

DOE Patents [OSTI]

A unique process cycle and apparatus design separates the consumer (cryogenic) load return flow from most of the recycle return flow of a refrigerator and/or liquefier process cycle. The refrigerator and/or liquefier process recycle return flow is recompressed by a multi-stage compressor set and the consumer load return flow is recompressed by an independent consumer load compressor set that maintains a desirable constant suction pressure using a consumer load bypass control valve and the consumer load return pressure control valve that controls the consumer load compressor's suction pressure. The discharge pressure of this consumer load compressor is thereby allowed to float at the intermediate pressure in between the first and second stage recycle compressor sets. Utilizing the unique gas management valve regulation, the unique process cycle and apparatus design in which the consumer load return flow is separate from the recycle return flow, the pressure ratios of each recycle compressor stage and all main pressures associated with the recycle return flow are allowed to vary naturally, thus providing a naturally regulated and balanced floating pressure process cycle that maintains optimal efficiency at design and off-design process cycle capacity and conditions automatically.

Ganni, Venkatarao (Yorktown, VA)

2007-10-09T23:59:59.000Z

206

Superfluid thermodynamic cycle refrigerator  

DOE Patents [OSTI]

A cryogenic refrigerator cools a heat source by cyclically concentrating and diluting the amount of .sup.3 He in a single phase .sup.3 He-.sup.4 He solution. The .sup.3 He in superfluid .sup.4 He acts in a manner of an ideal gas in a vacuum. Thus, refrigeration is obtained using any conventional thermal cycle, but preferably a Stirling or Carnot cycle. A single phase solution of liquid .sup.3 He at an initial concentration in superfluid .sup.4 He is contained in a first variable volume connected to a second variable volume through a superleak device that enables free passage of .sup.4 He while restricting passage of .sup.3 He. The .sup.3 He is compressed (concentrated) and expanded (diluted) in a phased manner to carry out the selected thermal cycle to remove heat from the heat load for cooling below 1 K.

Swift, Gregory W. (Santa Fe, NM); Kotsubo, Vincent Y. (La Canada, CA)

1992-01-01T23:59:59.000Z

207

Superfluid thermodynamic cycle refrigerator  

DOE Patents [OSTI]

A cryogenic refrigerator cools a heat source by cyclically concentrating and diluting the amount of [sup 3]He in a single phase [sup 3]He-[sup 4]He solution. The [sup 3]He in superfluid [sup 4]He acts in a manner of an ideal gas in a vacuum. Thus, refrigeration is obtained using any conventional thermal cycle, but preferably a Stirling or Carnot cycle. A single phase solution of liquid [sup 3]He at an initial concentration in superfluid [sup 4]He is contained in a first variable volume connected to a second variable volume through a superleak device that enables free passage of [sup 4]He while restricting passage of [sup 3]He. The [sup 3]He is compressed (concentrated) and expanded (diluted) in a phased manner to carry out the selected thermal cycle to remove heat from the heat load for cooling below 1 K. 12 figs.

Swift, G.W.; Kotsubo, V.Y.

1992-12-22T23:59:59.000Z

208

Understanding the petrochemical cycle  

SciTech Connect (OSTI)

The presentation will examine the nature of the supply, demand and profitability cycles that appear to be endemic in the petrochemical industry. The focus will be on the underlying factors that cause cyclicality. Data for ethylene and first line derivatives will be used both to provide quantitative illustrations of the magnitude of the cyclical effects and to give an improved perspective on the forces that drive cylicality. We will also examine to what extent cycle timing may be predictable, and present some scenario based projections.

Sedriks, W. [SRI Consulting, Melno Park, CA (United States)

1996-10-01T23:59:59.000Z

209

GENERAL CIRCULATION Energy Cycle  

E-Print Network [OSTI]

process. PE is useful for global energy balance. Solar radiant energy does not reach the Earth equally everywhere. On average, the tropics receive and absorb far more solar energy annually than the polar regionsGENERAL CIRCULATION Contents Energy Cycle Mean Characteristics Momentum Budget Overview Energy

Grotjahn, Richard

210

CLASS DESCRIPTIONS CYCLING SERIES  

E-Print Network [OSTI]

will utilize concepts from the 50-minute cycling class while going the distance to optimal health. Whether you're an avid cyclist, triathlete, or desire a longer class for a greater challenge, join us for this 75-minute AN URBANATHLETE Are you registered to compete in an adventure race like the Men's Health Urbanathlon, Warrior Dash

Pittendrigh, Barry

211

Life cycle assessment  

SciTech Connect (OSTI)

Life-Cycle Assessment (LCA) is a technical, data-based and holistic approach to define and subsequently reduce the environmental burdens associated with a product, process, or activity by identifying and quantifying energy and material usage and waste discharges, assessing the impact of those wastes on the environment, and evaluating and implementing opportunities to effect environmental improvements. The assessment includes the entire life-cycle of the product, process or activity encompassing extraction and processing of raw materials, manufacturing, transportation and distribution, use/reuse, recycling and final disposal. LCA is a useful tool for evaluating the environmental consequences of a product, process, or activity, however, current applications of LCA have not been performed in consistent or easily understood ways. This inconsistency has caused increased criticism of LCA. The EPA recognized the need to develop an LCA framework which could be used to provide consistent use across the board. Also, additional research is needed to enhance the understanding about the steps in the performance of an LCA and its appropriate usage. This paper will present the research activities of the EPA leading toward the development of an acceptable method for conducting LCA`s. This research has resulted in the development of two guidance manuals. The first manual is intended to be a practical guide to conducting and interpreting the life-cycle inventory. A nine-step approach to performing a comprehensive inventory is presented along with the general issues to be addressed. The second manual addresses life-cycle design.

Curran, M.A. [Environmental Protection Agency, Cincinnati, OH (United States)

1994-12-31T23:59:59.000Z

212

Combined Cycle Combustion Turbines  

E-Print Network [OSTI]

Combined Cycle Combustion Turbines Steven Simmons February 27 2014 1 #12;CCCT Today's Discussion 1 Meeting Pricing of 4 advanced units using information from Gas Turbine World Other cost estimates from E E3 EIA Gas Turbine World California Energy Commission Date 2010 Oct 2012, Dec 2013 Apr 2013 2013 Apr

213

An iterative technique for the factorization of polynomials  

E-Print Network [OSTI]

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

Gray, Jerry Edwin

2012-06-07T23:59:59.000Z

214

Water-cooled solid-breeder blanket concept for ITER  

SciTech Connect (OSTI)

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

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

1989-03-01T23:59:59.000Z

215

U. S. ITER shield and blanket design activities  

SciTech Connect (OSTI)

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

Baker, C.C.

1989-03-01T23:59:59.000Z

216

Krylov subspace iteration for eigenvalue response matrix calculations  

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

217

Engineering and manufacturing of ITER first mirror mock-ups  

SciTech Connect (OSTI)

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

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

2010-10-15T23:59:59.000Z

218

An Overview of US ITER Test Blanket Module Program  

SciTech Connect (OSTI)

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

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

2006-01-01T23:59:59.000Z

219

Atomic Physics in the Quest for Fusion Energy and ITER  

SciTech Connect (OSTI)

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

Charles H. Skinner

2008-02-27T23:59:59.000Z

220

Iterative solution of ordinary differential equations with polynomial coefficients  

E-Print Network [OSTI]

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

Forehand, Jimmie Charles Rhea

1965-01-01T23:59:59.000Z

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


221

Improved criticality convergence via a modified Monte Carlo iteration method  

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

222

Water-cooled solid-breeder concept for ITER  

SciTech Connect (OSTI)

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

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

1988-08-01T23:59:59.000Z

223

Progress and present status of ITER cryoline system  

SciTech Connect (OSTI)

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

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

2014-01-29T23:59:59.000Z

224

The investigation of exhaust powered, automotive air cycle air conditioning  

E-Print Network [OSTI]

domestic automobiles and trucks because of its proven success. This system requires approximately 4 hp (2. 983 kW)[3] for operation snd employs a pressurized fluorinated hydrocarbon (R-12), hereafter fluorocarbon, as a refrigerant. Most of the research... extraction and avoid the use of a fluorocarbon refrigerant. The maJority of work involved with the new units has associated itself in the area of utilizing an absorption cycle or air cycle. The absorption air conditioning unit differs significantly from...

Holley, James Andrew

1978-01-01T23:59:59.000Z

225

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

226

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

SciTech Connect (OSTI)

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

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

1999-09-01T23:59:59.000Z

227

The Energy Strategy Cycle  

E-Print Network [OSTI]

Effective long-range energy planning begins with a reflective analysis that encompasses the complexity of today's energy reality and sets a course for activity to achieve long-range continuing advancement. This strategy approach involves...

Korich, R. D.

1983-01-01T23:59:59.000Z

228

Stirling cycle engine  

DOE Patents [OSTI]

In a Stirling cycle engine having a plurality of working gas charges separated by pistons reciprocating in cylinders, the total gas content is minimized and the mean pressure equalization among the serial cylinders is improved by using two piston rings axially spaced at least as much as the piston stroke and by providing a duct in the cylinder wall opening in the space between the two piston rings and leading to a source of minimum or maximum working gas pressure.

Lundholm, Gunnar (Lund, SE)

1983-01-01T23:59:59.000Z

229

HEURISTIC SEARCH FOR HAMILTON CYCLES  

E-Print Network [OSTI]

by combining it with the remaining cycles. The following is the description of the main part of the algorithmHEURISTIC SEARCH FOR HAMILTON CYCLES IN CUBIC GRAPHS Janez ALES, Bojan MOHAR and Tomaz PISANSKI. A successful heuristic algorithm for nding Hamilton cycles in cubic graphs is described. Several graphs from

Mohar, Bojan

230

Edinburgh Research Explorer Money Cycles  

E-Print Network [OSTI]

Edinburgh Research Explorer Money Cycles Citation for published version: Clausen, A & Strub, C 2014 'Money Cycles' Edinburgh School of Economics Discussion Paper Series. Link: Link to publication record date: 11. Dec. 2014 #12;Edinburgh School of Economics Discussion Paper Series Number 249 Money Cycles

Millar, Andrew J.

231

Parallel computation of multigroup reactivity coefficient using iterative method  

SciTech Connect (OSTI)

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

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

2013-09-09T23:59:59.000Z

232

MULTIPARAMETER OPTIMIZATION STUDIES ON GEOTHERMAL ENERGY CYCLES  

E-Print Network [OSTI]

of Practical Cycles for Geothermal Power Plants." GeneralDesign and Optimize Geothermal Power Cycles." Presented atof Practical Cycles for Geothermal Power Plants." General

Pope, W.L.

2011-01-01T23:59:59.000Z

233

THE TRANSPOSED CRITICAL TEMPERATURE RANKINE THERMODYNAMIC CYCLE  

E-Print Network [OSTI]

Process Program for Geothermal Power Plant Cycles,'*for a Rankine Cycle Geothermal Power Plant," Proceedings,Design and Optimize Geothermal Power Cycles," presented at

Pope, William L.

2012-01-01T23:59:59.000Z

234

Life-cycle Assessment of Semiconductors  

E-Print Network [OSTI]

life-cycle energy requirements (e total ) and global warmingtotal life-cycle global warming impacts. Chapter 3 Life-cycle Energy and Global

Boyd, Sarah B.

2009-01-01T23:59:59.000Z

235

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

SciTech Connect (OSTI)

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

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

1995-11-01T23:59:59.000Z

236

Solitary Waves of the MRLW Equation by Variational Iteration Method  

SciTech Connect (OSTI)

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

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

2009-09-09T23:59:59.000Z

237

Status of the ITER IC H and CD System  

SciTech Connect (OSTI)

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

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

2009-11-26T23:59:59.000Z

238

Volkov solution for two laser beams and ITER  

E-Print Network [OSTI]

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

Miroslav Pardy

2005-07-12T23:59:59.000Z

239

U.S. ITER | Princeton Plasma Physics Lab  

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

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

240

Quantum thermodynamic cooling cycle  

E-Print Network [OSTI]

The quantum-mechanical and thermodynamic properties of a 3-level molecular cooling cycle are derived. An inadequacy of earlier models is rectified in accounting for the spontaneous emission and absorption associated with the coupling to the coherent driving field via an environmental reservoir. This additional coupling need not be dissipative, and can provide a thermal driving force - the quantum analog of classical absorption chillers. The dependence of the maximum attainable cooling rate on temperature, at ultra-low temperatures, is determined and shown to respect the recently-established fundamental bound based on the second and third laws of thermodynamics.

Palao, J P; Gordon, J M; Palao, Jose P.; Kosloff, Ronnie; Gordon, Jeffrey M.

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "involves iterative cycling" from the National Library of EnergyBeta (NLEBeta).
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241

Geothermal Life Cycle Calculator  

SciTech Connect (OSTI)

This calculator is a handy tool for interested parties to estimate two key life cycle metrics, fossil energy consumption (Etot) and greenhouse gas emission (ghgtot) ratios, for geothermal electric power production. It is based solely on data developed by Argonne National Laboratory for DOEs Geothermal Technologies office. The calculator permits the user to explore the impact of a range of key geothermal power production parameters, including plant capacity, lifetime, capacity factor, geothermal technology, well numbers and depths, field exploration, and others on the two metrics just mentioned. Estimates of variations in the results are also available to the user.

Sullivan, John

2014-03-11T23:59:59.000Z

242

Geothermal Life Cycle Calculator  

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

This calculator is a handy tool for interested parties to estimate two key life cycle metrics, fossil energy consumption (Etot) and greenhouse gas emission (ghgtot) ratios, for geothermal electric power production. It is based solely on data developed by Argonne National Laboratory for DOEs Geothermal Technologies office. The calculator permits the user to explore the impact of a range of key geothermal power production parameters, including plant capacity, lifetime, capacity factor, geothermal technology, well numbers and depths, field exploration, and others on the two metrics just mentioned. Estimates of variations in the results are also available to the user.

Sullivan, John

243

Quantum thermodynamic cooling cycle  

E-Print Network [OSTI]

The quantum-mechanical and thermodynamic properties of a 3-level molecular cooling cycle are derived. An inadequacy of earlier models is rectified in accounting for the spontaneous emission and absorption associated with the coupling to the coherent driving field via an environmental reservoir. This additional coupling need not be dissipative, and can provide a thermal driving force - the quantum analog of classical absorption chillers. The dependence of the maximum attainable cooling rate on temperature, at ultra-low temperatures, is determined and shown to respect the recently-established fundamental bound based on the second and third laws of thermodynamics.

Jose P. Palao; Ronnie Kosloff; Jeffrey M. Gordon

2001-06-08T23:59:59.000Z

244

Beowawe Binary Bottoming Cycle  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd: ScopeDepartment ofEnergyBeowawe Binary Bottoming Cycle

245

Dynamic Analysis of Fuel Cycle Transitioning  

SciTech Connect (OSTI)

This paper examines the time-dependent dynamics of transitioning from a once-through fuel cycle to a closed fuel cycle. The once-through system involves only Light Water Reactors (LWRs) operating on uranium oxide fuel UOX), while the closed cycle includes both LWRs and fast spectrum reactors (FRs) in either a single-tier system or two-tier fuel system. The single-tier system includes full transuranic recycle in FRs while the two-tier system adds one pass of mixed oxide uranium-plutonium (MOX U-Pu) fuel in the LWR. While the analysis primarily focuses on burner fast reactors, transuranic conversion ratios up to 1.0 are assessed and many of the findings apply to any fuel cycle transitioning from a thermal once-through system to a synergistic thermal-fast recycle system. These findings include uranium requirements for a range of nuclear electricity growth rates, the importance of back end fuel cycle facility timing and magnitude, the impact of employing a range of fast reactor conversion ratios, system sensitivity to used fuel cooling time prior to recycle, impacts on a range of waste management indicators, and projected electricity cost ranges for once-through, single-tier and two-tier systems. The study confirmed that significant waste management benefits can be realized as soon as recycling is initiated, but natural uranium savings are minimal in this century. The use of MOX in LWRs decouples the development of recycle facilities from fast reactor fielding, but also significantly delays and limits fast reactor deployment. In all cases, fast reactor deployment was significantly below than predicted by static equilibrium analyses.

Brent Dixon; Steve Piet; David Shropshire; Gretchen Matthern

2009-09-01T23:59:59.000Z

246

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

E-Print Network [OSTI]

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

Commer, M.

2012-01-01T23:59:59.000Z

247

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...

248

International nuclear fuel cycle fact book. Revision 4  

SciTech Connect (OSTI)

This Fact Book has been compiled in an effort to provide (1) an overview of worldwide nuclear power and fuel cycle programs and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids - international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.

1984-03-01T23:59:59.000Z

249

International Nuclear Fuel Cycle Fact Book. Revision 5  

SciTech Connect (OSTI)

This Fact Book has been compiled in an effort to provide: (1) an overview of worldwide nuclear power and fuel cycle programs; and (2) current data concerning fuel cycle and waste management facilities, R and D programs, and key personnel in countries other than the United States. Additional information on each country's program is available in the International Source Book: Nuclear Fuel Cycle Research and Development, PNL-2478, Rev. 2. The Fact Book is organized as follows: (1) Overview section - summary tables which indicate national involvement in nuclear reactor, fuel cycle, and waste management development activities; (2) national summaries - a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; (3) international agencies - a section for each of the international agencies which has significant fuel cycle involvement; (4) energy supply and demand - summary tables, including nuclear power projections; (5) fuel cycle - summary tables; and (6) travel aids international dialing instructions, international standard time chart, passport and visa requirements, and currency exchange rate.

Harmon, K.M.; Lakey, L.T.; Leigh, I.W.; Jeffs, A.G.

1985-01-01T23:59:59.000Z

250

The Kalina cycle and similar cycles for geothermal power production  

SciTech Connect (OSTI)

This report contains a brief discussion of the mechanics of the Kalina cycle and ideas to extend the concept to other somewhat different cycles. A modified cycle which has a potential heat rejection advantage but little or no performance improvement is discussed. Then, the results of the application of the Kalina cycle and the modified cycle to a geothermal application (360/degree/F resource) are discussed. The results are compared with published results for the Kalina cycle with high temperature sources and estimates about performance at the geothermal temperatures. Finally, the conclusions of this scoping work are given along with recommendations of the direction of future work in this area. 11 refs., 4 figs., 1 tab.

Bliem, C.J.

1988-09-01T23:59:59.000Z

251

Kouchoul cycle implication in the Tailer engine cycle  

SciTech Connect (OSTI)

The author presents here the study of the Tailer engine modified cycle using the concept of load transfer for the Kouchoul cycle. Theoretical equations and numerical simulation of the Tailer engine modified cycle implicating the Kouchoul cycle are developed. The Tailer engine modified cycle can be improved by approaching cycles of spark plug engines by the addition of a phase of cooling of gases to the bottom dead center (bdc). This is possible only by putting a reservoir of cooled gas in communication with the cylinder to the bottom dead center. So as not to complicate the kinematic of the engine, the communication between cylinder and cooled reservoir is executed by some holes of 1 mm distributed on the whole periphery of the cylinder at the bdc.

Arques, P.

1996-12-31T23:59:59.000Z

252

Solid breeder blanket option for the ITER conceptual design  

SciTech Connect (OSTI)

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

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

1989-10-01T23:59:59.000Z

253

Modeling results for the ITER cryogenic fore pump  

SciTech Connect (OSTI)

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

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

2014-01-29T23:59:59.000Z

254

Iterative image-domain decomposition for dual-energy CT  

SciTech Connect (OSTI)

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

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

2014-04-15T23:59:59.000Z

255

Cell Cycle . Author manuscript Aurora B kinase, an immobile passenger!  

E-Print Network [OSTI]

Cell Cycle . Author manuscript Page /1 2 Aurora B kinase, an immobile passenger! Marl ne Delacour Keywords Chromosomal passenger complex ; Aurora kinase ; Survivin ; INCENP ; Borealin ; FRAP ; Microtubule composed of Aurora B kinase, Survivin, Borealin and INCENP. The centromeric complex is involved

Boyer, Edmond

256

Life Cycle Inventory of a CMOS Chip  

E-Print Network [OSTI]

are shown. Keywords- Life Cycle Assessment (LCA); Life Cycleindustry, and Life Cycle Assessment (LCA) is emerging as a

Boyd, Sarah; Dornfeld, David; Krishnan, Nikhil

2006-01-01T23:59:59.000Z

257

Open cycle thermoacoustics  

SciTech Connect (OSTI)

A new type of thermodynamic device combining a thermodynamic cycle with the externally applied steady flow of an open thermodynamic process is discussed and experimentally demonstrated. The gas flowing through this device can be heated or cooled in a series of semi-open cyclic steps. The combination of open and cyclic flows makes possible the elimination of some or all of the heat exchangers (with their associated irreversibility). Heat is directly exchanged with the process fluid as it flows through the device when operating as a refrigerator, producing a staging effect that tends to increase First Law thermodynamic efficiency. An open-flow thermoacoustic refrigerator was built to demonstrate this concept. Several approaches are presented that describe the physical characteristics of this device. Tests have been conducted on this refrigerator with good agreement with a proposed theory.

Reid, Robert Stowers

2000-01-01T23:59:59.000Z

258

Stirling cycle rotary engine  

SciTech Connect (OSTI)

A Stirling cycle rotary engine for producing mechanical energy from heat generated by a heat source external to the engine, the engine including: an engine housing having an interior toroidal cavity with a central housing axis for receiving a working gas, the engine housing further having a cool as inlet port, a compressed gas outlet port, a heated compressed gas inlet port, and a hot exhaust gas outlet port at least three rotors each fixedly mounted to a respective rotor shaft and independently rotatable within the toroidal cavity about the central axis; each of the rotors including a pair of rotor blocks spaced radially on diametrically opposing sides of the respective rotor shaft, each rotor block having a radially fixed curva-linear outer surface for sealed rotational engagement with the engine housing.

Chandler, J.A.

1988-06-28T23:59:59.000Z

259

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

SciTech Connect (OSTI)

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

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

2012-10-15T23:59:59.000Z

260

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

E-Print Network [OSTI]

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

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


261

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

SciTech Connect (OSTI)

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

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

2014-01-15T23:59:59.000Z

262

Advanced regenerative absorption refrigeration cycles  

DOE Patents [OSTI]

Multi-effect regenerative absorption cycles which provide a high coefficient of performance (COP) at relatively high input temperatures. An absorber-coupled double-effect regenerative cycle (ADR cycle) (10) is provided having a single-effect absorption cycle (SEA cycle) (11) as a topping subcycle and a single-effect regenerative absorption cycle (1R cycle) (12) as a bottoming subcycle. The SEA cycle (11) includes a boiler (13), a condenser (21), an expansion device (28), an evaporator (31), and an absorber (40), all operatively connected together. The 1R cycle (12) includes a multistage boiler (48), a multi-stage resorber (51), a multisection regenerator (49) and also uses the condenser (21), expansion device (28) and evaporator (31) of the SEA topping subcycle (11), all operatively connected together. External heat is applied to the SEA boiler (13) for operation up to about 500 degrees F., with most of the high pressure vapor going to the condenser (21) and evaporator (31) being generated by the regenerator (49). The substantially adiabatic and isothermal functioning of the SER subcycle (12) provides a high COP. For higher input temperatures of up to 700 degrees F., another SEA cycle (111) is used as a topping subcycle, with the absorber (140) of the topping subcycle being heat coupled to the boiler (13) of an ADR cycle (10). The 1R cycle (12) itself is an improvement in that all resorber stages (50b-f) have a portion of their output pumped to boiling conduits (71a-f) through the regenerator (49), which conduits are connected to and at the same pressure as the highest pressure stage (48a) of the 1R multistage boiler (48).

Dao, Kim (14 Nace Ave., Piedmont, CA 94611)

1990-01-01T23:59:59.000Z

263

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

E-Print Network [OSTI]

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

Raffray, A. René

264

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

E-Print Network [OSTI]

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

Graham, Ivan

265

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

266

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

E-Print Network [OSTI]

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

267

S12.9Constrained Iterative Speech Enhance with Application to  

E-Print Network [OSTI]

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

Texas at Dallas, University of

268

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

E-Print Network [OSTI]

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

Abdou, Mohamed

2006-01-01T23:59:59.000Z

269

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

E-Print Network [OSTI]

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

Kavcic, Aleksandar

270

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

E-Print Network [OSTI]

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

271

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

E-Print Network [OSTI]

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

272

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

273

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

E-Print Network [OSTI]

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

Wang, Desheng

274

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

275

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

276

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

E-Print Network [OSTI]

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

Toint, Philippe

277

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

E-Print Network [OSTI]

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

278

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

E-Print Network [OSTI]

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

McCormick, Steve

279

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

E-Print Network [OSTI]

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

Raffray, A. René

280

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

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


281

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

282

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

283

AN AMMONIA-WATER ABSORPTION-HIAT-PUMP CYCLE Donald Kuhlenschmidt, Member ASHRAE  

E-Print Network [OSTI]

,000 Btuh) input unit reported. KLY WORDS Absorption Heat-pump Air conditioning heating Ammonia Donald conditioning chillers. The authors are involved in a project to use this cycle in an air source heat pump the cycle, comment on the design differences compared to the air conditioning application and report

Oak Ridge National Laboratory

284

Virtuous Cycle Cycles of activity and software projects  

E-Print Network [OSTI]

Inspection #12;Programming Cycle - single bug Selected Bug Shared Code Fix Bug Continuous Integration ~8 cycle cvscheck compilation style checking testing javadocs documentation jumble quality of unit testing #12;NetValue Development cvscheck - Source Code Control and Build Shared Centralized Automatic

Pfahringer, Bernhard

285

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

SciTech Connect (OSTI)

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

NONE

1998-12-31T23:59:59.000Z

286

STUDENT EMPLOYMENT Student Involvement Outcomes  

E-Print Network [OSTI]

STUDENT EMPLOYMENT Student Involvement Outcomes reflective assessment High impact practices ASSOCIATED STUDENTS, CSUF, INC. Committed TO ON-CAMPUS ENGAGEMENT · SUPPORTING STUDENT SUCCESS · UNIFYING THE STUDENT VOICE · FOSTERING TITAN PRIDE #12;Organizational Structure Associated Students, CSUF, Inc. (ASI

de Lijser, Peter

287

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

SciTech Connect (OSTI)

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

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

2006-07-01T23:59:59.000Z

288

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

E-Print Network [OSTI]

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

Torres-Verdín, Carlos

289

Iterative methods for dose reduction and image enhancement in tomography  

DOE Patents [OSTI]

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

Miao, Jianwei; Fahimian, Benjamin Pooya

2012-09-18T23:59:59.000Z

290

Simulations of Alpha Wall Load in ITER. Final report  

SciTech Connect (OSTI)

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

Carlsson, Johan

2010-10-20T23:59:59.000Z

291

Ideal MHD Stability of ITER Steady State Scenarios with ITBs  

SciTech Connect (OSTI)

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

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

2011-07-27T23:59:59.000Z

292

Occupational Radiation Exposure Analysis of US ITER DCLL TBM  

SciTech Connect (OSTI)

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

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

2007-08-01T23:59:59.000Z

293

DESIGN OF THE ITER IN-VESSEL COILS  

SciTech Connect (OSTI)

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

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

2010-11-27T23:59:59.000Z

294

An iterative technique for solving equations of statistical equilibrium  

E-Print Network [OSTI]

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

L. B. Lucy

2001-03-21T23:59:59.000Z

295

Status of ITER neutral beam cell remote handling system  

E-Print Network [OSTI]

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

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

2013-01-01T23:59:59.000Z

296

Power Transmission From The ITER Model Negative Ion Source  

SciTech Connect (OSTI)

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

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

2007-08-10T23:59:59.000Z

297

Development of the bus joint for the ITER Central Solenoid  

SciTech Connect (OSTI)

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

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

2013-01-01T23:59:59.000Z

298

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

299

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

300

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

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


301

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

302

Biomass Gasification Combined Cycle  

SciTech Connect (OSTI)

Gasification combined cycle continues to represent an important defining technology area for the forest products industry. The ''Forest Products Gasification Initiative'', organized under the Industry's Agenda 2020 technology vision and supported by the DOE ''Industries of the Future'' program, is well positioned to guide these technologies to commercial success within a five-to ten-year timeframe given supportive federal budgets and public policy. Commercial success will result in significant environmental and renewable energy goals that are shared by the Industry and the Nation. The Battelle/FERCO LIVG technology, which is the technology of choice for the application reported here, remains of high interest due to characteristics that make it well suited for integration with the infrastructure of a pulp production facility. The capital cost, operating economics and long-term demonstration of this technology area key input to future economically sustainable projects and must be verified by the 200 BDT/day demonstration facility currently operating in Burlington, Vermont. The New Bern application that was the initial objective of this project is not currently economically viable and will not be implemented at this time due to several changes at and around the mill which have occurred since the inception of the project in 1995. The analysis shows that for this technology, and likely other gasification technologies as well, the first few installations will require unique circumstances, or supportive public policies, or both to attract host sites and investors.

Judith A. Kieffer

2000-07-01T23:59:59.000Z

303

Life Cycle Asset Management  

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

(The following directives are deleted or consolidated into this Order and shall be phased out as noted in Paragraph 2: DOE 1332.1A; DOE 4010.1A; DOE 4300.1C; DOE 4320.1B; DOE 4320.2A; DOE 4330.4B; DOE 4330.5; DOE 4540.1C; DOE 4700.1). This Order supersedes specific project management provisions within DOE O 430.1A, LIFE CYCLE ASSET MANAGEMENT. The specific paragraphs canceled by this Order are 6e(7); 7a(3); 7b(11) and (14); 7c(4),(6),(7),(11), and (16); 7d(4) and (8); 7e(3),(10), and (17); Attachment 1, Definitions (item 30 - Line Item Project, item 42 - Project, item 48 - Strategic System); and Attachment 2, Contractor Requirements Document (paragraph 1d regarding a project management system). The remainder of DOE O 430.1A remains in effect. Cancels DOE O 430.1. Canceled by DOE O 413.3.

1998-10-14T23:59:59.000Z

304

Orbital Resonance and Solar Cycles  

E-Print Network [OSTI]

We present an analysis of planetary moves, encoded in DE406 ephemerides. We show resonance cycles between most planets in Solar System, of differing quality. The most precise resonance - between Earth and Venus, which not only stabilizes orbits of both planets, locks planet Venus rotation in tidal locking, but also affects the Sun: This resonance group (E+V) also influences Sunspot cycles - the position of syzygy between Earth and Venus, when the barycenter of the resonance group most closely approaches the Sun and stops for some time, relative to Jupiter planet, well matches the Sunspot cycle of 11 years, not only for the last 400 years of measured Sunspot cycles, but also in 1000 years of historical record of "severe winters". We show, how cycles in angular momentum of Earth and Venus planets match with the Sunspot cycle and how the main cycle in angular momentum of the whole Solar system (854-year cycle of Jupiter/Saturn) matches with climatologic data, assumed to show connection with Solar output power and insolation. We show the possible connections between E+V events and Solar global p-Mode frequency changes. We futher show angular momentum tables and charts for individual planets, as encoded in DE405 and DE406 ephemerides. We show, that inner planets orbit on heliocentric trajectories whereas outer planets orbit on barycentric trajectories.

P. A. Semi

2009-03-29T23:59:59.000Z

305

Extreme Financial cycles$ B. Candelonb,  

E-Print Network [OSTI]

Extreme Financial cycles$ B. Candelonb, , G. Gauliera , C. Hurlinb aUniversity Maastricht proposes a new approach to date extreme financial cycles. Elabo- rating on recent methods in extreme value theory, it elaborates an extension of the famous calculus rule to detect extreme peaks and troughs

Paris-Sud XI, Université de

306

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

307

Fuel cycle centers revisited: Consolidation of fuel cycle activities in a few countries  

SciTech Connect (OSTI)

Despite varied expressions, the general impression remains that the international fuel cycle center concept, whatever its merits, is visionary. It also is quite possibly unattainable in light of strong national pressures toward independence and self-sufficiency in all things nuclear. Is the fuel cycle center an idea that has come and gone? Is it an idea whose time has not yet come? Or is it, as this paper suggests, an idea that has already arrived on the scene, attracting little attention or even acknowledgement of its presence? The difficult in answering this questions arises, in part, from the fact that despite its long and obvious appeal, there has been very little systematic analysis of the concept itself. Such obvious questions as how many and where fuel cycle centers should be located; what characteristics should the hot country or countries possess; and what are the institutional forms or features that endow the concept with enhanced proliferation protection have rarely been seriously and systematically addressed. The title of this paper focuses on limiting the geographic spread of fuel cycle facilities, and some may suggest that doing so does not necessarily call for any type of international or multinational arrangements applicable to those that exist. It is a premise of this paper, however, that a restriction on the number of countries possessing sensitive fuel cycle facilities necessarily involves some degree of multinationalization. This is not only because in every instance a nonproliferation pledge and international or multinational safeguards, or both, will be applied to the facility, but also because a restriction on the number of countries possessing these facilities implies that those in existence will serve a multinational market. This feature in itself is an important form of international auspices. Thus, the two concepts--limitation and multinationalization--if not necessarily one and the same, are at least de facto corollaries.

Kratzer, M.B. [Kratzer (Myron B.), Annapolis, MD (United States)

1996-07-01T23:59:59.000Z

308

Supercritical carbon dioxide cycle control analysis.  

SciTech Connect (OSTI)

This report documents work carried out during FY 2008 on further investigation of control strategies for supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle energy converters. The main focus of the present work has been on investigation of the S-CO{sub 2} cycle control and behavior under conditions not covered by previous work. An important scenario which has not been previously calculated involves cycle operation for a Sodium-Cooled Fast Reactor (SFR) following a reactor scram event and the transition to the primary coolant natural circulation and decay heat removal. The Argonne National Laboratory (ANL) Plant Dynamics Code has been applied to investigate the dynamic behavior of the 96 MWe (250 MWt) Advanced Burner Test Reactor (ABTR) S-CO{sub 2} Brayton cycle following scram. The timescale for the primary sodium flowrate to coast down and the transition to natural circulation to occur was calculated with the SAS4A/SASSYS-1 computer code and found to be about 400 seconds. It is assumed that after this time, decay heat is removed by the normal ABTR shutdown heat removal system incorporating a dedicated shutdown heat removal S-CO{sub 2} pump and cooler. The ANL Plant Dynamics Code configured for the Small Secure Transportable Autonomous Reactor (SSTAR) Lead-Cooled Fast Reactor (LFR) was utilized to model the S-CO{sub 2} Brayton cycle with a decaying liquid metal coolant flow to the Pb-to-CO{sub 2} heat exchangers and temperatures reflecting the decaying core power and heat removal by the cycle. The results obtained in this manner are approximate but indicative of the cycle transient performance. The ANL Plant Dynamics Code calculations show that the S-CO{sub 2} cycle can operate for about 400 seconds following the reactor scram driven by the thermal energy stored in the reactor structures and coolant such that heat removal from the reactor exceeds the decay heat generation. Based on the results, requirements for the shutdown heat removal system may be defined. In particular, the peak heat removal capacity of the shutdown heat removal loop may be specified to be 1.1 % of the nominal reactor power. An investigation of the oscillating cycle behavior calculated by the ANL Plant Dynamics Code under specific conditions has been carried out. It has been found that the calculation of unstable operation of the cycle during power reduction to 0 % may be attributed to the modeling of main compressor operation. The most probable reason for such instabilities is the limit of applicability of the currently used one-dimensional compressor performance subroutines which are based on empirical loss coefficients. A development of more detailed compressor design and performance models is required and is recommended for future work in order to better investigate and possibly eliminate the calculated instabilities. Also, as part of such model development, more reliable surge criteria should be developed for compressor operation close to the critical point. It is expected that more detailed compressor models will be developed as a part of validation of the Plant Dynamics Code through model comparison with the experiment data generated in the small S-CO{sub 2} loops being constructed at Barber-Nichols Inc. and Sandia National Laboratories (SNL). Although such a comparison activity had been planned to be initiated in FY 2008, data from the SNL compression loop currently in operation at Barber Nichols Inc. has not yet become available by the due date of this report. To enable the transient S-CO{sub 2} cycle investigations to be carried out, the ANL Plant Dynamics Code for the S-CO{sub 2} Brayton cycle was further developed and improved. The improvements include further optimization and tuning of the control mechanisms as well as an adaptation of the code for reactor systems other than the Lead-Cooled Fast Reactor (LFR). Since the focus of the ANL work on S-CO{sub 2} cycle development for the majority of the current year has been on the applicability of the cycle to SFRs, work has started on modification of the ANL Plant Dynamics Code to allow

Moisseytsev, A.; Sienicki, J. J. (Nuclear Engineering Division)

2011-04-11T23:59:59.000Z

309

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

SciTech Connect (OSTI)

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

Francesca M. Poli and Charles Kessel

2012-12-03T23:59:59.000Z

310

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

SciTech Connect (OSTI)

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

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

2009-11-26T23:59:59.000Z

311

Evaluation and Optimization of a Supercritical Carbon Dioxide Power Conversion Cycle for Nuclear Applications  

SciTech Connect (OSTI)

There have been a number of studies involving the use of gases operating in the supercritical mode for power production and process heat applications. Supercritical carbon dioxide (CO2) is particularly attractive because it is capable of achieving relatively high power conversion cycle efficiencies in the temperature range between 550C and 750C. Therefore, it has the potential for use with any type of high-temperature nuclear reactor concept, assuming reactor core outlet temperatures of at least 550C. The particular power cycle investigated in this paper is a supercritical CO2 Recompression Brayton Cycle. The CO2 Recompression Brayton Cycle can be used as either a direct or indirect power conversion cycle, depending on the reactor type and reactor outlet temperature. The advantage of this cycle when compared to the helium Brayton Cycle is the lower required operating temperature; 550C versus 850C. However, the supercritical CO2 Recompression Brayton Cycle requires an operating pressure in the range of 20 MPa, which is considerably higher than the required helium Brayton cycle operating pressure of 8 MPa. This paper presents results of analyses performed using the UniSim process analyses software to evaluate the performance of the supercritical CO2 Brayton Recompression Cycle for different reactor outlet temperatures. The UniSim model assumed a 600 MWt reactor power source, which provides heat to the power cycle at a maximum temperature of between 550C and 750C. The UniSim model used realistic component parameters and operating conditions to model the complete power conversion system. CO2 properties were evaluated, and the operating range for the cycle was adjusted to take advantage of the rapidly changing conditions near the critical point. The UniSim model was then optimized to maximize the power cycle thermal efficiency at the different maximum power cycle operating temperatures. The results of the analyses showed that power cycle thermal efficiencies in the range of 40 to 50% can be achieved.

Edwin A. Harvego; Michael G. McKellar

2011-05-01T23:59:59.000Z

312

Optimization of Air Conditioning Cycling  

E-Print Network [OSTI]

on a 3-ton residential air conditioner are then presented to intuitively understand the effect of expansion valve and evaporator fan cycling in a real system. A real time optimization method is explored and the feasibility, recommendations for a...

Seshadri, Swarooph

2012-10-19T23:59:59.000Z

313

American business cycles and innovation  

E-Print Network [OSTI]

Economists have long studied innovation and its effects on business cycles. Economist Joseph Alois Schumpeter (1883-1950) was the first economist to thoroughly discuss these ideas in his Theorie der wirtschaftlichen Entwicklung, published in 1911...

Hood, Michael

2013-02-22T23:59:59.000Z

314

Life Cycle Inventory of a CMOS Chip  

E-Print Network [OSTI]

Reichl, H. Life cycle inventory analysis and identificationAllen, D.T. ; Life cycle inventory development for waferLife Cycle Inventory of a CMOS Chip Sarah Boyd and David

Boyd, Sarah; Dornfeld, David; Krishnan, Nikhil

2006-01-01T23:59:59.000Z

315

Life-cycle Assessment of Semiconductors  

E-Print Network [OSTI]

yield. A hybrid life cycle assessment (LCA) model is used;more accurate life-cycle assessment (LCA) of electronicthe purposes of life-cycle assessment (LCA). While it may be

Boyd, Sarah B.

2009-01-01T23:59:59.000Z

316

Development of the Long Pulse Negative Ion Source for ITER  

SciTech Connect (OSTI)

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

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

2005-04-06T23:59:59.000Z

317

TRANSP Tests Of TGLF and Predictions For ITER  

SciTech Connect (OSTI)

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

none,; Budny, Robert; Yuan, Xingqiu

2014-02-26T23:59:59.000Z

318

Status of the Design of the ITER ECE Diagnostic  

SciTech Connect (OSTI)

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

Taylor, Gary [PPPL

2014-04-01T23:59:59.000Z

319

An assessment of the base blanket for ITER  

SciTech Connect (OSTI)

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

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

1991-01-01T23:59:59.000Z

320

Helium-cooled solid breeder blanket for ITER  

SciTech Connect (OSTI)

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

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

1989-03-01T23:59:59.000Z

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


321

An Overview of the US DCLL ITER-TBM Program  

SciTech Connect (OSTI)

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

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

2010-12-01T23:59:59.000Z

322

An overview of the US DCLL ITER-TBM program  

SciTech Connect (OSTI)

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

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

2010-12-01T23:59:59.000Z

323

An Overview of the US DCLL ITER TBM Program  

SciTech Connect (OSTI)

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

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

2010-01-01T23:59:59.000Z

324

An assessment of the base blanket for ITER  

SciTech Connect (OSTI)

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

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

1991-12-31T23:59:59.000Z

325

International Nuclear Fuel Cycle Fact Book. Revision 12  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need exists costs for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book has been compiled to meet that need. The information contained in the International Nuclear Fuel Cycle Fact Book has been obtained from many unclassified sources: nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NMEA activities reports; and proceedings of conferences and workshops. The data listed typically do not reflect any single source but frequently represent a consolidation/combination of information.

Leigh, I.W.

1992-05-01T23:59:59.000Z

326

International nuclear fuel cycle fact book: Revision 9  

SciTech Connect (OSTI)

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States.

Leigh, I.W.

1989-01-01T23:59:59.000Z

327

International nuclear fuel cycle fact book. [Contains glossary  

SciTech Connect (OSTI)

As the US Department of Energy (DOE) and DOE contractors have become increasingly involved with other nations in nuclear fuel cycle and waste management cooperative activities, a need has developed for a ready source of information concerning foreign fuel cycle programs, facilities, and personnel. This Fact Book was compiled to meet that need. The information contained has been obtained from nuclear trade journals and newsletters; reports of foreign visits and visitors; CEC, IAEA, and OECD/NEA activities reports; proceedings of conferences and workshops; and so forth. Sources do not agree completely with each other, and the data listed herein does not reflect any one single source but frequently is a consolidation/combination of information. Lack of space as well as the intent and purpose of the Fact Book limit the given information to that pertaining to the Nuclear Fuel Cycle and to data considered of primary interest or most helpful to the majority of users.

Leigh, I.W.; Lakey, L.T.; Schneider, K.J.; Silviera, D.J.

1987-01-01T23:59:59.000Z

328

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

329

Iterative nonlinear beam propagation method and its application in nonlinear devices  

E-Print Network [OSTI]

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

Gao, Hanhong

2011-01-01T23:59:59.000Z

330

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

E-Print Network [OSTI]

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

331

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

E-Print Network [OSTI]

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

332

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

E-Print Network [OSTI]

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

Temkin, Richard J.

333

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

E-Print Network [OSTI]

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

Tamma, Raja Venkatesh

2004-09-30T23:59:59.000Z

334

Tritium inventory control in ITER Charles Skinner with key contributions from  

E-Print Network [OSTI]

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

Princeton Plasma Physics Laboratory

335

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

E-Print Network [OSTI]

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

Homburg, Ale Jan

336

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

SciTech Connect (OSTI)

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

Not Available

1991-01-01T23:59:59.000Z

337

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

E-Print Network [OSTI]

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

338

Development of the Hybrid Sulfur Thermochemical Cycle  

SciTech Connect (OSTI)

The production of hydrogen via the thermochemical splitting of water is being considered as a primary means for utilizing the heat from advanced nuclear reactors to provide fuel for a hydrogen economy. The Hybrid Sulfur (HyS) Process is one of the baseline candidates identified by the U.S. Department of Energy [1] for this purpose. The HyS Process is a two-step hybrid thermochemical cycle that only involves sulfur, oxygen and hydrogen compounds. Recent work has resulted in an improved process design with a calculated overall thermal efficiency (nuclear heat to hydrogen, higher heating value basis) approaching 50%. Economic analyses indicate that a nuclear hydrogen plant employing the HyS Process in conjunction with an advanced gas-cooled nuclear reactor system can produce hydrogen at competitive prices. Experimental work has begun on the sulfur dioxide depolarized electrolyzer, the major developmental component in the cycle. Proof-of-concept tests have established proton-exchange-membrane cells (a state-of-the-art technology) as a viable approach for conducting this reaction. This is expected to lead to more efficient and economical cell designs than were previously available. Considerable development and scale-up issues remain to be resolved, but the development of a viable commercial-scale HyS Process should be feasible in time to meet the commercialization schedule for Generation IV gas-cooled nuclear reactors.

Summers, William A.; Steimke, John L

2005-09-23T23:59:59.000Z

339

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

340

Vacuum photodiode detectors for soft x-ray ITER plasma tomography  

SciTech Connect (OSTI)

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

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

2005-07-15T23:59:59.000Z

Note: This page contains sample records for the topic "involves iterative cycling" from the National Library of EnergyBeta (NLEBeta).
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341

Qualification of the US made conductors for ITER TF magnet system  

SciTech Connect (OSTI)

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

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

2009-10-08T23:59:59.000Z

342

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

SciTech Connect (OSTI)

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

Not Available

1991-08-01T23:59:59.000Z

343

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

SciTech Connect (OSTI)

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

Not Available

1991-08-01T23:59:59.000Z

344

Edge plasma studies for ITER and related B2 code development  

SciTech Connect (OSTI)

During the past three years the B2 code has been entirely re-written. This contract report will serve as a provisional user guide for the new (B2.5) code, which is hereby made available to the ITER modellers. A definitive description of the new code will be prepared in the course of the present year. The following changes to the physics (with respect to the B2 code version now in wide use) should be noted. The representation of the atomic physics now relies on rate coefficients obtained from either of two code packages: the ADPAK collection developed by R. A. Hulse of Princeton PPL and the STRAHL collection developed by K. Behringer of Garching and JET. These are used to prepare tables of rate coefficients for ionization, recombination, radiation, and charge exchange, involving hydrogen and any impurities that are of interest. A fluid model is now available to describe the neutral species. The neutral fluid is governed by a convection-diffusion equation of similar form as all the other equations solved in the code; the diffusivity is based on the thermal velocity and the mean free path for ionization and charge exchange. The code has been extensively modified in the interest of clarity of design and ease of use. The internal documentation has been expanded, so that almost all variables are now clearly described and every small segment of code has a clearly stated purpose. Some steps were made toward including a full treatment of the electric potential and of diamagnetic transport. The poloidal transport is no longer tied to the parallel transport by a simple factor B[sub [theta

Weitzner, H.; Braams, B.

1992-03-01T23:59:59.000Z

345

Edge plasma studies for ITER and related B2 code development  

SciTech Connect (OSTI)

During the past three years the B2 code has been entirely re-written. This contract report will serve as a provisional user guide for the new (B2.5) code, which is hereby made available to the ITER modellers. A definitive description of the new code will be prepared in the course of the present year. The following changes to the physics (with respect to the B2 code version now in wide use) should be noted. The representation of the atomic physics now relies on rate coefficients obtained from either of two code packages: the ADPAK collection developed by R. A. Hulse of Princeton PPL and the STRAHL collection developed by K. Behringer of Garching and JET. These are used to prepare tables of rate coefficients for ionization, recombination, radiation, and charge exchange, involving hydrogen and any impurities that are of interest. A fluid model is now available to describe the neutral species. The neutral fluid is governed by a convection-diffusion equation of similar form as all the other equations solved in the code; the diffusivity is based on the thermal velocity and the mean free path for ionization and charge exchange. The code has been extensively modified in the interest of clarity of design and ease of use. The internal documentation has been expanded, so that almost all variables are now clearly described and every small segment of code has a clearly stated purpose. Some steps were made toward including a full treatment of the electric potential and of diamagnetic transport. The poloidal transport is no longer tied to the parallel transport by a simple factor B{sub {theta}}/B, but includes diffusive contributions. A two-dimensional elliptic equation is solved to obtain the electric potential, assuming an anomalous cross-field resistivity and thermo-electric coefficient of the plasma.

Weitzner, H.; Braams, B.

1992-03-01T23:59:59.000Z

346

Helium-cooled lithiuim compound suspension blanket concept for ITER  

SciTech Connect (OSTI)

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

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

1988-08-01T23:59:59.000Z

347

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

SciTech Connect (OSTI)

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

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

2005-01-01T23:59:59.000Z

348

A comparative genomic analysis of the oxidative enzymes potentially involved in lignin degradation by Agaricus bisporus  

E-Print Network [OSTI]

A comparative genomic analysis of the oxidative enzymes potentially involved in lignin degradation an important role in lignin degradation. On the other hand, the expression patterns of the related CROs suggest of the global carbon cycle. This substrate is composed of lignin, hemicellulose and cellulose and is degraded

Fried, Jeremy S.

349

The behavioral manipulation hypothesis Life cycle of  

E-Print Network [OSTI]

1 The behavioral manipulation hypothesis · No one knows how the parasite causes these Life cycle eat mostly hares · Linked cycles? Predator-Prey Cycles? · Think and then discuss: · Under the hypothesis that predators cause this cycle, what would you expect for the following when hare populations

Mitchell, Randall J.

350

Life-cycle Assessment of Semiconductors  

E-Print Network [OSTI]

Environmental Impacts . . . . . . . . . . . . . . . . . . . . . .Abatement Environmental impactLife-cycle Environmental Impacts . . . . . . . LCA of

Boyd, Sarah B.

2009-01-01T23:59:59.000Z

351

Advanced Nuclear Fuel Cycle Options  

SciTech Connect (OSTI)

A systematic evaluation has been conducted of the potential for advanced nuclear fuel cycle strategies and options to address the issues ascribed to the use of nuclear power. Issues included nuclear waste management, proliferation risk, safety, security, economics and affordability, and sustainability. The two basic strategies, once-through and recycle, and the range of possibilities within each strategy, are considered for all aspects of the fuel cycle including options for nuclear material irradiation, separations if needed, and disposal. Options range from incremental changes to todays implementation to revolutionary concepts that would require the development of advanced nuclear technologies.

Roald Wigeland; Temitope Taiwo; Michael Todosow; William Halsey; Jess Gehin

2010-06-01T23:59:59.000Z

352

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

SciTech Connect (OSTI)

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

NONE

1995-12-01T23:59:59.000Z

353

Iterative Solution of Elliptic Equations with a Small Parameter  

E-Print Network [OSTI]

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

Segatti, Antonio

354

PFB coal fired combined cycle development program: commercial plant economic analysis (Task 1. 6)  

SciTech Connect (OSTI)

The objectives of this program are to evaluate the Coal Fired Combined Cycle (CFCC) power plant conceptual design and to conduct supporting development programs for pressurized fluidized bed technology advancement in combustion/steam generator, gas turbine and hot gas cleanup technologies. The Coal-Fired Combined Cycle is the unique power plant concept developed under the leadership of the General Electric Company to provide a direct coal-burning gas turbine and steam turbine combined-cycle power plant. The advantages of the combined cycle for higher efficiency and the potential of the pressurized fluidized bed combustor improvements in emissions could offer a new and attractive option to the electric utility industry. The CFCC approach provides for cooling the fluid bed combustor through the use of steam tubes in the bed which supply a steam turbine generator. The partially cooled combustion gases drive a gas turbine generator after passing through a hot gas cleanup train. The Conceptual CFCC Commercial Plant has been defined in Report No. Fe-2357-28. This design, being conceptual in nature, has not been improved through the formal cost reduction iteration/design program. An economic analysis of this baseline plant is provided in this report. The General Electric Company believes that the combustion of coal by the pressurized fluidized bed process is one of the most effective and efficient means for the utilization of coal with respect to both environmental considerations and the cost of electricity.

Not Available

1980-11-01T23:59:59.000Z

355

Control system options and strategies for supercritical CO2 cycles.  

SciTech Connect (OSTI)

The Supercritical Carbon Dioxide (S-CO{sub 2}) Brayton Cycle is a promising alternative to Rankine steam cycle and recuperated gas Brayton cycle energy converters for use with Sodium-Cooled Fast Reactors (SFRs), Lead-Cooled Fast Reactors (LFRs), as well as other advanced reactor concepts. The S-CO{sub 2} Brayton Cycle offers higher plant efficiencies than Rankine or recuperated gas Brayton cycles operating at the same liquid metal reactor core outlet temperatures as well as reduced costs or size of key components especially the turbomachinery. A new Plant Dynamics Computer Code has been developed at Argonne National Laboratory for simulation of a S-CO{sub 2} Brayton Cycle energy converter coupled to an autonomous load following liquid metal-cooled fast reactor. The Plant Dynamics code has been applied to investigate the effectiveness of a control strategy for the S-CO{sub 2} Brayton Cycle for the STAR-LM 181 MWe (400 MWt) Lead-Cooled Fast Reactor. The strategy, which involves a combination of control mechanisms, is found to be effective for controlling the S-CO{sub 2} Brayton Cycle over the complete operating range from 0 to 100 % load for a representative set of transient load changes. While the system dynamic analysis of control strategy performance for STARLM is carried out for a S-CO{sub 2} Brayton Cycle energy converter incorporating an axial flow turbine and compressors, investigations of the S-CO{sub 2} Brayton Cycle have identified benefits from the use of centrifugal compressors which offer a wider operating range, greater stability near the critical point, and potentially further cost reductions due to fewer stages than axial flow compressors. Models have been developed at Argonne for the conceptual design and performance analysis of centrifugal compressors for use in the SCO{sub 2} Brayton Cycle. Steady state calculations demonstrate the wider operating range of centrifugal compressors versus axial compressors installed in a S-CO{sub 2} Brayton Cycle as well as the benefits in expanding the range over which individual control mechanisms are effective for cycle control. However, a combination of mechanisms is still required for control of the S-CO{sub 2} Brayton Cycle between 0 and 100 % load. An effort is underway to partially validate the Argonne models and codes by means of comparison with data from tests carried out using the small-scale Sandia Brayton Loop (SBL) recuperated gas closed Brayton cycle facility. The centrifugal compressor model has been compared with data from the SBL operating with nitrogen gas and good agreement is obtained between calculations and the measured data for the compressor outlet pressure versus flow rate, although it is necessary to assume values for certain model parameters which require information about the configuration or dimensions of the compressor components that is unavailable. Unfortunately, the compressor efficiency cannot be compared with experiment data due to the lack of outlet temperature data. A radial inflow turbine model has been developed to enable further comparison of calculations with data from the SBL which incorporates both a radial inflow turbine as well as a radial compressor. Preliminary calculations of pressure ratio and efficiency versus flow rate have been carried out using the radial inflow turbine model.

Moisseytsev, A.; Kulesza, K. P.; Sienicki, J. J.; Nuclear Engineering Division; Oregon State Univ.

2009-06-18T23:59:59.000Z

356

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

E-Print Network [OSTI]

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

Pennycook, Steve

357

Capacity fade of Sony 18650 cells cycled at elevated temperatures Part I. Cycling performance  

E-Print Network [OSTI]

Capacity fade of Sony 18650 cells cycled at elevated temperatures Part I. Cycling performance P of Sony 18650 Li-ion cells increases with increase in temperature. After 800 cycles, the cells cycled the capacity fade of commercial Li-ion cells cycled at high temperatures. We choose Sony 18650 cells with Li

Popov, Branko N.

358

Single-cycle nonlinear optics  

E-Print Network [OSTI]

g l e - C y c l e Nonlinear Optics E. G o u l i e l m a k iSingle-Cycle Nonlinear Optics E. Goulielmakis *, M.D-85748 Garching. Center for X-Ray Optics, Lawrence Berkeley

Goulielmakis, E.; Max-Planck-Institut fur Quantenoptik

2008-01-01T23:59:59.000Z

359

Modeling the Nuclear Fuel Cycle  

SciTech Connect (OSTI)

A review of existing nuclear fuel cycle systems analysis codes was performed to determine if any existing codes meet technical and functional requirements defined for a U.S. national program supporting the global and domestic assessment, development and deployment of nuclear energy systems. The program would be implemented using an interconnected architecture of different codes ranging from the fuel cycle analysis code, which is the subject of the review, to fundamental physical and mechanistic codes. Four main functions are defined for the code: (1) the ability to characterize and deploy individual fuel cycle facilities and reactors in a simulation, while discretely tracking material movements, (2) the capability to perform an uncertainty analysis for each element of the fuel cycle and an aggregate uncertainty analysis, (3) the inclusion of an optimization engine able to optimize simultaneously across multiple objective functions, and (4) open and accessible code software and documentation to aid in collaboration between multiple entities and facilitate software updates. Existing codes, categorized as annualized or discrete fuel tracking codes, were assessed according to the four functions and associated requirements. These codes were developed by various government, education and industrial entities to fulfill particular needs. In some cases, decisions were made during code development to limit the level of detail included in a code to ease its use or to focus on certain aspects of a fuel cycle to address specific questions. The review revealed that while no two of the codes are identical, they all perform many of the same basic functions. No code was able to perform defined function 2 or several requirements of functions 1 and 3. Based on this review, it was concluded that the functions and requirements will be met only with development of a new code, referred to as GENIUS.

Jacob J. Jacobson; Mary Lou Dunzik-Gougar; Christopher A. Juchau

2010-08-01T23:59:59.000Z

360

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

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


361

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

SciTech Connect (OSTI)

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

NONE

1995-01-01T23:59:59.000Z

362

Status of the 1 MeV Accelerator Design for ITER NBI  

SciTech Connect (OSTI)

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

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

2011-09-26T23:59:59.000Z

363

Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications  

SciTech Connect (OSTI)

There have been a number of studies involving the use of gases operating in the supercritical mode for power production and process heat applications. Supercritical carbon dioxide (CO2) is particularly attractive because it is capable of achieving relatively high power conversion cycle efficiencies in the temperature range between 550 C and 750 C. Therefore, it has the potential for use with any type of high-temperature nuclear reactor concept, assuming reactor core outlet temperatures of at least 550 C. The particular power cycle investigated in this paper is a supercritical CO2 Recompression Brayton Cycle. The CO2 Recompression Brayton Cycle can be used as either a direct or indirect power conversion cycle, depending on the reactor type and reactor outlet temperature. The advantage of this cycle when compared to the helium Brayton cycle is the lower required operating temperature; 550 C versus 850 C. However, the supercritical CO2 Recompression Brayton Cycle requires an operating pressure in the range of 20 MPa, which is considerably higher than the required helium Brayton cycle operating pressure of 8 MPa. This paper presents results of analyses performed using the UniSim process analyses software to evaluate the performance of both a direct and indirect supercritical CO2 Brayton Recompression cycle for different reactor outlet temperatures. The direct supercritical CO2 cycle transferred heat directly from a 600 MWt reactor to the supercritical CO2 working fluid supplied to the turbine generator at approximately 20 MPa. The indirect supercritical CO2 cycle assumed a helium-cooled Very High Temperature Reactor (VHTR), operating at a primary system pressure of approximately 7.0 MPa, delivered heat through an intermediate heat exchanger to the secondary indirect supercritical CO2 Brayton Recompression cycle, again operating at a pressure of about 20 MPa. For both the direct and indirect cycles, sensitivity calculations were performed for reactor outlet temperature between 550 C and 850 C. The UniSim models used realistic component parameters and operating conditions to model the complete reactor and power conversion systems. CO2 properties were evaluated, and the operating ranges of the cycles were adjusted to take advantage of the rapidly changing properties of CO2 near the critical point. The results of the analyses showed that, for the direct supercritical CO2 power cycle, thermal efficiencies in the range of 40 to 50% can be achieved. For the indirect supercritical CO2 power cycle, thermal efficiencies were approximately 10% lower than those obtained for the direct cycle over the same reactor outlet temperature range.

Edwin A. Harvego; Michael G. McKellar

2011-11-01T23:59:59.000Z

364

Prediction of future fifteen solar cycles  

E-Print Network [OSTI]

In the previous study (Hiremath 2006a), the solar cycle is modeled as a forced and damped harmonic oscillator and from all the 22 cycles (1755-1996), long-term amplitudes, frequencies, phases and decay factor are obtained. Using these physical parameters of the previous 22 solar cycles and by an {\\em autoregressive model}, we predict the amplitude and period of the future fifteen solar cycles. Predicted amplitude of the present solar cycle (23) matches very well with the observations. The period of the present cycle is found to be 11.73 years. With these encouraging results, we also predict the profiles of future 15 solar cycles. Important predictions are : (i) the period and amplitude of the cycle 24 are 9.34 years and 110 ($\\pm 11$), (ii) the period and amplitude of the cycle 25 are 12.49 years and 110 ($\\pm$ 11), (iii) during the cycles 26 (2030-2042 AD), 27 (2042-2054 AD), 34 (2118-2127 AD), 37 (2152-2163 AD) and 38 (2163-2176 AD), the sun might experience a very high sunspot activity, (iv) the sun might also experience a very low (around 60) sunspot activity during cycle 31 (2089-2100 AD) and, (v) length of the solar cycles vary from 8.65 yrs for the cycle 33 to maximum of 13.07 yrs for the cycle 35.

K. M. Hiremath

2007-04-11T23:59:59.000Z

365

Multi-cycle boiling water reactor fuel cycle optimization  

SciTech Connect (OSTI)

In this work a new computer code, BWROPT (Boiling Water Reactor Optimization), is presented. BWROPT uses the Parallel Simulated Annealing (PSA) algorithm to solve the out-of-core optimization problem coupled with an in-core optimization that determines the optimum fuel loading pattern. However it uses a Haling power profile for the depletion instead of optimizing the operating strategy. The result of this optimization is the optimum new fuel inventory and the core loading pattern for the first cycle considered in the optimization. Several changes were made to the optimization algorithm with respect to other nuclear fuel cycle optimization codes that use PSA. Instead of using constant sampling probabilities for the solution perturbation types throughout the optimization as is usually done in PSA optimizations the sampling probabilities are varied to get a better solution and/or decrease runtime. The new fuel types available for use can be sorted into an array based on any number of parameters so that each parameter can be incremented or decremented, which allows for more precise fuel type selection compared to random sampling. Also, the results are sorted by the new fuel inventory of the first cycle for ease of comparing alternative solutions. (authors)

Ottinger, K.; Maldonado, G.I. [University of Tennessee, 311 Pasqua Engineering Building, Knoxville, TN 37996-2300 (United States)

2013-07-01T23:59:59.000Z

366

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

SciTech Connect (OSTI)

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

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

2005-04-06T23:59:59.000Z

367

Implementation of the Iterative Proportion Fitting Algorithm for Geostatistical Facies Modeling  

SciTech Connect (OSTI)

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

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

2012-06-15T23:59:59.000Z

368

Tungsten spectroscopy relevant to the diagnostics development of ITER divertor plasmas  

SciTech Connect (OSTI)

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

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

2009-12-01T23:59:59.000Z

369

Single-cycle nonlinear optics  

SciTech Connect (OSTI)

Nonlinear optics plays a central role in the advancement of optical science and laser-based technologies. We report on the confinement of the nonlinear interaction of light with matter to a single wave cycle and demonstrate its utility for time-resolved and strong-field science. The electric field of 3.3-femtosecond, 0.72-micron laser pulses with a controlled and measured waveform ionizes atoms near the crests of the central wave cycle, with ionization being virtually switched off outside this interval. Isolated sub-100-attosecond pulses of extreme ultraviolet light (photon energy {approx} 80 electron volts), containing {approx} 0.5 nanojoule of energy, emerge from the interaction with a conversion efficiency of {approx} 10{sup -6}. These tools enable the study of the precision control of electron motion with light fields and electron-electron interactions with a resolution approaching the atomic unit of time ({approx} 24 attoseconds).

Max-Planck-Institut fur Quantenoptik; Goulielmakis, E.; Schultze, M.; Hofstetter, M.; Yakovlev, V. S.; Gagnon, J.; Uiberacker, M.; Aquila, A. L.; gullikson, E. M.; attwood, D. T.; Kienberger, R.; Krausz, F.; Kleineberg, U.

2008-11-05T23:59:59.000Z

370

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

SciTech Connect (OSTI)

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

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

2006-03-15T23:59:59.000Z

371

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

SciTech Connect (OSTI)

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

Zhai, Y

2014-03-03T23:59:59.000Z

372

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

SciTech Connect (OSTI)

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

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

2014-02-15T23:59:59.000Z

373

Non-destructive qualification tests for ITER cryogenic axial insulating breaks  

SciTech Connect (OSTI)

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

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

2014-01-29T23:59:59.000Z

374

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

E-Print Network [OSTI]

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

Wang, Chia-Wen

2008-10-10T23:59:59.000Z

375

Advanced Fuel Cycle Cost Basis  

SciTech Connect (OSTI)

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2008-03-01T23:59:59.000Z

376

Advanced Fuel Cycle Cost Basis  

SciTech Connect (OSTI)

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

2007-04-01T23:59:59.000Z

377

New Adsorption Cycles for Carbon Dioxide Capture and Concentration  

SciTech Connect (OSTI)

The objective of this three-year project was to study new pressure swing adsorption (PSA) cycles for CO{sub 2} capture and concentration at high temperature. The heavy reflux (HR) PSA concept and the use of a hydrotalcite like (HTlc) adsorbent that captures CO{sub 2} reversibly at high temperatures simply by changing the pressure were two key features of these new PSA cycles. Through the completion or initiation of nine tasks, a bench-scale experimental and theoretical program has been carried out to complement and extend the process simulation study that was carried out during Phase I (DE-FG26-03NT41799). This final report covers the entire project from August 1, 2005 to July 31, 2008. This program included the study of PSA cycles for CO{sub 2} capture by both rigorous numerical simulation and equilibrium theory analysis. The insight gained from these studies was invaluable toward the applicability of PSA for CO{sub 2} capture, whether done at ambient or high temperature. The rigorous numerical simulation studies showed that it is indeed possible to capture and concentrate CO{sub 2} by PSA. Over a wide range of conditions it was possible to achieve greater than 90% CO{sub 2} purity and/or greater than 90% CO{sub 2} recovery, depending on the particular heavy reflux (HR) PSA cycle under consideration. Three HR PSA cycles were identified as viable candidates for further study experimentally. The equilibrium theory analysis, which represents the upper thermodynamic limit of the performance of PSA process, further validated the use of certain HR PSA cycles for CO{sub 2} capture and concentration. A new graphical approach for complex PSA cycle scheduling was also developed during the course of this program. This new methodology involves a priori specifying the cycle steps, their sequence, and the number of beds, and then following a systematic procedure that requires filling in a 2-D grid based on a few simple rules, some heuristics and some experience. It has been tested successfully against several cycle schedules taken from the literature, including a 2-bed 4-step Skarstrom cycle, a 4-bed 9-step process with 2 equalization steps, a 9-bed 11-step process with 3 equalization steps, and a 6-bed 13-step process with 4 equalization steps and 4 idle steps. With respect to CO{sub 2} capture and concentration by PSA, this new approach is now providing a very straightforward way to determine all the viable 3-bed, 4-bed, 5-bed, n-bed, etc. HR PSA cycle schedules to explore using both simulation and experimentation. This program also touted the use of K-promoted HTlc as a high temperature, reversible adsorbent for CO{sub 2} capture by PSA. This program not only showed how to use this material in HR PSA cycles, but it also proposed a new CO{sub 2} interaction mechanism in conjunction with a non-equilibrium kinetic model that adequately describes the uptake and release of CO{sub 2} in this material, and some preliminary fixed bed adsorption breakthrough and desorption elution experiments were carried out to demonstrate complete reversibility on a larger scale. This information was essentially missing from the literature and deemed invaluable toward promoting the use of K-promoted HTlc as a high temperature, reversible adsorbent for CO{sub 2} capture by PSA. Overall, the objectives of this project were met. It showed the feasibility of using K-promoted hydrotalcite (HTlc) as a high temperature, reversible adsorbent for CO{sub 2} capture by PSA. It discovered some novel HR PSA cycles that might be useful for this purpose. Finally, it revealed a mechanistic understanding of the interaction of CO{sub 2} with K-promoted HTlc.

James Ritter; Armin Ebner; Steven Reynolds Hai Du; Amal Mehrotra

2008-07-31T23:59:59.000Z

378

Profit cycle dynamics by Kawika Pierson.  

E-Print Network [OSTI]

My thesis consists of three essays investigating the existence, causes, and mitigation of profit cycles at an industry level. The first essay examines profit cycles by proposing that the industry-specific features of how ...

Pierson, Kawika (Kawika Paul)

2011-01-01T23:59:59.000Z

379

Rethinking the light water reactor fuel cycle  

E-Print Network [OSTI]

The once through nuclear fuel cycle adopted by the majority of countries with operating commercial power reactors imposes a number of concerns. The radioactive waste created in the once through nuclear fuel cycle has to ...

Shwageraus, Evgeni, 1973-

2004-01-01T23:59:59.000Z

380

Search for relationship between duration of the extended solar cycles and amplitude of sunspot cycle  

E-Print Network [OSTI]

Duration of the extended solar cycles is taken into the consideration. The beginning of cycles is counted from the moment of polarity reversal of large-scale magnetic field in high latitudes, occurring in the sunspot cycle n till the minimum of the cycle n+2. The connection between cycle duration and its amplitude is established. Duration of the "latent" period of evolution of extended cycle between reversals and a minimum of the current sunspot cycle is entered. It is shown, that the latent period of cycles evolution is connected with the next sunspot cycle amplitude and can be used for the prognosis of a level and time of a sunspot maximum. The 24-th activity cycle prognosis is done. Long-term behavior of extended cycle's lengths is considered.

A. G. Tlatov

2007-03-27T23:59:59.000Z

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


381

Search for relationship between duration of the extended solar cycles and amplitude of sunspot cycle  

E-Print Network [OSTI]

Duration of the extended solar cycles is taken into the consideration. The beginning of cycles is counted from the moment of polarity reversal of large-scale magnetic field in high latitudes, occurring in the sunspot cycle n till the minimum of the cycle n+2. The connection between cycle duration and its amplitude is established. Duration of the "latent" period of evolution of extended cycle between reversals and a minimum of the current sunspot cycle is entered. It is shown, that the latent period of cycles evolution is connected with the next sunspot cycle amplitude and can be used for the prognosis of a level and time of a sunspot maximum. The 24-th activity cycle prognosis is done. Long-term behavior of extended cycle's lengths is considered.

Tlatov, A G

2007-01-01T23:59:59.000Z

382

Development Plan for the Fuel Cycle Simulator  

SciTech Connect (OSTI)

The Fuel Cycle Simulator (FCS) project was initiated late in FY-10 as the activity to develop a next generation fuel cycle dynamic analysis tool for achieving the Systems Analysis Campaign 'Grand Challenge.' This challenge, as documented in the Campaign Implementation Plan, is to: 'Develop a fuel cycle simulator as part of a suite of tools to support decision-making, communication, and education, that synthesizes and visually explains the multiple attributes of potential fuel cycles.'

Brent Dixon

2011-09-01T23:59:59.000Z

383

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

E-Print Network [OSTI]

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

Texas at Dallas, University of

384

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

E-Print Network [OSTI]

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

Ghoniem, Nasr M.

385

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

E-Print Network [OSTI]

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

Hung, Shih-Hao

386

D-Cycle - 4-Differential -Stroke Cycle | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTieCelebratePartners with Siemens31, 2015ofVisualizationD-Cycle -

387

SPACETELESCOPESCIENCEINSTITUTE WFPC2 Cycle 14 Calibration  

E-Print Network [OSTI]

/chip combinations used for science in Cycle 14 + Close Out ~10% reserve 2 Placeholder for unexpected items. TOTALSPACETELESCOPESCIENCEINSTITUTE WFPC2 Cycle 14 Calibration Director's Review 8 August 2005 John Biretta 1 Cycle 14 WFPC2 Calibration Plan Overall Goals: · Monitor & maintain WFPC2 health & safety

Sirianni, Marco

388

How Minds Work The IDA Cognitive Cycle  

E-Print Network [OSTI]

1 How Minds Work The IDA Cognitive Cycle Stan Franklin Computer Science Division & Institute for Intelligent Systems The University of Memphis #12;HMW: The IDA Cognitive Cycle 2 Memory Systems #12;HMW: The IDA Cognitive Cycle 3 Global Workspace Theory I · The nervous system is a distributed parallel

Memphis, University of

389

Generating Resources Combined Cycle Combustion Turbine  

E-Print Network [OSTI]

11/17/2014 1 Generating Resources Combined Cycle Combustion Turbine Utility Scale Solar PV Steven doing recently around two key supply-side resource technologies 1. Combined Cycle Combustion Turbine #12;11/17/2014 4 Combined Cycle Combustion Turbine Background Primary Components Gas-fired combustion

390

Studies involving low protein broiler diets  

E-Print Network [OSTI]

STUDIES INVOLVING L(% PROTEIN BROILER DIETS A Thesis by David Palmer Parkin Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE May 1971 Major Subject...: Poultry Science STUDIES INVOLVING LS& PROTEIN BROILER DIETS A Thesis by David Palmer Parkin Approved as to style and content by: (Chairman of Commit e) ead of. Departmen Me er) (Member) (Memb ) May 1971 ABSTRACT Studies Involving Low Protein...

Parkin, David Palmer

1971-01-01T23:59:59.000Z

391

Time-dependent tritium inventories and flow rates in fuel cycle components of a tokamak fusion reactor  

SciTech Connect (OSTI)

The dynamic behavior of the fuel cycle in a fusion reactor is of crucial importance due to the need to keep track of the large amount of tritium being constantly produced, transported, and processed in the reactor system. Because tritium is a source of radioactivity, loss and exhaust to the environment must be kept to a minimum. With ITER advancing to its Engineering Design phase, there is a need to accurately predict the dynamic tritium inventories and flow rates throughout the fuel cycle and to study design variations to meet the demands of low tritium inventory. In this paper, time-dependent inventories and flow rates for several components of the fuel cycle are modeled and studied through the use of a new modular-type model for the dynamic simulation of the fuel cycle in a fusion reactor. The complex dynamic behavior in the modeled subsystems is analyzed using this new model. Previous dynamic models focusing on the fuel cycle dealt primarily with a residence time parameter ({tau}{sub res}) defining each subsystem of the model. In this modular model, this residence time approach is avoided in favor of a more accurate and flexible model that utilizes real design parameters and operating schedules of the various subsystems modeled.

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

1994-12-31T23:59:59.000Z

392

Life cycle assessment: A stewardship tool  

SciTech Connect (OSTI)

As the chemical industry searches for tools to practice product stewardship. it is getting more involved in life cycle assessment (LCA) techniques, which examine the full environmental impact of a product or process over its lifetime and identify areas for improvement. The industry views LCA as a component of product stewardship,' says James P. Mieure, Monsanto's product safety director/chemicals group, who is the liaison between the Chemical manufacturers Association's (CMA; Washington) LCA and product stewardship work groups. Product stewardship includes examining energy used and waste produced as key parameters to consider when developing a new product or process or in modifying an existing one, Mieure says, which is part of what an LCA does. The work being done by the LCA group at CMA, cautions Mieure, doesn't lend itself to practical applications. The group hopes to help companies implement LCA when the time is right, he says. The time is not right yet, Mieure adds, mostly because of the slowness with which the impact analysis stage is progressing. Although the LCA concept has been around for more than 20 years, activity in applying it in industry has taken off since 1990.

Not Available

1992-12-09T23:59:59.000Z

393

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

E-Print Network [OSTI]

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

394

M. Bahrami ENSC 461 (S 11) Brayton Cycle 1 Open GasTurbine Cycle  

E-Print Network [OSTI]

generation. High thermal efficiencies up to 44%. Suitable for combined cycles (with steam power plantM. Bahrami ENSC 461 (S 11) Brayton Cycle 1 Open GasTurbine Cycle Fig.1: Schematic for an open gas-turbine cycle. Working Principal Fresh air enters the compressor at ambient temperature where its pressure

Bahrami, Majid

395

Combined-cycle solarised gas turbine with steam, organic and CO2 bottoming cycles  

E-Print Network [OSTI]

Combined-cycle solarised gas turbine with steam, organic and CO2 bottoming cycles John Pye, Keith of the technical feasibility a solarised combined-cycle gas turbines with a dish concentrator, with several, optimised for the new SG4 collector. This study aims to determine whether a combined-cycle gas turbine (CCGT

396

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

E-Print Network [OSTI]

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

397

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

E-Print Network [OSTI]

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

398

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

E-Print Network [OSTI]

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

Mignotte, Max

399

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

E-Print Network [OSTI]

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

Bertini, Robert L.

400

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

E-Print Network [OSTI]

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

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


401

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

E-Print Network [OSTI]

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

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

2015-01-01T23:59:59.000Z

402

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

E-Print Network [OSTI]

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

Pennycook, Steve

403

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

404

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

E-Print Network [OSTI]

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

405

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

E-Print Network [OSTI]

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

406

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

SciTech Connect (OSTI)

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

Hyeon K. Park

2008-02-22T23:59:59.000Z

407

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

E-Print Network [OSTI]

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

408

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

E-Print Network [OSTI]

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

Nangare, Nitin Ashok

2006-08-16T23:59:59.000Z

409

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

E-Print Network [OSTI]

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

410

AN ITERATIVE SPATIO-TEMPORAL SPEECH ENHANCEMENT ALGORITHM FOR MICROPHONE ARRAYS  

E-Print Network [OSTI]

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

Douglas, Scott C.

411

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

E-Print Network [OSTI]

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

412

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

E-Print Network [OSTI]

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

413

Solution characters of iterative coupling between energy simulation and CFD programs  

E-Print Network [OSTI]

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

Chen, Qingyan "Yan"

414

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

E-Print Network [OSTI]

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

Paris-Sud XI, Université de

415

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

E-Print Network [OSTI]

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

Ramanujam, J. "Ram"

416

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

E-Print Network [OSTI]

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

California at Los Angeles, University of

417

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

E-Print Network [OSTI]

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

Miller, John R.

418

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

E-Print Network [OSTI]

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

419

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

E-Print Network [OSTI]

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

Raffray, A. René

420

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

E-Print Network [OSTI]

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

Makous, Walter

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


421

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

E-Print Network [OSTI]

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

422

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

E-Print Network [OSTI]

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

Abdou, Mohamed

423

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

E-Print Network [OSTI]

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

Abdou, Mohamed

424

Geographically Differentiated Life-cycle Impact Assessment of Human Health  

E-Print Network [OSTI]

indicators in life-cycle assessment (LCA). Human Ecologicalindicators in life-cycle assessment (LCA). Human EcologicalI explore how life-cycle assessment (LCA) results can

Humbert, Sebastien

2009-01-01T23:59:59.000Z

425

Advanced Fuel Cycle Economic Sensitivity Analysis  

SciTech Connect (OSTI)

A fuel cycle economic analysis was performed on four fuel cycles to provide a baseline for initial cost comparison using the Gen IV Economic Modeling Work Group G4 ECON spreadsheet model, Decision Programming Language software, the 2006 Advanced Fuel Cycle Cost Basis report, industry cost data, international papers, the nuclear power related cost study from MIT, Harvard, and the University of Chicago. The analysis developed and compared the fuel cycle cost component of the total cost of energy for a wide range of fuel cycles including: once through, thermal with fast recycle, continuous fast recycle, and thermal recycle.

David Shropshire; Kent Williams; J.D. Smith; Brent Boore

2006-12-01T23:59:59.000Z

426

Rankine cycle system and method  

DOE Patents [OSTI]

A Rankine cycle waste heat recovery system uses a receiver with a maximum liquid working fluid level lower than the minimum liquid working fluid level of a sub-cooler of the waste heat recovery system. The receiver may have a position that is physically lower than the sub-cooler's position. A valve controls transfer of fluid between several of the components in the waste heat recovery system, especially from the receiver to the sub-cooler. The system may also have an associated control module.

Ernst, Timothy C.; Nelson, Christopher R.

2014-09-09T23:59:59.000Z

427

Test Strategy for the European HCPB Test Blanket Module in ITER  

SciTech Connect (OSTI)

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

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

2005-05-15T23:59:59.000Z

428

VISION: Verifiable Fuel Cycle Simulation Model  

SciTech Connect (OSTI)

The nuclear fuel cycle is a very complex system that includes considerable dynamic complexity as well as detail complexity. In the nuclear power realm, there are experts and considerable research and development in nuclear fuel development, separations technology, reactor physics and waste management. What is lacking is an overall understanding of the entire nuclear fuel cycle and how the deployment of new fuel cycle technologies affects the overall performance of the fuel cycle. The Advanced Fuel Cycle Initiatives systems analysis group is developing a dynamic simulation model, VISION, to capture the relationships, timing and delays in and among the fuel cycle components to help develop an understanding of how the overall fuel cycle works and can transition as technologies are changed. This paper is an overview of the philosophy and development strategy behind VISION. The paper includes some descriptions of the model and some examples of how to use VISION.

Jacob J. Jacobson; Abdellatif M. Yacout; Gretchen E. Matthern; Steven J. Piet; David E. Shropshire

2009-04-01T23:59:59.000Z

429

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

E-Print Network [OSTI]

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

430

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

E-Print Network [OSTI]

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

Raffray, A. René

431

MHD Integrated Topping Cycle Project  

SciTech Connect (OSTI)

The overall objective of the project is to design and construct prototypical hardware for an integrated MHD topping cycle, and conduct long duration proof-of-concept tests of integrated system at the US DOE Component Development and Integration Facility in Butte, Montana. The results of the long duration tests will augment the existing engineering design data base on MHD power train reliability, availability, maintainability, and performance, and will serve as a basis for scaling up the topping cycle design to the next level of development, an early commercial scale power plant retrofit. The components of the MHD power train to be designed, fabricated, and tested include: A slagging coal combustor with a rated capacity of 50 MW thermal input, capable of operation with an Eastern (Illinois {number sign}6) or Western (Montana Rosebud) coal, a segmented supersonic nozzle, a supersonic MHD channel capable of generating at least 1.5 MW of electrical power, a segmented supersonic diffuser section to interface the channel with existing facility quench and exhaust systems, a complete set of current control circuits for local diagonal current control along the channel, and a set of current consolidation circuits to interface the channel with the existing facility inverter.

Not Available

1992-01-01T23:59:59.000Z

432

MHD Integrated Topping Cycle Project  

SciTech Connect (OSTI)

The Magnetohydrodynamics (MHD) Integrated Topping Cycle (ITC) Project represents the culmination of the proof-of-concept (POC) development stage in the US Department of Energy (DOE) program to advance MHD technology to early commercial development stage utility power applications. The project is a joint effort, combining the skills of three topping cycle component developers: TRW, Avco/TDS, and Westinghouse. TRW, the prime contractor and system integrator, is responsible for the 50 thermal megawatt (50 MW{sub t}) slagging coal combustion subsystem. Avco/TDS is responsible for the MHD channel subsystem (nozzle, channel, diffuser, and power conditioning circuits), and Westinghouse is responsible for the current consolidation subsystem. The ITC Project will advance the state-of-the-art in MHD power systems with the design, construction, and integrated testing of 50 MW{sub t} power train components which are prototypical of the equipment that will be used in an early commercial scale MHD utility retrofit. Long duration testing of the integrated power train at the Component Development and Integration Facility (CDIF) in Butte, Montana will be performed, so that by the early 1990's, an engineering data base on the reliability, availability, maintainability and performance of the system will be available to allow scaleup of the prototypical designs to the next development level. This Sixteenth Quarterly Technical Progress Report covers the period May 1, 1991 to July 31, 1991.

Not Available

1992-03-01T23:59:59.000Z

433

Technology development life cycle processes.  

SciTech Connect (OSTI)

This report and set of appendices are a collection of memoranda originally drafted in 2009 for the purpose of providing motivation and the necessary background material to support the definition and integration of engineering and management processes related to technology development. At the time there was interest and support to move from Capability Maturity Model Integration (CMMI) Level One (ad hoc processes) to Level Three. As presented herein, the material begins with a survey of open literature perspectives on technology development life cycles, including published data on %E2%80%9Cwhat went wrong.%E2%80%9D The main thrust of the material presents a rational expose%CC%81 of a structured technology development life cycle that uses the scientific method as a framework, with further rigor added from adapting relevant portions of the systems engineering process. The material concludes with a discussion on the use of multiple measures to assess technology maturity, including consideration of the viewpoint of potential users.

Beck, David Franklin

2013-05-01T23:59:59.000Z

434

Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative  

SciTech Connect (OSTI)

A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

Santi, Peter A [Los Alamos National Laboratory; Demuth, Scott F [Los Alamos National Laboratory; Klasky, Kristen L [Los Alamos National Laboratory; Lee, Haeok [Los Alamos National Laboratory; Miller, Michael C [Los Alamos National Laboratory; Sprinkle, James K [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Williams, Bradley [DOE, NE

2009-01-01T23:59:59.000Z

435

Uncertainty in Life Cycle Greenhouse Gas Emissions from United States Coal  

E-Print Network [OSTI]

analyses involving coal. Greenhouse gas emissions from fuel use and methane releases at coal mines, fuel.5 million metric tons of methane emissions. Close to 95% of domestic coal was consumed by the electricityUncertainty in Life Cycle Greenhouse Gas Emissions from United States Coal Aranya Venkatesh

Jaramillo, Paulina

436

Answering Key Fuel Cycle Questions  

SciTech Connect (OSTI)

The Advanced Fuel Cycle Initiative (AFCI) program has both outcome and process goals because it must address both waste already accumulating as well as completing the fuel cycle in connection with advanced nuclear power plant concepts. The outcome objectives are waste geological repository capacity and cost, energy security and sustainability, proliferation resistance, fuel cycle economics, and safety. The process objectives are readiness to proceed and adaptability and robustness in the face of uncertainties. A classic decision-making approach to such a multi-attribute problem would be to weight individual quantified criteria and calculate an overall figure of merit. This is inappropriate for several reasons. First, the goals are not independent. Second, the importance of different goals varies among stakeholders. Third, the importance of different goals is likely to vary with time, especially the energy future. Fourth, some key considerations are not easily or meaningfully quantifiable at present. Instead, at this point, we have developed 16 questions the AFCI program should answer and suggest an approach of determining for each whether relevant options improve meeting each of the program goals. We find that it is not always clear which option is best for a specific question and specific goal; this helps identify key issues for future work. In general, we suggest attempting to create as many win-win decisions (options that are attractive or neutral to most goals) as possible. Thus, to help clarify why the program is exploring the options it is, and to set the stage for future narrowing of options, we have developed 16 questions, as follows: What are the AFCI program goals? Which potential waste disposition approaches do we plan for? What are the major separations, transmutation, and fuel options? How do we address proliferation resistance? Which potential energy futures do we plan for? What potential external triggers do we plan for? Should we separate uranium? If we separate uranium, should we recycle it, store it or dispose of it? Is it practical to plan to fabricate and handle hot fuel? Which transuranic elements (TRU) should be separated and transmuted? Of those TRU separated, which should be transmuted together? Should we separate and/or transmute Cs and Sr isotopes that dominate near-term repository heating? Should we separate and/or transmute very long-lived Tc and I isotopes? Which separation technology? What mix of transmutation technologies? What fuel technology best supports the above decisions?

Steven J. Piet; Brent W. Dixon; J. Stephen Herring; David E. Shropshire; Mary Lou Dunzik-Gougar

2003-10-01T23:59:59.000Z

437

Fuel Cycle System Analysis Handbook  

SciTech Connect (OSTI)

This Handbook aims to improve understanding and communication regarding nuclear fuel cycle options. It is intended to assist DOE, Campaign Managers, and other presenters prepare presentations and reports. When looking for information, check here. The Handbook generally includes few details of how calculations were performed, which can be found by consulting references provided to the reader. The Handbook emphasizes results in the form of graphics and diagrams, with only enough text to explain the graphic, to ensure that the messages associated with the graphic is clear, and to explain key assumptions and methods that cause the graphed results. Some of the material is new and is not found in previous reports, for example: (1) Section 3 has system-level mass flow diagrams for 0-tier (once-through), 1-tier (UOX to CR=0.50 fast reactor), and 2-tier (UOX to MOX-Pu to CR=0.50 fast reactor) scenarios - at both static and dynamic equilibrium. (2) To help inform fast reactor transuranic (TRU) conversion ratio and uranium supply behavior, section 5 provides the sustainable fast reactor growth rate as a function of TRU conversion ratio. (3) To help clarify the difference in recycling Pu, NpPu, NpPuAm, and all-TRU, section 5 provides mass fraction, gamma, and neutron emission for those four cases for MOX, heterogeneous LWR IMF (assemblies mixing IMF and UOX pins), and a CR=0.50 fast reactor. There are data for the first 10 LWR recycle passes and equilibrium. (4) Section 6 provides information on the cycle length, planned and unplanned outages, and TRU enrichment as a function of fast reactor TRU conversion ratio, as well as the dilution of TRU feedstock by uranium in making fast reactor fuel. (The recovered uranium is considered to be more pure than recovered TRU.) The latter parameter impacts the required TRU impurity limits specified by the Fuels Campaign. (5) Section 7 provides flows for an 800-tonne UOX separation plant. (6) To complement 'tornado' economic uncertainty diagrams, which show at a glance combined uncertainty information, section 9.2 has a new set of simpler graphs that show the impact on fuel cycle costs for once through, 1-tier, and 2-tier scenarios as a function of key input parameters.

Steven J. Piet; Brent W. Dixon; Dirk Gombert; Edward A. Hoffman; Gretchen E. Matthern; Kent A. Williams

2009-06-01T23:59:59.000Z

438

Factors Involved in Search Dog Training  

E-Print Network [OSTI]

involved in training competent search dogs. Obedience training methods, age training was initiated, previous handler canine training experience, and handler perception and emotional attachment to their search dog were examined through a sixty-six question...

Alexander, Michael B.

2010-07-14T23:59:59.000Z

439

LARSON--MATH 556--CLASSROOM WORKSHEET 07 Hamilton Cycles  

E-Print Network [OSTI]

Last name First name LARSON--MATH 556--CLASSROOM WORKSHEET 07 Hamilton Cycles An alternating-cycle. A cycle which includes every point of a graph G is called a Hamilton cycle of G. 1. Draw the complete graph K5. Find one Hamilton cycle in K5. 2. Does every complete graph have a Hamilton cycle? Explain. 3

Larson, Craig E.

440

Air-blown Integrated Gasification Combined Cycle demonstration project  

SciTech Connect (OSTI)

Clean Power Cogeneration, Inc. (CPC) has requested financial assistance from DOE for the design construction, and operation of a normal 1270 ton-per-day (120-MWe), air-blown integrated gasification combined-cycle (IGCC) demonstration plant. The demonstration plant would produce both power for the utility grid and steam for a nearby industrial user. The objective of the proposed project is to demonstrate air-blown, fixed-bed Integrated Gasification Combined Cycle (IGCC) technology. The integrated performance to be demonstrated will involve all the subsystems in the air-blown IGCC system to include coal feeding; a pressurized air-blown, fixed-bed gasifier capable of utilizing caking coal; a hot gas conditioning systems for removing sulfur compounds, particulates, and other contaminants as necessary to meet environmental and combustion turbine fuel requirements; a conventional combustion turbine appropriately modified to utilize low-Btu coal gas as fuel; a briquetting system for improved coal feed performance; the heat recovery steam generation system appropriately modified to accept a NO{sub x} reduction system such as the selective catalytic reduction process; the steam cycle; the IGCC control systems; and the balance of plant. The base feed stock for the project is an Illinois Basin bituminous high-sulfur coal, which is a moderately caking coal. 5 figs., 1 tab.

Not Available

1991-01-01T23:59:59.000Z

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


441

Optimal operation of simple vapour compression cycles  

E-Print Network [OSTI]

is the air-conditioner (A/C). In colder regions a cycle operating in the opposite direction, the "heat pump. The coefficients of performance for a heating cycle (heat pump) and a cooling cycle (refrigerator, A/C) are defined as COPh = Qh Ws = h1 - h2 h1 - h4 and COPc = Qc Ws = h4 - h3 h1 - h4 (1.1) respectively. Heat pumps

Skogestad, Sigurd

442

Metabolic Futile Cycles and Their Functions: A Systems Analysis of Energy and Control  

E-Print Network [OSTI]

It has long been hypothesized that futile cycles in cellular metabolism are involved in the regulation of biochemical pathways. Following the work of Newsholme and Crabtree, we develop a quantitative theory for this idea based on open-system thermodynamics and metabolic control analysis. It is shown that the {\\it stoichiometric sensitivity} of an intermediary metabolite concentration with respect to changes in steady-state flux is governed by the effective equilibrium constant of the intermediate formation, and the equilibrium can be regulated by a futile cycle. The direction of the shift in the effective equilibrium constant depends on the direction of operation of the futile cycle. High stoichiometric sensitivity corresponds to ultrasensitivity of an intermediate concentration to net flow through a pathway; low stoichiometric sensitivity corresponds to super-robustness of concentration with respect to changes in flux. Both cases potentially play important roles in metabolic regulation. Futile cycles actively shift the effective equilibrium by expending energy; the magnitude of changes in effective equilibria and sensitivities is a function of the amount of energy used by a futile cycle. This proposed mechanism for control by futile cycles works remarkably similarly to kinetic proofreading in biosynthesis. The sensitivity of the system is also intimately related to the rate of concentration fluctuations of intermediate metabolites. The possibly different roles of the two major mechanisms for cellular biochemical regulation, namely reversible chemical modifications via futile cycles and shifting equilibrium by macromolecular binding, are discussed.

Hong Qian; Daniel A. Beard

2006-06-14T23:59:59.000Z

443

Variable pressure power cycle and control system  

DOE Patents [OSTI]

A variable pressure power cycle and control system that is adjustable to a variable heat source is disclosed. The power cycle adjusts itself to the heat source so that a minimal temperature difference is maintained between the heat source fluid and the power cycle working fluid, thereby substantially matching the thermodynamic envelope of the power cycle to the thermodynamic envelope of the heat source. Adjustments are made by sensing the inlet temperature of the heat source fluid and then setting a superheated vapor temperature and pressure to achieve a minimum temperature difference between the heat source fluid and the working fluid.

Goldsberry, Fred L. (Spring, TX)

1984-11-27T23:59:59.000Z

444

Seeing the Forest of Secular Cycles  

E-Print Network [OSTI]

imperial cycles (The Old and Middle Kingdoms of Egypt).In the case of Egypt, the mapping thatproduced separated ancient Egypt into two adjacent imperial

Sirag, Jr., David J

2012-01-01T23:59:59.000Z

445

PCM energy storage during defective thermal cycling:.  

E-Print Network [OSTI]

??Incomplete thermal cycling affects storage capacities of phase change materials (PCMs). Existing PCM measuring methods are presented with their drawbacks. A new device named the (more)

Koekenbier, S.F.

2011-01-01T23:59:59.000Z

446

THE TRANSPOSED CRITICAL TEMPERATURE RANKINE THERMODYNAMIC CYCLE  

E-Print Network [OSTI]

of Electricity from Geothermal Energy," Brown University,Simulation of Geothermal Energy Cycles), LBL publication-Manager), Economics "Geothermal Energy Conversion and Case

Pope, William L.

2012-01-01T23:59:59.000Z

447

Fuel Cycle Research and Development Program  

Office of Environmental Management (EM)

29, 2009 Fuel Cycle Research and Development DM 195665 5 Identify the governing phenomenology Identify the governing phenomenology Develop a first-principle based model of the...

448

Combined rankine and vapor compression cycles  

DOE Patents [OSTI]

An organic rankine cycle system is combined with a vapor compression cycle system with the turbine generator of the organic rankine cycle generating the power necessary to operate the motor of the refrigerant compressor. The vapor compression cycle is applied with its evaporator cooling the inlet air into a gas turbine, and the organic rankine cycle is applied to receive heat from a gas turbine exhaust to heat its boiler within one embodiment, a common condenser is used for the organic rankine cycle and the vapor compression cycle, with a common refrigerant, R-245a being circulated within both systems. In another embodiment, the turbine driven generator has a common shaft connected to the compressor to thereby eliminate the need for a separate motor to drive the compressor. In another embodiment, an organic rankine cycle system is applied to an internal combustion engine to cool the fluids thereof, and the turbo charged air is cooled first by the organic rankine cycle system and then by an air conditioner prior to passing into the intake of the engine.

Radcliff, Thomas D.; Biederman, Bruce P.; Brasz, Joost J.

2005-04-19T23:59:59.000Z

449

Most fish have a forward undulatory swimming mechanism that involves a kinematic propulsive wave travelling down the  

E-Print Network [OSTI]

Most fish have a forward undulatory swimming mechanism that involves a kinematic propulsive wave backwards in a similar way. We compared the kinematics (wave speed, cycle frequency, amplitude, local in the direction opposite to that of swimming. We observe two major kinematic differences. First, the slope of wave

D'Août, Kristiaan

450

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

SciTech Connect (OSTI)

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

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

2013-12-15T23:59:59.000Z

451

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

SciTech Connect (OSTI)

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

NONE

1996-08-01T23:59:59.000Z

452

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

SciTech Connect (OSTI)

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

Dolan, T.J.; Anderl, R.A.

1994-09-01T23:59:59.000Z

453

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

SciTech Connect (OSTI)

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

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

1990-09-01T23:59:59.000Z

454

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

SciTech Connect (OSTI)

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

Baker, C.C.

1988-08-01T23:59:59.000Z

455

Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report  

SciTech Connect (OSTI)

Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest.

NONE

1997-04-18T23:59:59.000Z

456

The ITER pre-compression rings A first in cryogenic composite technology  

SciTech Connect (OSTI)

The ITER Pre-Compression Rings represent one of the heaviest composite structures ever manufactured as a single piece and the largest - the outer diameter will be above 5.5 meters - intended for use in a cryogenic environment. With a cross section of 337 mm 288 mm, each item will weigh more than 3,000 kg. A development program, based on filament wound and dry wound S2 glass unidirectional fibers, the latter processed by VARTM, was completed on one fifth scale rings, and these materials and techniques were shown to be satisfactory. The paper describes how a technology applied to build up primary structures of European launchers is being accommodated to produce the ITER Pre-Compression Rings, fulfilling its extremely challenging requirements. In addition, we will describe how the structural analysis is correlated with the test results of scaled down rings, as well as how the pre-compression rings manufacturing process will be qualified.

Rajainmaki, Hannu; Fanthome, John; Losasso, Marcello [Fusion for Energy, C/ Josep Pla, n. 2, E-08019 Barcelona (Spain); Foussat, Arnaud [ITER Organisation, 13108 St. Paul-lez-Durance (France); Rodriguez, Jesus [EADS CASA Espacio S.L., Av. de Aragn 404, E-28022 Madrid (Spain); Evans, David; Diaz, Victor [Advanced Cryogenic Materials Ltd, Abingdon, OX14 2HQ (United Kingdom)

2014-01-27T23:59:59.000Z

457

Experimental neutronics tests for a neutron activation system for the European ITER TBM  

SciTech Connect (OSTI)

We are investigating methods for neutron flux measurement in the ITER TBM. In particular we have tested sets of activation materials leading to induced gamma activities with short half-lives of the order of tens of seconds up to minutes and standard activation materials. Packages of activation foils have been irradiated with the intense neutron generator of Technical University of Dresden in a pure DT neutron field as well as in a neutronics mock-up of the European ITER HCLL TBM. An important aim was to check whether the gamma activity induced in the activation foils in these packages could be measured simultaneously. It was indeed possible to identify gamma lines of interest in gamma-ray measurements immediately after extraction from the irradiation.

Klix, A.; Fischer, U. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Gehre, D. [Technical University of Dresden, IKTP, Zellescher Weg 19, 01062 Dresden (Germany); Kleizer, G. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Raj, P. [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and Universit Paris-Sud, 15 rue Georges Clemenceau, F-91405 Paris (France); Rovni, I. [Budapest University of Technology and Economics, M?egyetem rkp. 3-9. H-1111 Budapest (Hungary); Ruecker, Tom [Karlsruhe Institute of Technology (KIT), INR, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen, Germany and University of Applied Sciences Zittau-Goerlitz, Theodor-Krner-Allee 16, D-02754 Zittau (Germany)

2014-08-21T23:59:59.000Z

458

In-Vessel Coil Material Failure Rate Estimates for ITER Design Use  

SciTech Connect (OSTI)

The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

L. C. Cadwallader

2013-01-01T23:59:59.000Z

459

Clover Action for Blue Gene-Q and Iterative solvers for DWF  

E-Print Network [OSTI]

In Lattice QCD, a major challenge in simulating physical quarks is the computational complexity of these simulations. In this proceeding, we describe the optimisation of Clover fermion action for Blue gene-Q architecture and how different iterative solvers behave for Domain Wall Fermion action. We find that the optimised Clover term achieved a maximum efficiency of 29.1% and 20.2% for single and double precision respectively for iterative Conjugate Gradient solver. For Domain Wall Fermion action (DWF) we found that Modified Conjugate Residual(MCR) as the most efficient solver compared to CG and GCR. We have developed a new multi-shift MCR algorithm that is 18.5% faster compared to multi-shift CG for the evaluation of rational functions in RHMC.

Karthee Sivalingam; Peter Boyle

2014-08-28T23:59:59.000Z

460

Iterative procedure for in-situ EUV optical testing with an incoherent source  

SciTech Connect (OSTI)

We propose an iterative method for in-situ optical testing under partially coherent illumination that relies on the rapid computation of aerial images. In this method a known pattern is imaged with the test optic at several planes through focus. A model is created that iterates through possible aberration maps until the through-focus series of aerial images matches the experimental result. The computation time of calculating the through-focus series is significantly reduced by a-SOCS, an adapted form of the Sum Of Coherent Systems (SOCS) decomposition. In this method, the Hopkins formulation is described by an operator S which maps the space of pupil aberrations to the space of aerial images. This operator is well approximated by a truncated sum of its spectral components.

Miyawaka, Ryan; Naulleau, Patrick; Zakhor, Avideh

2009-12-01T23:59:59.000Z

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


461

Design and Overview of 100 kV Bushing for the DNB Injector of ITER  

SciTech Connect (OSTI)

The 100 kV bushing is one of the most important and technologically challenging Safety Important Class (SIC) components of the Diagnostic Neutral Beam (DNB) injector of ITER. It forms interface between gas insulated electrical transmission line and torus primary vacuum and acts as a vacuum feedthrough of ITER. Design optimization has been carried out to meet the electric and structural requirements based on its classification. Unlike HNB bushing, single stage bushing is designed to provide 100 kV isolation. Finite Element Analysis (FEA) based optimization has been carried out for electrostatic and structural analysis. Manufacturing assembly sequence is studied and presented in this paper. However validation of the same is foreseen from manufacturer.

Shah, Sejal; Bandyopadhyay, M.; Rotti, C.; Singh, M. J.; Roopesh, G.; Chakraborty, A. K. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Rajesh, S. [ITER-India, Institute for Plasma Research, Gandhinagar-382025, Gujarat (India); Microelectronics and Materials Physics Labs, P.O.Box 4500, FIN-90014 University of Oulu (Finland); Nishad, S.; Srusti, B. [DesignTech Systems Ltd, Banjara Hills, Hyderabad, Andhra Pradesh-500034 (India); Schunke, B.; Hemsworth, R.; Chareyre, J.; Svensson, L. [ITER Organisation, Route de Vinon, CS 90 046, 13067 St. Paul lez Durance Cedex (France)

2011-09-26T23:59:59.000Z

462

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

SciTech Connect (OSTI)

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

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

2007-04-30T23:59:59.000Z

463

Current Control in ITER Steady State Plasmas With Neutral Beam Steering  

SciTech Connect (OSTI)

Predictions of quasi steady state DT plasmas in ITER are generated using the PTRANSP code. The plasma temperatures, densities, boundary shape, and total current (9 - 10 MA) anticipated for ITER steady state plasmas are specified. Current drive by negative ion neutral beam injection, lower-hybrid, and electron cyclotron resonance are calculated. Four modes of operation with different combinations of current drive are studied. For each mode, scans with the NNBI aimed at differing heights in the plasma are performed to study effects of current control on the q profile. The timeevolution of the currents and q are calculated to evaluate long duration transients. Quasi steady state, strongly reversed q profiles are predicted for some beam injection angles if the current drive and bootstrap currents are sufficiently large.

R.V. Budny

2009-09-10T23:59:59.000Z

464

Irradiation tests of ITER candidate Hall sensors using two types of neutron spectra  

SciTech Connect (OSTI)

We report on irradiation tests of InSb based Hall sensors at two irradiation facilities with two distinct types of neutron spectra. One was a fission reactor neutron spectrum with a significant presence of thermal neutrons, while another one was purely fast neutron field. Total neutron fluence of the order of 10{sup 16} cm{sup -2} was accumulated in both cases, leading to significant drop of Hall sensor sensitivity in case of fission reactor spectrum, while stable performance was observed at purely fast neutron spectrum. This finding suggests that performance of this particular type of Hall sensors is governed dominantly by transmutation. Additionally, it further stresses the need to test ITER candidate Hall sensors under neutron flux with ITER relevant spectrum.

Duran, I. [Institute of Plasma Physics AS CR, v. v. i., Association EURATOM/IPP.CR, 182 00 Prague 8 (Czech Republic); Bolshakova, I.; Holyaka, R. [Magnetic Sensor Laboratory, Lviv Polytechnic National University, 790 31 Lviv (Ukraine); Viererbl, L.; Lahodova, Z. [Nuclear Research Institute plc., 250 68 Husinec-Rez (Czech Republic); Sentkerestiova, J. [Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, 115 19 Prague 1 (Czech Republic); Bem, P. [Nuclear Physics Institute AS CR, v. v. i., 250 68 Husinec-Rez (Czech Republic)

2010-10-15T23:59:59.000Z

465

Tritium processing system for the ITER Li/V blanket test module  

SciTech Connect (OSTI)

The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refueling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.

Sze, D.K.; Hua, T.Q. [Argonne National Lab., IL (United States); Abdou, M.A. [Univ. of California, Los Angeles, CA (United States); Dagher, M.A.; Waganer, L.M.

1997-04-01T23:59:59.000Z

466

A Pseudo Random Numbers Generator Based on Chaotic Iterations. Application to Watermarking  

E-Print Network [OSTI]

In this paper, a new chaotic pseudo-random number generator (PRNG) is proposed. It combines the well-known ISAAC and XORshift generators with chaotic iterations. This PRNG possesses important properties of topological chaos and can successfully pass NIST and TestU01 batteries of tests. This makes our generator suitable for information security applications like cryptography. As an illustrative example, an application in the field of watermarking is presented.

Christophe Guyeux; Qianxue Wang; Jacques M. Bahi

2010-12-21T23:59:59.000Z

467

Absolutely and uniformly convergent iterative approach to inverse scattering with an infinite radius of convergence  

DOE Patents [OSTI]

A method and system for solving the inverse acoustic scattering problem using an iterative approach with consideration of half-off-shell transition matrix elements (near-field) information, where the Volterra inverse series correctly predicts the first two moments of the interaction, while the Fredholm inverse series is correct only for the first moment and that the Volterra approach provides a method for exactly obtaining interactions which can be written as a sum of delta functions.

Kouri, Donald J. (Houston, TX); Vijay, Amrendra (Houston, TX); Zhang, Haiyan (Houston, TX); Zhang, Jingfeng (Houston, TX); Hoffman, David K. (Ames, IA)

2007-05-01T23:59:59.000Z

468

Design of irradiation rig for reactor testing of prototype bolometers for ITER  

SciTech Connect (OSTI)

We describe the design of an experimental rig, which was developed to allow reactor testing at relevant conditions, i.e. vacuum and {approx}400 deg.C temperature, of prototype resistive bolometers, which will be used in ITER to acquire information on the radiated power distribution from the main plasma and in the diverter region. The main feature of the design is that the rig has no active temperature control. (authors)

Gusarov, A.; Huysmans, S. [SCK.CEN Belgian Nucrear Research Center, 2400 Mol (Belgium); Meister, H. [Max-Planck-Institut fuer Plasmaphysik, Boltzmannstr. 2, D-85748 Garching b. Muenchen (Germany); Hodgson, E. [Euratom/CIEMAT Fusion Association, Avenida Complutense 22, 28040 Madrid (Spain)

2011-07-01T23:59:59.000Z

469

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

E-Print Network [OSTI]

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

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

2014-07-17T23:59:59.000Z

470

Atomic data for the ITER Core Imaging X-ray Spectrometer  

SciTech Connect (OSTI)

The parameters of the ITER core plasmas will be measured using the Core Imaging X-ray Spectrometer (CIXS), a high-resolution crystal spectrometer focusing on the L-shell spectra of highly ionized tungsten atoms. In order to correctly infer the plasma properties accurate atomic data are required. Here, some aspects of the underlying physics are discussed using experimental data and theoretical predictions from modeling.

Clementson, J; Beiersdorfer, P; Biedermann, C; Bitter, M; Delgado-Aparicio, L F; Graf, A; Gu, M F; Hill, K W; Barnsley, R

2012-06-15T23:59:59.000Z

471

Going with the group in a competitive game of iterated reasoning Seth Frey (sethfrey@indiana.edu)  

E-Print Network [OSTI]

Going with the group in a competitive game of iterated reasoning Seth Frey (sethfrey their strategy individually. John Nash proved that every game has at least one such equilib- rium. Mapped onto

Goldstone, Robert

472

Detailed search US supports Japanese bid to host ITER as France urges Europe to go it alone  

E-Print Network [OSTI]

support of his country for the Japanese bid to host the international thermonuclear site (ITER thermonuclear site if the French candidate is not selected for the international project. However

473

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

SciTech Connect (OSTI)

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

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

1995-08-01T23:59:59.000Z

474

White Paper for Developing Electromagnetic Particle Injector system for ITER on NSTX-U University of Washington (19 July 2012)  

E-Print Network [OSTI]

discharges in ITER, both the time response of this system and the controllability on demand - Conventional gas guns will inject gas before capsule and trigger pre rail gun We plan to finish the design during 2012 and to build

475

Recent progress on lower hybrid current drive and implications for ITER  

E-Print Network [OSTI]

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

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

2015-01-01T23:59:59.000Z

476

An investigation into optimization of iteration parameters for solving partial differential equations by the alternating-direction implicit procedure  

E-Print Network [OSTI]

AN INVESTIGATION INTO OPTIMIZATION OF ITERATION PARAMETERS FOR SOLVING PARTIAL DIFFERENTIAL EQUATIONS BY THE ALTERNATING-DIRECTION IMPLICIT PROCEDURE A Thesis GERALD NELSON PITTS Submitted to the Graduate College of the Texas A&M University... in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1967 Major Subject Com uter Science AN INVESTIGATION INTO OPTIMIZATION OF ITERATION PARAMETERS FOR SOLVING PARTIAL DIFFERENTIAL EQUATIONS BY THE ALTERNATING...

Pitts, Gerald Nelson

1967-01-01T23:59:59.000Z

477

S and H Cycle Engine  

SciTech Connect (OSTI)

Our thirst for energy is increasing at an astounding rate. World population growth is estimated to increase by 40% (to 8.5 billion) by 2050, with annual electrical energy usage estimated increase by 100% (to 25 terawatt-hours). We must find new means and fuels as well as significantly improve the efficiency of current power plants to accommodate this growing electrical energy demand. This demand is also growing in the field of space flight. Present energy and propulsion systems are limited in the amount of power (energy) that can be generated by today's technology. This limits the distance that can be safely traveled by manned and un-manned space systems. Space flight is primarily governed by two factors: time and energy. Increasing energy of space propulsion systems will decrease flight time or allow reaching farther out into space safely for manned exploration of our solar system. For example, a round trip manned mission to Mars would take about 400 days with a NERVA type thermal nuclear rocket. To reduce the 400 days to 80 days would require an increase of energy by a factor of five. We need to develop space propulsion systems with much greater energy capability than we have today to satisfy the expansion of space exploration. The S and H Cycle nuclear engine provides a revolutionary technological approach that can contribute significantly toward solving the World electrical energy and the space travel energy requirements. (authors)

Strobl, William C. [2906 Via Pepita, Carlsbad, Ca. 92009 (United States); Holland, Joe P. [10671 Jasper Ave., Redlands, Ca. 92374 (United States)

2002-07-01T23:59:59.000Z

478

MHD Integrated Topping Cycle Project  

SciTech Connect (OSTI)

This fourteenth quarterly technical progress report of the MHD Integrated Topping Cycle Project presents the accomplishments during the period November 1, 1990 to January 31, 1991. Testing of the High Pressure Cooling Subsystem electrical isolator was completed. The PEEK material successfully passed the high temperature, high pressure duration tests (50 hours). The Combustion Subsystem drawings were CADAM released. The procurement process is in progress. An equipment specification and RFP were prepared for the new Low Pressure Cooling System (LPCS) and released for quotation. Work has been conducted on confirmation tests leading to final gas-side designs and studies to assist in channel fabrication.The final cathode gas-side design and the proposed gas-side designs of the anode and sidewall are presented. Anode confirmation tests and related analyses of anode wear mechanisms used in the selection of the proposed anode design are presented. Sidewall confirmation tests, which were used to select the proposed gas-side design, were conducted. The design for the full scale CDIF system was completed. A test program was initiated to investigate the practicality of using Avco current controls for current consolidation in the power takeoff (PTO) regions and to determine the cause of past current consolidation failures. Another important activity was the installation of 1A4-style coupons in the 1A1 channel. A description of the coupons and their location with 1A1 channel is presented herein.

Not Available

1992-02-01T23:59:59.000Z

479

Solar cycle changes in coronal holes and space weather cycles J. G. Luhmann,1  

E-Print Network [OSTI]

Solar cycle changes in coronal holes and space weather cycles J. G. Luhmann,1 Y. Li,1 C. N. Arge,2-heliolatitude solar wind over approximately the last three solar cycles. Related key parameters like interplanetary explain solar magnetic field control of long-term interplanetary variations. In particular, the enduring

California at Berkeley, University of

480

Physics challenges for advanced fuel cycle assessment  

SciTech Connect (OSTI)

Advanced fuel cycles and associated optimized reactor designs will require substantial improvements in key research area to meet new and more challenging requirements. The present paper reviews challenges and issues in the field of reactor and fuel cycle physics. Typical examples are discussed with, in some cases, original results.

Giuseppe Palmiotti; Massimo Salvatores; Gerardo Aliberti

2014-06-01T23:59:59.000Z

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


481

mathematics Study program cycle and type  

E-Print Network [OSTI]

mathematics academic study programmm 11 #12;12 #12;· Study program cycle and type: First cycle academic study program. · AAnnttiicciippaatteedd aaccaaddeemmiicc ttiittllee:: Bachelor in Mathematics ggooaallss:: The principal goal of the academic study program in Mathematics is to qualify its graduates

?umer, Slobodan

482

Fuel cycles for the 80's  

SciTech Connect (OSTI)

Papers presented at the American Nuclear Society's topical meeting on the fuel cycle are summarized. Present progress and goals in the areas of fuel fabrication, fuel reprocessing, spent fuel storage, accountability, and safeguards are reported. Present governmental policies which affect the fuel cycle are also discussed. Individual presentations are processed for inclusion in the Energy Data Base.(DMC)

Not Available

1980-01-01T23:59:59.000Z

483

Assessment 101: The Assessment Cycle, Clear and  

E-Print Network [OSTI]

Assessment 101: The Assessment Cycle, Clear and Simple October 1, 2014 Kellogg West Conference Center, Pomona, CA Resource Binder #12;2014-2015 WASC Senior College and University Commission is pleased expectations. Assessment 101: The Assessment Cycle, Clear and Simple October 1, 2014. Kellogg West, Pomona, CA

Su, Xiao

484

Uncertainty Analyses of Advanced Fuel Cycles  

SciTech Connect (OSTI)

The Department of Energy is developing technology, experimental protocols, computational methods, systems analysis software, and many other capabilities in order to advance the nuclear power infrastructure through the Advanced Fuel Cycle Initiative (AFDI). Our project, is intended to facilitate will-informed decision making for the selection of fuel cycle options and facilities for development.

Laurence F. Miller; J. Preston; G. Sweder; T. Anderson; S. Janson; M. Humberstone; J. MConn; J. Clark

2008-12-12T23:59:59.000Z

485

VISION: Verifiable Fuel Cycle Simulation Model  

SciTech Connect (OSTI)

The nuclear fuel cycle consists of a set of complex components that work together in unison. In order to support the nuclear renaissance, it is necessary to understand the impacts of changes and timing of events in any part of the fuel cycle system. The Advanced Fuel Cycle Initiatives systems analysis group is developing a dynamic simulation model, VISION, to capture the relationships, timing, and changes in and among the fuel cycle components to help develop an understanding of how the overall fuel cycle works. This paper is an overview of the philosophy and development strategy behind VISION. The paper includes some descriptions of the model components and some examples of how to use VISION.

Jacob Jacobson; A. M. Yacout; Gretchen Matthern; Steven Piet; David Shropshire; Tyler Schweitzer

2010-11-01T23:59:59.000Z

486

Life-cycle assessments: Linking energy, economics, and the environment. Paper No. 571  

SciTech Connect (OSTI)

The Pacific Northwest Laboratory has been involved in a number of life-cycle assessment (LCA) projects that assess the complete lifetime energy, economic, and environmental impacts of alternative technology options. Life-cycle assessments offer one-stop shopping answers to the total energy and environmental implications of alternative technologies, as well as providing employment and income consequences. In one recently completed study, the lifetime impacts of scenarios involving the production and use of biomass ethanol transportation fuels were assessed. In an ongoing study, the lifetime impacts of electric-powered vehicles versus conventional fuels are being assessed. In a proposed study, the impacts of recycled office paper versus office paper from virgin sources would be assessed. A LCA proceeds by developing mass and energy inventories during all phases of the life-cycle. Special attention is given to energy consumption and environmental releases. Economics are incorporated by evaluating the macroeconomic impacts of the alternative policies, such as employment, wages, and output. Economics can also be incorporated by attempting to place values on the damages imposed by the environmental releases associated with alternative scenarios. This paper discusses life-cycle assessment techniques and their application to building energy issues. Life-cycle assessments show great promise for analysis of buildings energy policy questions.

Shankle, S.A.

1994-08-01T23:59:59.000Z

487

Automatic Control Strategy Development for the Supercritical CO{sub 2} Brayton Cycle for LFR Autonomous Load Following  

SciTech Connect (OSTI)

The supercritical carbon dioxide (S-CO{sub 2}) Brayton cycle is a promising advanced alternative to the Rankine saturated steam cycle and ideal gas Brayton cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO{sub 2} Brayton cycle coupled to an autonomous Lead-Cooled Fast Reactor (LFR). The plant dynamics code was used to develop an automatic control strategy for the whole plant in response to changes in the demand from the electrical grid. The specific features of the S-CO{sub 2} Brayton cycle that result in limitations on the control range and speed of specific control mechanisms are discussed. Calculations of whole-plant responses to plant operational transients involving step and continuous changes in grid demand are demonstrated. (authors)

Moisseytsev, Anton; Sienicki, James J. [Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL, 60439 (United States)

2006-07-01T23:59:59.000Z

488

Fire Classifications Fires involving the ordinary  

E-Print Network [OSTI]

, plastics, etc. Fires involving combustible or flammable liquids such as gasoline, kerosene, oils, grease is protected by various devices such as smoke detectors, sprinkler systems, and manual fire alarm pull stations. Manual pull stations are strategically located throughout the University. Usually located by each exit

Jia, Songtao

489

Production of Meson Pairs Involving $L \  

E-Print Network [OSTI]

We present a formalism for studying the exclusive production or decay of mesons with any value of the internal orbital angular momentum L. As an application, we discuss the production of meson pairs (involving tensor and pseudotensor mesons) in photon-photon collisions.

Houra-Yaou, L; Parisi, J; Murgia, F; Hansson, J

1997-01-01T23:59:59.000Z

490

Environmental science and ecology involve studies  

E-Print Network [OSTI]

Environmental science and ecology involve studies of the biosphere, hydro- sphere, and lithosphere in environmental science is conducted on spatial scales varying from a single algal cell to the Earth as a whole's environmental scientists require investigation by an interdisciplinary team, including members from several

Christensen, Dan

491

Sustainability Indicators for Open-Cycle Thorium-Fuelled Nuclear Energy  

E-Print Network [OSTI]

to candidate countries is the Global Nuclear Energy Partnership (see Larry Browns report in Reference (IAEA2006a)). This fuel cycle involves the spent nuclear fuel being shipped back to the country which manufactured the fuel which, after reprocessing... -Cycle Stage (Fig. 1) Emissions Freshwater Aquatic Eco-Toxicity Potential FAETP kg 1,4- DCB(eq) Mn, Ml, CE, Fu, Re, SFR, DGD Marine Aquatic Eco-Toxicity Potential MAETP kg 1,4- DCB(eq) Mn, Ml, CE, Fu, Re, SFR, DGD Global Warming Potential...

Ashley, S.F.; Fenner, R.A.; Nuttall, W.J.; Parks, G.T.

2012-06-28T23:59:59.000Z

492

Process system optimization for life cycle improvement  

SciTech Connect (OSTI)

Life Cycle Assessment (LCA) is an analytic tool for quantifying the environmental impacts of all processes used in converting raw materials into a final product. The LCA consists of three parts. Life cycle inventory quantifies all material and energy use, and environmental emissions for the entire product life cycle, while impact assessment evaluates actual and potential environmental and human health consequences of the activities identified in the inventory phase. Most importantly, life cycle improvement aims at reducing the risk of these consequences occurring to make the product more benign. when the LCA is performed in conjunction with a technoeconomic analysis, the total economic and environmental benefits and shortcomings of a product or process can be quantified. A methodology has been developed incorporating process performance, economics, and life cycle inventory data to synthesize process systems, which meet life cycle impact-improvement targets at least cost. The method relies on a systematic description of the product life cycle and utilizes successive Linear Programming to formulate and optimize the non-linear, constrained problem which results. The practicality and power of this approach have been demonstrated by examining options for the reduction of emissions of the greenhouse gas CO{sub 2} from petroleum-based fuels.

Marano, J.J.; Rogers, S.

1999-12-31T23:59:59.000Z

493

EVOLVING LEG CYCLES TO PRODUCE HEXAPOD GAITS GARY B. PARKER  

E-Print Network [OSTI]

movement by the servos. The best means of combining these leg cycles into a gait cycle is learnedEVOLVING LEG CYCLES TO PRODUCE HEXAPOD GAITS GARY B. PARKER Computer Science, Connecticut College by dividing the prob- lem into two parts: leg cycle learning and gait cycle learning. Servo pulses required

Parker, Gary B.

494

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

495

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect (OSTI)

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Carter, J.

2011-01-03T23:59:59.000Z

496

Regulation of the genes involved in nitrification.  

SciTech Connect (OSTI)

OAK-B135 This project focuses on the characterization of the regulation of the genes involved in nitrification in the bacterium Nitrosomonas europaea. The key genes in the nitrification pathway, amo and hao, are present in multiple copies in the genome. The promoters for these genes were identified and characterized. It was shown that there were some differences in the transcriptional regulation of the copies of these genes.

Arp, D.J.; Sayavedra-Soto, L.A.

2003-08-14T23:59:59.000Z

497

Performance evaluation of two-stage fuel cycle from SFR to PWR  

SciTech Connect (OSTI)

One potential fuel cycle option being considered is a two-stage fuel cycle system involving the continuous recycle of transuranics in a fast reactor and the use of bred plutonium in a thermal reactor. The first stage is a Sodium-cooled Fast Reactor (SFR) fuel cycle with metallic U-TRU-Zr fuel. The SFRs need to have a breeding ratio greater than 1.0 in order to produce fissile material for use in the second stage. The second stage is a PWR fuel cycle with uranium and plutonium mixed oxide fuel based on the design and performance of the current state-of-the-art commercial PWRs with an average discharge burnup of 50 MWd/kgHM. This paper evaluates the possibility of this fuel cycle option and discusses its fuel cycle performance characteristics. The study focuses on an equilibrium stage of the fuel cycle. Results indicate that, in order to avoid a positive coolant void reactivity feedback in the stage-2 PWR, the reactor requires high quality of plutonium from the first stage and minor actinides in the discharge fuel of the PWR needs to be separated and sent back to the stage-1 SFR. The electricity-sharing ratio between the 2 stages is 87.0% (SFR) to 13.0% (PWR) for a TRU inventory ratio (the mass of TRU in the discharge fuel divided by the mass of TRU in the fresh fuel) of 1.06. A sensitivity study indicated that by increasing the TRU inventory ratio to 1.13, The electricity generation fraction of stage-2 PWR is increased to 28.9%. The two-stage fuel cycle system considered in this study was found to provide a high uranium utilization (>80%). (authors)

Fei, T.; Hoffman, E.A.; Kim, T.K.; Taiwo, T.A. [Nuclear Engineering Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL (United States)

2013-07-01T23:59:59.000Z

498

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation InInformation InExplosion Monitoring:Home|Physics ResearchLCLS Sign Register today for

499

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:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof2014 EIA Energy Conference U.S. Crude Oil

500

Free Energy and Internal Combustion Engine Cycles  

E-Print Network [OSTI]

The performance of one type (Carnot) of Internal Combustion Engine (ICE) cycle is analyzed within the framework of thermodynamic free energies. ICE performance is different from that of an External Combustion Engine (ECE) which is dictated by Carnot's rule.

Harris, William D

2012-01-01T23:59:59.000Z