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  1. US ITER

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

    Production toroidal field coil integrated and jacketed at High Performance Magnetics in Tallahassee, FL. Photo: US ITER The US ITER project engages more than 500 companies, ...

  2. US ITER | Jobs

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

    Postings Careers in Fusion Science ITER Jobs Home > Jobs > US ITER Positions US ITER Positions US

  3. US ITER | Media Corner

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

    of Terms Project Background Creating a Star - The Global ITER Partnership Photo Books ITER Progress in Pictures 2015 (US edition) ITER Progress in Pictures 2015 (ITER...

  4. Status of the ITER Tokamac Exhaust Process System

    Office of Environmental Management (EM)

    the ITER Tokamak Exhaust Process System Anita Poore Bernice Rogers 2014 Spring Tritium Focus Group Meeting April 24, 2014 SRNL-STI-2014-00175 The views and opinions expressed herein do not necessarily reflect those of the ITER Organization, US ITER or the US Government. Presentation Outline * Overview of ITER DT Fuel Cycle * Select ITER requirements Fuel Cycle * Process Requirements * Design Approach * Simplified Process Flow Diagram * Spatial Interface * Risk Mitigation Activities * Potential

  5. Public involvement in the regulatory activities regarding nuclear fuel cycle facilities: A case study

    SciTech Connect (OSTI)

    Austin, D.E.

    1995-12-01

    This paper reviews the involvement of a community-based organization in the activities of the Nuclear Regulatory Commission (NRC) regarding a uranium conversion facility that operated near Gore, Oklahoma from 1970 until 1992. Effective participation requires access to decision making. Access is a complex phenomenon that includes: (1) opportunity, both procedural and physical, (2) a common language, and (3) time and resources. The paper describes how both the community organization and the NRC responded to these requirements for access, the strategies that were most effective in securing meaningful public involvement in the decision making, and the impacts of that involvement on the organization.

  6. US ITER | About

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

    US ITER About US ITER ABOUT US ITER | WHY FUSION? | DOING BUSINESS WITH US ITER | MEDIA CORNER | JOBS | CONTACT US About US ITER US Hardware Contributions About US ITER Home > About US ITER Background US ITER is a DOE Office of Science project hosted by Oak Ridge National Laboratory in Tennessee. Partner labs are Princeton Plasma Physics Laboratory and Savannah River National Laboratory. The US is a partner nation in ITER, an unprecedented international collaboration of scientists and

  7. US ITER | Jobs

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

    Postings Careers in Fusion Science ITER Jobs Home > Jobs > International Job Postings International ITER Postions International

  8. US ITER | Media Corner

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

    India DA Project Director Visits US ITER Project Office India DA Project Director Visits US ITER Project Office Published Janaury 5, 2012 India DA Project Director Visits US ITER Project Office US ITER project manager Ned Sauthoff and India DA project director Shishir Deshpande share a laugh while watching a skit during the US ITER staff holiday luncheon. Photo: US ITER/ORNL Shishir P. Deshpande, Project Director for the ITER India Domestic Agency, visited the US ITER Project Office on December

  9. US ITER | Media Corner

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

    Corner Fact Sheets Hydrogen Fusion ITER Project US ITER Progress US ITER Participants More Project Background Creating a Star - The Global ITER Partnership Features and Highlights Winding completed on first central solenoid module [ITER Newsline, Arpril 11, 2016] Fusion diagnostics heat up across the US [US ITER, October 22, 2015] Preparing a unique fabrication line for the central solenoid modules [US ITER, September 14, 2015] Central solenoid insert coil confirms conductor readiness for ITER

  10. US ITER | Contact Us

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

    Organizational Charts ABOUT US ITER | WHY FUSION? | DOING BUSINESS WITH US ITER | MEDIA CORNER | JOBS | CONTACT US Visitor Information Key Contact Staff Directory Organizational Charts U.S. ITER Contacts Home > Contact Us> Organizational Charts Organizational Charts US ITER Organizational Chart Oak Ridge National Laboratory Organizational Chart ITER Organization (IO) Structure Chart ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma

  11. US ITER | Media Corner

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

    9 News Archive: 2009 Schedule Concerns Delay ITER's Go-Ahead [Science Magazine, November 27, 2009] ITER council delays project [Physics Today, November 20, 2009] ITER Blueprints Near Completion, But Financial Hurdles Lie Ahead [Science Magazine, November 13, 2009] ORNL director testifies on ITER, fusion research [Knoxville News Sentinel, October 29, 2009] Herron named deputy director of US ITER [Knoxville News Sentinel, October 15, 2009] US ITER awards $33.6M for magnet materials [Knoxville News

  12. US ITER | Media Corner

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

    New Division Management in Place at US ITER New Division Management in Place at US ITER Published September 20, 2011 After an extensive international search, US ITER selected John Bumgardner as the US ITER nuclear systems division director and John Haines as the US ITER non-nuclear systems division director. These new managers will provide important leadership as the project transitions from research and design to the engagement of industry in fabrication of US ITER hardware contributions. Both

  13. US ITER | Media Corner

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

    Building the Heartbeat of ITER Building the Heartbeat of ITER Preparing a unique fabrication line for the central solenoid modules -Lynne Degitz September 14, 2015 A partial view...

  14. US ITER | Doing Business

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

    US ITER > Business Opportunties > For Vendors > Tokamak Cooling Water System Opportunities Tokamak Cooling Water System (TCWS) Opportunities US ITER has contracted with AREVA...

  15. US ITER | Doing Business

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

    U.S. ITER > Business Opportunities Business Opportunities U.S. ITER International ITER International Organization (IO) Competitive Task Agreements ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated:

  16. US ITER | Jobs

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

    US ITER Jobs ABOUT US ITER | WHY FUSION? | DOING BUSINESS WITH US ITER | MEDIA CORNER | JOBS | CONTACT US US Job Postings International Job Postings Careers in Fusion Science ITER Jobs Home > US ITER Jobs Be a Part of Something Big! US ITER is a Department of Energy multi-laboratory project that executes the US contributions to ITER for the US. The US is a non-host partner in the seven-member international collaboration between the United States, China, India, Japan, Korea, Russia, and the

  17. US ITER | Doing Business

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

    Business Opportunties > ITER Clauses, Documents & Forms ITER Clauses, Documents & Forms Technical Proposal Disclosure Policy (April 2013) Identification of Background Intellectual Property by Prospective Subcontractors QA/QC Questionnaire Required Coordination with ITER Logistical Services Provider (April 2013) Patent Rights - Acquisition by the Government - ITER (March 2007) Exhibit 1B Patent Rights - Retention by the Seller (Short Form) - ITER (August 20, 2015) Exhibit 1C Exhibit 9

  18. US ITER | Jobs

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

    Postings Careers in Fusion Science ITER Jobs Home > Jobs > Careers in Fusion Science Learn More About Working at US ITER and Careers in Fusion Science Jan Berry Takes a Different Path (US ITER Tokamak Cooling Water System Team Leader) Ted Biewer: An International Career in Plasma Diagnostics (Fusion Energy Division, ORNL) video Frank Casella: Assuring Safety and Quality (US ITER Quality Assurance Officer) Kevin Chan: Optimizing Superconducting Strand (US ITER Toroidal Field Coil Conductor

  19. US ITER | Media Corner

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

    ITER's central magnet requires a powerful support cage ITER's central magnet requires a powerful support cage Prototypes for the central solenoid support components have been fabricated and are being tested -Lynne Degitz Published May 21, 2013 US ITER is building one of the world's largest and most powerful electromagnets to energize the ITER tokamak, a device that confines plasma in the shape of a doughnut. The 13 meter tall central solenoid will be located in the heart of the ITER fusion

  20. US ITER | Media Corner

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

    Solutions developed for housing ITER diagnostics Solutions developed for housing ITER diagnostics US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate -Lynne Degitz Published March 27, 2013 Modular approach to housing the extensive diagnostic systems. Princeton Plasma Physics Laboratory's Russ Feder (left) and Dave Johnson developed key features for a modular approach to housing the extensive diagnostic systems that will be installed on the ITER

  1. US ITER | Media Corner

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

    US Production of Miles of Superconducting Wire is Under Way for ITER's Super-Sized Toroidal Field Magnets US Production of Miles of Superconducting Wire is Under Way for ITER's Super-Sized Toroidal Field Magnets -Agatha Bardoel Published February 22, 2012 US ITER Toridal Field Coil Conductor US ITER toroidal field coil conductor production requires miles of niobium-tin superconducting wire. Photo: Luvata Waterbury, Inc. The ITER experimental fusion facility, now under construction in southern

  2. US ITER | Media Corner

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

    Videos US ITER Moving Forward US ITER Moving Forward (2012) Ned Sauthoff and Susan McGinnis - Fusion Reaction Energy for the Future (2011) Ned Sauthoff and Susan McGinnis - Fusion Reaction Fusion Reaction in a Tokamak (2010) Project Manager Ned Sauthoff talks about US ITER Project Manager Ned Sauthoff talks about US ITER (2009) Videos from the Around the World of Fusion (Link to complete list.) Fusion Energy Production by Neutral Particle Injection This visualization demonstrates how the ITER

  3. US ITER | Doing Business

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

    ITER US ITER Procurement Division is responsible for the acquisition of goods and services for the US ITER project. Business Opportunities US: Upcoming US ITER Procurements US: Business Opportunities with Other Partner Laboratories International: Calls for Nominations, Calls for Expertise and Market Surveys/Requests for Interest International: Opportunities with Other International Partners ITER International Organization (IO) Competitive Task Agreements. For Vendors Vendors wishing to do

  4. US ITER | Media Corner

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

    Central solenoid insert coil confirms conductor readiness for ITER Central solenoid insert coil confirms conductor readiness for ITER Central solenoid insert coil confirms conductor readiness for ITER -Lynne Degitz Published August 13, 2015 The insert coil being lowered into the test facility at Naka, Japan. The insert coil being lowered into the test facility at Naka, Japan. Photo: JAEA In another step towards building the ITER fusion reactor, the US ITER team worked with international partners

  5. US ITER | Media Corner

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

    ITER pump design benefits from testing at ORNL Spallation Neutron Source cryogenic facility ITER pump design benefits from testing at ORNL Spallation Neutron Source cryogenic facility ITER pump design benefits from testing at ORNL Spallation Neutron Source cryogenic facility -Lynne Degitz Published August 4, 2015 Robert Duckworth oversaw the testing of the 9-foot tall ITER cryoviscous compress pump prototype at the Spallation Neutron Source cryogenic test facility. Photo: US ITER/ORNL. Robert

  6. US ITER | Media Corner

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

    US delivers multiple "firsts" for ITER site US delivers multiple "firsts" for ITER site Conductor for toroidal field magnets, drain tanks and electrical components are being delivered to Europe for installation at the ITER site -Lynne Degitz March 19, 2015 Conductor for toroidal field magnets A close-up view of toroidal field production conductor. The conductor delivered in January is approximately 800 meters in length. Photo: US ITER As the international ITER magnetic fusion

  7. US ITER | About

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

    ITER Magnet System ITER Magnet System (WBS 1.1.1) The ITER Magnet System magnetically confines, shapes and controls the plasma inside the tokamak vacuum vessel. For maximum efficiency and to limit energy consumption, ITER uses superconducting magnets that lose their resistance when cooled to very low temperatures. The magnet system for ITER consists of: 18 toroidal field (TF) coils | more on US contribution Central solenoid (CS) with 6 segments | more on US contribution 6 poloidal field (PF)

  8. US ITER | Media Corner

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

    UT Magnet Lab Advances US ITER and Next Generation of Engineers, Scientists UT Magnet Lab Advances US ITER and Next Generation of Engineers, Scientists -Agatha Bardoel Published December 29, 2011 UT Magnet Lab Sample of glass/epoxy composite produced at the MDL for US ITER magnet insulator testing. Photo: US ITER/ORNL Tucked away in an unassuming building off Pellissippi Parkway in Knoxville, The University of Tennessee's Magnet Development Laboratory is under contract to the US ITER project for

  9. US ITER Moving Forward

    ScienceCinema (OSTI)

    US ITER / ORNL

    2012-03-16

    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.

  10. US ITER | Media Corner

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

    Neutronics at Wisconsin, ORNL advances ITER shielding and international collaboration "Neutronics" at Wisconsin, ORNL advances ITER shielding and international collaboration Computer codes calculate nuclear heating, neutron radiation damage and activation of fusion reactor materials. -Lynne Degitz Published June 18, 2012 A neutronics model of ITER is behind (left to right) Ed Marriott, Tim Bohm, Paul Wilson, Mohamed Sawan and Ahmad Ibrahim, US ITER researchers at the University of

  11. US ITER | Media Corner

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

    New Procurement Arrangement Signed for Low Field Side Reflectometer Diagnostic New Procurement Arrangement Signed for Low Field Side Reflectometer Diagnostic -Agatha Bardoel Published June 21, 2012 US ITER Project Manger Ned Sauthoff and ITER Director-General Osamu Motojima US ITER Project Manager Ned Sauthoff and ITER Director-General Osamu Motojima sign the low field side reflectometer Procurement Agreement on June 20, 2012 in Washington, DC. This diagnostic system will monitor electron

  12. US ITER | Media Corner

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

    fabrication of early delivery components for ITER advances US fabrication of early delivery components for ITER advances Delivery of tokamak cooling water system drain tanks will begin in 2014 -Katie Elyce Jones Published August 19, 2013 Vacuum Pressure Impregnation Vessel Drain tank heads, shown in fabrication at ODOM Industries in Milford Ohio, will be assembled at Joseph Oat Corporation in Camden, New Jersey. Photo: US ITER/ORNL Drain tank fabrication for ITER's tokamak cooling water system

  13. US ITER | Media Corner

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

    Newsletter Newsletter December 2015 July 2015 November 2014 February 2014 July 2013 January 2013 May 2012 December 2011 July 2011 March 2011 September 2010 Subscribe to the US ITER Newsletter Need an Expert? Media are welcome to contact Mark Uhran for assistance in reaching an appropriate US ITER expert. US ITER staff members are also available for presentations on fusion energy and the ITER project to technical, civic, community, and student groups. To make arrangements for a speaker, please

  14. INSIDE: ITER Site Progress

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

    Industry, Universities and Labs Job Openings Upcoming Events ITER's Central Magnet Requires a Powerful Support Cage Prototypes for the central solenoid support components have been fabricated and are being tested US ITER is building one of the world's largest and most powerful electromagnets to energize the ITER tokamak, a device that confines plasma in the shape of a doughnut. The 13 meter tall central solenoid will be located in the heart of the ITER fusion experiment. In order to maintain

  15. US ITER | About

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

    Diagnostics Diagnostics (WBS 1.5.3) Fact Sheet ITER Diagnostics Image Highlighted in pink: US contributions to ITER diagnostics. The US is responsible for 14% of port-based diagnostic systems, including integration of 4 diagnostic port plugs, plus 7 instrumentation systems out of a total of approximately 40 individual diagnostic systems. The European Union, Japan, the Russian Federation, China, Korea, and India are also contributing to ITER diagnostics. ITER diagnostic systems provide

  16. US ITER | Media Corner

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

    US ITER Major Vendors, Project Director to Speak at FPA Annual Meeting US ITER Major Vendors, Project Director to Speak at FPA Annual Meeting in December Published September 28, 2011 Speakers from US ITER contractors Areva Federal Services and General Atomics, plus US ITER project director Ned Sauthoff will be among the presenters at the 32nd annual Fusion Power Associates meeting and symposium titled "Fusion Energy: Expectations" on December 14-15, 2011 in Washington, DC. A proposed

  17. US ITER | Doing Business

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

    Opportunties > For Vendors For Vendors US ITER Vendor Database (For US ITER internal use only) Vendor Account Status System ORNL Procurement ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated: 02/24

  18. US ITER | Media Corner

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

    In Jacob's Room at US ITER In Jacob's Room at US ITER College Student Models, Simulates and Designs a Cooling Subsystem for the ITER Tokamak -Agatha Bardoel Published June 24, 2011 US ITER Project Manger Ned Sauthoff and ITER Director-General Osamu Motojima Jacob Clary is working under the guidance of Dr. Juan Ferrada to develop a cooling loop model. Nineteen-year-olds are not often found modeling and simulating a novel design for a cooling subsystem of the giant international Tokamak reactor

  19. US ITER | About

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

    Systems EC Transmission Lines Electrical Network Exhaust IC Transmission Lines Magnet Pellet Injection Vacuum US Hardware Home > About US ITER > US Hardware US Hardware Contributions The ITER Tokamak will be the largest ever built, with a plasma volume of 840 cubic metres and a weight of 23,000 tons. The maximum plasma volume in current tokamaks is 100 cubic metres - achieved by both Europe's JET and Japan's JT-60. ITER members will share hardware procurements for the design and

  20. US ITER | Media Corner

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

    3D printing yields advantages for US ITER engineers Desktop additive printers are changing the engineering design process 3D printing yields advantages for US ITER engineers Desktop additive printers are changing the engineering design process -Lynne Degitz Published March 11, 2014 A "toy"-sized, but accurately scaled, version of the ITER central solenoid (left) with one of the 18 toroidal field coils, printed on a desktop 3D printer. The pink oval represents the plasma. Notice the

  1. US ITER | Media Corner

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

    Building the heartbeat of ITER Building the heartbeat of ITER US ITER prepares for the fabrication of the international fusion reactor's central solenoid -Lynne Degitz Published February 24, 2014 Drive shaft gears General Atomics in San Diego, Calif., is overseeing the fabrication of the central solenoid, including the development of specialized tooling stations. This de-spooling tool-being developed by Tauring in Torino, Italy-will become part of the part of the conductor winding station at GA.

  2. US ITER | Media Corner

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

    ORNL's Fusion Pellet Fueling Lab Innovations Support US ITER Systems ORNL's Fusion Pellet Fueling Lab Innovations Support US ITER Systems -Agatha Bardoel Published January 3, 2012 UT Magnet Lab Steve Combs holds target materials for evaluating disruption mitigation pellet size.Photo: US ITER/ORNL Oak Ridge National Laboratory's Fusion Pellet Fueling Lab has been at the center of design and testing of plasma fueling systems for tokamak research applications for decades. Since the mid-1970s, lab

  3. US ITER | Media Corner

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

    US ITER high-performance pellet injection system advances to next stage US ITER high-performance pellet injection system advances to next stage Preparation is underway for full-scale prototype testing -Lynne Degitz Published September 16, 2013 Drive shaft gears The Oak Ridge National Laboratory-developed pellet injector is installed on the DIII-D tokamak for fueling and plasma edge control experiments. Photo: US ITER/ORNL Researchers at Oak Ridge National Laboratory developed a continuous

  4. US ITER | Media Corner

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

    toroidal field conductor fabrication advances US toroidal field conductor fabrication advances -Lynne Degitz Published January 7, 2013 A neutronics model of ITER is behind (left to right) Ed Marriott, Tim Bohm, Paul Wilson, Mohamed Sawan and Ahmad Ibrahim, US ITER researchers at the University of Wisconsin. Superconducting strand is cabled at New England Wire Technologies on 2.5 meter wide by 2 meter tall spools before shipment to Florida for conductor jacketing. Photo: NEWT . US ITER and its

  5. What is ITER

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

    ITER? ITER is a large international fusion experiment aimed at demonstrating the scientific and technological feasibility of fusion energy. ITER (Latin for "the way") will play a crit- ical role advancing the worldwide availability of energy from fusion - the power source of the sun and the stars. To produce practical amounts of fusion power on earth, heavy forms of hydrogen are joined together at high tem- perature with an accompanying production of heat en- ergy. The fuel must be

  6. US ITER | About

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

    Maps Maps The maps below will help you find your way to the US ITER Project Office and around ORNL and Oak Ridge. They are all provided in PDF format unless noted. ITER - Oak Ridge Office (Google Maps) ITER - Route from Knoxville McGhee-Tyson Airport ORNL Visitors Center Oak Ridge Oak Ridge/Knoxville to Visitor Center Oak Ridge Area/Knoxville Area Route from Knoxville McGhee-Tyson Airport to Oak Ridge ORNL Main Campus (close-up)

  7. US ITER | Media Corner

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

    Testing Central Solenoid Structural Integrity Testing Central Solenoid Structural Integrity Key steps forward for US ITER magnet efforts -Agatha Bardoel Published October 7, 2011 Vacuum Pressure Impregnation Vessel The vacuum pressure impregnation vessel will be used in testing methods for sealing and insulating ITER magnet modules. Photo: University of Tennessee Engineers and scientists at US ITER currently working on magnet projects have several key testing benchmarks over the next few months.

  8. US ITER | Media Corner

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

    US ITER preps for high performance plasma heating US ITER preps for high performance plasma heating New test results and innovations advance ion cyclotron high power transmission line progress for US ITER -Lynne Degitz Published April 29, 2014 A "toy"-sized, but accurately scaled, version of the ITER central solenoid (left) with one of the 18 toroidal field coils, printed on a desktop 3D printer. The pink oval represents the plasma. Notice the action figure at right showing the model's

  9. US ITER | Contact Us

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

    US Key Contact Key Contact Mark Uhran Communications Manager 865-574-8381 ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma...

  10. What is ITER

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

    facility, ITER will allow scientists to study reactor-scale burning plasmas and explore technical challenges related to the development of a power- producing fusion reactor. ...

  11. US ITER | Media Corner

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

    test bed ring will load ITER transmission lines with up to 6 megawatts New test bed ring will load ITER transmission lines with up to 6 megawatts -Agatha Bardoel Published April 30, 2012 US ITER Toridal Field Coil Conductor The ion cyclotron resonance ring test stand at Oak Ridge National Laboratory's Energy Systems Test Complex. New test bed ring will load ITER transmission lines with up to 6 megawatts 'This is roughly a factor of 3 higher than any RF transmission line ever used in fusion

  12. US ITER | Media Corner

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

    Life-size Mock-Up Helps R&D Staff Get a Feel for the Scale of ITER Life-size Mock-Up Helps R&D Staff Get a Feel for the Scale of ITER -Agatha Bardoel Published October 7, 2011 A Mockup of the Central Solenoid Module A mockup of the central solenoid module will help the magnet team identify issues relevant for construction, installation, and maintenance. Photo: US ITER/ORNL At the University of Tennessee Magnet Development Lab, a full-scale wooden mock-up of a single ITER central solenoid

  13. US ITER | Doing Business

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

    International: Business Opportunities with Other International Partners International: Business Opportunities with Other International Partners European Union The European Union maintains a website with additional ITER Business Opportunities. ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated: 06/25/2015

  14. US ITER | Media Corner

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

    6 News Archive: 2006 Is Nuclear Fusion Possible? [Energy Central, December 4, 2006] ORNL Plays Key Part in Fusion Deal [ORNL Neutron Science Division, November 22, 2006] US ITER Project Completes Management Team [ORNL News Release, August 17, 2006] US ITER Project Office, a partnership of Princeton Plasma Physics Laboratory and Oak Ridge National Laboratory, relocating to ORNL [ORNL News Release, February 1, 2006

  15. Preconditioned Iterative Solver

    Energy Science and Technology Software Center (OSTI)

    2002-08-01

    AztecOO contains a collection of preconditioned iterative methods for the solution of sparse linear systems of equations. In addition to providing many of the common algebraic preconditioners and basic iterative methods, AztecOO can be easily extended to interact with user-provided preconditioners and matrix operators.

  16. US ITER | Media Corner

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

    Winding of the central solenoid mock-up module has begun Winding of the central solenoid mock-up module has begun -Lynne Degitz Published November 17, 2014 The first part of the central solenoid winding station is a de-spooler, shown here unwinding material for the mock-up coil. Photo: US ITER. The first part of the central solenoid winding station is a de-spooler, shown here unwinding material for the mock-up coil. Photo: US ITER . At the heart of the ITER international fusion reactor-scale

  17. INSIDE: ITER Site Progress

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

    Industry Monaco/ITER Postdoctoral Fellowship Program Upcoming Events US Researchers Parse Complex Plasma Issues From "Snowballs in Hell" to "Burping the Baby" - by Agatha Bardoel The design, testing, and manufacture of a pellet injection system is one of the key contributions of the United States to ITER. Physicist David Rasmussen serves as the lead for US ITER's fueling team and as a group leader in the Fusion Energy Division at Oak Ridge National Laboratory. He points out

  18. US ITER | Jobs

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

    Nicolai Martovetsky US ITER Magnet Systems R&D Manager and Chief Engineer Tell us about your background Nicolai Martovetsky Nicolai Martovetsky I earned my Ph.D. at the Kurchatov Institute of Atomic Energy in Moscow, in 1985. I am a mechanical engineer. What were you doing before you came to US ITER? Before coming to US ITER, I was a research scientist at Lawrence Livermore National Laboratory (LLNL), in Livermore, Calif. I am currently on assignment here at Oak Ridge National Laboratory,

  19. US ITER | Contact Us

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

    Staff Directory Staff Directory Lookup Fields Last Name Institution Submit Reset ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated: 03/08/2016

  20. INSIDE: ITER Site Progress

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

    of all 400 kV substation equipment and all 22 kV switchgear. 2 Four US-supplied HV transformers were the first plant components installed at the ITER site in October 2015. Photo:...

  1. US ITER - Why Fusion?

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

    Educational Resources Fusion Educational Resources DOE Office of Science Fusion Energy Programs Education Links FuseNet: The European Fusion Education Network General Atomics Fusion Education PPPL Science Education Program PPPL FusEdWeb Educational Outreach: US ITER staff members are available for presentations on fusion energy and the ITER project to technical, civic, community, and student groups. To make arrangements for a speaker, please contact Mark Uhran, Communications Manager,

  2. US ITER | Doing Business

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

    ITER International Organization Competitive Task Agreements International Organization Competitive Task Agreements There are currently no requests for proposals or expressions of interest. If there are any questions regarding the task agreements, please contact Wayne Steffey (865-574-8364) or Mary Jane Maelzer (865-574-0358). ITER International Department of Energy Office of Science Oak Ridge National Laboratory Princeton Plasma Physics Laboratory Savannah River National Laboratory Last updated:

  3. INSIDE: ITER Site Progress

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

    Continued on page 8 INSIDE: ITER Site Progress View from DOE US Systems Update Engaging Industry, Universities and Labs Upcoming Events Disruption Mitigation Researchers Investigate Design Options ITER, the world's first reactor-scale fusion machine, will have a plasma volume more than 10 times that of the next largest tokamak, JET. Plasma disruptions that can occur in a tokamak when the plasma becomes unstable can potentially damage plasma-facing surfaces of the machine. To lessen the impact of

  4. US ITER | Media Corner

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

    Fusion diagnostics heat up across the US Fusion diagnostics heat up across the US Teams are developing tools to monitor and control ITER plasma -Lynne Degitz October 22, 2015 ITER, the world's largest tokamak now under construction in France, will have over 60 diagnostic systems installed to enable plasma control, optimize plasma performance, and support machine protection¬. Princeton Plasma Physics Laboratory and Oak Ridge National Laboratory, in collaboration with industry and universities,

  5. US ITER | About

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

    EC Transmission Lines Electrical Network Exhaust IC Transmission Lines Magnet Pellet Injection Vacuum US Hardware Home > About US ITER > US Hardware > Toroidal Field (TF) Magnets Central Solenoid (CS) (WBS 1.1.1) Fact Sheet Central Solenoid Highlighted in pink: The central solenoid, or "backbone" of the ITER Magnet System. The US is responsible for 100% of the central solenoid (CS) magnet, including design, R&D, fabrication of 7 CS modules using supplied conductor (from

  6. US ITER | About

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

    Tokamak Cooling Water System Tokamak Cooling Water System (WBS 1.2.1) Fact Sheet Cooling Water Systems Image Highlighted in pink: ITER Tokamak Cooling Water System. The US is responsible for 100% of the design, engineering, and procurement of the Tokamak Cooling Water System (TCWS). ITER's fusion power will reach 500 MW during the deuterium-tritium inductive plasma operation with an energy input of only 50 MW, yielding an energy multiplication factor of 10. Heat will be transferred by the

  7. US ITER | About

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

    Tokamak Exhaust Processing Systems Tokamak Exhaust Processing System (WBS 1.3.2) FactSheet Exhaust Process Image The ITER tokamak exhaust process design. The US is responsible for 100% of the final design, fabrication, assembly, testing, and shipment of the Tokamak Exhaust Processing (TEP) system. This effort is under way at Savannah River National Laboratory, in partnership with Los Alamos National Laboratory. ITER will require the processing of an unprecedented rate of hydrogen isotopes. To

  8. US ITER | About

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

    Pellet Injection System Pellet Injection System (WBS 1.3.1) Fact Sheet ITER Vacuum Vessle and Cryostat Image Highlighted in pink: Vacuum Pumping and Pellet Injection Systems. The US will contribute 100% towards the fueling and edge localized mode mitigation system. To: The US will contribute 100% towards the pellet injection system for fueling and edge localized mode mitigation. ITER will require significant fueling capability to operate at high density for long durations. Pellet injection

  9. US ITER | About

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

    Toroidal Field (TF) Magnets Toroidal Field (TF) Magnets (WBS 1.1.1) Fact Sheet TF Coil Highlighted in pink: One of the 18 toroidal field magents around the torus of the ITER tokamak design. The US will contribute 8% of the toroidal field (TF) coil conductors. The ITER Organization is responsible for the conductor design which is released for fabrication. Japan, the European Union, the Russian Federation, Korea, and China are also contributing TF conductor. The 18 toroidal field coils produce a

  10. US ITER | About

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

    Vacuum Auxiliary Systems Vacuum Auxiliary Systems (WBS 1.3.1) Fact Sheet ITER Vacuum Vessle and Cryostat Image Highlighted in pink: Vacuum Pumping and Pellet Injection Systems. The US will contribute 100% towards the roughing pumps and vacuum auxiliary system. The ITER tokamak, cryostat, and auxiliary vacuum chambers must be evacuated prior to and during operations. The roughing pump system exhausts the torus and neutral beam injector cryopumps, service vacuum, and cryostat. This system will

  11. US ITER | Jobs

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

    Kevin Chan US ITER Toroidal Field Coil Conductor Project Engineer Tell us about your background Kevin Chan Kevin Chan I was born in Pittsburgh, Pennsylvania and I am a mechanical engineer. What were you doing before you came to US ITER? From 1996-2003, I was maintenance supervisor, project planner, project engineer, and area manager for AK Steel, in Middletown, Ohio, a company that produces flat-rolled steel and aluminum coated stainless steel for the automotive, appliance, construction, and

  12. US ITER | Media Corner

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

    US ITER ships 30,000 pounds of magnet system hardware to Europe US ITER ships 30,000 pounds of magnet system hardware to Europe An 800-meter length of sample toroidal field conductor is en route to La Spezia, Italy -Lynne Degitz Published June 9, 2014 The 800-meter sample toroidal field conductor was transferred to a container ship at the port of Charleston, S.C., on May 28, 2014 for its voyage to La Spezia, Italy. The 800-meter sample toroidal field conductor was transferred to a container ship

  13. US ITER | Jobs

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

    Frank Casella US ITER Quality Assurance, Environmental, Safety and Health and Licensing Support Manager Tell us about your background Frank Casella Frank Casella I was born in Brooklyn, New York, but grew up in northern New Hampshire, where I went to high school. I attended Colgate University and then joined the Navy. I trained for the nuclear power program and specifically for nuclear submarines, and then spent four years on a nuclear sub. What were you doing before you came to US ITER? After I

  14. US ITER | Jobs

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

    Suzanne Herron US ITER Deputy Project Manager Tell us about your background Suzanne Herron Suzanne Herron I have a BS in mathematics, a master's degree in Industrial and Systems Engineering and am a certified project manager. I was born in Ohio. However, I have lived and worked in Tennessee for the past 25 years. What were you doing before you came to US ITER? I have had a variety of experiences in my career. I started out in Ohio, working on the Gaseous Diffusion Program for the enrichment of

  15. US ITER | Media Corner

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

    In Jacob's Room at US ITER Fusion Comes to the Secret City Published June 20, 2011 The USIPO joined ORNL neighbor Spallation Neutron Source to offer an interactive "science village" at the annual Secret City Festival in Oak Ridge, Tennessee on June 17-18, 2011. This is the first year that current science projects hosted at Oak Ridge have been represented at the festival. Over 1000 visitors toured the exhibits and learned more about fusion, ITER progress, and other cutting edge research

  16. ITER Fusion Energy

    ScienceCinema (OSTI)

    Dr. Norbert Holtkamp

    2010-01-08

    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.

  17. ITER | Princeton Plasma Physics Lab

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

    ITER Subscribe to RSS - ITER ITER is a large international fusion experiment aimed at demonstrating the scientific and technological feasibility of fusion energy. ITER (Latin for "the way") will play a critical role advancing the worldwide availability of energy from fusion - the power source of the sun and the stars. To produce practical amounts of fusion power on earth, heavy forms of hydrogen are joined together at high temperature with an accompanying production of heat energy. The

  18. US ITER | About

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

    Information Visitor Information Welcome to East Tennessee, Oak Ridge National Laboratory (ORNL), and the U.S. ITER Project Office. This is a scenic and geographically diverse area with much to offer. Economic opportunities are evolving rapidly, and academic opportunities are abundant. East Tennessee is an area rich with friendly people, cultural experiences, and unlimited outdoor activities The purpose of this site is to help you acquire basic information and contacts that will enhance your stay

  19. US ITER | Doing Business

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

    International: Calls for Nominations and Calls for Expertise International Opportunities For questions about calls for nominations or calls for expertise, please contact Terri Cleveland at clevelandtd@ornl.gov or 865-574-1022. If you are a US company and wish to express an interest in participating in a bid process for one of the above International ITER Organization requirements, please review USIPO's Export Control Awareness document. If you agree to follow the guidance provided in this

  20. US ITER | Media Corner

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

    Cryogenic deuterium machine gun corrals edgy plasma Cryogenic deuterium machine gun corrals edgy plasma -Agatha Bardoel Published May 3, 2012 Cryogenic deuterium machine gun Internal image of the three-barrel repeating pneumatic deuterium pellet injector used on DIII-D for pellet ELM pacing experiments. Photo: US ITER/ORNL Using a cryogenic deuterium pellet injector installed on the DIII-D tokamak operated for the Department of Energy Office of Science by General Atomics in San Diego, ORNL

  1. US ITER | Media Corner

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

    Disruption mitigation researchers investigate design options Disruption mitigation researchers investigate design options -Lynne Degitz Published January 4, 2013 ITER, the world's first reactor-scale fusion machine, will have a plasma volume more than 10 times that of the next largest tokamak, JET. Plasma disruptions that can occur in a tokamak when the plasma becomes unstable can potentially damage plasma-facing surfaces of the machine. To lessen the impact of high energy plasma disruptions, US

  2. US ITER | Media Corner

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

    7 News Archive: 2007 SRNL to help in study of fusion [Aiken Standard, January 16, 2007] United States-Japan Cooperation on Energy Security [Media Newswire, January 11, 2007] ORNL researchers, supercomputer have large roles in DOE projects [ORNL News Release, January 9, 2007] SNS completion highlights year of ORNL achievements [The Oak Ridger, January 4, 2007] US and German Leaders Explore Climate Cooperation [Environment News Service, January 4, 2007] Head of US ITER project named IEEE Fellow

  3. US ITER | Media Corner

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

    8 News Archive: 2008 New insights on fusion power [PhysOrg.com, December 3, 2008] Nuclear Fusion Moves One Step Closer [LiveScience.com, December 3, 2008] NRC Committee Reviews DOE Fusion Plan [SEA, November 19, 2008] ORNL's stainless steel attracts global interest [Knoxville News Sentinel, November 4, 2008] Scientists develop high-performance steel for ITER [The Oak Ridger, November 2, 2008] Can Engineers Achieve the Holy Grail of Energy: Infinite and Clean? [Discover Magazine, October 6, 2008]

  4. US ITER | About

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

    Electron Cyclotron Heating Transmission Lines Electron Cyclotron Heating Transmission Lines (WBS 1.5.2) Fact Sheet Electron Cyclotron Heating System Image Highlighted in pink: ITER Electron Cyclotron Heating Transmission Lines. The US is responsible for 88% of the electron cyclotron transmission lines, including research and development (with Oak Ridge National Laboratory and Massachusetts Institute of Technology), design, fabrication, and interfaces. The IO is responsible for installing the

  5. US ITER | About

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

    Ion Cyclotron Heating Transmission Lines Ion Cyclotron Heating Transmission Lines (WBS 1.5.1) Fact Sheet ICH Image Highlighted in pink: ITER Ion Cyclotron Heating Transmission Lines. The US is responsible for 88% of the ion cyclotron transmission lines, including research and development (with Oak Ridge National Laboratory and Princeton Plasma Physics Laboratory), design, fabrication, and interfaces. The IO is responsible for installing the ion cyclotron transmission lines (12%). The ion

  6. US ITER | About

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

    Steady-State Electrical Network Steady State Electrical Network (WBS 1.4.1) Fact Sheet The US contributes 75% of the equipment required for the Steady-State Electrical Network (SSEN), excluding cables and emergency power. The European Union contributes the remaining equipment and is also responsible for the design and installation of the system. The Steady-State Electrical Network is an AC power substation and distribution system that supplies electrical power to all ITER conventional systems

  7. US ITER | About

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

    Transportation Transportation Taxi and limousine service is available from the Knoxville airport to Oak Ridge and Knoxville hotels. Because a taxi may not be available when you want it and because you will need to provide your own transportation to and from US ITER. A rental car is suggested for short stays. A driver's license, credit card, and proof of insurance is required by man driving car rental car agencies. An international driver's license is required for foreign national visitors.

  8. US ITER | Jobs

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

    Kelli Kizer Subcontract Administrator Tell us about your background Kelli Kizer Kelli Kizer I was born in Knoxville, Tennessee, attended Lenoir City High School, then studied and graduated from the University of Tennessee, Knoxville (UTK) with a BS in Business Administration. What were you doing before you came to US ITER? When I was a sophomore at UTK, I began to intern during summers at the Oak Ridge National Laboratory. Upon graduating, I began working in the Environmental Restoration

  9. US ITER | Media Corner

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

    Videos from the Around the World of Fusion Fusion Power: Quest for the Ultimate Energy Source An interview with US fusion researcher Steve Dean, Founder of Fusion Power Associates. [August 18, 2013, interview by Tim Truett] Fusion Energy Production by Neutral Particle Injection This visualization demonstrates how the ITER reactor will create a burning plasma. [Sept. 28, 2012, National Center for Computational Sciences at Oak Ridge National Laboratory, 4:40] An earlier version of this animation

  10. Iterative reconstruction of magnetic induction using Lorentz...

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

    Iterative reconstruction of magnetic induction using Lorentz transmission electron tomography Title Iterative reconstruction of magnetic induction using Lorentz transmission...

  11. US ITER | Doing Business

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

    US Business Opportunities US Business Opportunities Upcoming US ITER Procurements WBS Description RFP Projected Date Projected Award Date $ Estimate POC WBS 1.1.1.2 Multi Jack Bolt Tensioners June 2016 August 2016 >$1M Kelly West (luckettwestk@ornl.gov) 865-576-6880 WBS 1.1.1.2 Lead Support Brackets/Manifold Platforms/Module Alignment System June 2016 August 2016 >$500K Kelly West (luckettwestk@ornl.gov) 865-576-6880 WBS 1.1.1.2 Fabrication of Lower Components Note: CS structure lower

  12. US ITER | Why Fusion?

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

    Why Fusion? US Fusion Research Educational Resources Why Fusion? Home > Why Fusion? What is Fusion? Fusion is a key element in long-term US energy plans. ITER will allow scientists to explore the physics of a burning plasma at energy densities close to that of a commercial power plant. This is a critical step towards producing and delivering electricity from fusion to the grid. Nuclear fusion occurs naturally in stars, like our sun. When hydrogen gets hot enough, the process of fusion

  13. US ITER | Media Corner

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

    From Snowballs in Hell to Burping the Baby From "Snowballs in Hell" to "Burping the Baby" US Researchers Parse Complex Plasma Issues -Agatha Bardoel Published October 31, 2011 Vacuum Pressure Impregnation Vessel A large (+16 mm) pellet is undergoing testing for ITER disruption mitigation. In this photo, the pellet, on the left, is exiting the guide tube just before hitting a simple target plate. It will shatter once it hits the plate. (Photo: Combs, ORNL) Heated to extreme

  14. ITER helium ash accumulation

    SciTech Connect (OSTI)

    Hogan, J.T.; Hillis, D.L.; Galambos, J.; Uckan, N.A. ); Dippel, K.H.; Finken, K.H. . Inst. fuer Plasmaphysik); Hulse, R.A.; Budny, R.V. . Plasma Physics Lab.)

    1990-01-01

    Many studies have shown the importance of the ratio {upsilon}{sub He}/{upsilon}{sub E} in determining the level of He ash accumulation in future reactor systems. Results of the first tokamak He removal experiments have been analysed, and a first estimate of the ratio {upsilon}{sub He}/{upsilon}{sub E} to be expected for future reactor systems has been made. The experiments were carried out for neutral beam heated plasmas in the TEXTOR tokamak, at KFA/Julich. Helium was injected both as a short puff and continuously, and subsequently extracted with the Advanced Limiter Test-II pump limiter. The rate at which the He density decays has been determined with absolutely calibrated charge exchange spectroscopy, and compared with theoretical models, using the Multiple Impurity Species Transport (MIST) code. An analysis of energy confinement has been made with PPPL TRANSP code, to distinguish beam from thermal confinement, especially for low density cases. The ALT-II pump limiter system is found to exhaust the He with maximum exhaust efficiency (8 pumps) of {approximately}8%. We find 1<{upsilon}{sub He}/{upsilon}{sub E}<3.3 for the database of cases analysed to date. Analysis with the ITER TETRA systems code shows that these values would be adequate to achieve the required He concentration with the present ITER divertor He extraction system.

  15. ITER | Princeton Plasma Physics Lab

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

    fusion experiment aimed at demonstrating the scientific and technological feasibility of fusion energy. ITER (Latin for "the way") will play a critical role advancing...

  16. US Contributions to ITER Project

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

    Contributions to ITER Project 12/7/15 † = D etailee * M = M atrix * S /C = S ubcontractor * * = D ual C apacity 2

  17. BBC Video Looks at ITER | Princeton Plasma Physics Lab

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

    BBC Video Looks at ITER American Fusion News Category: U.S. ITER Link: BBC Video Looks at ITER

  18. ITER Diagnostic First Wal

    SciTech Connect (OSTI)

    G. Douglas Loesser, et. al.

    2012-09-21

    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.

  19. Travel Requirements - ITER (June 2014

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

    Travel Requirements - ITER (June 2014) Prior to any travel under this subcontract, the Seller shall submit their request to travel with the following information to the Technical Project Officer (TPO) for approval, with a copy to the identified US ITER Project Office Travel Administrative Coordinator (TAC), via email: name of traveler as it appears on passport; e-mail address of traveler; dates of travel; purpose of travel; business city; date business begins; and date business ends. The TAC for

  20. ODE System Solver W. Krylov Iteration & Rootfinding

    Energy Science and Technology Software Center (OSTI)

    1991-09-09

    LSODKR is a new initial value ODE solver for stiff and nonstiff systems. It is a variant of the LSODPK and LSODE solvers, intended mainly for large stiff systems. The main differences between LSODKR and LSODE are the following: (a) for stiff systems, LSODKR uses a corrector iteration composed of Newton iteration and one of four preconditioned Krylov subspace iteration methods. The user must supply routines for the preconditioning operations, (b) Within the corrector iteration,more » LSODKR does automatic switching between functional (fixpoint) iteration and modified Newton iteration, (c) LSODKR includes the ability to find roots of given functions of the solution during the integration.« less

  1. ODE System Solver W. Krylov Iteration & Rootfinding

    Energy Science and Technology Software Center (OSTI)

    1991-09-09

    LSODKR is a new initial value ODE solver for stiff and nonstiff systems. It is a variant of the LSODPK and LSODE solvers, intended mainly for large stiff systems. The main differences between LSODKR and LSODE are the following: (a) for stiff systems, LSODKR uses a corrector iteration composed of Newton iteration and one of four preconditioned Krylov subspace iteration methods. The user must supply routines for the preconditioning operations, (b) Within the corrector iteration,moreLSODKR does automatic switching between functional (fixpoint) iteration and modified Newton iteration, (c) LSODKR includes the ability to find roots of given functions of the solution during the integration.less

  2. ORC Closed Loop Control Systems for Transient and Steady State Duty Cycles

    Broader source: Energy.gov [DOE]

    System-level models using iterative concept analysis are being used on a closed loop controlled, waste heat recovery system running automatically over various drive cycles.

  3. RIGHT OF ACCESS BY OTHERS - ITER (December 2013

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

    RIGHT OF ACCESS BY OTHERS - ITER (December 2013) In order to ensure the quality and fitness of components and systems procured for ITER, the Company, ITER International...

  4. Microsoft Word - ex15-ITER-sept10.doc

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

    - ITER UT-B Contracts Div Sept 2010 Page 1 of 1 ex15-ITER-sept10.doc Exhibit 15-ITER Ref: FAR 52.227-17 RIGHTS IN DATA SPECIAL WORKS ITER (Sept 2010) (a) Definitions. (1)...

  5. Nuclear Forensic Inferences Using Iterative Multidimensional Statistics

    SciTech Connect (OSTI)

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

    2009-06-09

    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.

  6. Customer Involvement

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

    Projects Expand Projects Skip navigation links Ancillary and Control Area Services (ACS) Practices Forum Meetings Customer Comments Attachment K 2015 Planning Cycle 2014...

  7. Identification of Export Control Classification Number - ITER

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

    Identification of Export Control Classification Number - ITER (April 2012) As the "Shipper of Record" please provide the appropriate Export Control Classification Number (ECCN) for the products (equipment, components and/or materials) and if applicable the nonproprietary associated installation/maintenance documentation that will be shipped from the United States to the ITER International Organization in Cadarache, France or to ITER Members worldwide on behalf of the Company. In rare

  8. ETR/ITER systems code

    SciTech Connect (OSTI)

    Barr, W.L.; Bathke, C.G.; Brooks, J.N.; Bulmer, R.H.; Busigin, A.; DuBois, P.F.; Fenstermacher, M.E.; Fink, J.; Finn, P.A.; Galambos, J.D.; Gohar, Y.; Gorker, G.E.; Haines, J.R.; Hassanein, A.M.; Hicks, D.R.; Ho, S.K.; Kalsi, S.S.; Kalyanam, K.M.; Kerns, J.A.; Lee, J.D.; Miller, J.R.; Miller, R.L.; Myall, J.O.; Peng, Y-K.M.; Perkins, L.J.; Spampinato, P.T.; Strickler, D.J.; Thomson, S.L.; Wagner, C.E.; Willms, R.S.; Reid, R.L.

    1988-04-01

    A tokamak systems code capable of modeling experimental test reactors has been developed and is described in this document. The code, named TETRA (for Tokamak Engineering Test Reactor Analysis), consists of a series of modules, each describing a tokamak system or component, controlled by an optimizer/driver. This code development was a national effort in that the modules were contributed by members of the fusion community and integrated into a code by the Fusion Engineering Design Center. The code has been checked out on the Cray computers at the National Magnetic Fusion Energy Computing Center and has satisfactorily simulated the Tokamak Ignition/Burn Experimental Reactor II (TIBER) design. A feature of this code is the ability to perform optimization studies through the use of a numerical software package, which iterates prescribed variables to satisfy a set of prescribed equations or constraints. This code will be used to perform sensitivity studies for the proposed International Thermonuclear Experimental Reactor (ITER). 22 figs., 29 tabs.

  9. Iterative reconstruction of magnetic induction using Lorentz...

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

    induction of a nanostructure. This allows for implementing the reconstruction as a linear algebra problem such that various iterative algebraic reconstruction methods can be...

  10. Identification of Export Control Classification Number - ITER

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

    Identification of Export Control Classification Number - ITER (April 2012) As the "Shipper of Record" please provide the appropriate Export Control Classification Number (ECCN) for...

  11. Looking northeast over the ITER construction site

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

    significant approval of a project baseline by the ITER Council, to the appointment ... (IO) - unanimously approved the project baseline as presented by the IO. The baseline ...

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

    SciTech Connect (OSTI)

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

    2014-08-21

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

  13. Qualification of the Joints for the ITER Central Solenoid

    SciTech Connect (OSTI)

    Martovetsky, N; Berryhill, A; Kenney, S

    2011-09-01

    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.

  14. Neutronics at Wisconsin, ORNL advances ITER shielding and international

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

    collaboration | Princeton Plasma Physics Lab Neutronics at Wisconsin, ORNL advances ITER shielding and international collaboration American Fusion News Category: U.S. ITER Link: Neutronics at Wisconsin, ORNL advances ITER shielding and international collaboration

  15. The ITER Project: International Collaboration to Demonstrate Nuclear Fusion

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

    | Princeton Plasma Physics Lab The ITER Project: International Collaboration to Demonstrate Nuclear Fusion American Fusion News Category: U.S. ITER Link: The ITER Project: International Collaboration to Demonstrate Nuclear Fusion

  16. ITER Ion Cyclotron Heating and Fueling Systems

    SciTech Connect (OSTI)

    Rasmussen, D.A.; Baylor, L.R.; Combs, S.K.; Fredd, E.; Goulding, R.H.; Hosea, J.; Swain, D.W.

    2005-04-15

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

  17. Anderson Acceleration for Fixed-Point Iterations

    SciTech Connect (OSTI)

    Walker, Homer F.

    2015-08-31

    The purpose of this grant was to support research on acceleration methods for fixed-point iterations, with applications to computational frameworks and simulation problems that are of interest to DOE.

  18. GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS

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

    1 GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS (2014) Definitions ..................................................................................................................... 3 Article 1. Law and language of the Contract ................................................................................. 3 Article 2. Communications ............................................................................................................ 3 Article 3. Performance of the

  19. PPPL--2702 Power Radiated from ITER

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

    702 " Power Radiated from ITER and CIT by Impurities D E ~ O 014715 J. Cummings, S. A. Cohen, R Hulse, D. E. Post, M. H. Redi and J. Perkinst Princeton Plasma Physics Laboratory Princeton University, Rinceton, NJ 08543 Abstract The MIST code has been used to model impurity radiation from the edge and core plasmas in ITER and CIT. A broad range of parameters have been varied, including Zeff, impurity species, impurity transport coefficients, and plasma temperature and density profiles,

  20. Novel aspects of plasma control in ITER

    SciTech Connect (OSTI)

    Humphreys, D.; Jackson, G.; Walker, M.; Welander, A.; Ambrosino, G.; Pironti, A.; Felici, F.; Kallenbach, A.; Raupp, G.; Treutterer, W.; Kolemen, E.; Lister, J.; Sauter, O.; Moreau, D.; Schuster, E.

    2015-02-15

    ITER plasma control design solutions and performance requirements are strongly driven by its nuclear mission, aggressive commissioning constraints, and limited number of operational discharges. In addition, high plasma energy content, heat fluxes, neutron fluxes, and very long pulse operation place novel demands on control performance in many areas ranging from plasma boundary and divertor regulation to plasma kinetics and stability control. Both commissioning and experimental operations schedules provide limited time for tuning of control algorithms relative to operating devices. Although many aspects of the control solutions required by ITER have been well-demonstrated in present devices and even designed satisfactorily for ITER application, many elements unique to ITER including various crucial integration issues are presently under development. We describe selected novel aspects of plasma control in ITER, identifying unique parts of the control problem and highlighting some key areas of research remaining. Novel control areas described include control physics understanding (e.g., current profile regulation, tearing mode (TM) suppression), control mathematics (e.g., algorithmic and simulation approaches to high confidence robust performance), and integration solutions (e.g., methods for management of highly subscribed control resources). We identify unique aspects of the ITER TM suppression scheme, which will pulse gyrotrons to drive current within a magnetic island, and turn the drive off following suppression in order to minimize use of auxiliary power and maximize fusion gain. The potential role of active current profile control and approaches to design in ITER are discussed. Issues and approaches to fault handling algorithms are described, along with novel aspects of actuator sharing in ITER.

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

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

    ITER Organization has to change accordingly: It will become simpler, centralized, and task-force oriented to adapt to the new era of construction. Among our most important...

  2. Microsoft Word - ex9rdf-ITER-sept09.doc

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

    RDF - Technical Data - ITER UT-B Contracts Div Sept 2009 Page 1 of 5 ex9rdf-ITER-sept09.doc Exhibit 9RDF-ITER Ref: DEAR 970.5227-1 TECHNICAL DATA - ITER (Sept 2009) 1. Rights in ...

  3. Microsoft Word - ex9-ITER-june11.doc

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

    Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9-ITER-june11.doc Exhibit 9 ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt.V, 52.227-16 TECHNICAL DATA - ITER (June ...

  4. In-vessel ITER tubing failure rates for selected materials and coolants

    SciTech Connect (OSTI)

    Marshall, T.D.; Cadwallader, L.C.

    1994-03-01

    Several materials have been suggested for fabrication of ITER in-vessel coolant tubing: beryllium, copper, Inconel, niobium, stainless steel, titanium, and vanadium. This report generates failure rates for the materials to identify the best performer from an operational safety and availability perspective. Coolant types considered in this report are helium gas, liquid lithium, liquid sodium, and water. Failure rates for the materials are generated by including the influence of ITER`s operating environment and anticipated tubing failure mechanisms with industrial operating experience failure rates. The analyses define tubing failure mechanisms for ITER as: intergranular attack, flow erosion, helium induced swelling, hydrogen damage, neutron irradiation embrittlement, cyclic fatigue, and thermal cycling. K-factors, multipliers, are developed to model each failure mechanism and are applied to industrial operating experience failure rates to generate tubing failure rates for ITER. The generated failure rates identify the best performer by its expected reliability. With an average leakage failure rate of 3.1e-10(m-hr){sup {minus}1}and an average rupture failure rate of 3.1e-11(m-hr){sup {minus}1}, titanium proved to be the best performer of the tubing materials. The failure rates generated in this report are intended to serve as comparison references for design safety and optimization studies. Actual material testing and analyses are required to validate the failure rates.

  5. Preliminary Master Logic Diagram for ITER operation

    SciTech Connect (OSTI)

    Cadwallader, L.C.; Taylor, N.P.; Poucet, A.E.

    1998-04-01

    This paper describes the work performed to develop a Master Logic Diagram (MLD) for the operations phase of the International Thermonuclear Experimental Reactor (ITER). The MLD is a probabilistic risk assessment tool used to identify the broad set of potential initiating events that could lead to an offsite radioactive or toxic chemical release from the facility under study. The MLD described here is complementary to the failure modes and effects analyses (FMEAs) that have been performed for ITER`s major plant systems in the engineering evaluation of the facility design. While the FMEAs are a bottom-up or component level approach, the MLD is a top-down or facility level approach to identifying the broad spectrum of potential events. Strengths of the MLD are that it analyzes the entire plant, depicts completeness in the accident initiator process, provides an independent method for identification, and can also identify potential system interactions. MLDs have been used successfully as a hazard analysis tool. This paper describes the process used for the ITER MLD to treat the variety of radiological and toxicological source terms present in the ITER design. One subtree of the nineteen page MLD is shown to illustrate the levels of the diagram.

  6. UGE Scheduler Cycle Time

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

    UGE Scheduler Cycle Time UGE Scheduler Cycle Time Genepool Cycle Time Genepool Daily Genepool Weekly Phoebe Cycle Time Phoebe Daily Phoebe Weekly What is the Scheduler Cycle? The...

  7. DOE/SC Lehman Review of US ITER Project, USIPO,

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

    SC Lehman Review of US ITER Project, USIPO, Oak Ridge, Tennessee, April 5-7, 2011 - Ned Sauthoff Project Manager, US ITER INSIDE: ITER Site Progress Secret City View from DOE US Project Highlights Engaging Industry New PPPL Head of ITER Department PPPL to Cadarache New Division Director Positions Open at US ITER Upcoming Events ORNL 2011-G00858/jpp It has been a busy season for US ITER, as the team positions for fabrication in late-FY 12 and FY 13. Our priorities remain completing designs,

  8. In-vessel tritium retention and removal in ITER

    SciTech Connect (OSTI)

    Federici, G.; Anderl, R.A.; Andrew, P.

    1998-06-01

    The International Thermonuclear Experimental Reactor (ITER) is envisioned to be the next major step in the world`s fusion program from the present generation of tokamaks and is designed to study fusion plasmas with a reactor relevant range of plasma parameters. During normal operation, it is expected that a fraction of the unburned tritium, that is used to routinely fuel the discharge, will be retained together with deuterium on the surfaces and in the bulk of the plasma facing materials (PFMs) surrounding the core and divertor plasma. The understanding of he basic retention mechanisms (physical and chemical) involved and their dependence upon plasma parameters and other relevant operation conditions is necessary for the accurate prediction of the amount of tritium retained at any given time in the ITER torus. Accurate estimates are essential to assess the radiological hazards associated with routine operation and with potential accident scenarios which may lead to mobilization of tritium that is not tenaciously held. Estimates are needed to establish the detritiation requirements for coolant water, to determine the plasma fueling and tritium supply requirements, and to establish the needed frequency and the procedures for tritium recovery and clean-up. The organization of this paper is as follows. Section 2 provides an overview of the design and operating conditions of the main components which define the plasma boundary of ITER. Section 3 reviews the erosion database and the results of recent relevant experiments conducted both in laboratory facilities and in tokamaks. These data provide the experimental basis and serve as an important benchmark for both model development (discussed in Section 4) and calculations (discussed in Section 5) that are required to predict tritium inventory build-up in ITER. Section 6 emphasizes the need to develop and test methods to remove the tritium from the codeposited C-based films and reviews the status and the prospects of the most attractive techniques. Section 7 identifies the unresolved issues and provides some recommendations on potential R and D avenues for their resolution. Finally, a summary is provided in Section 8.

  9. Annex I ITER Organization Service Contract General Conditions...

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

    All property of the Contractor while at the ITER Organization premises shall be at the risk of the Contractor and the ITER Organization shall accept no liability for any loss or...

  10. Annex I ITER Organization Service Contract General Conditions (2014)

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

    Annex I ITER Organization Service Contract General Conditions (2014) Page 1 of 21 GENERAL CONDITIONS FOR ITER ORGANIZATION SERVICE CONTRACTS (2014) Definitions ..................................................................................................................... 3 Article 1. Law and language of the Contract ................................................................................. 3 Article 2. Communications

  11. International Workshop: MFE Roadmapping in the ITER Era | Princeton Plasma

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

    Physics Lab International Workshop: MFE Roadmapping in the ITER Era International Workshop: MFE Roadmapping in the ITER Era Contact Information Website: International Workshop: MFE Roadmapping in the ITER Era Coordinator(s): Pamela Hampton phampton@pppl.gov Host(s): G.H. Neilson hneilson@pppl.gov Learn More Fusion roadmapping

  12. Microsoft Word - ex9ed-ITER-june11.doc

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

    ED - Technical Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9ed-ITER-june11.doc ... IV, 52.227-14 Alt. V, 52.227-16 TECHNICAL DATA - ITER (June 2011) 1. RIGHTS IN ...

  13. Annex II Technical Specifications Project Integration of ITER

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

    Project Integration of ITER Neutron Diagnostics ITER_D_SSYW98 v 2.0 ITER_D_R83AFD Page 2 of 8 Table of Contents 1 Abstract .................................................................................. Error! Bookmark not defined. 2 Background and Objectives ...............................................................................................3 3 Scope of Work ......................................................................................................................4 4

  14. Statistical properties of an iterated arithmetic mapping

    SciTech Connect (OSTI)

    Feix, M.R.; Rouet, J.L.

    1994-07-01

    We study the (3x = 1)/2 problem from a probabilistic viewpoint and show a forgetting mechanism for the last k binary digits of the seed after k iterations. The problem is subsequently generalized to a trifurcation process, the (lx + m)/3 problem. Finally the sequence of a set of seeds is empirically shown to be equivalent to a random walk of the variable log{sub 2}x (or log{sub 3} x) though computer simulations.

  15. US ITER is a strong contributor in plan to enhance international sharing of

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

    prime ITER real estate | Princeton Plasma Physics Lab US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate American Fusion News Category: U.S. ITER Link: US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate

  16. PPPL's Hawryluk Named ITER Deputy Director-General | Princeton Plasma

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

    Physics Lab PPPL's Hawryluk Named ITER Deputy Director-General By Patti Wieser March 8, 2011 Tweet Widget Google Plus One Share on Facebook Richard Hawryluk (Photo by Elle Starkman, PPPL Office of Communications) Richard Hawryluk Richard Hawryluk, a senior scientist at the DOE Princeton Plasma Physics Laboratory (PPPL), has been appointed deputy director-general of the ITER Organization and director of its administration department. The ITER project, currently under construction in France,

  17. PPPL's Hawryluk Named ITER Deputy Director-General | Princeton Plasma

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

    Physics Lab PPPL's Hawryluk Named ITER Deputy Director-General By Patti Wieser March 8, 2011 Tweet Widget Google Plus One Share on Facebook Richard Hawryluk (Photo by Elle Starkman, PPPL Office of Communications) Richard Hawryluk Richard Hawryluk, a senior scientist at the DOE Princeton Plasma Physics Laboratory (PPPL), has been appointed deputy director-general of the ITER Organization and director of its administration department. The ITER project, currently under construction in France,

  18. Simulation and Analysis of the Hybrid Operating Mode in ITER

    SciTech Connect (OSTI)

    Kessel, C.E.; Budny, R.V.; Indireshkumar, K.

    2005-09-22

    The hybrid operating mode in ITER is examined with 0D systems analysis, 1.5D discharge scenario simulations using TSC and TRANSP, and the ideal MHD stability is discussed. The hybrid mode has the potential to provide very long pulses and significant neutron fluence if the physics regime can be produced in ITER. This paper reports progress in establishing the physics basis and engineering limitation for the hybrid mode in ITER.

  19. Diverse Power Iteration Embeddings and Its Applications

    SciTech Connect (OSTI)

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

    2014-12-14

    Abstract—Spectral 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.

  20. Technological Institute of Renewable Energy ITER | Open Energy...

    Open Energy Info (EERE)

    to: navigation, search Name: Technological Institute of Renewable Energy (ITER) Place: Santa Cruz de Tenerife, Spain Zip: 38611 Sector: Solar, Wind energy Product: Spain-based,...

  1. PPPL's Rich Hawryluk recognized for service to ITER international...

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

    Department. ITER is an international fusion experiment that is under construction in France. Hawryluk, a former deputy director of PPPL, completed a two-year assignment at...

  2. Microsoft Word - ex15-ITER-sept10.doc

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

    5 - Rights in Data-Special Works - ITER UT-B Contracts Div Sept 2010 Page 1 of 1 ex15-ITER-sept10.doc Exhibit 15-ITER Ref: FAR 52.227-17 RIGHTS IN DATA í SPECIAL WORKS í ITER (Sept 2010) (a) Definitions. (1) "Data", as used in this clause, means recorded information, regardless of form or the media on which it may be recorded. The term includes technical data and computer software. The term does not include information incidental to contract administration, such as financial,

  3. Microsoft Word - ex1b-ITER-mar07.doc

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

    B - Patent Rights - Acquisition by the Government - ITER UT-B Contracts Div March 2007 Page 1 of 6 ex1b-ITER-mar07.doc Exhibit 1B ITER Ref: DEAR 952.227-13 PATENT RIGHTS - ACQUISITION BY THE GOVERNMENT - ITER (Mar 2007) (a) Definitions. (1) "Invention", as used in this clause, means any invention or discovery which is or may be patentable or otherwise protectable under title 35 of the United States Code or any novel variety of plant that is or may be protectable under the Plant Variety

  4. Microsoft Word - ex9-ITER-june11.doc

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

    - Technical Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9-ITER-june11.doc Exhibit 9 ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt.V, 52.227-16 TECHNICAL DATA - ITER (June 2011) 1. RIGHTS IN DATA - GENERAL (a) Definitions. (1) "Computer data bases," as used in this clause, means a collection of data in a form capable of, and for the purpose of, being stored in, processed, and operated on by a computer. The term does not include computer software. (2) "Computer

  5. Microsoft Word - ex9ed-ITER-june11.doc

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

    ED - Technical Data - ITER UT-B Contracts Div June 2011 Page 1 of 5 ex9ed-ITER-june11.doc Exhibit 9ED ITER Ref: DEAR 927.409; FAR 52.227-14, 52.227-14 Alt. IV, 52.227-14 Alt. V, 52.227-16 TECHNICAL DATA - ITER (June 2011) 1. RIGHTS IN DATA-GENERAL (a) Definitions. (1) "Computer data bases," as used in this clause, means a collection of data in a form capable of, and for the purpose of, being stored in, processed, and operated on by a computer. The term does not include computer

  6. Microsoft Word - ex9rdf-ITER-sept09.doc

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

    RDF - Technical Data - ITER UT-B Contracts Div Sept 2009 Page 1 of 5 ex9rdf-ITER-sept09.doc Exhibit 9RDF-ITER Ref: DEAR 970.5227-1 TECHNICAL DATA - ITER (Sept 2009) 1. Rights in Data-Facilities. (a) Definitions. (1) "Computer Data Bases", as used in this clause, means a collection of data in a form capable of, and for the purpose of, being stored in, processed, and operated on by a computer. The term does not include Computer Software. (2) "Computer Software", as used in this

  7. An Iterated, Multipoint Differential Transform Method for Numerically...

    Office of Scientific and Technical Information (OSTI)

    ...Value Problems Citation Details In-Document Search Title: An Iterated, Multipoint Differential Transform Method for Numerically Evolving Partial Differential Equation Initial-Value ...

  8. COLLOQUIUM: ITER and its Diagnostics - Rising to the Challenge...

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

    measure the performance and provide the control signals for this device. A diagnostic set will be installed on the ITER machine to provide the measurements necessary to control, ...

  9. Evaluating iterative reconstruction performance in computed tomography

    SciTech Connect (OSTI)

    Chen, Baiyu Solomon, Justin; Ramirez Giraldo, Juan Carlos; Samei, Ehsan

    2014-12-15

    Purpose: Iterative reconstruction (IR) offers notable advantages in computed tomography (CT). However, its performance characterization is complicated by its potentially nonlinear behavior, impacting performance in terms of specific tasks. This study aimed to evaluate the performance of IR with both task-specific and task-generic strategies. Methods: The performance of IR in CT was mathematically assessed with an observer model that predicted the detection accuracy in terms of the detectability index (d′). d′ was calculated based on the properties of the image noise and resolution, the observer, and the detection task. The characterizations of image noise and resolution were extended to accommodate the nonlinearity of IR. A library of tasks was mathematically modeled at a range of sizes (radius 1–4 mm), contrast levels (10–100 HU), and edge profiles (sharp and soft). Unique d′ values were calculated for each task with respect to five radiation exposure levels (volume CT dose index, CTDI{sub vol}: 3.4–64.8 mGy) and four reconstruction algorithms (filtered backprojection reconstruction, FBP; iterative reconstruction in imaging space, IRIS; and sinogram affirmed iterative reconstruction with strengths of 3 and 5, SAFIRE3 and SAFIRE5; all provided by Siemens Healthcare, Forchheim, Germany). The d′ values were translated into the areas under the receiver operating characteristic curve (AUC) to represent human observer performance. For each task and reconstruction algorithm, a threshold dose was derived as the minimum dose required to achieve a threshold AUC of 0.9. A task-specific dose reduction potential of IR was calculated as the difference between the threshold doses for IR and FBP. A task-generic comparison was further made between IR and FBP in terms of the percent of all tasks yielding an AUC higher than the threshold. Results: IR required less dose than FBP to achieve the threshold AUC. In general, SAFIRE5 showed the most significant dose reduction potentials (11–54 mGy, 77%–84%), followed by SAFIRE3 (7–36 mGy, 50%–61%) and IRIS (6–26 mGy, 37%–50%). The dose reduction potentials highly depended on task size and task contrast, with tasks of lower contrasts and smaller sizes, i.e., more challenging tasks, indicating higher dose reductions. Softer edge profile showed higher dose reduction potentials with SAFIRE3 and SAFIRE5, but not with IRIS. The task-generic comparison between IR and FBP demonstrated the overall superiority of IR performance, as IR allowed a larger percent of tasks to exceed the threshold AUC: IRIS, 8%–12%; SAFIRE3, 10%–16%; and SAFIRE5, 20%–33%. The improvement with IR was generally more pronounced at lower dose levels. Conclusions: Expanding beyond traditional contrast and noise based assessments of IR, we performed both task-specific and task-generic evaluations of IR performance. The task-specific evaluation demonstrated the dependency of IR’s dose reduction potential on task attributes, which can be employed to optimize IR for clinical indications with specific range of size and contrast. The task-generic evaluation demonstrated IR’s overall superiority over FBP in terms of the range of tasks exceeding a threshold performance level, which can be employed for general comparisons between algorithms.

  10. UGE Scheduler Cycle Time

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

    UGE Scheduler Cycle Time UGE Scheduler Cycle Time Genepool Cycle Time Genepool Scheduler Cycle Time Genepool Jobs Dispatched / Hour What is the Scheduler Cycle? The Univa Grid Engine Scheduler cycle performs a number of important tasks, including: Prioritizing Jobs Reserving Resources for jobs requesting more resources (slots / memory) Dispatching jobs or tasks to the compute nodes Evaluating job dependencies The "cycle time" is the length of time it takes the scheduler to complete all

  11. Nuclear Fuel Cycle | Department of Energy

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

    Fuel Cycle Nuclear Fuel Cycle GC-52 provides legal advice to DOE regarding research and development of nuclear fuel and waste management technologies that meet the nation's energy supply, environmental, and energy security needs. GC-52 also advises DOE on issues involving support for international fuel cycle initiatives aimed at advancing a common vision of the necessity of the expansion of nuclear energy for peaceful purposes worldwide in a safe and secure manner. In addition, GC-52 provides

  12. ARM - What is the Carbon Cycle?

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

    Outreach Home Room News Publications Traditional Knowledge Kiosks Barrow, Alaska Tropical Western Pacific Site Tours Contacts Students Study Hall About ARM Global Warming FAQ Just for Fun Meet our Friends Cool Sites Teachers Teachers' Toolbox Lesson Plans What is the Carbon Cycle? Oceanic Properties Future Trends Carbon Cycle Balance Destination of Atmospheric Carbon Sources of Atmospheric Carbon The cycling of carbon from the atmosphere to organic compounds and back again not only involves

  13. Nuclear modules of ITER tokamak systems code

    SciTech Connect (OSTI)

    Gohar, Y.; Baker, C.; Brooks, J.; Finn, P.; Hassanein, A.; Willms, S.; Barr, W.; Bushigin, A.; Kalyanam, K.M.; Haines, J.

    1987-10-01

    Nuclear modules were developed to model various reactor components in the ITER systems code. Several design options and cost algorithms are included for each component. The first wall, blanket and shield modules calculate the beryllium zone thickness, the disruptions results, the nuclear responses in different components including the toroidal field coils. Tungsten shield/water coolant/steel structure and steel shield/water coolant are the shield options for the inboard and outboard sections of the reactor. Lithium nitrate dissolved in the water coolant with a variable beryllium zone thickness in the outboard section of the reactor provides the tritium breeding capability. The reactor vault module defines the thickness of the reactor wall and the roof based on the dose equivalent during operation including skyshine contribution. The impurity control module provides the design parameters for the divertor including plate design, heat load, erosion rate, tritium permeation through the plate material to the coolant, plasma contamination by sputtered impurities, and plate lifetime. Several materials: Be, C, V, Mo, and W can be used for the divertor plate to cover a range of plasma edge temperatures. The tritium module calculates tritium and deuterium flow rates for the reactor plant. The tritium inventory in the fuelers, neutral beams, vacuum pumps, impurity control, first wall, and blanket is calculated. Tritium requirements are provided for different operating conditions. The nuclear models are summarized in this paper including the different design options and key analyses of each module. 39 refs., 3 tabs.

  14. Microsoft Word - Second_ ITER Council Press Release.doc

    Energy Savers [EERE]

    Neil Calder Tel: 00 33 (0)6 14 16 41 75 ITER GAINS MOMENTUM Aomori, Japan 18 June 2008 On 17-18 June 2008, the ITER Council, the Governing Body of the new international Organization, convened for its second meeting. The two day meeting in Aomori, Japan, brought together senior representatives from the seven ITER Members: China, the European Union, India, Japan, Korea, Russia and the United States. Mr. Shingo Mimura, Governor of the Aomori Prefecture, welcomed delegates with a reminder of the

  15. Simple ocean carbon cycle models

    SciTech Connect (OSTI)

    Caldeira, K.; Hoffert, M.I.; Siegenthaler, U.

    1994-02-01

    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.

  16. Princeton Plasma Physics Lab - U.S. ITER

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

    Video Looks at ITER http:www.pppl.govnode1536

  17. An Overview Of The ITER In-Vessel Coil Systems

    SciTech Connect (OSTI)

    Heitzenroeder, P J; Chrzanowski, J H; Dahlgren, F; Hawryluk, R J; Loesser, G D; Neumeyer, C; Mansfield, C; Smith, J P; Schaffer, M; Humphreys, D; Cordier, J J; Campbell, D; Johnson, G A; Martin, A; Rebut, P H; Tao, J O; Fogarty, P J; Nelson, B E

    2009-09-24

    ELM mitigation is of particular importance in ITER in order to prevent rapid erosion or melting of the divertor surface, with the consequent risk of water leaks, increased plasma impurity content and disruptivity. Exploitable "natural" small or no ELM regimes might yet be found which extrapolate to ITER but this cannot be depended upon. Resonant Magnetic Perturbation has been added to pellet pacing as a tool for ITER to mitigate ELMs. Both are required, since neither method is fully developed and much work remains to be done. In addition, in-vessel coils enable vertical stabilization and RWM control. For these reasons, in-vessel coils (IVCs) are being designed for ITER to provide control of Edge Localized Modes (ELMs) in addition to providing control of moderately unstable resistive wall modes (RWMs) and the vertical stability (VS) of the plasma.

  18. Electrostatic Dust Detection and Removal for ITER

    SciTech Connect (OSTI)

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

    2008-09-01

    We present some recent results on two innovative applications of microelectronics technology to dust inventory measurement and dust removal in ITER. A novel device to detect the settling of dust particles on a remote surface has been developed in the laboratory. A circuit board with a grid of two interlocking conductive traces with 25 μm spacing is biased to 30 – 50 V. Carbon particles landing on the energized grid create a transient short circuit. The current flowing through the short circuit creates a voltage pulse that is recorded by standard nuclear counting electronics and the total number of counts is related to the mass of dust impinging on the grid. The particles typically vaporize in a few seconds restoring the previous voltage standoff. Experience on NSTX however, showed that in a tokamak environment it was still possible for large particles or fibers to remain on the grid causing a long term short circuit. We report on the development of a gas puff system that uses helium to clear such particles. Experiments with varying nozzle designs, backing pressures, puff durations, and exit flow orientations have given an optimal configuration that effectively removes particles from an area up to 25 cm² with a single nozzle. In a separate experiment we are developing an advanced circuit grid of three interlocking traces that can generate a miniature electrostatic traveling wave for transporting dust to a suitable exit port. We have fabricated such a 3-pole circuit board with 25 micron insulated traces that operates with voltages up to 200 V. Recent results showed motion of dust particles with the application of only 50 V bias voltage. Such a device could potentially remove dust continuously without dedicated interventions and without loss of machine availability for plasma operations.

  19. 2013 Planning Cycle

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

    Projects Expand Projects Skip navigation links Ancillary and Control Area Services (ACS) Practices Forum Attachment K 2015 Planning Cycle 2014 Planning Cycle 2013 Planning...

  20. 2014 Planning Cycle

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

    Projects Expand Projects Skip navigation links Ancillary and Control Area Services (ACS) Practices Forum Attachment K 2015 Planning Cycle 2014 Planning Cycle 2013 Planning...

  1. 2015 Planning Cycle

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

    Projects Expand Projects Skip navigation links Ancillary and Control Area Services (ACS) Practices Forum Attachment K 2015 Planning Cycle 2014 Planning Cycle 2013 Planning...

  2. Fuel Cycle Subcommittee

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

    2015 Fuel Cycle Subcommittee meeting is given below. The meeting provided members an overview of various research efforts funded by the DOE Office of Nuclear Energy's Fuel Cycle ...

  3. PPPL's Rich Hawryluk recognized for service to ITER international fusion

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

    project | Princeton Plasma Physics Lab PPPL's Rich Hawryluk recognized for service to ITER international fusion project By John Greenwald July 23, 2013 Tweet Widget Google Plus One Share on Facebook (Photo by U.S. Department of Energy) Gallery: From left, Energy Secretary Ernest Moniz and Rich Hawryluk (Photo by U.S. Department of Energy) From left, Energy Secretary Ernest Moniz and Rich Hawryluk Rich Hawryluk served as Deputy Director-General for the ITER Organization and Director of the

  4. United States and International Partners Initial ITER Agreement |

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

    Department of Energy International Partners Initial ITER Agreement United States and International Partners Initial ITER Agreement May 24, 2006 - 10:48am Addthis Paves the Way for Large-Scale, Clean Fusion Energy Project BRUSSELS, BELGIUM - Representing the United States, Dr. Raymond L. Orbach, Director of the U.S. Department of Energy's (DOE) Office of Science, joined counterparts from China, the European Union, India, Japan, the Republic of Korea, and the Russian Federation today to

  5. An Iterated, Multipoint Differential Transform Method for Numerically

    Office of Scientific and Technical Information (OSTI)

    Evolving Partial Differential Equation Initial-Value Problems (Journal Article) | SciTech Connect Journal Article: An Iterated, Multipoint Differential Transform Method for Numerically Evolving Partial Differential Equation Initial-Value Problems Citation Details In-Document Search Title: An Iterated, Multipoint Differential Transform Method for Numerically Evolving Partial Differential Equation Initial-Value Problems Authors: Finkel, H. J. [1] + Show Author Affiliations (LCF) Publication

  6. French landmark decree authorizes ITER construction | Princeton Plasma

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

    Physics Lab French landmark decree authorizes ITER construction By John Greenwald November 20, 2012 Tweet Widget Google Plus One Share on Facebook The French government has capped more than two years of review by issuing a license for the construction of ITER, the international fusion project that the European Union, the United States and five other countries are building in Cadarache, France, to demonstrate the feasibility of fusion energy. French Prime Minister Jean-Marc Ayrault signed the

  7. A review of the US joining technologies for plasma facing components in the ITER fusion reactor

    SciTech Connect (OSTI)

    Odegard, B.C. Jr.; Cadden, C.H.; Watson, R.D.; Slattery, K.T.

    1998-02-01

    This paper is a review of the current joining technologies for plasma facing components in the US for the International Thermonuclear Experimental Reactor (ITER) project. Many facilities are involved in this project. Many unique and innovative joining techniques are being considered in the quest to join two candidate armor plate materials (beryllium and tungsten) to a copper base alloy heat sink (CuNiBe, OD copper, CuCrZr). These techniques include brazing and diffusion bonding, compliant layers at the bond interface, and the use of diffusion barrier coatings and diffusion enhancing coatings at the bond interfaces. The development and status of these joining techniques will be detailed in this report.

  8. 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 committed to our neighbors August 1, 2013 Lab Director McMillan talks with...

  9. US ITER is a strong contributor in plan to enhance international sharing of

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

    prime ITER real estate | Princeton Plasma Physics Lab US ITER is a strong contributor in plan to enhance international sharing of prime ITER real estate By Lynne Degitz, US ITER March 28, 2013 Tweet Widget Google Plus One Share on Facebook PPPL's Russell Feder, left, and David Johnson developed key features for a modular approach to housing the extensive diagnostic systems that will be installed on the ITER tokamak. (Photo by Elle Starkman/PPPL Office of Communications) PPPL's Russell Feder,

  10. Design and Analysis of the ITER Vertical Stability Coils

    SciTech Connect (OSTI)

    Peter H. Titus, et. al.

    2012-09-06

    The ITER vertical stability (VS) coils have been developed through the preliminary design phase by Princeton Plasma Physics Laboratory (PPPL). Final design, prototyping and construction will be carried out by the Chinese Participant Team contributing lab, Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The VS coils are a part of the in-vessel coil systems which include edge localized mode (ELM) coils as well as the VS coils. An overview of the ELM coils is provided in another paper at this conference. 15 The VS design employs four turns of stainless steel jacketed mineral insulated copper (SSMIC) conductors The mineral insulation is Magnesium Oxide (MgO). Joule and nuclear heat is removed by water flowing at 3 m/s through the hollow copper conductor. A key element in the design is that slightly elevated temperatures in the conductor and its support spine during operation impose compressive stresses that mitigate fatigue damage. Away from joints, and break-outs, conductor thermal stresses are low because of the axisymmetry of the winding (there are no corner bends as in the ELM coils).The 120 degree segment joint, and break-out or terminal regions are designed with similar but imperfect constraint compared with the ring coil portion of the VS. The support for the break-out region is made from a high strength copper alloy, CuCrZr. This is needed to conduct nuclear heat to the actively cooled conductor and to the vessel wall. The support "spine" for the ring coil portion of the VS is 316 stainless steel, held to the vessel with preloaded 718 bolts. Lorentz loads resulting from normal operating loads, disruption loads and loads from disruption currents in the support spine shared with vessel, are applied to the VS coil. The transmission of the Lorentz and thermal expansion loads from the "spine" to the vessel rails is via friction augmented with a restraining "lip" to ensure the coil frictional slip is minimal and acceptable. Stresses in the coil, joints, and break-outs are presented. These are compared with static and fatigue allowables. Design for fatigue is much less demanding than for the ELM coils. A total of 30,000 cycles is required for VS design. Loads on the vessel due to the thermal expansion of the coil and spine are significant. Efforts to reduce these by reducing the cross section of the spine have been made but the vessel still must support loads resulting from restraint of thermal expansion.

  11. Cell cycle nucleic acids, polypeptides and uses thereof

    DOE Patents [OSTI]

    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)

    2007-08-14

    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.

  12. Status of research toward the ITER disruption mitigation system

    SciTech Connect (OSTI)

    Hollmann, E. M.; Izzo, V. A.; Aleynikov, P. B.; Lehnen, M.; Snipes, J. A.; Flp, T.; Humphreys, D. A.; Lukash, V. E.; Papp, G.; Pautasso, G.; Saint-Laurent, F.

    2015-02-15

    An overview of the present status of research toward the final design of the ITER disruption mitigation system (DMS) is given. The ITER DMS is based on massive injection of impurities, in order to radiate the plasma stored energy and mitigate the potentially damaging effects of disruptions. The design of this system will be extremely challenging due to many physics and engineering constraints such as limitations on port access and the amount and species of injected impurities. Additionally, many physics questions relevant to the design of the ITER disruption mitigation system remain unsolved such as the mechanisms for mixing and assimilation of injected impurities during the rapid shutdown and the mechanisms for the subsequent formation and dissipation of runaway electron current.

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

    SciTech Connect (OSTI)

    Younkin, T. R.; Biewer, T. M.; Klepper, C. C.; Marcus, C.

    2014-11-15

    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.

  14. Is Carbon a Realistic Choice for ITER's Divertor?

    SciTech Connect (OSTI)

    C.H. Skinner; G. Federici

    2005-05-13

    Tritium retention by co-deposition with carbon on the divertor target plate is predicted to limit ITER's DT burning plasma operations (e.g. to about 100 pulses for the worst conditions) before the in-vessel tritium inventory limit, currently set at 350 g, is reached. At this point, ITER will only be able to continue its burning plasma program if technology is available that is capable of rapidly removing large quantities of tritium from the vessel with over 90% efficiency. The removal rate required is four orders of magnitude faster than that demonstrated in current tokamaks. Eighteen years after the observation of co-deposition on JET and TFTR, such technology is nowhere in sight. The inexorable conclusion is that either a major initiative in tritium removal should be funded or that research priorities for ITER should focus on metal alternatives.

  15. Diamond neutral particle spectrometer for fusion reactor ITER

    SciTech Connect (OSTI)

    Krasilnikov, V.; Amosov, V.; Kaschuck, Yu.; Skopintsev, D.

    2014-08-21

    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.

  16. Intel C++ compiler error: stl_iterator_base_types.h

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

    C++ compiler error: stl_iterator_base_types.h Intel C++ compiler error: stl_iterator_base_types.h December 7, 2015 by Scott French Because the system-supplied version of GCC is relatively old (4.3.4) it is common practice to load the gcc module on our Cray systems when C++11 support is required under the Intel C++ compilers. While this works as expected under the GCC 4.8 and 4.9 series compilers, the 5.x series can cause Intel C++ compile-time errors similar to the following:

  17. Bragg x-ray survey spectrometer for ITER

    SciTech Connect (OSTI)

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

    2012-10-15

    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.

  18. United States Research and Development effort on ITER magnet tasks

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Martovetsky, Nicolai N.; Reierson, Wayne T.

    2011-01-22

    This study presents the status of research and development (R&D) magnet tasks that are being performed in support of the U.S. ITER Project Office (USIPO) commitment to provide a central solenoid assembly and toroidal field conductor for the ITER machine to be constructed in Cadarache, France. The following development tasks are presented: winding development, inlets and outlets development, internal and bus joints development and testing, insulation development and qualification, vacuum-pressure impregnation, bus supports, and intermodule structure and materials characterization.

  19. ARM - The Hydrologic Cycle

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

    Hydrologic Cycle Outreach Home Room News Publications Traditional Knowledge Kiosks Barrow, Alaska Tropical Western Pacific Site Tours Contacts Students Study Hall About ARM Global Warming FAQ Just for Fun Meet our Friends Cool Sites Teachers Teachers' Toolbox Lesson Plans The Hydrologic Cycle The hydrologic cycle is the cycle through which water passes from sea to land and from land to sea. Water vapor enters the air through the evaporation of water. Water vapor in the air eventually condenses

  20. The Photosynthetic Cycle

    DOE R&D Accomplishments [OSTI]

    Calvin, Melvin

    1955-03-21

    A cyclic sequence of transformations, including the carboxylation of RuDP (ribulose diphosphate) and its re-formation, has been deduced as the route for the creation of reduced carbon compounds in photosynthetic organisms. With the demonstration of RuDP as substrate for the carboxylation in a cell-free system, each of the reactions has now been carried out independently in vitro. Further purification of this last enzyme system has confirmed the deduction that the carboxylation of RuDP leads directly to the two molecules of PGA (phosphoglyceric acid) involving an internal dismutation and suggesting the name "carboxydismutase" for the enzyme. As a consequence of this knowledge of each of the steps in the photosynthetic CO{sub 2} reduction cycle, it is possible to define the reagent requirements to maintain it. The net requirement for the reduction of one molecule of CO{sub 2} is four equivalents of [H]and three molecules of ATP (adenine triphosphate). These must ultimately be supplied by the photochemical reaction. Some possible ways in which this may be accomplished are discussed.

  1. Visions for Data Management and Remote Collaboration on ITER

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

    I P 0.9 MA P IN 2.3 MW H98 1.3 M. Greenwald, et al., APS-DPP November 2007 C-Mod Data Helps Break Covariance Between EFF and nn G Makes Extrapolation To ITER More...

  2. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

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

    1991-05-01

    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.

  3. TPA Public Involvement Survey

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

    Hanford Tri-Party Agencies' Annual Public Involvement Survey Activities for Calendar Year 2008 Nolan Curtis Washington State Department of Ecology Nuclear Waste Program August 5,...

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

    SciTech Connect (OSTI)

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

    2013-09-30

    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.

  5. Atomic data for the ITER Core Imaging X-ray Spectrometer (Conference...

    Office of Scientific and Technical Information (OSTI)

    Atomic data for the ITER Core Imaging X-ray Spectrometer Citation Details In-Document Search Title: Atomic data for the ITER Core Imaging X-ray Spectrometer You are accessing a ...

  6. U.S.Statements on International Fusion Reactor (ITER) Siting Decision |

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

    Department of Energy U.S.Statements on International Fusion Reactor (ITER) Siting Decision U.S.Statements on International Fusion Reactor (ITER) Siting Decision June 28, 2005 - 1:45pm Addthis WASHINGTON, DC - Today in Moscow, Russia, the ministers representing the six ITER parties, including Dr. Raymond L. Orbach, Director of the U.S. Department of Energy's Office of Science, announced the ITER international fusion reactor will be located at the EU site in Cadarache, France. Below are

  7. Statement of Bernard Bigot Director-General ITER International Fusion Energy Organization

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

    Bernard Bigot Director-General ITER International Fusion Energy Organization Before the Subcommittee on Energy Committee on Science, Space and Technology U.S House of Representatives The ITER Project: Moving Forward April 20, 2016 Thank you Chairman Weber, Ranking Member Grayson, and distinguished members of the Committee. I am grateful for this opportunity to present to you the status of progress on the ITER Project. Introduction Today we are at a critical time in the history of the ITER

  8. ITER movie created by Oak Ridge National Laboratory, National Center for

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

    Computational Sciences | Princeton Plasma Physics Lab ITER movie created by Oak Ridge National Laboratory, National Center for Computational Sciences American Fusion News Category: U.S. ITER Link: ITER movie created by Oak Ridge National Laboratory, National Center for Computational Sciences

  9. Water Cycle Pilot Study

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

    1 Water Cycle Pilot Study To learn more about Earth's water cycle, the U.S. Department of Energy (DOE) has established a multi-laboratory science team representing five DOE national laboratories: Argonne, Brookhaven, Lawrence Berkeley, Los Alamos, and Oak Ridge. The science team will conduct a three- year Water Cycle Pilot Study within the ARM SGP CART site, primarily in the Walnut River Watershed east of Wichita, Kansas. The host facility in the Walnut River Watershed is the Atmospheric

  10. 10 MWe power cycle

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

    MWe power cycle - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy ...

  11. Soil metagenomics and carbon cycling

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

    Biosecurity, and Health Environmental Microbiology Soil metagenomics and carbon cycling Soil metagenomics and carbon cycling Establishing a foundational understanding...

  12. Optimization studies of the ITER low field side reflectometer

    SciTech Connect (OSTI)

    Hanson, Gregory R; Wilgen, John B; Bigelow, Tim S; Diem, Stephanie J

    2010-01-01

    Microwave reflectometry will be used on ITER to measure the electron density profile, density fluctuations due to MHD/turbulence, ELM density transients, and as a L-H transition monitor. The ITER low field side (LFS) reflectometer system will measure both core and edge quantities using multiple antenna arrays spanning frequency ranges of 15-155 GHz for the O-mode system and 55-220 GHz for the X-mode system. Optimization studies using the GENRAY ray-tracing code have been done for edge and core measurements. The reflectometer launchers will utilize the HE11 mode launched from circular corrugated waveguide. The launched beams are assumed to be Gaussian with a beam waist diameter of 0.643 times the waveguide diameter. Optimum launcher size and placement are investigated by computing the antenna coupling between launchers, assuming the launched and received beams have a Gaussian beam pattern.

  13. Optimization studies of the ITER low field side reflectometer

    SciTech Connect (OSTI)

    Diem, S. J.; Wilgen, J. B.; Bigelow, T. S.; Hanson, G. R.; Harvey, R. W.; Smirnov, A. P.

    2010-10-15

    Microwave reflectometry will be used on ITER to measure the electron density profile, density fluctuations due to MHD/turbulence, edge localized mode (ELM) density transients, and as an L-H transition monitor. The ITER low field side reflectometer system will measure both core and edge quantities using multiple antenna arrays spanning frequency ranges of 15-155 GHz for the O-mode system and 55-220 GHz for the X-mode system. Optimization studies using the GENRAY ray-tracing code have been done for edge and core measurements. The reflectometer launchers will utilize the HE11 mode launched from circular corrugated waveguide. The launched beams are assumed to be Gaussian with a beam waist diameter of 0.643 times the waveguide diameter. Optimum launcher size and placement are investigated by computing the antenna coupling between launchers, assuming the launched and received beams have a Gaussian beam pattern.

  14. Variable frequency iteration MPPT for resonant power converters

    DOE Patents [OSTI]

    Zhang, Qian; Bataresh, Issa; Chen, Lin

    2015-06-30

    A method of maximum power point tracking (MPPT) uses an MPPT algorithm to determine a switching frequency for a resonant power converter, including initializing by setting an initial boundary frequency range that is divided into initial frequency sub-ranges bounded by initial frequencies including an initial center frequency and first and second initial bounding frequencies. A first iteration includes measuring initial powers at the initial frequencies to determine a maximum power initial frequency that is used to set a first reduced frequency search range centered or bounded by the maximum power initial frequency including at least a first additional bounding frequency. A second iteration includes calculating first and second center frequencies by averaging adjacent frequent values in the first reduced frequency search range and measuring second power values at the first and second center frequencies. The switching frequency is determined from measured power values including the second power values.

  15. An iterative learning controller for nonholonomic mobile robots

    SciTech Connect (OSTI)

    Oriolo, G.; Panzieri, S.; Ulivi, G.

    1998-09-01

    The authors present an iterative learning controller that applies to nonholonomic mobile robots, as well as other systems that can be put in chained form. The learning algorithm exploits the fact that chained-form. The learning algorithm exploits the fact that chained-form systems are linear under piecewise-constant inputs. The proposed control scheme requires the execution of a small number of experiments to drive the system to the desired state in finite time, with nice convergence and robustness properties with respect to modeling inaccuracies as well as disturbances. To avoid the necessity of exactly reinitializing the system at each iteration, the basic method is modified so as to obtain a cyclic controller, by which the system is cyclically steered through an arbitrary sequence of states. As a case study, a carlike mobile robot is considered. Both simulation and experimental results are reported to show the performance of the method.

  16. Fuel cycle for a fusion neutron source

    SciTech Connect (OSTI)

    Ananyev, S. S. Spitsyn, A. V. Kuteev, B. V.

    2015-12-15

    The concept of a tokamak-based stationary fusion neutron source (FNS) for scientific research (neutron diffraction, etc.), tests of structural materials for future fusion reactors, nuclear waste transmutation, fission reactor fuel production, and control of subcritical nuclear systems (fusion–fission hybrid reactor) is being developed in Russia. The fuel cycle system is one of the most important systems of FNS that provides circulation and reprocessing of the deuterium–tritium fuel mixture in all fusion reactor systems: the vacuum chamber, neutral injection system, cryogenic pumps, tritium purification system, separation system, storage system, and tritium-breeding blanket. The existing technologies need to be significantly upgraded since the engineering solutions adopted in the ITER project can be only partially used in the FNS (considering the capacity factor higher than 0.3, tritium flow up to 200 m{sup 3}Pa/s, and temperature of reactor elements up to 650°C). The deuterium–tritium fuel cycle of the stationary FNS is considered. The TC-FNS computer code developed for estimating the tritium distribution in the systems of FNS is described. The code calculates tritium flows and inventory in tokamak systems (vacuum chamber, cryogenic pumps, neutral injection system, fuel mixture purification system, isotope separation system, tritium storage system) and takes into account tritium loss in the fuel cycle due to thermonuclear burnup and β decay. For the two facility versions considered, FNS-ST and DEMO-FNS, the amount of fuel mixture needed for uninterrupted operation of all fuel cycle systems is 0.9 and 1.4 kg, consequently, and the tritium consumption is 0.3 and 1.8 kg per year, including 35 and 55 g/yr, respectively, due to tritium decay.

  17. The Manuel Lujan Jr. Neutron Scattering Center (LANSCE) experiment reports 1993 run cycle. Progress report

    SciTech Connect (OSTI)

    Farrer, R.; Longshore, A.

    1995-06-01

    This year the Manuel Lujan Jr. Neutron Scattering Center (LANSCE) ran an informal user program because the US Department of Energy planned to close LANSCE in FY1994. As a result, an advisory committee recommended that LANSCE scientists and their collaborators complete work in progress. At LANSCE, neutrons are produced by spallation when a pulsed, 800-MeV proton beam impinges on a tungsten target. The proton pulses are provided by the Clinton P. Anderson Meson Physics Facility (LAMPF) accelerator and a associated Proton Storage Ring (PSR), which can Iter the intensity, time structure, and repetition rate of the pulses. The LAMPF protons of Line D are shared between the LANSCE target and the Weapons Neutron Research (WNR) facility, which results in LANSCE spectrometers being available to external users for unclassified research about 80% of each annual LAMPF run cycle. Measurements of interest to the Los Alamos National Laboratory (LANL) may also be performed and may occupy up to an additional 20% of the available beam time. These experiments are reviewed by an internal program advisory committee. This year, a total of 127 proposals were submitted. The proposed experiments involved 229 scientists, 57 of whom visited LANSCE to participate in measurements. In addition, 3 (nuclear physics) participating research teams, comprising 44 scientists, carried out experiments at LANSCE. Instrument beam time was again oversubscribed, with 552 total days requested an 473 available for allocation.

  18. Alfven Eigenmode Stability with Beams in ITER-like Plasma

    SciTech Connect (OSTI)

    N.N. Gorelenkov; H.L. Berk; R.V. Budny

    2004-07-16

    Toroidicity Alfven Eigenmodes (TAE) in ITER can be driven unstable by two groups of energetic particles, the 3.5 MeV {alpha}-particle fusion products and the tangentially injected 1MeV beam ions. Stability conditions are established using the perturbative NOVA/NOVA-K codes. A quasi-linear diffusion model is then used to assess the induced redistribution of energetic particles.

  19. Power Plant Cycling Costs

    SciTech Connect (OSTI)

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

    2012-07-01

    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.

  20. Life Cycle Cost Estimate

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

    1997-03-28

    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.

  1. Progress and present status of ITER cryoline system

    SciTech Connect (OSTI)

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

    2014-01-29

    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.

  2. Modeling Results For the ITER Cryogenic Fore Pump. Final Report

    SciTech Connect (OSTI)

    Pfotenhauer, John M.; Zhang, Dongsheng

    2014-03-31

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

  3. 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 committed to our neighbors August 1, 2013 Lab Director McMillan talks with Lab historian Ellen McGhee during Lab tour Lab Director McMillan talks with Lab historian Ellen McGhee during Lab tour RELATED IMAGES http://farm4.staticflickr.com/3815/9442115459_390e5bc841_t.jpg Enlarge http://farm8.staticflickr.com/7111/7650961650_ed1571174f_t.jpg Enlarge

  4. Duty Cycle Software Model

    Energy Science and Technology Software Center (OSTI)

    2010-12-31

    The Software consists of code which is capable of processing a large volume of data to create a “duty cycle” which is representative of how equipment will function under certain conditions.

  5. Life Cycle Inventory Database

    Broader source: Energy.gov [DOE]

    The U.S. Life Cycle Inventory (LCI) Database serves as a central repository for information about the total energy and resource impacts of developing and using various commercial building materials...

  6. Fuel Cycle Subcommittee

    Energy Savers [EERE]

    October 22, 2015 Washington, DC December 7, 2015 Al Sattelberger (Chair), Carol Burns, Margaret Chu, Raymond Juzaitis, Chris Kouts, Sekazi Mtingwa, Ronald Omberg, Joy Rempe, Dominique Warin 2 I. Introduction The agenda for the October 22, 2015 Fuel Cycle Subcommittee meeting is given below. The meeting provided members an overview of several research efforts funded by the DOE Office of Nuclear Energy's Fuel Cycle Technologies (FCT) program and related research that is coordinated with the FCT

  7. ITER Generic Diagnostic Upper Port Plug Nuclear Heating and Personnel Dose Rate Assesment

    SciTech Connect (OSTI)

    Russell E. Feder and Mahmoud Z. Youssef

    2009-01-28

    Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of a large aperture diagnostic were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding and a small aperture (Vis-IR) and minimal shielding with a large aperture. The neutronics discrete-ordinates code ATTILA and SEVERIAN (the ATTILA parallel processing version) was used. Material properties and the 500 MW D-T volume source were taken from the ITER Brand Model MCNP benchmark model. A biased quadrature set equivelant to Sn=32 and a scattering degree of Pn=3 were used along with a 46-neutron and 21-gamma FENDL energy subgrouping. Total nuclear heating (neutron plug gamma heating) in the upper port plugs ranged between 380 and 350 kW for the Vis-IR and Large Aperture cases. The Large Aperture model exhibited lower total heating but much higher peak volumetric heating on the upper port plug structure. Personnel dose rates are calculated in a three step process involving a neutron-only transport calculation, the generation of activation volume sources at pre-defined time steps and finally gamma transport analyses are run for selected time steps. ANSI-ANS 6.1.1 1977 Flux-to-Dose conversion factors were used. Dose rates were evaluated for 1 full year of 500 MW DT operation which is comprised of 3000 1800-second pulses. After one year the machine is shut down for maintenance and personnel are permitted to access the diagnostic interspace after 2-weeks if dose rates are below 100 ?Sv/hr. Dose rates in the Visible-IR diagnostic model after one day of shutdown were 130 ?Sv/hr but fell below the limit to 90 ?Sv/hr 2-weeks later. The Large Aperture style shielding model exhibited higher and more persistent dose rates. After 1-day the dose rate was 230 ?Sv/hr but was still at 120 ?Sv/hr 4-weeks later.

  8. 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 , Member Vice Chair 1 : Shannon Cram, Member Committee Members 2 : Shelley Cimon Liz Mattson Alissa Cordner Ken Niles Shannon Cram Ed Pacheco Rob Davis Dan Serres Tom Galioto Jean Vanni Floyd Hodges Steve White Paige Knight Unofficial Committee Members or Other Interested Parties 3 : Earl Fordham Gerry Pollet Paige Knight Steve Hudson 4 Susan Leckband 4 Facilitator: Cathy McCague 4 Agency & Technical Support: Kris Holmes

  9. Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle...

    Office of Scientific and Technical Information (OSTI)

    Title: Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies Authors: Harrison, Thomas J 1 + Show Author Affiliations ORNL ORNL Publication Date: 2013-01-01 ...

  10. Global ICRF system designs for ITER and TPX

    SciTech Connect (OSTI)

    Goulding, R.H.; Hoffman, D.J.; Ryan, P.M.; Durodie, F.

    1995-09-01

    The design of feed networks for ICRF antenna arrays on ITER and TPX are discussed. Features which are present in one or both of the designs include distribution of power to several straps from a single generator, the capability to vary phases of the currents on antenna elements rapidly without the need to rematch, and passive elements which present a nearly constant load to the generators during ELM induced loading transients of a factor of I0 or more. The FDAC (Feedline/Decoupler/Antenna Calculator) network modeling code is described, which allows convenient modeling of the electrical performance of nearly arbitrary ICRF feed networks.

  11. Helium process cycle

    DOE Patents [OSTI]

    Ganni, Venkatarao

    2007-10-09

    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.

  12. Helium process cycle

    DOE Patents [OSTI]

    Ganni, Venkatarao

    2008-08-12

    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.

  13. Microsoft Word - Second_ ITER Council Press Release.doc | Department of

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

    Energy Second_ ITER Council Press Release.doc Microsoft Word - Second_ ITER Council Press Release.doc PDF icon Microsoft Word - Second_ ITER Council Press Release.doc More Documents & Publications Before the House Subcommittee on Energy - Committee on Science, Space, and Technology Joint Statement by Energy Ministers of G8, The People's Republic of China, India and The Republic of Korea (June 2008) Joint Statement by Energy Ministers of G8, The People's Republic of China, India and The

  14. Axisymmetric Simulations of the ITER Vertical Stability Coil

    SciTech Connect (OSTI)

    Titus, Peter H.

    2013-07-09

    The ITER in-vessel coil system includes Vertical Stability (VS) coils and Edge Localized Mode (ELM) coils. There are two large VS ring coils, one upper and one lower. Each has four turns which are independently connected. The VS coils are needed for successful operation of ITER for most all of its operating modes. The VS coils must be highly reliable and fault tolerant. The operating environment includes normal and disruption Lorentz forces. To parametrically address all these design conditions in a tractable analysis requires a simplified model. The VS coils are predominately axisymmetric, and this suggests that an axisymmetric model can be meaningfully used to address the variations in mechanical design, loading, material properties, and time dependency. The axisymmetric finite element analysis described in this paper includes simulations of the bolted frictional connections used for the mounting details. Radiation and elastic-plastic response are modeled particularly for the extreme faulted conditions. Thermal connectivity is varied to study the effects of partial thermal connection of the actively cooled conductor to the remaining structure.

  15. Tungsten dust impact on ITER-like plasma edge

    SciTech Connect (OSTI)

    Smirnov, R. D. Krasheninnikov, S. I.; Pigarov, A. Yu.; Rognlien, T. D.

    2015-01-15

    The impact of tungsten dust originating from divertor plates on the performance of edge plasma in ITER-like discharge is evaluated using computer modeling with the coupled dust-plasma transport code DUSTT-UEDGE. Different dust injection parameters, including dust size and mass injection rates, are surveyed. It is found that tungsten dust injection with rates as low as a few mg/s can lead to dangerously high tungsten impurity concentrations in the plasma core. Dust injections with rates of a few tens of mg/s are shown to have a significant effect on edge plasma parameters and dynamics in ITER scale tokamaks. The large impact of certain phenomena, such as dust shielding by an ablation cloud and the thermal force on tungsten ions, on dust/impurity transport in edge plasma and consequently on core tungsten contamination level is demonstrated. It is also found that high-Z impurities provided by dust can induce macroscopic self-sustained plasma oscillations in plasma edge leading to large temporal variations of edge plasma parameters and heat load to divertor target plates.

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

    SciTech Connect (OSTI)

    Niu, Tianye; Dong, Xue; Petrongolo, Michael; Zhu, Lei

    2014-04-15

    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.

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

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

    systems that will be installed on the ITER tokamak. Gallery: Diagram of an equatorial port plug shows the three vertical diagnostic shield modules with detachable first wall...

  18. 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)

    ITER is designed to demonstrate the scientific and technological feasibility of fusion power by the late 2020s. PPPL provides hardware, fabrication and research and development for ...

  19. Superfluid thermodynamic cycle refrigerator

    DOE Patents [OSTI]

    Swift, Gregory W.; Kotsubo, Vincent Y.

    1992-01-01

    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.

  20. Superfluid thermodynamic cycle refrigerator

    DOE Patents [OSTI]

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

    1992-12-22

    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.

  1. Terrestrial Carbon Cycle

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

    Terrestrial Carbon Cycle "Only about half of the CO2 released into the atmosphere by human activities currently resides in the atmosphere, the rest absorbed on land and in the oceans. The period over which the carbon will be sequestered is unclear, and the efficiency of future sinks is unknown." US Carbon Cycle Research Plan "We" desire to be able to predict the future spatial and temporal distribution of sources and sinks of atmospheric CO2 and their interaction (forcing and

  2. Cycles in fossil diversity

    SciTech Connect (OSTI)

    Rohde, Robert A.; Muller, Richard A.

    2004-10-20

    It is well-known that the diversity of life appears to fluctuate during the course the Phanerozoic, the eon during which hard shells and skeletons left abundant fossils (0-542 Ma). Using Sepkoski's compendium of the first and last stratigraphic appearances of 36380 marine genera, we report a strong 62 {+-} 3 Myr cycle, which is particularly strong in the shorter-lived genera. The five great extinctions enumerated by Raup and Sepkoski may be an aspect of this cycle. Because of the high statistical significance, we also consider contributing environmental factors and possible causes.

  3. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I.W.

    1992-05-01

    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.

  4. International Nuclear Fuel Cycle Fact Book

    SciTech Connect (OSTI)

    Leigh, I W; Mitchell, S J

    1990-01-01

    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.

  5. International nuclear fuel cycle fact book

    SciTech Connect (OSTI)

    Leigh, I.W.

    1988-01-01

    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.

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

    DOE Patents [OSTI]

    Miao, Jianwei; Fahimian, Benjamin Pooya

    2012-09-18

    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.

  7. The workshop on iterative methods for large scale nonlinear problems

    SciTech Connect (OSTI)

    Walker, H.F.; Pernice, M.

    1995-12-01

    The aim of the workshop was to bring together researchers working on large scale applications with numerical specialists of various kinds. Applications that were addressed included reactive flows (combustion and other chemically reacting flows, tokamak modeling), porous media flows, cardiac modeling, chemical vapor deposition, image restoration, macromolecular modeling, and population dynamics. Numerical areas included Newton iterative (truncated Newton) methods, Krylov subspace methods, domain decomposition and other preconditioning methods, large scale optimization and optimal control, and parallel implementations and software. This report offers a brief summary of workshop activities and information about the participants. Interested readers are encouraged to look into an online proceedings available at http://www.usi.utah.edu/logan.proceedings. In this, the material offered here is augmented with hypertext abstracts that include links to locations such as speakers` home pages, PostScript copies of talks and papers, cross-references to related talks, and other information about topics addresses at the workshop.

  8. Occupational Radiation Exposure Analysis of US ITER DCLL TBM

    SciTech Connect (OSTI)

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

    2007-08-01

    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.

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

    SciTech Connect (OSTI)

    Martovetsky, Nicolai N; Irick, David Kim; Kenney, Steven J

    2013-01-01

    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.

  10. Proposal of an Arc Detection Technique Based on RF Measurements for the ITER ICRF Antenna

    SciTech Connect (OSTI)

    Huygen, S.; Dumortier, P.; Durodie, F.; Messiaen, A.; Vervier, M.; Vrancken, M.

    2011-12-23

    RF arc detection is a key operational and safety issue for the ICRF system on ITER. Indeed the high voltages inside the antenna put it at risk of arcing, which could cause substantial damage. This paper describes the various possibilities explored by circuit simulation and the strategy now considered to protect the ITER ICRF antenna from RF arcs.

  11. Stirling cycle engine

    DOE Patents [OSTI]

    Lundholm, Gunnar

    1983-01-01

    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.

  12. Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Dale, Deborah J.

    2014-10-28

    These slides will be presented at the training course “International Training Course on Implementing State Systems of Accounting for and Control (SSAC) of Nuclear Material for States with Small Quantity Protocols (SQP),” on November 3-7, 2014 in Santa Fe, New Mexico. The slides provide a basic overview of the Nuclear Fuel Cycle. This is a joint training course provided by NNSA and IAEA.

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

    SciTech Connect (OSTI)

    Subber, Waad Sarkar, Abhijit

    2014-01-15

    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.

  14. A Comparison of Modifications to MELCOR versions 1.8.2 and 1.8.6 for ITER Safety Analysis

    SciTech Connect (OSTI)

    B. J. Merrill; P. W. Humrickhouse

    2010-06-01

    During the Engineering Design Activity of the International Thermonuclear Experimental Reactor (ITER), the MELCOR 1.8.2 code was selected as one of several codes to be used to perform ITER safety analyses [1]. MELCOR was chosen because it has the capability of predicting coolant pressure, temperature, mass flow rate, and radionuclide and aerosol transport in nuclear facilities and reactor cooling systems. MELCOR can also predict structural temperatures (e.g. first wall, blanket, divertor, and vacuum vessel) resulting from energy produced by radioactive decay heat and/or chemical reactions (oxidation). The Idaho National Laboratory (INL) Fusion Safety Program (FSP) made fusion specific modifications to the MELCOR 1.8.2 code [2-6], including models for water freezing, air condensation, beryllium, carbon, and tungsten oxidation in steam and air environments, flow boiling in coolant loops, and radiation in enclosures, that allowed MELCOR to assess the thermal hydraulic response of ITER cooling systems and the transport of radionuclides as aerosols during accident conditions. Recently, the ITER International Organization (IO) used a “pedigreed” version of MELCOR 1.8.2 [7] to perform accident analyses for ITER’s “Rapport Préliminaire de Sûreté” (Report Preliminary on Safety - RPrS). The MELCOR thermal-hydraulics code [8] is currently under development at the Sandia National Laboratory (SNL) for the US Nuclear Regulatory Commission (NRC). MELCOR is used to model the progression of severe accidents in light water fission reactors. Because MELCOR has undergone many improvements between version 1.8.2 and 1.8.6, the INL FSP decided to introduce fusion modifications into MELCOR 1.8.6, and thereby produce a version of MELCOR 1.8.6 with similar capabilities to the pedigreed version of MELCOR 1.8.2 used for the ITER RPrS. We have applied this version of MELCOR 1.8.6 to the same set of problems used in the MELCOR 1.8.2 pedigree analysis [7]. Section 2 describes a non-regression analysis that involves comparing the results from the modified version of MELCOR 1.8.6 against those predicted by the original, unmodified version of MELCOR 1.8.6. The purpose of this non-regression analysis is to demonstrate that the modifications made to the MELCOR 1.8.6 code do not drastically alter the intended functions of the MELCOR base code, and if they do to explain why the departure occurs and if the change is needed. The analysis was performed using the demonstration problem that came with the MELCOR 1.8.6 source distribution. Section 3 makes a comparison between the pedigreed version of MELCOR 1.8.2 and the new modified version of MELCOR 1.8.6 on a set of accident problems used by the ITER Joint Central Team (JCT) in the Generic Site Safety Report (GSSR) [9]. Finally, in section 4, the two versions of the code are compared on a series of developmental test problems described in the change documents [2-4, 6].

  15. Thermo-structural development of the ITER ICRF strap housing module

    SciTech Connect (OSTI)

    Winkler, K.; Shannon, M.; Lockley, D.

    2014-02-12

    Since March 2010 the preliminary design of the ITER ICRF Antennas have been developed by CYCLE, a consortium consisting of IPP (Garching), CCFE (Culham), CEA (Cadarache), Politecnico di Torino (Torino) and LPPERM/KMS (Brussels). This paper describes the steps taken to develop the present geometry of the triplet pair Strap Housing Module from a thermal and structural perspective, and shows the critical areas of the structure. Key issues are the manufacturability, (achieved by HIPing - Hot Isostatic Pressing), the ability to handle the radiating plasma thermal flux of 0.35 MW/m{sup 2}, the RF losses and the neutronic radiation. HIPing is necessary to achieve the complicated system of cooling channels inside the structure, which divides the coolant equally in order to supply each strap in the triplet with 1 l/s of water. The components have also to withstand the strong mechanical forces generated by plasma disruptions affecting all internal structures and the elevated design cooling water pressure of 5MPa. In order to maximise reliability, joints between different materials in the cooling water system have been kept to a minimum. Therefore, in the interests of fabricability and availability, the whole structure is manufactured out of stainless steel (316L(N)IG). The low conductivity of 316L(N)IG demands small wall thicknesses to avoid hot spots; however this reduces the mechanical strength. Consequently an in depth FEM analysis is presented, which was used to find and to improve the critical aspects of this important component and was the best means of finding the optimum between thermal and mechanical performance.

  16. Stirling cycle machine

    SciTech Connect (OSTI)

    Burnett, S.C.; Purcell, J.R.; Creedon, W.P.; Joshi, C.H.

    1990-06-05

    This patent describes an improvement in a Stirling cycle machine including first and second variable-volume, compression-expansion chambers containing a gas a regenerator interconnecting the chambers and for conducting the gas therebetween, and eccentric drive means for driving the first and second chambers. It comprises: the eccentric drive means comprising a pair of rotatably mounted shafts, at least one pair of eccentric disks fixed on the shafts in phase with each other, and means for causing the shafts and thereby the eccentric disks to rotate in opposite directions.

  17. Wetland (peat) Carbon Cycle

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

    Wetland (peat) Carbon Cycle Methane (CH4) is an important greenhouse gas, twenty times more potent than CO2, but atmospheric concentrations of CH4 under future climate change are uncertain. This is in part because many climate-sensitive ecosystems release both CH4 and carbon dioxide (CO2) and it is unknown how these systems will partition future releases of carbon to the atmosphere. Ecosystem observations of CH4 emissions lack mechanistic links to the processes that govern CH4 efflux: microbial

  18. Geothermal Life Cycle Calculator

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

    Sullivan, John

    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.

  19. Geothermal Life Cycle Calculator

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

    Sullivan, John

    2014-03-11

    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.

  20. Geothermal Life Cycle Calculator

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

    Sullivan, John

    2014-03-11

    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 DOE’s 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.

  1. DESIGN, ANALYSIS AND TEST CONCEPT FOR PROTOTYPE CRYOLINE OF ITER

    SciTech Connect (OSTI)

    Sarkar, B.; Badgujar, S.; Vaghela, H.; Shah, N.; Bhattacharya, R.; Chakrapani, Ch.

    2008-03-16

    The ITER cryo-distribution and cryoline is a part of the in-kind supply for India. The design of the systems is in progress. The topology of torus and neutral beam cryoline is defined as six process pipes along with thermal shield at 80 K and outer vacuum jacket. In order to develop confidence in the concept and to establish the high level of engineering and manufacturing technology, a prototype testing has been proposed. The prototype test will be carried out on 1:1 model in terms of dimension. However, the mass flow rate of the supercritical helium at 4.5 K and gaseous helium at 80 K will be on a 1:10 scale. The prototype cryoline has been designed and analyzed for thermal, structural and hydraulic parameters. The objective of this prototype test is to verify mechanical behavior due to thermal stress and pressure force, thermal and hydraulic performances. The concept of test facility has been realized along with the Piping and Instrumentation (P and I) diagram, instrumentation, controls, data acquisition, 80 K helium generation system along with supply and return valve boxes and interfacing hardware. The design concept, methodology for analysis and results, as well as the test facility have been discussed.

  2. Status of the design of the ITER ECE diagnostic

    SciTech Connect (OSTI)

    Taylor, G.; Austin, M. E.; Beno, J. H.; Danani, S.; Feder, R.; Hesler, J. L.; Hubbard, A. E.; Johnson, D. W.; Kumar, R.; Pandya, H. K. B.; Roman, C.; Rowan, W. L.; Udintsev, V.; Vayakis, G.; Walsh, M.; Kubo, S.

    2015-03-12

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

  3. Status of the design of the ITER ECE diagnostic

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Taylor, G.; Austin, M. E.; Beno, J. H.; Danani, S.; Ellis, R. F.; Feder, R.; Hesler, J. L.; Hubbard, A. E.; Johnson, D. W.; Kumar, R.; et al

    2015-03-12

    In this study, 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 inmore » 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.« less

  4. COLLOQUIUM: Functional capabilities and design of the ITER EC H&CD system |

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

    Princeton Plasma Physics Lab 17, 2016, 4:15pm to 5:30pm Colloquia MBG Auditorium, PPPL (284 cap.) COLLOQUIUM: Functional capabilities and design of the ITER EC H&CD system Dr. Mark Henderson ITER Organization A 24MW Electron Cyclotron (EC) system operating at 170 GHz and 3600 s pulse length is to be installed on ITER. The EC plant shall deliver 20MW of this power to the plasma for Heating and Current Drive (H&CD) applications. The EC system is designed for plasma initiation, central

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

    SciTech Connect (OSTI)

    Francesca M. Poli and Charles Kessel

    2012-12-03

    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.

  6. Open cycle thermoacoustics

    SciTech Connect (OSTI)

    Reid, Robert Stowers

    2000-01-01

    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.

  7. Stirling cycle rotary engine

    SciTech Connect (OSTI)

    Chandler, J.A.

    1988-06-28

    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.

  8. Fuel Cycle Technologies | Department of Energy

    Office of Environmental Management (EM)

    Initiatives Fuel Cycle Technologies Fuel Cycle Technologies Fuel Cycle Technologies Preparing for Tomorrow's Energy Demands Powerful imperatives drive the continued need for...

  9. Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core...

    Office of Scientific and Technical Information (OSTI)

    Design Review Support Citation Details In-Document Search Title: Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray Spectrometer Conceptual Design ...

  10. Electromagnetic analysis of forces and torques on the ITER shield modules due to plasma disruption.

    SciTech Connect (OSTI)

    Kotulski, Joseph Daniel; Coats, Rebecca Sue; Pasik, Michael Francis; Ulrickson, Michael Andrew

    2009-06-01

    An electromagnetic analysis is performed on the ITER shield modules under different plasma disruption scenarios using the OPERA-3d software. The modeling procedure is explained, electromagnetic torques are presented, and results of the modeling are discussed.

  11. during the ITER era S.J. Zinkle; J.P. Planchard; R.W. Callis...

    Office of Scientific and Technical Information (OSTI)

    Fusion materials science and technology research opportunities now and during the ITER era S.J. Zinkle; J.P. Planchard; R.W. Callis; C.E. Kessel; P.J. Lee; K.A. McCarty; Various...

  12. ITER (International Thermonuclear Experimental Reactor) shield and blanket work package report

    SciTech Connect (OSTI)

    Not Available

    1988-06-01

    This report summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. The purpose of this work was to prepare for the first international ITER workshop devoted to defining a basic ITER concept that will serve as a basis for an indepth conceptual design activity over the next 2-1/2 years. Primary tasks carried out during the past year included: 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. 44 refs., 31 figs., 29 tabs.

  13. Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core...

    Office of Scientific and Technical Information (OSTI)

    Core Imaging X-Ray Spectrometer Conceptual Design Review Support Citation Details In-Document Search Title: Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core ...

  14. An adaptive sparse-grid-based iterative ensemble Kalman filter approach for

    Office of Scientific and Technical Information (OSTI)

    parameter field estimation (Journal Article) | SciTech Connect An adaptive sparse-grid-based iterative ensemble Kalman filter approach for parameter field estimation Citation Details In-Document Search Title: An adaptive sparse-grid-based iterative ensemble Kalman filter approach for parameter field estimation Authors: Gunzburger, Max D [1] ; Webster, Clayton G [1] ; Zhang, Guannan [1] + Show Author Affiliations ORNL Publication Date: 2013-01-01 OSTI Identifier: 1096322 DOE Contract Number:

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

    SciTech Connect (OSTI)

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

    2009-10-08

    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.

  16. Qualification of the US Made Conductors for ITER TF Magnet System

    SciTech Connect (OSTI)

    Martovetsky, Nicolai N; Hatfield, Daniel R; Miller, John R; Bruzzone, P.; Stepanov, B.; Seber, B.

    2010-01-01

    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.

  17. Unique PPPL-led workshop assesses research crucial to the success of ITER |

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

    Princeton Plasma Physics Lab Unique PPPL-led workshop assesses research crucial to the success of ITER By John Greenwald July 30, 2013 Tweet Widget Google Plus One Share on Facebook Workshop participants from left: PPPL Director Stewart Prager and Theory Head Amitava Bhattacharjee with David Campbell, director of plasma operations at ITER. (Photo by Elle Starkman/ PPPL Office of Communications) Workshop participants from left: PPPL Director Stewart Prager and Theory Head Amitava

  18. Dynamic Analysis of Fuel Cycle Transitioning

    SciTech Connect (OSTI)

    Brent Dixon; Steve Piet; David Shropshire; Gretchen Matthern

    2009-09-01

    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.

  19. Solar spectral irradiance changes during cycle 24

    SciTech Connect (OSTI)

    Marchenko, S. V.; DeLand, M. T.

    2014-07-10

    We use solar spectra obtained by the Ozone Monitoring Instrument (OMI) on board the Aura satellite to detect and follow long-term (years) and short-term (weeks) changes in the solar spectral irradiance (SSI) in the 265-500 nm spectral range. During solar Cycle 24, in the relatively line-free regions the SSI changed by ?0.6% 0.2% around 265 nm. These changes gradually diminish to 0.15% 0.20% at 500 nm. All strong spectral lines and blends, with the notable exception of the upper Balmer lines, vary in unison with the solar 'continuum'. Besides the lines with strong chromospheric components, the most involved species include Fe I blends and all prominent CH, NH, and CN spectral bands. Following the general trend seen in the solar 'continuum', the variability of spectral lines also decreases toward longer wavelengths. The long-term solar cycle SSI changes are closely, to within the quoted 0.1%-0.2% uncertainties, matched by the appropriately adjusted short-term SSI variations derived from the 27 day rotational modulation cycles. This further strengthens and broadens the prevailing notion about the general scalability of the UV SSI variability to the emissivity changes in the Mg II 280 nm doublet on timescales from weeks to years. We also detect subtle deviations from this general rule: the prominent spectral lines and blends at ? ? 350 nm show slightly more pronounced 27 day SSI changes when compared to the long-term (years) trends. We merge the solar data from Cycle 21 with the current Cycle 24 OMI and GOME-2 observations and provide normalized SSI variations for the 170-795 nm spectral region.

  20. Public Involvement and Communications Committee:

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

    purposes only 09.08.15 Excerpt from the HAB Process Manual January 2012 Public Involvement and Communications Committee: Develops Board Advice for the TPA agencies on the...

  1. Public Involvement Committee - Transcribed Flipcharts

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

    September 3, 2014 Public Involvement Opportunities * Review of PI materials and agency websites, listservs (use of and purpose of notifications). * CD process - approach to PI...

  2. Public Involvement Committee - Transcribed Flipcharts

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

    education materials, including web materials * Evaluate effectiveness of TPA public involvement activities. Page 5 FY2015 Work Plan Ideas * Share innovative approaches to public...

  3. The motional Stark effect diagnostic for ITER using a line-shift approach

    SciTech Connect (OSTI)

    Foley, E. L.; Levinton, F. M.; Yuh, H. Y.; Zakharov, L. E.

    2008-10-15

    The United States has been tasked with the development and implementation of a motional Stark effect (MSE) system on ITER. In the harsh ITER environment, MSE is particularly susceptible to degradation, as it depends on polarimetry, and the polarization reflection properties of surfaces are highly sensitive to thin film effects due to plasma deposition and erosion of a first mirror. Here we present the results of a comprehensive study considering a new MSE-based approach to internal plasma magnetic field measurements for ITER. The proposed method uses the line shifts in the MSE spectrum (MSE-LS) to provide a radial profile of the magnetic field magnitude. To determine the utility of MSE-LS for equilibrium reconstruction, studies were performed using the ESC-ERV code system. A near-term opportunity to test the use of MSE-LS for equilibrium reconstruction is being pursued in the implementation of MSE with laser-induced fluorescence on NSTX. Though the field values and beam energies are very different from ITER, the use of a laser allows precision spectroscopy with a similar ratio of linewidth to line spacing on NSTX as would be achievable with a passive system on ITER. Simulation results for ITER and NSTX are presented, and the relative merits of the traditional line polarization approach and the new line-shift approach are discussed.

  4. Advanced regenerative absorption refrigeration cycles

    DOE Patents [OSTI]

    Dao, Kim

    1990-01-01

    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).

  5. 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 cycling to improve climate modeling and carbon management. Get Expertise Principle Investigator Cheryl Kuske Bioscience Division 505 665 4800 Email Get Expertise John Dunbar Bioscience Division Email Get Expertise Chris Yeager Bioscience Division Email Get Expertise Jean Challacombe Bioscience Division Email This

  6. Nuclear Fuel Cycle Options Catalog

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

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management ...

  7. Organic rankine cycle fluid

    DOE Patents [OSTI]

    Brasz, Joost J.; Jonsson, Ulf J.

    2006-09-05

    A method of operating an organic rankine cycle system wherein a liquid refrigerant is circulated to an evaporator where heat is introduced to the refrigerant to convert it to vapor. The vapor is then passed through a turbine, with the resulting cooled vapor then passing through a condenser for condensing the vapor to a liquid. The refrigerant is one of CF.sub.3CF.sub.2C(O)CF(CF.sub.3).sub.2, (CF.sub.3).sub.2 CFC(O)CF(CF.sub.3).sub.2, CF.sub.3(CF.sub.2).sub.2C(O)CF(CF.sub.3).sub.2, CF.sub.3(CF.sub.2).sub.3C(O)CF(CG.sub.3).sub.2, CF.sub.3(CF.sub.2).sub.5C(O)CF.sub.3, CF.sub.3CF.sub.2C(O)CF.sub.2CF.sub.2CF.sub.3, CF.sub.3C(O)CF(CF.sub.3).sub.2.

  8. Life Cycle Asset Management

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

    1998-10-14

    (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.

  9. International nuclear fuel cycle fact book. Revision 4

    SciTech Connect (OSTI)

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

    1984-03-01

    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.

  10. International Nuclear Fuel Cycle Fact Book. Revision 5

    SciTech Connect (OSTI)

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

    1985-01-01

    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.

  11. Public Involvment Plan - Rifle, Colorado

    Office of Legacy Management (LM)

    4-TAR MAC-GWRIF 7.1 UMTRA Ground Water Project Public Involvement Plan for the Environmental Assessment of Ground Water Compliance at the New and Old Rifle, Colorado, Uranium Mill Tailings Sites May 1999 Prepared by U.S. Department of Energy Grand Junction Office Grand Junction, Colorado Work performed under DOE Contract No. DE-AC13-96GJ87335 Public Involvement Plan for the Rifle UMTRA Sites Page 2 Introduction This Public Involvement Plan is tiered to the Uranium Mill Tailings Remedial Action

  12. Failure analysis of beryllium tile assembles following high heat flux testing for the ITER program

    SciTech Connect (OSTI)

    B. C. Odegard, Jr.; C. H. Cadden; N. Y. C. Yang

    2000-05-01

    The following document describes the processing, testing and post-test analysis of two Be-Cu assemblies that have successfully met the heat load requirements for the first wall and dome sections for the ITER (International Thermonuclear Experimental Reactor) fusion reactor. Several different joint assemblies were evaluated in support of a manufacturing technology investigation aimed at diffusion bonding or brazing a beryllium armor tile to a copper alloy heat sink for fusion reactor applications. Judicious selection of materials and coatings for these assemblies was essential to eliminate or minimize interactions with the highly reactive beryllium armor material. A thin titanium layer was used as a diffusion barrier to isolate the copper heat sink from the beryllium armor. To reduce residual stresses produced by differences in the expansion coefficients between the beryllium and copper, a compliant layer of aluminum or aluminum-beryllium (AlBeMet-150) was used. Aluminum was chosen because it does not chemically react with, and exhibits limited volubility in, beryllium. Two bonding processes were used to produce the assemblies. The primary process was a diffusion bonding technique. In this case, undesirable metallurgical reactions were minimized by keeping the materials in a solid state throughout the fabrication cycle. The other process employed an aluminum-silicon layer as a brazing filler material. In both cases, a hot isostatic press (HIP) furnace was used in conjunction with vacuum-canned assemblies in order to minimize oxidation and provide sufficient pressure on the assemblies for full metal-to-metal contact and subsequent bonding. The two final assemblies were subjected to a suite of tests including: tensile tests and electron and optical metallography. Finally, high heat flux testing was conducted at the electron beam testing system (EBTS) at Sandia National Laboratories, New Mexico. Here, test mockups were fabricated and subjected to normal heat loads to 10 MW/m{sup 2} (3 Hz) and abnormal heat loads to 250 MJ/m{sup 2} (0.5s) to determine their performance under simulated fusion reactor conditions for first wall components. Both assemblies survived the normal heat loads with no visual damage. Optical and electron microscopy were used to evaluate the extent of the damage at the interfaces following the VDE simulations.

  13. Fuel cycle cost uncertainty from nuclear fuel cycle comparison

    SciTech Connect (OSTI)

    Li, J.; McNelis, D.; Yim, M.S.

    2013-07-01

    This paper examined the uncertainty in fuel cycle cost (FCC) calculation by considering both model and parameter uncertainty. Four different fuel cycle options were compared in the analysis including the once-through cycle (OT), the DUPIC cycle, the MOX cycle and a closed fuel cycle with fast reactors (FR). The model uncertainty was addressed by using three different FCC modeling approaches with and without the time value of money consideration. The relative ratios of FCC in comparison to OT did not change much by using different modeling approaches. This observation was consistent with the results of the sensitivity study for the discount rate. Two different sets of data with uncertainty range of unit costs were used to address the parameter uncertainty of the FCC calculation. The sensitivity study showed that the dominating contributor to the total variance of FCC is the uranium price. In general, the FCC of OT was found to be the lowest followed by FR, MOX, and DUPIC. But depending on the uranium price, the FR cycle was found to have lower FCC over OT. The reprocessing cost was also found to have a major impact on FCC.

  14. Appendix V Public Involvement Plan

    Office of Legacy Management (LM)

    V Public Involvement Plan Revision No.: 6 February 2008 Federal Facility Agreement and Consent Order (FFACO) FFACO, Appendix V February 2008 i FFACO Public Involvement Plan U.S. Department of Energy National Nuclear Security Administration Nevada Site Office Las Vegas, Nevada U.S. Department of Defense Defense Threat Reduction Agency Detachment 1, Nevada Operations Mercury, Nevada U.S. Department of Energy Office of Legacy Management Grand Junction, Colorado FFACO, Appendix V February 2008 ii

  15. THE CRYOPLANT FOR THE ITER NEUTRAL BEAM TEST FACILITY TO BE BUILT AT RFX IN PADOVA, ITALY

    SciTech Connect (OSTI)

    Pengo, R.; Fellin, F.; Sonato, P.

    2010-04-09

    The Neutral Beam Test Facility (NBTF), planned to be constructed in Padua (Italy), will constitute the prototype of the two Neutral Beam Injectors (NBI), which will be installed in the ITER plant (Cadarache-France). The NBTF is composed of a 1 MV accelerator that can produce a 40 A deuteron pulsed neutral beam particles. The necessary vacuum needed in the accelerator is achieved by two large cryopumps, designed by FZK-Karlsruhe, with radiation shields cooled between 65 K and 90 K and with cryopanels cooled by 4 bar supercritical helium (ScHe) between 4.5 K and 6.5 K. A new cryoplant facility will be installed with two large helium refrigerators: a Shield Refrigerator (SR), whose cooling capacity is up to 30 kW between 65 K and 90 K, and a helium Main Refrigerator (MR), whose equivalent cooling capacity is up to 800 W at 4.5 K. The cooling of the cryopanels is obtained with two (ScHe) 30 g/s pumps (one redundant), working in a closed cycle around 4 bar producing a pressure head of 100 mbar. Two heat exchangers are immersed in a buffer dewar connected to the MR. The MR and SR different operation modes are described in the paper, as well as the new cryoplant installation.

  16. Method and apparatus for iterative lysis and extraction of algae

    DOE Patents [OSTI]

    Chew, Geoffrey; Boggs, Tabitha; Dykes, Jr., H. Waite H.; Doherty, Stephen J.

    2015-12-01

    A method and system for processing algae involves the use of an ionic liquid-containing clarified cell lysate to lyse algae cells. The resulting crude cell lysate may be clarified and subsequently used to lyse algae cells. The process may be repeated a number of times before a clarified lysate is separated into lipid and aqueous phases for further processing and/or purification of desired products.

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

    SciTech Connect (OSTI)

    1995-01-01

    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.

  18. Investigation of statistical iterative reconstruction for dedicated breast CT

    SciTech Connect (OSTI)

    Makeev, Andrey; Glick, Stephen J.

    2013-08-15

    Purpose: Dedicated breast CT has great potential for improving the detection and diagnosis of breast cancer. Statistical iterative reconstruction (SIR) in dedicated breast CT is a promising alternative to traditional filtered backprojection (FBP). One of the difficulties in using SIR is the presence of free parameters in the algorithm that control the appearance of the resulting image. These parameters require tuning in order to achieve high quality reconstructions. In this study, the authors investigated the penalized maximum likelihood (PML) method with two commonly used types of roughness penalty functions: hyperbolic potential and anisotropic total variation (TV) norm. Reconstructed images were compared with images obtained using standard FBP. Optimal parameters for PML with the hyperbolic prior are reported for the task of detecting microcalcifications embedded in breast tissue.Methods: Computer simulations were used to acquire projections in a half-cone beam geometry. The modeled setup describes a realistic breast CT benchtop system, with an x-ray spectra produced by a point source and an a-Si, CsI:Tl flat-panel detector. A voxelized anthropomorphic breast phantom with 280 ?m microcalcification spheres embedded in it was used to model attenuation properties of the uncompressed woman's breast in a pendant position. The reconstruction of 3D images was performed using the separable paraboloidal surrogates algorithm with ordered subsets. Task performance was assessed with the ideal observer detectability index to determine optimal PML parameters.Results: The authors' findings suggest that there is a preferred range of values of the roughness penalty weight and the edge preservation threshold in the penalized objective function with the hyperbolic potential, which resulted in low noise images with high contrast microcalcifications preserved. In terms of numerical observer detectability index, the PML method with optimal parameters yielded substantially improved performance (by a factor of greater than 10) compared to FBP. The hyperbolic prior was also observed to be superior to the TV norm. A few of the best-performing parameter pairs for the PML method also demonstrated superior performance for various radiation doses. In fact, using PML with certain parameter values results in better images, acquired using 2 mGy dose, than FBP-reconstructed images acquired using 6 mGy dose.Conclusions: A range of optimal free parameters for the PML algorithm with hyperbolic and TV norm-based potentials is presented for the microcalcification detection task, in dedicated breast CT. The reported values can be used as starting values of the free parameters, when SIR techniques are used for image reconstruction. Significant improvement in image quality can be achieved by using PML with optimal combination of parameters, as compared to FBP. Importantly, these results suggest improved detection of microcalcifications can be obtained by using PML with lower radiation dose to the patient, than using FBP with higher dose.

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

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

    The D-Cycle offers the opportunity to use less fuel and gain more power while being able to be retrofit to an OEM and aftermarket engines PDF icon deer09_conti.pdf More Documents & Publications Improving Diesel Engine Sweet-spot Efficiency and Adapting it to Improve Duty-cycle MPG - plus Increasing Propulsion and Reducing Cost Two-Stroke Engines: New Frontier in Engine Efficiency Building America Technology Solutions for New and Existing Homes: Advanced Boiler Load Monitoring Controllers,

  20. Numerical studies of the imaging properties of doubly focussing crystals and their application to ITER

    SciTech Connect (OSTI)

    Bitter, M.; Fraenkel, B.; Hill, K.W.; Hsuan, H.; von Goeler, S. )

    1995-01-01

    Line brightness calculations for the parameters at the International Thermonuclear Experimental Reactor (ITER) and results from recent experiments on the Tokamak Fusion Test Reactor (TFTR) indicate that time-resolved measurements of the central ion temperature and other central plasma parameters should be feasible on ITER with nonperturbing amounts of krypton. Since the measurements will have to be performed in the presence of high fluxes of 14-MeV neutrons from DT-fusion reactions, the size of windows, apertures and x-ray detectors must be as small as possible. Under these conditions, the use of doubly focussing crystals can significantly enhance the signal-to-noise ratio. This paper describes numerical studies of the focussing properties of spherically bent crystals and their application to ITER.

  1. Public Involvement Committee - Transcribed Flipcharts

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

    December 10, 2013 100-F 1. Public involvement/mtg in March - How to sequence Board Review with public comment period * Path 1: Could request comment period extension * Path 2: Could request HAB comments considered post comment period * If comment period starts in March, HAB could request to comment in May (advice) Page 1 What might be topics for policy-level discussions? What might be ways, other than meetings, to solicit involvement? What might be useful to present at March Board mtg? Page 2

  2. Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray

    Office of Scientific and Technical Information (OSTI)

    Spectrometer Conceptual Design Review Support (Technical Report) | SciTech Connect Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray Spectrometer Conceptual Design Review Support Citation Details In-Document Search Title: Final Report on ORDER No. 5312-20110620-JOHNSON-01ITER: Core Imaging X-Ray Spectrometer Conceptual Design Review Support Authors: Beiersdorfer, P Publication Date: 2013-09-20 OSTI Identifier: 1097747 Report Number(s): LLNL-SR-644215 DOE Contract

  3. Rich Hawryluk recalls "exciting and challenging" years working on ITER

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

    | Princeton Plasma Physics Lab Rich Hawryluk recalls "exciting and challenging" years working on ITER By John Greenwald April 23, 2013 Tweet Widget Google Plus One Share on Facebook Gallery: What is it like to be at the center of ITER, the huge international fusion experiment that is under construction in Cadarache, France? "It's both exciting and challenging," said physicist Rich Hawryluk, who recently returned to PPPL after a two-year stint as deputy director-general

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

    SciTech Connect (OSTI)

    Zhai, Y

    2014-03-03

    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.

  5. COLLOQUIUM: DIII-D Explorations of Fusion Science to Prepare for ITER and

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

    FNSF | Princeton Plasma Physics Lab December 10, 2013, 11:00am to 12:30pm Colloquia MBG Auditorium COLLOQUIUM: DIII-D Explorations of Fusion Science to Prepare for ITER and FNSF Dr. Richard Buttery General Atomics, DIII-D Presentation: File Presentation Abstract: PDF icon COLL.12.10.13.pdf Recent DIII-D research has provided significant new information for the physics basis of key scientific issues for successful operation of ITER and future steady state fusion tokamaks, including control of

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

    SciTech Connect (OSTI)

    McAdams, R.

    2014-02-15

    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.

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

    SciTech Connect (OSTI)

    Kratzer, M.B.

    1996-07-01

    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.

  8. Photovoltaics: Life-cycle Analyses

    SciTech Connect (OSTI)

    Fthenakis V. M.; Kim, H.C.

    2009-10-02

    Life-cycle analysis is an invaluable tool for investigating the environmental profile of a product or technology from cradle to grave. Such life-cycle analyses of energy technologies are essential, especially as material and energy flows are often interwoven, and divergent emissions into the environment may occur at different life-cycle-stages. This approach is well exemplified by our description of material and energy flows in four commercial PV technologies, i.e., mono-crystalline silicon, multi-crystalline silicon, ribbon-silicon, and cadmium telluride. The same life-cycle approach is applied to the balance of system that supports flat, fixed PV modules during operation. We also discuss the life-cycle environmental metrics for a concentration PV system with a tracker and lenses to capture more sunlight per cell area than the flat, fixed system but requires large auxiliary components. Select life-cycle risk indicators for PV, i.e., fatalities, injures, and maximum consequences are evaluated in a comparative context with other electricity-generation pathways.

  9. Supercritical carbon dioxide cycle control analysis.

    SciTech Connect (OSTI)

    Moisseytsev, A.; Sienicki, J. J.

    2011-04-11

    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 the dynamic simulation of the ABTR. The code modifications have reached the point where a transient simulation can be run in steady state mode; i.e., to determine the steady state initial conditions at full power without an initiating event. The results show that the steady state solution is maintained with minimal variations during at least 4,000 seconds of the transient. More SFR design specific modifications to the ANL Plant Dynamics Code are required to run the code in a full transient mode, including models for the sodium pumps and their control as well as models for reactivity feedback and control of the reactor power.

  10. Reliability and availability requirements analysis for DEMO: fuel cycle system

    SciTech Connect (OSTI)

    Pinna, T.; Borgognoni, F.

    2015-03-15

    The Demonstration Power Plant (DEMO) will be a fusion reactor prototype designed to demonstrate the capability to produce electrical power in a commercially acceptable way. Two of the key elements of the engineering development of the DEMO reactor are the definitions of reliability and availability requirements (or targets). The availability target for a hypothesized Fuel Cycle has been analysed as a test case. The analysis has been done on the basis of the experience gained in operating existing tokamak fusion reactors and developing the ITER design. Plant Breakdown Structure (PBS) and Functional Breakdown Structure (FBS) related to the DEMO Fuel Cycle and correlations between PBS and FBS have been identified. At first, a set of availability targets has been allocated to the various systems on the basis of their operating, protection and safety functions. 75% and 85% of availability has been allocated to the operating functions of fuelling system and tritium plant respectively. 99% of availability has been allocated to the overall systems in executing their safety functions. The chances of the systems to achieve the allocated targets have then been investigated through a Failure Mode and Effect Analysis and Reliability Block Diagram analysis. The following results have been obtained: 1) the target of 75% for the operations of the fuelling system looks reasonable, while the target of 85% for the operations of the whole tritium plant should be reduced to 80%, even though all the tritium plant systems can individually reach quite high availability targets, over 90% - 95%; 2) all the DEMO Fuel Cycle systems can reach the target of 99% in accomplishing their safety functions. (authors)

  11. Solar Fuels and Carbon Cycle 2.0 (Carbon Cycle 2.0) (Conference...

    Office of Scientific and Technical Information (OSTI)

    Solar Fuels and Carbon Cycle 2.0 (Carbon Cycle 2.0) Citation Details In-Document Search Title: Solar Fuels and Carbon Cycle 2.0 (Carbon Cycle 2.0) Paul Alivisatos, LBNL Director...

  12. Framework for fuel-cycle approaches to IAEA safeguards

    SciTech Connect (OSTI)

    Fishbone, L.G.

    1986-10-01

    In order to compare several nuclear-safeguards verification approaches to one another and to the conventional facility-oriented approach, we establish a framework of the classes of information routinely verifiable by IAEA safeguards inspections. For each facility type within a State nuclear fuel cycle, the classes include flow data, inventory data, and shipper and receiver data. By showing which classes of information are verified for each facility type within three fuel cycles of different complexity, we distinguish the inspection approaches from one anoter and exhibit their fuel-cycle dependence, i.e., their need for sets of safeguards inspection activities different from those required under the facility-oriented approach at similar facilities in fuel cycles of differing complexity. Tables V-1, V-2, and V-3 graphically depict these relations and give a qualitative summary of the relative effectiveness and effort requirements of the approaches classified. The zone, information-correlation, diversion-assumption-change, and randomization-over-facilities approaches depend intrinsically on the complexity of the fuel cycle: their very definition implies fuel-cycle dependence. The approaches involving randomization over activities and goal relaxations do not have such dependence.

  13. Duty Cycle Software - Energy Innovation Portal

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

    Find More Like This Return to Search Duty Cycle Software National Renewable Energy Laboratory Contact NREL About This Technology Technology Marketing Summary Duty cycles capture the ...

  14. New Cycle Capital LLC | Open Energy Information

    Open Energy Info (EERE)

    Cycle Capital LLC Jump to: navigation, search Name: New Cycle Capital, LLC. Place: San Francisco, California Zip: 94103 Product: San Francisco-based venture capitalist firm...

  15. Carbon Cycle Engineering | Open Energy Information

    Open Energy Info (EERE)

    Cycle Engineering Jump to: navigation, search Name: Carbon Cycle Engineering Address: 13725 Dutch Creek Road Place: Athens, Ohio Zip: 45701 Sector: Biofuels, Biomass, Efficiency,...

  16. Fast Acting Eddy Current Driven Valve for Massive Gas Injection on ITER

    SciTech Connect (OSTI)

    Lyttle, Mark S; Baylor, Larry R; Carmichael, Justin R; Combs, Stephen Kirk; Ericson, Milton Nance; Ezell, N Dianne Bull; Meitner, S. J.; Rasmussen, David A; Warmack, Robert J Bruce; Maruyama, So; Kiss, Gabor

    2015-01-01

    Tokamak plasma disruptions present a significant challenge to ITER as they can result in intense heat flux, large forces from halo and eddy currents, and potential first-wall damage from the generation of multi-MeV runaway electrons. Massive gas injection (MGI) of high Z material using fast acting valves is being explored on existing tokamaks and is planned for ITER as a method to evenly distribute the thermal load of the plasma to prevent melting, control the rate of the current decay to minimize mechanical loads, and to suppress the generation of runaway electrons. A fast acting valve and accompanying power supply have been designed and first test articles produced to meet the requirements for a disruption mitigation system on ITER. The test valve incorporates a flyer plate actuator similar to designs deployed on TEXTOR, ASDEX upgrade, and JET [1 3] of a size useful for ITER with special considerations to mitigate the high mechanical forces developed during actuation due to high background magnetic fields. The valve includes a tip design and all-metal valve stem sealing for compatibility with tritium and high neutron and gamma fluxes.

  17. Amesos2 and Belos: Direct and Iterative Solvers for Large Sparse Linear Systems

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Bavier, Eric; Hoemmen, Mark; Rajamanickam, Sivasankaran; Thornquist, Heidi

    2012-01-01

    Solvers for large sparse linear systems come in two categories: direct and iterative. Amesos2, a package in the Trilinos software project, provides direct methods, and Belos, another Trilinos package, provides iterative methods. Amesos2 offers a common interface to many different sparse matrix factorization codes, and can handle any implementation of sparse matrices and vectors, via an easy-to-extend C++ traits interface. It can also factor matrices whose entries have arbitrary “Scalar” type, enabling extended-precision and mixed-precision algorithms. Belos includes many different iterative methods for solving large sparse linear systems and least-squares problems. Unlike competing iterative solver libraries, Belos completely decouples themore » algorithms from the implementations of the underlying linear algebra objects. This lets Belos exploit the latest hardware without changes to the code. Belos favors algorithms that solve higher-level problems, such as multiple simultaneous linear systems and sequences of related linear systems, faster than standard algorithms. The package also supports extended-precision and mixed-precision algorithms. Together, Amesos2 and Belos form a complete suite of sparse linear solvers.« less

  18. Mixed direct-iterative methods for boundary integral formulations of continuum dielectric solvation models

    SciTech Connect (OSTI)

    Corcelli, S.A.; Kress, J.D.; Pratt, L.R.

    1995-08-07

    This paper develops and characterizes mixed direct-iterative methods for boundary integral formulations of continuum dielectric solvation models. We give an example, the Ca{sup ++}{hor_ellipsis}Cl{sup {minus}} pair potential of mean force in aqueous solution, for which a direct solution at thermal accuracy is difficult and, thus for which mixed direct-iterative methods seem necessary to obtain the required high resolution. For the simplest such formulations, Gauss-Seidel iteration diverges in rare cases. This difficulty is analyzed by obtaining the eigenvalues and the spectral radius of the non-symmetric iteration matrix. This establishes that those divergences are due to inaccuracies of the asymptotic approximations used in evaluation of the matrix elements corresponding to accidental close encounters of boundary elements on different atomic spheres. The spectral radii are then greater than one for those diverging cases. This problem is cured by checking for boundary element pairs closer than the typical spatial extent of the boundary elements and for those cases performing an ``in-line`` Monte Carlo integration to evaluate the required matrix elements. These difficulties are not expected and have not been observed for the thoroughly coarsened equations obtained when only a direct solution is sought. Finally, we give an example application of hybrid quantum-classical methods to deprotonation of orthosilicic acid in water.

  19. Modeling the Nuclear Fuel Cycle

    SciTech Connect (OSTI)

    Jacob J. Jacobson; A. M. Yacout; G. E. Matthern; S. J. Piet; A. Moisseytsev

    2005-07-01

    The Advanced Fuel Cycle Initiative is developing a system dynamics model as part of their broad systems analysis of future nuclear energy in the United States. The model will be used to analyze and compare various proposed technology deployment scenarios. The model will also give a better understanding of the linkages between the various components of the nuclear fuel cycle that includes uranium resources, reactor number and mix, nuclear fuel type and waste management. Each of these components is tightly connected to the nuclear fuel cycle but usually analyzed in isolation of the other parts. This model will attempt to bridge these components into a single model for analysis. This work is part of a multi-national laboratory effort between Argonne National Laboratory, Idaho National Laboratory and United States Department of Energy. This paper summarizes the basics of the system dynamics model and looks at some results from the model.

  20. Twin-Screw Extruder Development for the ITER Pellet Injection System

    SciTech Connect (OSTI)

    Meitner, Steven J; Baylor, Larry R; Combs, Stephen Kirk; Fehling, Dan T; McGill, James M; Rasmussen, David A; Leachman, J. W.

    2009-01-01

    The ITER pellet injection system is comprised of devices to form and accelerate pellets, and will be connected to inner wall guide tubes for fueling, and outer wall guide tubes for ELM pacing. An extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with a gas gun into the plasma. The ITER pellet injection system is required to provide a plasma fueling rate of 120 Pa-m3/s (900 mbar-L/s) and durations of up to 3000 s. The fueling pellets will be injected at a rate up to 10 Hz and pellets used to trigger ELMs will be injected at higher rates up to 20 Hz. A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. A one-fifth ITER scale prototype has been built and has demonstrated the production of a continuous solid deuterium extrusion. The 27 mm diameter, intermeshed, counter-rotating extruder screws are rotated at a rate up to ?5 rpm. Deuterium gas is pre-cooled and liquefied and solidified in separate extruder barrels. The precooler consists of a deuterium gas filled copper coil suspended in a separate stainless steel vessel containing liquid nitrogen. The liquefier is comprised of a copper barrel connected to a Cryomech AL330 cryocooler, which has a machined helical groove surrounded by a copper jacket, through which the pre-cooled deuterium condenses. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at ?15 K) before it is forced through the extruder die. The die forms the extrusion to a 3 mm x 4 mm rectangular cross section. Design improvements have been made to improve the pre-cooler and liquefier heat exchangers, to limit the loss of extrusion through gaps in the screws. This paper will describe the design improvements for the next iteration of the extruder prototype.

  1. A sequential partly iterative approach for multicomponent reactive transport with CORE2D

    SciTech Connect (OSTI)

    Samper, J.; Xu, T.; Yang, C.

    2008-11-01

    CORE{sup 2D} V4 is a finite element code for modeling partly or fully saturated water flow, heat transport and multicomponent reactive solute transport under both local chemical equilibrium and kinetic conditions. It can handle coupled microbial processes and geochemical reactions such as acid-base, aqueous complexation, redox, mineral dissolution/precipitation, gas dissolution/exsolution, ion exchange, sorption via linear and nonlinear isotherms, sorption via surface complexation. Hydraulic parameters may change due to mineral precipitation/dissolution reactions. Coupled transport and chemical equations are solved by using sequential iterative approaches. A sequential partly-iterative approach (SPIA) is presented which improves the accuracy of the traditional sequential noniterative approach (SNIA) and is more efficient than the general sequential iterative approach (SIA). While SNIA leads to a substantial saving of computing time, it introduces numerical errors which are especially large for cation exchange reactions. SPIA improves the efficiency of SIA because the iteration between transport and chemical equations is only performed in nodes with a large mass transfer between solid and liquid phases. The efficiency and accuracy of SPIA are compared to those of SIA and SNIA using synthetic examples and a case study of reactive transport through the Llobregat Delta aquitard in Spain. SPIA is found to be as accurate as SIA while requiring significantly less CPU time. In addition, SPIA is much more accurate than SNIA with only a minor increase in computing time. A further enhancement of the efficiency of SPIA is achieved by improving the efficiency of the Newton-Raphson method used for solving chemical equations. Such an improvement is obtained by working with increments of log-concentrations and ignoring the terms of the Jacobian matrix containing derivatives of activity coefficients. A proof is given for the symmetry and non-singularity of the Jacobian matrix. Numerical analyses performed with synthetic examples confirm that these modifications improve the efficiency and convergence of the iterative algorithm.

  2. Advanced Nuclear Fuel Cycle Options

    SciTech Connect (OSTI)

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

    2010-06-01

    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.

  3. SNMR pulse sequence phase cycling

    DOE Patents [OSTI]

    Walsh, David O; Grunewald, Elliot D

    2013-11-12

    Technologies applicable to SNMR pulse sequence phase cycling are disclosed, including SNMR acquisition apparatus and methods, SNMR processing apparatus and methods, and combinations thereof. SNMR acquisition may include transmitting two or more SNMR pulse sequences and applying a phase shift to a pulse in at least one of the pulse sequences, according to any of a variety cycling techniques. SNMR processing may include combining SNMR from a plurality of pulse sequences comprising pulses of different phases, so that desired signals are preserved and indesired signals are canceled.

  4. HOW YOU CAN BE INVOLVED

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

    HOW YOU CAN BE INVOLVED www.youtube.com/hanfordsite www.twitter.com/hanfordsite www.facebook.com/hanfordsite The Hanford Site sits on 586-square-miles of shrub-steppe desert in southeastern Washington state. The site was created in 1943 as part of the Manhattan Project to produce plutonium for nuclear weapons. Between 1943 and 1963, nine nuclear reactors were built along the banks of the Columbia River. By 1988, all nine reactors were shut down. The weapons material production mission ended in

  5. International nuclear fuel cycle fact book. [Contains glossary

    SciTech Connect (OSTI)

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

    1987-01-01

    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.

  6. International Nuclear Fuel Cycle Fact Book. Revision 12

    SciTech Connect (OSTI)

    Leigh, I.W.

    1992-05-01

    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.

  7. International nuclear fuel cycle fact book: Revision 9

    SciTech Connect (OSTI)

    Leigh, I.W.

    1989-01-01

    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.

  8. GAX absorption cycle design process

    SciTech Connect (OSTI)

    Priedeman, D.K.; Christensen, R.N.

    1999-07-01

    This paper presents an absorption system design process that relies on computer simulations that are validated by experimental findings. An ammonia-water absorption heat pump cycle at 3 refrigeration tons (RT) and chillers at 3.3 RT and 5 RT (10.5 kW, 11.6 kW, and 17.6 kW) were initially modeled and then built and tested. The experimental results were used to calibrate both the cycle simulation and the component simulations, yielding computer design routines that could accurately predict component and cycle performance. Each system was a generator-absorber heat exchange (GAX) cycle, and all were sized for residential and light commercial use, where very little absorption equipment is currently used. The specific findings of the 5 RT (17.6 kW) chiller are presented. Modeling incorporated a heat loss from the gas-fired generator and pressure drops in both the evaporator and absorber. Simulation results and experimental findings agreed closely and validated the modeling method and simulation software.

  9. Public Involvement and Communications Committee Page 1

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

    8, 2012 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING February 8, 2012 Richland, WA Topics in this Meeting Summary Welcome and Introductions .......................................................................................................................... 1 Update on Timely Public Involvement Topics ............................................................................................. 1 Public Involvement for Technical

  10. Reducing the effects of acoustic heterogeneity with an iterative reconstruction method from experimental data in microwave induced thermoacoustic tomography

    SciTech Connect (OSTI)

    Wang, Jinguo; Zhao, Zhiqin Song, Jian; Chen, Guoping; Nie, Zaiping; Liu, Qing-Huo

    2015-05-15

    Purpose: An iterative reconstruction method has been previously reported by the authors of this paper. However, the iterative reconstruction method was demonstrated by solely using the numerical simulations. It is essential to apply the iterative reconstruction method to practice conditions. The objective of this work is to validate the capability of the iterative reconstruction method for reducing the effects of acoustic heterogeneity with the experimental data in microwave induced thermoacoustic tomography. Methods: Most existing reconstruction methods need to combine the ultrasonic measurement technology to quantitatively measure the velocity distribution of heterogeneity, which increases the system complexity. Different to existing reconstruction methods, the iterative reconstruction method combines time reversal mirror technique, fast marching method, and simultaneous algebraic reconstruction technique to iteratively estimate the velocity distribution of heterogeneous tissue by solely using the measured data. Then, the estimated velocity distribution is used subsequently to reconstruct the highly accurate image of microwave absorption distribution. Experiments that a target placed in an acoustic heterogeneous environment are performed to validate the iterative reconstruction method. Results: By using the estimated velocity distribution, the target in an acoustic heterogeneous environment can be reconstructed with better shape and higher image contrast than targets that are reconstructed with a homogeneous velocity distribution. Conclusions: The distortions caused by the acoustic heterogeneity can be efficiently corrected by utilizing the velocity distribution estimated by the iterative reconstruction method. The advantage of the iterative reconstruction method over the existing correction methods is that it is successful in improving the quality of the image of microwave absorption distribution without increasing the system complexity.

  11. Multi-cycle boiling water reactor fuel cycle optimization

    SciTech Connect (OSTI)

    Ottinger, K.; Maldonado, G.I.

    2013-07-01

    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)

  12. DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING...

    Office of Environmental Management (EM)

    Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING ... related to emergency response to a transportation accident involving radioactive material. ...

  13. Community Involvement | Y-12 National Security Complex

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

    Involvement Community Involvement Y-12 is committed to keeping the community informed in areas of operations, environmental concerns, safety and emergency preparedness. To...

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

    SciTech Connect (OSTI)

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

    1994-09-01

    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.

  15. Science and Technology Research and Development in Support to ITER and the Broader Approach at CEA

    SciTech Connect (OSTI)

    Becoulet, A.; Hoang, G T; Abiteboul, J.; Achard, J.; Alarcon, T.; Klepper, C Christopher

    2013-01-01

    In parallel to the direct contribution to the procurement phase of ITER and Broader Approach, CEA has initiated research & development programmes, accompanied by experiments together with a significant modelling effort, aimed at ensuring robust operation, plasma performance, as well as mitigating the risks of the procurement phase. This overview reports the latest progress in both fusion science and technology including many areas, namely the mitigation of superconducting magnet quenches, disruption-generated runaway electrons, edge-localized modes (ELMs), the development of imaging surveillance, and heating and current drive systems for steady-state operation. The WEST (W Environment for Steady-state Tokamaks) project, turning Tore Supra into an actively cooled W-divertor platform open to the ITER partners and industries, is presented.

  16. Evaluation of graphite/steam interactions for ITER (International Thermonuclear Experimental Reactor)

    SciTech Connect (OSTI)

    Smolik, G.R.; Merrill, B.J.; Piet, S.J.; Holland, D.F.

    1990-09-01

    In this report we present the results of an experimental/analytical study designed to determine the quantity of hydrogen generated during a coolant inleakage accident in ITER. This hydrogen could represent a potential explosive hazard, provided the proper conditions exist, causing machine damage and release of radioactive material. We have measured graphite/steam reaction rates for several graphites and carbon-based composites at temperatures between 1000 C and 1700 C. The effects of steam flow rate, and partial pressure were also examined. The measured reaction rates correlated well with two Arrhenius type relationships. We have used the relationships for GraphNOL N3M in a thermal model to determine that for ITER the quantity of hydrogen produced would range between 5 and 35 kg, depending upon how the graphite tiles are attached to the first wall. While 5 kg is not a significant concern, 35 kg presents an explosive hazard. 20 refs., 14 figs., 1 tab.

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

    SciTech Connect (OSTI)

    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)

    2011-09-26

    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.

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

    SciTech Connect (OSTI)

    L. C. Cadwallader

    2013-01-01

    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.

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

    SciTech Connect (OSTI)

    Baker, C.C.

    1988-08-01

    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.

  20. Radiation dose reduction in medical x-ray CT via Fourier-based iterative reconstruction

    SciTech Connect (OSTI)

    Fahimian, Benjamin P.; Zhao Yunzhe; Huang Zhifeng; Fung, Russell; Zhu Chun; Miao Jianwei; Mao Yu; Khatonabadi, Maryam; DeMarco, John J.; McNitt-Gray, Michael F.; Osher, Stanley J.

    2013-03-15

    Purpose: A Fourier-based iterative reconstruction technique, termed Equally Sloped Tomography (EST), is developed in conjunction with advanced mathematical regularization to investigate radiation dose reduction in x-ray CT. The method is experimentally implemented on fan-beam CT and evaluated as a function of imaging dose on a series of image quality phantoms and anonymous pediatric patient data sets. Numerical simulation experiments are also performed to explore the extension of EST to helical cone-beam geometry. Methods: EST is a Fourier based iterative algorithm, which iterates back and forth between real and Fourier space utilizing the algebraically exact pseudopolar fast Fourier transform (PPFFT). In each iteration, physical constraints and mathematical regularization are applied in real space, while the measured data are enforced in Fourier space. The algorithm is automatically terminated when a proposed termination criterion is met. Experimentally, fan-beam projections were acquired by the Siemens z-flying focal spot technology, and subsequently interleaved and rebinned to a pseudopolar grid. Image quality phantoms were scanned at systematically varied mAs settings, reconstructed by EST and conventional reconstruction methods such as filtered back projection (FBP), and quantified using metrics including resolution, signal-to-noise ratios (SNRs), and contrast-to-noise ratios (CNRs). Pediatric data sets were reconstructed at their original acquisition settings and additionally simulated to lower dose settings for comparison and evaluation of the potential for radiation dose reduction. Numerical experiments were conducted to quantify EST and other iterative methods in terms of image quality and computation time. The extension of EST to helical cone-beam CT was implemented by using the advanced single-slice rebinning (ASSR) method. Results: Based on the phantom and pediatric patient fan-beam CT data, it is demonstrated that EST reconstructions with the lowest scanner flux setting of 39 mAs produce comparable image quality, resolution, and contrast relative to FBP with the 140 mAs flux setting. Compared to the algebraic reconstruction technique and the expectation maximization statistical reconstruction algorithm, a significant reduction in computation time is achieved with EST. Finally, numerical experiments on helical cone-beam CT data suggest that the combination of EST and ASSR produces reconstructions with higher image quality and lower noise than the Feldkamp Davis and Kress (FDK) method and the conventional ASSR approach. Conclusions: A Fourier-based iterative method has been applied to the reconstruction of fan-bean CT data with reduced x-ray fluence. This method incorporates advantageous features in both real and Fourier space iterative schemes: using a fast and algebraically exact method to calculate forward projection, enforcing the measured data in Fourier space, and applying physical constraints and flexible regularization in real space. Our results suggest that EST can be utilized for radiation dose reduction in x-ray CT via the readily implementable technique of lowering mAs settings. Numerical experiments further indicate that EST requires less computation time than several other iterative algorithms and can, in principle, be extended to helical cone-beam geometry in combination with the ASSR method.

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

    SciTech Connect (OSTI)

    Rajainmaki, Hannu; Fanthome, John; Losasso, Marcello; Rodriguez, Jesus; Evans, David; Diaz, Victor

    2014-01-27

    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.

  2. Registration of range data using a hybrid simulated annealing and iterative closest point algorithm

    SciTech Connect (OSTI)

    LUCK,JASON; LITTLE,CHARLES Q.; HOFF,WILLIAM

    2000-04-17

    The need to register data is abundant in applications such as: world modeling, part inspection and manufacturing, object recognition, pose estimation, robotic navigation, and reverse engineering. Registration occurs by aligning the regions that are common to multiple images. The largest difficulty in performing this registration is dealing with outliers and local minima while remaining efficient. A commonly used technique, iterative closest point, is efficient but is unable to deal with outliers or avoid local minima. Another commonly used optimization algorithm, simulated annealing, is effective at dealing with local minima but is very slow. Therefore, the algorithm developed in this paper is a hybrid algorithm that combines the speed of iterative closest point with the robustness of simulated annealing. Additionally, a robust error function is incorporated to deal with outliers. This algorithm is incorporated into a complete modeling system that inputs two sets of range data, registers the sets, and outputs a composite model.

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

    SciTech Connect (OSTI)

    1997-04-18

    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.

  4. Vacuum Bellows, Vacuum Piping, Cryogenic Break, and Copper Joint Failure Rate Estimates for ITER Design Use

    SciTech Connect (OSTI)

    L. C. Cadwallader

    2010-06-01

    The ITER international project design teams are working to produce an engineering design in preparation for construction of the International Thermonuclear Experimental Reactor (ITER) tokamak. During the course of this work, questions have arisen in regard to safety barriers and equipment reliability as important facets of system design. The vacuum system designers have asked several questions about the reliability of vacuum bellows and vacuum piping. The vessel design team has asked about the reliability of electrical breaks and copper-copper joints used in cryogenic piping. Research into operating experiences of similar equipment has been performed to determine representative failure rates for these components. The following chapters give the research results and the findings for vacuum system bellows, power plant stainless steel piping (amended to represent vacuum system piping), cryogenic system electrical insulating breaks, and copper joints.

  5. 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)

    with leading-edge ideas and design | Princeton Plasma Physics Lab and ITER: Lab teams support the world's largest fusion experiment with leading-edge ideas and design By John Greenwald May 7, 2013 Tweet Widget Google Plus One Share on Facebook PPPL scientists, engineers, technicians and other specialists contribute to the international project. (Photo by Elle Starkman/ PPPL Office of Communications) PPPL scientists, engineers, technicians and other specialists contribute to the international

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

    DOE Patents [OSTI]

    Kouri, Donald J.; Vijay, Amrendra; Zhang, Haiyan; Zhang, Jingfeng; Hoffman, David K.

    2007-05-01

    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.

  7. Effects of coupling and asymmetries on load resilience of IC ITER-like structures

    SciTech Connect (OSTI)

    Bosia, G.; Bremond, S.; Colas, L.

    2005-09-26

    ITER-like structures feature an intrinsic resilience to load variations, which is related to the symmetry of the currents in the two branches of the structure. It has been suggested that the effects of coupling between the array elements would significantly impair the load resilience of the structure. In this paper the effect of inter strap coupling and of however induced electrical array asymmetries on the structure load resilience are quantitatively examined.

  8. Nuclear Fuel Cycle Options Catalog

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

    Options Catalog - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  9. Control system options and strategies for supercritical CO2 cycles.

    SciTech Connect (OSTI)

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

    2009-06-18

    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.

  10. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    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

    2009-12-01

    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 modules—23 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.

  11. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

    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

    2008-03-01

    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 modules—23 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.

  12. Advanced Fuel Cycle Cost Basis

    SciTech Connect (OSTI)

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

    2007-04-01

    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 modules—24 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.

  13. Benchmark of numerical tools simulating beam propagation and secondary particles in ITER NBI

    SciTech Connect (OSTI)

    Sartori, E. Veltri, P.; Serianni, G.; Dlougach, E.; Hemsworth, R.; Singh, M.

    2015-04-08

    Injection of high energy beams of neutral particles is a method for plasma heating in fusion devices. The ITER injector, and its prototype MITICA (Megavolt ITER Injector and Concept Advancement), are large extrapolations from existing devices: therefore numerical modeling is needed to set thermo-mechanical requirements for all beam-facing components. As the power and charge deposition originates from several sources (primary beam, co-accelerated electrons, and secondary production by beam-gas, beam-surface, and electron-surface interaction), the beam propagation along the beam line is simulated by comprehensive 3D models. This paper presents a comparative study between two codes: BTR has been used for several years in the design of the ITER HNB/DNB components; SAMANTHA code was independently developed and includes additional phenomena, such as secondary particles generated by collision of beam particles with the background gas. The code comparison is valuable in the perspective of the upcoming experimental operations, in order to prepare a reliable numerical support to the interpretation of experimental measurements in the beam test facilities. The power density map calculated on the Electrostatic Residual Ion Dump (ERID) is the chosen benchmark, as it depends on the electric and magnetic fields as well as on the evolution of the beam species via interaction with the gas. Finally the paper shows additional results provided by SAMANTHA, like the secondary electrons produced by volume processes accelerated by the ERID fringe-field towards the Cryopumps.

  14. Engineering aspects of design and integration of ECE diagnostic in ITER

    SciTech Connect (OSTI)

    Udintsev, V. S.; Taylor, G.; Pandya, H. K.B.; Austin, M. E.; Casal, N.; Catalin, R.; Clough, M.; Cuquel, B.; Dapena, M.; Drevon, J. -M.; Feder, R.; Friconneau, J. P.; Giacomin, T.; Guirao, J.; Henderson, M. A.; Hughes, S.; Iglesias, S.; Johnson, D.; Kumar, Siddhart; Kumar, Vina; Levesy, B.; Loesser, D.; Messineo, M.; Penot, C.; Portalès, M.; Oosterbeek, J. W.; Sirinelli, A; Vacas, C.; Vayakis, G.; Walsh, M. J.; Kubo, S.

    2015-03-12

    ITER ECE diagnostic [1] needs not only to meet measurement requirements, but also to withstand various loads, such as electromagnetic, mechanical, neutronic and thermal, and to be protected from stray ECH radiation at 170 GHz and other millimeter wave emission, like Collective Thomson scattering which is planned to operate at 60 GHz. Same or similar loads will be applied to other millimetre-wave diagnostics [2], located both in-vessel and in-port plugs. These loads must be taken into account throughout the design phases of the ECE and other microwave diagnostics to ensure their structural integrity and maintainability. The integration of microwave diagnostics with other ITER systems is another challenging activity which is currently ongoing through port integration and in-vessel integration work. Port Integration has to address the maintenance and the safety aspects of diagnostics, too. Engineering solutions which are being developed to support and to operate ITER ECE diagnostic, whilst complying with safety and maintenance requirements, are discussed in this paper.

  15. Uncertainty assessment and analysis of ITER in-VV tritium inventory determination

    SciTech Connect (OSTI)

    Cristescu, I. R.; Cristescu, I.; Glugla, M.; Murdoch, D.; Ciattaglia, S.

    2008-07-15

    Tracking of tritium inventories on ITER will be essential to ensure that the safety limits established for the mobilizable tritium inventory in the vacuum vessel are not violated. Tritium will be delivered to the ITER site from outside suppliers. Staring with the tritium imports the value of tritium inventory at ITER site will be known with a certain error that will propagate in time. During plasma operation, shot by shot measurements of the tritium delivered to the Torus and recovered will allow the amount of tritium trapped in the Torus to be computed at the end of the day. A case study for different measuring techniques and several measuring points for the tritium recovered from Torus have been done. An alternative method is to measure overnight the variation in the inventory of the storage and delivery system and the associated error when this method will be employed are presented. In order to reduce the errors on the tritium trapped in-vessel, at certain time intervals a method of global tritium inventory will be performed. The method envisages the transfer of all the mobilizable tritium from the plant and measurement of this inventory in the self-assay beds from the storage and delivery system. Evaluation of the most important sources of error for the tritium trapped in-vessel and means of minimization are eventually presented. (authors)

  16. Engineering aspects of design and integration of ECE diagnostic in ITER

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Udintsev, V. S.; Taylor, G.; Pandya, H. K.B.; Austin, M. E.; Casal, N.; Catalin, R.; Clough, M.; Cuquel, B.; Dapena, M.; Drevon, J. -M.; et al

    2015-03-12

    ITER ECE diagnostic [1] needs not only to meet measurement requirements, but also to withstand various loads, such as electromagnetic, mechanical, neutronic and thermal, and to be protected from stray ECH radiation at 170 GHz and other millimeter wave emission, like Collective Thomson scattering which is planned to operate at 60 GHz. Same or similar loads will be applied to other millimetre-wave diagnostics [2], located both in-vessel and in-port plugs. These loads must be taken into account throughout the design phases of the ECE and other microwave diagnostics to ensure their structural integrity and maintainability. The integration of microwave diagnosticsmore » with other ITER systems is another challenging activity which is currently ongoing through port integration and in-vessel integration work. Port Integration has to address the maintenance and the safety aspects of diagnostics, too. Engineering solutions which are being developed to support and to operate ITER ECE diagnostic, whilst complying with safety and maintenance requirements, are discussed in this paper.« less

  17. Paducah WDA CERCLA Process & Public Involvement

    Broader source: Energy.gov [DOE]

    DOE is committed to fostering meaningful community involvement in environmental remediation decision making at the site.

  18. Validation of the thermal transport model used for ITER startup scenario predictions with DIII-D experimental data

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Casper, T. A.; Meyer, W. H.; Jackson, G. L.; Luce, T. C.; Hyatt, A. W.; Humphreys, D. A.; Turco, F.

    2010-12-08

    We are exploring characteristics of ITER startup scenarios in similarity experiments conducted on the DIII-D Tokamak. In these experiments, we have validated scenarios for the ITER current ramp up to full current and developed methods to control the plasma parameters to achieve stability. Predictive simulations of ITER startup using 2D free-boundary equilibrium and 1D transport codes rely on accurate estimates of the electron and ion temperature profiles that determine the electrical conductivity and pressure profiles during the current rise. Here we present results of validation studies that apply the transport model used by the ITER team to DIII-D discharge evolutionmore » and comparisons with data from our similarity experiments.« less

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

    SciTech Connect (OSTI)

    Ulrickson, M.A.; Manly, W.D.; Dombrowski, D.E.

    1995-08-01

    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.

  20. DOE - NNSA/NFO -- EM Public Involvement

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

    Public Involvement NNSA/NFO Language Options U.S. DOE/NNSA - Nevada Field Office Click to subscribe to NNSS News Public Involvement Public Involvement Outreach Photo An integral component of the Environmental Management Program is the public involvement function. Communication with the public is an essential element in successfully conducting Environmental Management work. Public involvement initiatives include developing and distributing fact sheets, publications, and exhibits as well as

  1. Tsiklauri-Durst combined cycle (T-D Cycle{trademark}) application for nuclear and fossil-fueled power generating plants

    SciTech Connect (OSTI)

    Tsiklauri, B.; Korolev, V.N.; Durst, B.M.; Shen, P.K.

    1998-07-01

    The Tsiklauri-Durst combined cycle is a combination of the best attributes of both nuclear power and combined cycle gas power plants. A technology patented in 1994 by Battelle Memorial Institute offers a synergistic approach to power generation. A typical combined cycle is defined as the combination of gas turbine Brayton Cycle, topping steam turbine Rankine Cycle. Exhaust from the gas turbine is used in heat recovery steam generators to produce steam for a steam turbine. In a standard combined cycle gas turbine-steam turbine application, the gas turbine generates about 65 to 70 percent of system power. The thermal efficiency for such an installation is typically about 45 to 50 percent. A T-D combined cycle takes a new, creative approach to combined cycle design by directly mixing high enthalpy steam from the heat recovery steam generator, involving the steam generator at more than one pressure. Direct mixing of superheated and saturated steam eliminates the requirement for a large heat exchanger, making plant modification simple and economical.

  2. Binary Cycle Power Plant | Open Energy Information

    Open Energy Info (EERE)

    binary-cycle power plants in the future will be binary-cycle plants1 Enel's Salts Wells Geothermal Plant in Nevada: This plant is a binary system that is rated at 13 MW...

  3. Fuel Cycle Research and Development Program

    Office of Environmental Management (EM)

    James C. Bresee, ScD, JD Advisory Board Member Office of Nuclear Energy July 29, 2009 July 29, 2009 Fuel Cycle Research and Development DM 195665 2 Outline Fuel Cycle R&D Mission ...

  4. Integrated Climate and Carbon-cycle Model

    Energy Science and Technology Software Center (OSTI)

    2006-03-06

    The INCCA model is a numerical climate and carbon cycle modeling tool for use in studying climate change and carbon cycle science. The model includes atmosphere, ocean, land surface, and sea ice components.

  5. EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE...

    Office of Environmental Management (EM)

    ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive ...

  6. Pilot Application to Nuclear Fuel Cycle Options

    Broader source: Energy.gov [DOE]

    A Screening Method for Guiding R&D Decisions: Pilot Application to Screen Nuclear Fuel Cycle Options

  7. Fuel Cycle Research and Development Presentation Title

    Energy Savers [EERE]

    Materials Recovery and Waste Form Development Campaign Overview Jim Bresee, DOE NE NEET Webinar September 17, 2014 Campaign Objectives  Develop advanced fuel cycle material recovery and waste management technologies that improve current fuel cycle performance and enable a sustainable fuel cycle, with minimal processing, waste generation, and potential for material diversion to provide options for future fuel cycle policy decisions  Campaign strategy is based on developing: - Technologies

  8. Development Plan for the Fuel Cycle Simulator

    SciTech Connect (OSTI)

    Brent Dixon

    2011-09-01

    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.'

  9. Rankine cycle system and method

    DOE Patents [OSTI]

    Ernst, Timothy C.; Nelson, Christopher R.

    2014-09-09

    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.

  10. Title: The Life-cycle

    Office of Scientific and Technical Information (OSTI)

    The Life-cycle of Operons Authors: Morgan N. Price, Adam P. Arkin, and Eric J. Alm Author affiliation: Lawrence Berkeley Lab, Berkeley CA, USA and the Virtual Institute for Microbial Stress and Survival. A.P.A. is also affiliated with the Howard Hughes Medical Institute and the UC Berkeley Dept. of Bioengineering. Corresponding author: Eric Alm, ejalm@lbl.gov, phone 510-486-6899, fax 510-486-6219, address Lawrence Berkeley National Lab, 1 Cyclotron Road, Mailstop 977-152, Berkeley, CA 94720

  11. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    This eighteenth quarterly technical progress report of the MHD Integrated Topping cycle Project presents the accomplishments during the period November 1, 1991 to January 31, 1992. The precombustor is fully assembled. Manufacturing of all slagging stage components has been completed. All cooling panels were welded in place and the panel/shell gap was filled with RTV. Final combustor assembly is in progress. The low pressure cooling subsystem (LPCS) was delivered to the CDIF. Second stage brazing issues were resolved. The construction of the two anode power cabinets was completed.

  12. US ITER

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

    exposure at the Commerce Park site. Individuals are not required to wear the blue dosimeter badges at this site. 2.11 Worksite Warning Signs and Labels The typical signs you...

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

    SciTech Connect (OSTI)

    Edwin A. Harvego; Michael G. McKellar

    2011-11-01

    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.

  14. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    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.

  15. Technology development life cycle processes.

    SciTech Connect (OSTI)

    Beck, David Franklin

    2013-05-01

    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.

  16. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    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.

  17. Summary of non-US national and international fuel cycle and radioactive waste management programs 1982

    SciTech Connect (OSTI)

    Harmon, K.M.; Kelman, J.A.

    1982-08-01

    Brief program overviews of fuel cycle, spent fuel, and waste management activities in the following countries are provided: Argentina, Australia, Austria, Belgium, Brazil, Canada, China, Denmark, Finland, France, German Federal Republic, India, Italy, Japan, Republic of Korea, Mexico, Netherlands, Pakistan, South Africa, Spain, Sweden, Switzerland, Taiwan, USSR, and the United Kingdom. International nonproliferation activities, multilateral agreements and projects, and the international agencies specifically involved in the nuclear fuel cycle are also described.

  18. Nuclear Fuel Cycle | Department of Energy

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

    Cycle Nuclear Fuel Cycle This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. This is an illustration of a nuclear fuel cycle that shows the required steps to process natural uranium from ore for preparation for fuel to be loaded in nuclear reactors. The mission of NE-54 is primarily focused on activities related to the front end of the nuclear fuel cycle which includes mining,

  19. Advanced Fuel Cycle Economic Sensitivity Analysis

    SciTech Connect (OSTI)

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

    2006-12-01

    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.

  20. Public Involvement Plan | Department of Energy

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

    Public Involvement Plan Public Involvement Plan Every three years, the Public Involvement Plan is updated, prepared, and published by the U.S. Department of Energy Oak Ridge Office of Environmental Management (DOE-OREM) to communicate to you, as a member of the public, the opportunities you have to participate in decisions and information exchanges regarding the remediation of contaminated areas on the Oak Ridge Site. DOE is committed to fostering meaningful public involvement in all aspects of

  1. ITER Generic Diagnostic Upper Port Plug Nuclear Heating and Personnel Dose Rate Assesment Neutronics Analysis using the ATTILA Discrete Ordinates Code

    SciTech Connect (OSTI)

    Russell Feder and Mahmoud Z. Yousef

    2009-05-29

    Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of the ECH heating system were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding and a small aperture (Vis-IR) and minimal shielding with a large aperture (ECH). The neutronics discrete-ordinates code ATTILA and SEVERIAN (the ATTILA parallel processing version) was used. Material properties and the 500 MW D-T volume source were taken from the ITER Brand Model MCNP benchmark model. A biased quadrature set equivelant to Sn=32 and a scattering degree of Pn=3 were used along with a 46-neutron and 21-gamma FENDL energy subgrouping. Total nuclear heating (neutron plug gamma heating) in the upper port plugs ranged between 380 and 350 kW for the Vis-IR and ECH cases. The ECH or Large Aperture model exhibited lower total heating but much higher peak volumetric heating on the upper port plug structure. Personnel dose rates are calculated in a three step process involving a neutron-only transport calculation, the generation of activation volume sources at pre-defined time steps and finally gamma transport analyses are run for selected time steps. ANSI-ANS 6.1.1 1977 Flux-to-Dose conversion factors were used. Dose rates were evaluated for 1 full year of 500 MW DT operation which is comprised of 3000 1800-second pulses. After one year the machine is shut down for maintenance and personnel are permitted to access the diagnostic interspace after 2-weeks if dose rates are below 100 ?Sv/hr. Dose rates in the Visible-IR diagnostic model after one day of shutdown were 130 ?Sv/hr but fell below the limit to 90 ?Sv/hr 2-weeks later. The Large Aperture or ECH style shielding model exhibited higher and more persistent dose rates. After 1-day the dose rate was 230 ?Sv/hr but was still at 120 ?Sv/hr 4-weeks later. __________________________________________________

  2. VISION: Verifiable Fuel Cycle Simulation Model

    SciTech Connect (OSTI)

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

    2009-04-01

    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.

  3. Public Involvement and Communications Committee Page 1

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

    11, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING October 11, 2011 Richland, WA Topics in this Meeting Summary Welcome and Introductions ............................................................................................................ 1 Draft Advice - Draft Hanford Public Involvement Plan ................................................................ 1 Public Meetings - Draft Hanford Public Involvement Plan

  4. Development of ITER 15 MA ELMy H-mode Inductive Scenario

    SciTech Connect (OSTI)

    Kessel, C. E.; Campbell, D.; Gribov, Y.; Saibene, G.; Ambrosino, G.; Casper, T.; Cavinato, M.; Fujieda, H.; Hawryluk, R.; Horton, L. D.; Kavin, A.; Kharyrutdinov, R.; Koechl, F.; Leuer, J.; Loarte, A.; Lomas, P. J.; Luce, T.; Lukash, V.; Mattei, M.; Nunes, I.; Parail, V.; Polevoi, A.; Portone, A.; Sartori, R.; Sips, A. C.C.; Thomas, P. R.; Welander, A.; Wesley, J.

    2008-10-16

    The poloidal field (PF) coil system on ITER, which provides both feedforward and feedback control of plasma position, shape, and current, is a critical element for achieving mission performance. Analysis of PF capabilities has focused on the 15 MA Q = 10 scenario with a 300-500 s flattop burn phase. The operating space available for the 15 MA ELMy H-mode plasma discharges in ITER and upgrades to the PF coils or associated systems to establish confidence that ITER mission objectives can be reached have been identified. Time dependent self-consistent free-boundary calculations were performed to examine the impact of plasma variability, discharge programming, and plasma disturbances. Based on these calculations a new reference scenario was developed based upon a large bore initial plasma, early divertor transition, low level heating in L-mode, and a late H-mode onset. Equilibrium analyses for this scenario indicate that the original PF coil limitations do not allow low li (<0.8) operation or lower flux states, and the flattop burn durations were predicted to be less than the desired 400 s. This finding motivates the expansion of the operating space, considering several upgrade options to the PF coils. Analysis was also carried out to examine the feedback current reserve required in the CS and PF coils during a series of disturbances and a feasibility assessment of the 17 MA scenario was undertaken. Results of the studies show that the new scenario and modified PF system will allow a wide range of 15 MA 300-500 s operation and more limited but finite 17 MA operation.

  5. TU-F-18A-02: Iterative Image-Domain Decomposition for Dual-Energy CT

    SciTech Connect (OSTI)

    Niu, T; Dong, X; Petrongolo, M; Zhu, L

    2014-06-15

    Purpose: Dual energy CT (DECT) imaging plays an important role in advanced imaging applications due to its material decomposition capability. Direct decomposition via matrix inversion suffers from significant degradation of image signal-to-noise ratios, which reduces clinical value. Existing de-noising 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. We 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. It includes the inverse of the estimated variance-covariance matrix of the decomposed images as the penalty weight in the least-square term. Performance is evaluated using an evaluation phantom (Catphan 600) and an anthropomorphic head phantom. Results are compared to those generated using direct matrix inversion with no noise suppression, a de-noising method applied on the decomposed images, and an existing algorithm with similar formulation but with an edge-preserving regularization term. Results: On the Catphan phantom, our method retains the same spatial resolution as the CT images before decomposition while reducing the noise standard deviation of decomposed images by over 98%. The other methods either degrade spatial resolution or achieve less low-contrast detectability. Also, our method yields lower electron density measurement error than direct matrix inversion and reduces error variation by over 97%. On the head phantom, it reduces the noise standard deviation of decomposed images by over 97% without blurring the sinus structures. Conclusion: We 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. The proposed algorithm shows superior performance on noise suppression with high image spatial resolution and low-contrast detectability. This work is supported by a Varian MRA grant.

  6. Fuel Cycle System Analysis Handbook

    SciTech Connect (OSTI)

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

    2009-06-01

    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.

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

    SciTech Connect (OSTI)

    Saad, Yousef

    2014-01-16

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

  8. Engineer Russ Feder leads development of diagnostic tools for US ITER as

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

    physicist Dave Johnson shifts to part-time work | Princeton Plasma Physics Lab Engineer Russ Feder leads development of diagnostic tools for US ITER as physicist Dave Johnson shifts to part-time work By John Greenwald March 16, 2015 Tweet Widget Google Plus One Share on Facebook Dave Johnson, left, and Russ Feder with design for component of a diagnostic system behind them. (Photo by Elle Starkman/PPPL Office of Communications) Dave Johnson, left, and Russ Feder with design for component of

  9. Engineer Russ Feder leads development of diagnostic tools for US ITER as

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

    physicist Dave Johnson shifts to part-time work | Princeton Plasma Physics Lab Engineer Russ Feder leads development of diagnostic tools for US ITER as physicist Dave Johnson shifts to part-time work By John Greenwald March 16, 2015 Tweet Widget Google Plus One Share on Facebook Dave Johnson, left, and Russ Feder with design for component of a diagnostic system behind them. (Photo by Elle Starkman/PPPL Office of Communications) Dave Johnson, left, and Russ Feder with design for component of

  10. Development of the prototype pneumatic transfer system for ITER neutron activation system

    SciTech Connect (OSTI)

    Cheon, M. S.; Seon, C. R.; Pak, S.; Lee, H. G.; Bertalot, L.

    2012-10-15

    The neutron activation system (NAS) measures neutron fluence at the first wall and the total neutron flux from the ITER plasma, providing evaluation of the fusion power for all operational phases. The pneumatic transfer system (PTS) is one of the key components of the NAS for the proper operation of the system, playing a role of transferring encapsulated samples between the capsule loading machine, irradiation stations, counting stations, and disposal bin. For the validation and the optimization of the design, a prototype of the PTS was developed and capsule transfer tests were performed with the developed system.

  11. Source term evaluation for accident transients in the experimental fusion facility ITER

    SciTech Connect (OSTI)

    Virot, F.; Barrachin, M.; Cousin, F.

    2015-03-15

    We have studied the transport and chemical speciation of radio-toxic and toxic species for an event of water ingress in the vacuum vessel of experimental fusion facility ITER with the ASTEC code. In particular our evaluation takes into account an assessed thermodynamic data for the beryllium gaseous species. This study shows that deposited beryllium dusts of atomic Be and Be(OH){sub 2} are formed. It also shows that Be(OT){sub 2} could exist in some conditions in the drain tank. (authors)

  12. A new frequency domain arc furnace model for iterative harmonic analysis

    SciTech Connect (OSTI)

    Mayordomo, J.G.; Beites, L.F.; Asensi, R.; Izzeddine, M.; Zabala, L.; Amantegui, J.

    1997-10-01

    This paper presents a new frequency domain Arc Furnace model for Iterative Harmonic Analysis (IHA) by means of a Newton method. Powerful analytical expressions for harmonic currents and their derivatives are obtained under the balanced conditions of the system. The model offers a three phase configuration where there is no path for homopolar currents. Moreover, it contemplates continuous and discontinuous evolution of the arc current. The solution obtained is validated by means of time domain simulations. Finally, the model was integrated in a harmonic power flow where studies have been performed in a network with more than 700 busbars and 7 actual Arc Furnace Loads.

  13. "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER,

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

    dies at 80 | Princeton Plasma Physics Lab "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER, dies at 80 By John Greenwald August 11, 2014 Tweet Widget Google Plus One Share on Facebook Francis "Rip" Perkins Francis "Rip" Perkins Gallery: "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee, left, and John Krommes, right. "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee,

  14. "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER,

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

    dies at 80 | Princeton Plasma Physics Lab "Rip" Perkins, pioneering PPPL physicist and a design leader for ITER, dies at 80 By John Greenwald August 11, 2014 Tweet Widget Google Plus One Share on Facebook Francis "Rip" Perkins Francis "Rip" Perkins Gallery: "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee, left, and John Krommes, right. "Rip" Perkins, center, as head of the PPPL Theory Department with Wei-li Lee,

  15. Note: Readout of a micromechanical magnetometer for the ITER fusion reactor

    SciTech Connect (OSTI)

    Rimminen, H.; Kyynaeraeinen, J.

    2013-05-15

    We present readout instrumentation for a MEMS magnetometer, placed 30 m away from the MEMS element. This is particularly useful when sensing is performed in high-radiation environment, where the semiconductors in the readout cannot survive. High bandwidth transimpedance amplifiers are used to cancel the cable capacitances of several nanofarads. A frequency doubling readout scheme is used for crosstalk elimination. Signal-to-noise ratio in the range of 60 dB was achieved and with sub-percent nonlinearity. The presented instrument is intended for the steady-state magnetic field measurements in the ITER fusion reactor.

  16. Momentum space iterative solution of the time-dependent Schrödinger equation

    SciTech Connect (OSTI)

    Kiss, G. Zs.; Borbély, S.; Nagy, L.

    2013-11-13

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

  17. X-ray crystal spectrometer upgrade for ITER-like wall experiments at JET

    SciTech Connect (OSTI)

    Shumack, A. E.; Rzadkiewicz, J.; Chernyshova, M.; Czarski, T.; Karpinski, L.; Jakubowska, K.; Scholz, M.; Byszuk, A.; Cieszewski, R.; Kasprowicz, G.; Pozniak, K.; Wojenski, A.; Zabolotny, W.; Dominik, W.; Conway, N. J.; Dalley, S.; Tyrrell, S.; Zastrow, K.-D.; Figueiredo, J. [EFDA-CSU, Culham Science Centre, Abingdon OX14 3DB; Associao EURATOM and others

    2014-11-15

    The high resolution X-Ray crystal spectrometer at the JET tokamak has been upgraded with the main goal of measuring the tungsten impurity concentration. This is important for understanding impurity accumulation in the plasma after installation of the JET ITER-like wall (main chamber: Be, divertor: W). This contribution provides details of the upgraded spectrometer with a focus on the aspects important for spectral analysis and plasma parameter calculation. In particular, we describe the determination of the spectrometer sensitivity: important for impurity concentration determination.

  18. Efficiency combined cycle power plant

    SciTech Connect (OSTI)

    Pavel, J.; Meyers, G.A.; Baldwin, T.S.

    1990-06-12

    This patent describes a method of operating a combined cycle power plant. It comprises: flowing exhaust gas from a combustion turbine through a heat recovery steam generator (HRSG); flowing feed water through an economizer section of the HRSG at a flow rate and providing heated feed water; flowing a first portion of the heated feed water through an evaporator section of the HRSG and producing saturated steam at a production rate, the flow rate of the feed water through the economizer section being greater than required to sustain the production rate of steam in the evaporator section; flowing fuel for the turbine through a heat exchanger; and, flowing a second portion of the heated feed water provided by the economizer section through the heat exchanger then to an inlet of the economizer section, thereby heating the fuel flowing through the heat exchanger.

  19. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-07-01

    This seventeenth quarterly technical progress report of the MHD Integrated Topping Cycle Project presents the accomplishments during the period August 1, 1991 to October 31, 1991. Manufacturing of the prototypical combustor pressure shell has been completed including leak, proof, and assembly fit checking. Manufacturing of forty-five cooling panels was also completed including leak, proof, and flow testing. All precombustor internal components (combustion can baffle and swirl box) were received and checked, and integration of the components was initiated. A decision was made regarding the primary and backup designs for the 1A4 channel. The assembly of the channel related prototypical hardware continued. The cathode wall electrical wiring is now complete. The mechanical design of the diffuser has been completed.

  20. Fuel Cycle Assessment: Evaluation and Analyses using ORION for...

    Office of Scientific and Technical Information (OSTI)

    Fuel Cycle Assessment: Evaluation and Analyses using ORION for US Fuel Cycle Options Citation Details In-Document Search Title: Fuel Cycle Assessment: Evaluation and Analyses using ...

  1. Technical Cost Modeling - Life Cycle Analysis Basis for Program...

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

    More Documents & Publications Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Technical Cost Modeling - Life Cycle Analysis Basis for Program Focus Life Cycle ...

  2. Minimize Boiler Short Cycling Losses | Department of Energy

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

    Minimize Boiler Short Cycling Losses Minimize Boiler Short Cycling Losses This tip sheet on minimizing boiler short cycling losses provides how-to advice for improving industrial...

  3. Development of a Twin-Screw D-2 Extruder for the ITER Pellet Injection System

    SciTech Connect (OSTI)

    Meitner, Steven J; Baylor, Larry R; Carbajo, Juan J; Combs, Stephen Kirk; Fehling, Dan T; Foust, Charles R; McFee, Marshall T; McGill, James M; Rasmussen, David A; Sitterson, R G; Sparks, Dennis O; Qualls, A L

    2009-07-01

    A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. The extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with single-stage gas gun into the plasma. A one-fifth ITER scale prototype extruder has been built to produce a continuous solid deuterium extrusion. Deuterium gas is precooled and liquefied before being introduced into the extruder. The precooler consists of a copper vessel containing liquid nitrogen surrounded by a deuterium gas filled copper coil. The liquefier is comprised of a copper cylinder connected to a Cryomech AL330 cryocooler, which is surrounded by a copper coil that the precooled deuterium flows through. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at approximate to 15 K) before it is forced through the extruder nozzle. A viewport located below the extruder nozzle provides a direct view of the extrusion. A camera is used to document the extrusion quality and duration. A data acquisition system records the extruder temperatures, torque, and speed, upstream, and downstream pressures. This paper will describe the prototype twin-screw extruder and initial extrusion results.

  4. Material migration studies with an ITER first wall panel proxy on EAST

    SciTech Connect (OSTI)

    Ding, R.; Pitts, R. A.; Borodin, D.; Carpentier, S.; Ding, F.; Gong, X. Z.; Guo, H. Y.; Kirschner, A.; Kocan, M.; Li, J. G.; Luo, G. -N.; Mao, H. M.; Qian, J. P.; Stangeby, P. C.; Wampler, W. R.; Wang, H. Q.; Wang, W. Z.; Chen, J. L.; Gan, K. F.

    2015-01-23

    The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring panels arising from assembly tolerances. This departure from a perfectly cylindrical surface automatically leads to magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide a benchmark for a series of erosion/re-deposition simulation studies performed for the ITER FW panels, dedicated experiments have been performed on the EAST tokamak using a specially designed, instrumented test limiter acting as a proxy for the FW panel geometry. Carbon coated molybdenum plates forming the limiter front surface were exposed to the outer midplane boundary plasma of helium discharges using the new Material and Plasma Evaluation System (MAPES). Net erosion and deposition patterns are estimated using ion beam analysis to measure the carbon layer thickness variation across the surface after exposure. The highest erosion of about 0.8 µm is found near the midplane, where the surface is closest to the plasma separatrix. No net deposition above the measurement detection limit was found on the proxy wall element, even in shadowed regions. The measured 2D surface erosion distribution has been modelled with the 3D Monte Carlo code ERO, using the local plasma parameter measurements together with a diffusive transport assumption. In conclusion, excellent agreement between the experimentally observed net erosion and the modelled erosion profile has been obtained.

  5. ITER Core Imaging X-Ray Spectrometer Conceptual Design and Performance Assessment - Phase 2

    SciTech Connect (OSTI)

    Beiersdorfer, P; Wen, J; Dunn, J; Morris, K

    2011-01-02

    During Phase 2 of our study of the CIXS conceptual design we have tackled additional important issues that are unique to the ITER environment. These include the thermal control of the crystal and detector enclosures located in an environment with a 100-250 C ambient temperature, tritium containment, and the range of crystal and detector movement based on the need for spectral adjustments and the desire to make measurements of colder plasmas. In addressing these issues we have selected a ''Dewar''-type enclosure for the crystals and detectors. Applying realistic view factors for radiant heat and making allowance for conduction we have made engineering studies of this enclosure and showed that the cooling requirements can be solved and the temperature can be kept sufficiently constant without compromising the specification parameters of the CIXS. We have chosen a minimum 3 mm combined thickness of the six beryllium windows needed in a Dewar-type enclosure and showed that a single window of 0.5 mm thickness satisfies tritium containment requirements. For measuring the temperature in cooler ITER plasmas, we have chosen to use the K-shell lines of Fe24+. Iron is the preferred choice because its radiation can be analyzed with the identical CIXS settings used for analyzing the tungsten radiation, i.e., essentially no adjustments besides a simple crystal rotation need to be made. We have, however, included an xy{theta}-drive motor arrangement in our design for fine adjustments and full rotation of the crystal mounts.

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

    SciTech Connect (OSTI)

    Chilton, Sven; Chilton, Sven H.

    2008-07-01

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

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

    SciTech Connect (OSTI)

    Vries, P. C. de Hogeweij, G. M. D.; Baruzzo, M.; Murari, A.; Jachmich, S.; Lomas, P. J.; Matthews, G. F.; Ptterich, T.; Vega, J.; Collaboration: JET-EFDA Contributors

    2014-05-15

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

  8. The targeted heating and current drive applications for the ITER electron cyclotron system

    SciTech Connect (OSTI)

    Henderson, M.; Darbos, C.; Gandini, F.; Gassmann, T.; Loarte, A.; Omori, T.; Purohit, D.; Saibene, G.; Gagliardi, M.; Farina, D.; Figini, L.; Hanson, G.; Poli, E.; Takahashi, K.

    2015-02-15

    A 24?MW Electron Cyclotron (EC) system operating at 170?GHz and 3600?s pulse length is to be installed on ITER. The EC plant shall deliver 20?MW of this power to the plasma for Heating and Current Drive (H and CD) applications. The EC system is designed for plasma initiation, central heating, current drive, current profile tailoring, and Magneto-hydrodynamic control (in particular, sawteeth and Neo-classical Tearing Mode) in the flat-top phase of the plasma. A preliminary design review was performed in 2012, which identified a need for extended application of the EC system to the plasma ramp-up, flattop, and ramp down phases of ITER plasma pulse. The various functionalities are prioritized based on those applications, which can be uniquely addressed with the EC system in contrast to other H and CD systems. An initial attempt has been developed at prioritizing the allocated H and CD applications for the three scenarios envisioned: ELMy H-mode (15 MA), Hybrid (?12 MA), and Advanced (?9 MA) scenarios. This leads to the finalization of the design requirements for the EC sub-systems.

  9. Material migration studies with an ITER first wall panel proxy on EAST

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ding, R.; Pitts, R. A.; Borodin, D.; Carpentier, S.; Ding, F.; Gong, X. Z.; Guo, H. Y.; Kirschner, A.; Kocan, M.; Li, J. G.; et al

    2015-01-23

    The ITER beryllium (Be) first wall (FW) panels are shaped to protect leading edges between neighbouring panels arising from assembly tolerances. This departure from a perfectly cylindrical surface automatically leads to magnetically shadowed regions where eroded Be can be re-deposited, together with co-deposition of tritium fuel. To provide a benchmark for a series of erosion/re-deposition simulation studies performed for the ITER FW panels, dedicated experiments have been performed on the EAST tokamak using a specially designed, instrumented test limiter acting as a proxy for the FW panel geometry. Carbon coated molybdenum plates forming the limiter front surface were exposed tomore » the outer midplane boundary plasma of helium discharges using the new Material and Plasma Evaluation System (MAPES). Net erosion and deposition patterns are estimated using ion beam analysis to measure the carbon layer thickness variation across the surface after exposure. The highest erosion of about 0.8 µm is found near the midplane, where the surface is closest to the plasma separatrix. No net deposition above the measurement detection limit was found on the proxy wall element, even in shadowed regions. The measured 2D surface erosion distribution has been modelled with the 3D Monte Carlo code ERO, using the local plasma parameter measurements together with a diffusive transport assumption. In conclusion, excellent agreement between the experimentally observed net erosion and the modelled erosion profile has been obtained.« less

  10. Fuel Cycle Technologies | Department of Energy

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

    Fuel Cycle Technologies Fuel Cycle Technologies Fuel Cycle Technologies Preparing for Tomorrow's Energy Demands Powerful imperatives drive the continued need for nuclear power, among them the need for reliable, baseload electricity and the threat of global climate change. As the only large-scale source of nearly greenhouse gas-free energy, nuclear power is an essential part of our all-of-the-above energy strategy, generating about 20 percent of our nation's electricity and more than 60 percent

  11. NEAC Fuel Cycle Technologies Subcommittee Report Presentation...

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

    and Joint Fuel Cycle Study Accident Tolerant Fuel (ATF) Update ... EChem and Aqueous performance 4 Accident Tolerant Fuel (ATF) Update Comments ...

  12. Fuel Cycle Research and Development Presentation Title

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

    economical deployment * Concept through engineering-scale ...Closed Fuel Cycles Environmental National Security MRWFD ... performance and lower cost supply of uranium from seawater ...

  13. Splitting the Cycle the Right Way

    Broader source: Energy.gov [DOE]

    The unique opposed-cylinder configuration of the TourEngine allows superior thermal management and efficient gas transfer compared to other split-cycle designs.

  14. Stirling Cycles Inc | Open Energy Information

    Open Energy Info (EERE)

    search Name: Stirling Cycles Inc Place: California Product: A company developing Stirling engine technology at Idealab, acquired by Infinia in June 2007. References:...

  15. Variable pressure power cycle and control system

    DOE Patents [OSTI]

    Goldsberry, Fred L.

    1984-11-27

    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.

  16. GREET Life-Cycle Analysis of Biofuels

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

    ... and data to Billion Ton Study Sustainability Chapter in collaboration with other ... and academia use to assess life-cycle energy and environmental metrics of biofuels. ...

  17. Combined rankine and vapor compression cycles

    DOE Patents [OSTI]

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

    2005-04-19

    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.

  18. 2014 Brayton Cycle Workshop and Industry Day

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

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management ...

  19. recuperative heat transfer within the Brayton cycle

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

    recuperative heat transfer within the Brayton cycle - Sandia Energy Energy Search Icon ... SunShot Grand Challenge: Regional Test Centers recuperative heat transfer within the ...

  20. Combustion and Carbon Cycle 2.0 and Computation in CC 2.0 (Carbon Cycle

    Office of Scientific and Technical Information (OSTI)

    2.0) (Conference) | SciTech Connect Combustion and Carbon Cycle 2.0 and Computation in CC 2.0 (Carbon Cycle 2.0) Citation Details In-Document Search Title: Combustion and Carbon Cycle 2.0 and Computation in CC 2.0 (Carbon Cycle 2.0) Robert Cheng and Juan Meza provide two presentations in one session at the Carbon Cycle 2.0 kick-off symposium Feb. 3, 2010. We emit more carbon into the atmosphere than natural processes are able to remove - an imbalance with negative consequences. Carbon Cycle

  1. Public Involvement and Communications Committee Summaries - Hanford...

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

    05, 2012 Final Attachment 1: Tri-Party Agreement Agencies - Public Involvement Calendar Fiscal Year 2012 - not available Attachment 2: PIC Meeting Transcribed Flip Chart Notes...

  2. Community Involvement and Making a Difference

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

    2016 all issues All Issues submit Community Involvement and Making a Difference A personal message from Kurt Steinhaus, Community Programs Director, Los Alamos National...

  3. Public Involvement and Communications Committee Page 1

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

    November 2, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING November 2, 2011 Kennewick, WA Topics in this Meeting Summary...

  4. Central Plateau Principles Public Involvement Advice DETAILED...

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

    v0, 12914 Central Plateau Principles Public Involvement Advice DETAILED BACKGROUND Cleanup of Hanford's Central Plateau is expected to take another four decades or longer, and...

  5. MHD Integrated Topping Cycle Project

    SciTech Connect (OSTI)

    Not Available

    1992-02-01

    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.

  6. Permafrost soils and carbon cycling

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ping, C. L.; Jastrow, J. D.; Jorgenson, M. T.; Michaelson, G. J.; Shur, Y. L.

    2015-02-05

    Knowledge of soils in the permafrost region has advanced immensely in recent decades, despite the remoteness and inaccessibility of most of the region and the sampling limitations posed by the severe environment. These efforts significantly increased estimates of the amount of organic carbon stored in permafrost-region soils and improved understanding of how pedogenic processes unique to permafrost environments built enormous organic carbon stocks during the Quaternary. This knowledge has also called attention to the importance of permafrost-affected soils to the global carbon cycle and the potential vulnerability of the region's soil organic carbon (SOC) stocks to changing climatic conditions. Inmore » this review, we briefly introduce the permafrost characteristics, ice structures, and cryopedogenic processes that shape the development of permafrost-affected soils, and discuss their effects on soil structures and on organic matter distributions within the soil profile. We then examine the quantity of organic carbon stored in permafrost-region soils, as well as the characteristics, intrinsic decomposability, and potential vulnerability of this organic carbon to permafrost thaw under a warming climate. Overall, frozen conditions and cryopedogenic processes, such as cryoturbation, have slowed decomposition and enhanced the sequestration of organic carbon in permafrost-affected soils over millennial timescales. Due to the low temperatures, the organic matter in permafrost soils is often less humified than in more temperate soils, making some portion of this stored organic carbon relatively vulnerable to mineralization upon thawing of permafrost.« less

  7. Permafrost soils and carbon cycling

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ping, C. L.; Jastrow, J. D.; Jorgenson, M. T.; Michaelson, G. J.; Shur, Y. L.

    2014-10-30

    Knowledge of soils in the permafrost region has advanced immensely in recent decades, despite the remoteness and inaccessibility of most of the region and the sampling limitations posed by the severe environment. These efforts significantly increased estimates of the amount of organic carbon (OC) stored in permafrost-region soils and improved understanding of how pedogenic processes unique to permafrost environments built enormous OC stocks during the Quaternary. This knowledge has also called attention to the importance of permafrost-affected soils to the global C cycle and the potential vulnerability of the region's soil OC stocks to changing climatic conditions. In this review,more » we briefly introduce the permafrost characteristics, ice structures, and cryopedogenic processes that shape the development of permafrost-affected soils and discuss their effects on soil structures and on organic matter distributions within the soil profile. We then examine the quantity of OC stored in permafrost-region soils, as well as the characteristics, intrinsic decomposability, and potential vulnerability of this OC to permafrost thaw under a warming climate.« less

  8. SU-E-I-33: Initial Evaluation of Model-Based Iterative CT Reconstruction Using Standard Image Quality Phantoms

    SciTech Connect (OSTI)

    Gingold, E; Dave, J

    2014-06-01

    Purpose: The purpose of this study was to compare a new model-based iterative reconstruction with existing reconstruction methods (filtered backprojection and basic iterative reconstruction) using quantitative analysis of standard image quality phantom images. Methods: An ACR accreditation phantom (Gammex 464) and a CATPHAN600 phantom were scanned using 3 routine clinical acquisition protocols (adult axial brain, adult abdomen, and pediatric abdomen) on a Philips iCT system. Each scan was acquired using default conditions and 75%, 50% and 25% dose levels. Images were reconstructed using standard filtered backprojection (FBP), conventional iterative reconstruction (iDose4) and a prototype model-based iterative reconstruction (IMR). Phantom measurements included CT number accuracy, contrast to noise ratio (CNR), modulation transfer function (MTF), low contrast detectability (LCD), and noise power spectrum (NPS). Results: The choice of reconstruction method had no effect on CT number accuracy, or MTF (p<0.01). The CNR of a 6 HU contrast target was improved by 167% with iDose4 relative to FBP, while IMR improved CNR by 145367% across all protocols and dose levels. Within each scan protocol, the CNR improvement from IMR vs FBP showed a general trend of greater improvement at lower dose levels. NPS magnitude was greatest for FBP and lowest for IMR. The NPS of the IMR reconstruction showed a pronounced decrease with increasing spatial frequency, consistent with the unusual noise texture seen in IMR images. Conclusion: Iterative Model Reconstruction reduces noise and improves contrast-to-noise ratio without sacrificing spatial resolution in CT phantom images. This offers the possibility of radiation dose reduction and improved low contrast detectability compared with filtered backprojection or conventional iterative reconstruction.

  9. A comparison of conjugate gradient, SIP, and other iterative methods for the solution of Poisson's equation with irregular boundary conditions

    SciTech Connect (OSTI)

    Bergmann, D.J.

    1990-06-01

    Several well known iterative methods for solving Poisson's equation, including Strongly Implicit Procedure and several preconditioned conjugate gradient methods are first applied to a problem with simple boundary conditions and a known solution. Then a problem with more complicated boundary conditions, similar to those encountered when modeling AVLIS plasmas, is solved. Differences in the solutions of the various methods are examined through the use of Fourier analysis. It was found that combinations of different iterative schemes will in some cases be the most efficient method of solution. 22 refs., 29 figs.

  10. Examination of the Entry to Burn and Burn Control for the ITER 15 MA Baseline and Other Scenarios

    SciTech Connect (OSTI)

    Kesse, Charles E.; Kim, S-H.; Koechl, F.

    2014-09-01

    The entry to burn and flattop burn control in ITER will be a critical need from the first DT experiments. Simulations are used to address time-dependent behavior under a range of possible conditions that include injected power level, impurity content (W, Ar, Be), density evolution, H-mode regimes, controlled parameter (Wth, Pnet, Pfusion), and actuator (Paux, fueling, fAr), with a range of transport models. A number of physics issues at the L-H transition require better understanding to project to ITER, however, simulations indicate viable control with sufficient auxiliary power (up to 73 MW), while lower powers become marginal (as low as 43 MW).

  11. The high-β{sub N} hybrid scenario for ITER and FNSF steady-state missions

    SciTech Connect (OSTI)

    Turco, F.; Petty, C. C.; Luce, T. C.; Carlstrom, T. N.; Van Zeeland, M. A.; Ferron, J. R.; Heidbrink, W.; Carpanese, F.; Holcomb, C. T.

    2015-05-15

    New experiments on DIII-D have demonstrated the steady-state potential of the hybrid scenario, with 1 MA of plasma current driven fully non-inductively and β{sub N} up to 3.7 sustained for ∼3 s (∼1.5 current diffusion time, τ{sub R}, in DIII-D), providing the basis for an attractive option for steady-state operation in ITER and FNSF. Excellent confinement is achieved (H{sub 98y2} ∼ 1.6) without performance limiting tearing modes. The hybrid regime overcomes the need for off-axis current drive efficiency, taking advantage of poloidal magnetic flux pumping that is believed to be the result of a saturated 3/2 tearing mode. This allows for efficient current drive close to the axis, without deleterious sawtooth instabilities. In these experiments, the edge surface loop voltage is driven down to zero for >1 τ{sub R} when the poloidal β is increased above 1.9 at a plasma current of 1.0 MA and the ECH power is increased to 3.2 MW. Stationary operation of hybrid plasmas with all on-axis current drive is sustained at pressures slightly above the ideal no-wall limit, while the calculated ideal with-wall MHD limit is β{sub N} ∼ 4–4.5. Off-axis Neutral Beam Injection (NBI) power has been used to broaden the pressure and current profiles in this scenario, seeking to take advantage of higher predicted kink stability limits and lower values of the tearing stability index Δ′, as calculated by the DCON and PEST3 codes. Results based on measured profiles predict ideal limits at β{sub N} > 4.5, 10% higher than the cases with on-axis NBI. A 0-D model, based on the present confinement, β{sub N} and shape values of the DIII-D hybrid scenario, shows that these plasmas are consistent with the ITER 9 MA, Q = 5 mission and the FNSF 6.7 MA scenario with Q = 3.5. With collisionality and edge safety factor values comparable to those envisioned for ITER and FNSF, the high-β{sub N} hybrid represents an attractive high performance option for the steady-state missions of these devices.

  12. Physics challenges for advanced fuel cycle assessment

    SciTech Connect (OSTI)

    Giuseppe Palmiotti; Massimo Salvatores; Gerardo Aliberti

    2014-06-01

    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.

  13. Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Conference: Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies Citation Details In-Document Search Title: Fast Reactor Fuel Cycle Cost Estimates for Advanced Fuel Cycle Studies Authors: Harrison, Thomas J [1] + Show Author Affiliations ORNL [ORNL Publication Date: 2013-01-01 OSTI Identifier: 1107836 DOE Contract Number: DE-AC05-00OR22725 Resource Type: Conference Resource Relation: Conference: Technical Meeting on Fast Reactors and Related

  14. Triple-effect absorption chiller cycles

    SciTech Connect (OSTI)

    DeVault, R.C. ); Grossman, G. )

    1992-01-01

    Gas-fired absorption chillers are widely used for air-conditioning buildings. Even the highest efficiency double-effect absorption chillers used more primary energy for air-conditioning buildings than the better electric chillers. Two different triple-effect absorption chiller cycles are capable of substantial performance improvement over equivalent double-effect cycles. One cycle uses two condensers and two absorbers to achieve the triple effect.'' A second cycle, the Double-Condenser Coupled Triple-Effect, uses three condensers as well as a third condenser subcooler (which exchanges heat with the lowest temperature first-effect generator). These triple-effect absorption cycles have the potential to be as energy efficient (on a primary fuel basis) as the best electric chillers. 19 refs.

  15. Triple-effect absorption chiller cycles

    SciTech Connect (OSTI)

    DeVault, R.C.; Grossman, G.

    1992-06-01

    Gas-fired absorption chillers are widely used for air-conditioning buildings. Even the highest efficiency double-effect absorption chillers used more primary energy for air-conditioning buildings than the better electric chillers. Two different triple-effect absorption chiller cycles are capable of substantial performance improvement over equivalent double-effect cycles. One cycle uses two condensers and two absorbers to achieve the ``triple effect.`` A second cycle, the Double-Condenser Coupled Triple-Effect, uses three condensers as well as a third condenser subcooler (which exchanges heat with the lowest temperature first-effect generator). These triple-effect absorption cycles have the potential to be as energy efficient (on a primary fuel basis) as the best electric chillers. 19 refs.

  16. Design Analysis and Manufacturing Studies for ITER In-Vessel Coils

    SciTech Connect (OSTI)

    Kalish, M.; Heitzenroeder, P.; Neumeyer, C.; Titus, P.; Zhai, Y.; Zatz, I.; Messineo, M.; Gomez, M.; Hause, C.; Daly, E.; Martin, A.; Wu, Y.; Jin, J.; Long, F.; Song, Y.; Wang, Z.; Yun, Zan; Hsiao, J.; Pillsbury, J. R.; Bohm, T.; Sawan, M.; Jiang, NFN

    2014-07-01

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

  17. FETI Prime Domain Decomposition base Parallel Iterative Solver Library Ver.1.0

    Energy Science and Technology Software Center (OSTI)

    2003-09-15

    FETI Prime is a library for the iterative solution of linear equations in solid and structural mechanics. The algorithm employs preconditioned conjugate gradients, with a domain decomposition-based preconditioner. The software is written in C++ and is designed for use with massively parallel computers, using MPI. The algorithm is based on the FETI-DP method, with additional capabilities for handling constraint equations, as well as interfacing with the Salinas structural dynamics code and the Finite Element Interfacemore » (FEI) library. Practical Application: FETI Prime is designed for use with finite element-based simulation codes for solid and structural mechanics. The solver uses element matrices, connectivity information, nodal information, and force vectors computed by the host code and provides back the solution to the linear system of equations, to the user specified level of accuracy, The library is compiled with the host code and becomes an integral part of the host code executable.« less

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

    SciTech Connect (OSTI)

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

    1999-04-01

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

  19. Iterative Monte Carlo analysis of spin-dependent parton distributions

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Sato, Nobuo; Melnitchouk, Wally; Kuhn, Sebastian E.; Ethier, Jacob J.; Accardi, Alberto

    2016-04-05

    We present a comprehensive new global QCD analysis of polarized inclusive deep-inelastic scattering, including the latest high-precision data on longitudinal and transverse polarization asymmetries from Jefferson Lab and elsewhere. The analysis is performed using a new iterative Monte Carlo fitting technique which generates stable fits to polarized parton distribution functions (PDFs) with statistically rigorous uncertainties. Inclusion of the Jefferson Lab data leads to a reduction in the PDF errors for the valence and sea quarks, as well as in the gluon polarization uncertainty at x ≳ 0.1. Furthermore, the study also provides the first determination of the flavor-separated twist-3 PDFsmore » and the d2 moment of the nucleon within a global PDF analysis.« less

  20. Pipeline bottoming cycle study. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    The technical and economic feasibility of applying bottoming cycles to the prime movers that drive the compressors of natural gas pipelines was studied. These bottoming cycles convert some of the waste heat from the exhaust gas of the prime movers into shaft power and conserve gas. Three typical compressor station sites were selected, each on a different pipeline. Although the prime movers were different, they were similar enough in exhaust gas flow rate and temperature that a single bottoming cycle system could be designed, with some modifications, for all three sites. Preliminary design included selection of the bottoming cycle working fluid, optimization of the cycle, and design of the components, such as turbine, vapor generator and condensers. Installation drawings were made and hardware and installation costs were estimated. The results of the economic assessment of retrofitting bottoming cycle systems on the three selected sites indicated that profitability was strongly dependent upon the site-specific installation costs, how the energy was used and the yearly utilization of the apparatus. The study indicated that the bottoming cycles are a competitive investment alternative for certain applications for the pipeline industry. Bottoming cycles are technically feasible. It was concluded that proper design and operating practices would reduce the environmental and safety hazards to acceptable levels. The amount of gas that could be saved through the year 2000 by the adoption of bottoming cycles for two different supply projections was estimated as from 0.296 trillion ft/sup 3/ for a low supply projection to 0.734 trillion ft/sup 3/ for a high supply projection. The potential market for bottoming cycle equipment for the two supply projections varied from 170 to 500 units of varying size. Finally, a demonstration program plan was developed.

  1. Ultralow dose computed tomography attenuation correction for pediatric PET CT using adaptive statistical iterative reconstruction

    SciTech Connect (OSTI)

    Brady, Samuel L.; Shulkin, Barry L.

    2015-02-15

    Purpose: To develop ultralow dose computed tomography (CT) attenuation correction (CTAC) acquisition protocols for pediatric positron emission tomography CT (PET CT). Methods: A GE Discovery 690 PET CT hybrid scanner was used to investigate the change to quantitative PET and CT measurements when operated at ultralow doses (1035 mA s). CT quantitation: noise, low-contrast resolution, and CT numbers for 11 tissue substitutes were analyzed in-phantom. CT quantitation was analyzed to a reduction of 90% volume computed tomography dose index (0.39/3.64; mGy) from baseline. To minimize noise infiltration, 100% adaptive statistical iterative reconstruction (ASiR) was used for CT reconstruction. PET images were reconstructed with the lower-dose CTAC iterations and analyzed for: maximum body weight standardized uptake value (SUV{sub bw}) of various diameter targets (range 837 mm), background uniformity, and spatial resolution. Radiation dose and CTAC noise magnitude were compared for 140 patient examinations (76 post-ASiR implementation) to determine relative dose reduction and noise control. Results: CT numbers were constant to within 10% from the nondose reduced CTAC image for 90% dose reduction. No change in SUV{sub bw}, background percent uniformity, or spatial resolution for PET images reconstructed with CTAC protocols was found down to 90% dose reduction. Patient population effective dose analysis demonstrated relative CTAC dose reductions between 62% and 86% (3.2/8.30.9/6.2). Noise magnitude in dose-reduced patient images increased but was not statistically different from predose-reduced patient images. Conclusions: Using ASiR allowed for aggressive reduction in CT dose with no change in PET reconstructed images while maintaining sufficient image quality for colocalization of hybrid CT anatomy and PET radioisotope uptake.

  2. Evaluation of static mixer flow enhancements for cryogenic viscous compressor prototype for ITER vacuum system

    SciTech Connect (OSTI)

    Duckworth, Robert C.; Baylor, Larry R.; Meitner, Steven J.; Combs, Stephen K.; Ha, Tam; Morrow, Michael; Biewer, T. [Fusion and Materials for Nuclear System Division, Oak Ridge National Laboratory, Oak Ridge (United States); Rasmussen, David A.; Hechler, Michael P. [U.S. ITER Project Office, Oak Ridge National Laboratory, Oak Ridge (United States); Pearce, Robert J. H.; Dremel, Mattias [ITER Organization, 13115 St. Paul-lez-Durance (France); Boissin, J.-C. [Consultant, Grenoble (France)

    2014-01-29

    As part of the U.S. ITER contribution to the vacuum systems for the ITER fusion project, a cryogenic viscous compressor (CVC) is being designed and fabricated to cryopump hydrogenic gases in the torus and neutral beam exhaust streams and to regenerate the collected gases to controlled pressures such that they can be mechanically pumped with controlled flows to the tritium reprocessing facility. One critical element of the CVC design that required additional investigation was the determination of flow rates of the low pressure (up to 1000 Pa) exhaust stream that would allow for complete pumping of hydrogenic gases while permitting trace levels of helium to pass through the CVC to be pumped by conventional vacuum pumps. A sub-scale prototype test facility was utilized to determine the effectiveness of a static mixer pump tube concept, which consisted of a series of rotated twisted elements brazed into a 2-mm thick, 5-cm diameter stainless steel tube. Cold helium gas flow provided by a dewar and helium transfer line was used to cool the exterior of the static mixer pump tube. Deuterium gas was mixed with helium gas through flow controllers at different concentrations while the composition of the exhaust gas was monitored with a Penning gauge and optical spectrometer to determine the effectiveness of the static mixer. It was found that with tube wall temperatures between 6 K and 9 K, the deuterium gas was completely cryopumped and only helium passed through the tube. These results have been used to design the cooling geometry and the static mixer pump tubes in the full-scale CVC prototype.

  3. Advancing the Physics Basis of Quiescent H-mode through Exploration of ITER Relevant Parameters

    SciTech Connect (OSTI)

    Solomon, W. M.; Burrell, K. H.; Fenstermacher, M. E.; Garofalo, A. M.; Grierson, B. A.; Loarte, A.; McKee, G. R.; Nazikian, R.; Snyder, B. P.

    2014-09-01

    Recent experiments on DIII-D have overcome a long-standing limitation in accessing quiescent H-mode (QH-mode), a high confinement state of the plasma that does not exhibit the explosive instabilities associated with edge localized modes (ELMs). In the past, QH-mode was associated with low density operation, but has now been extended to high normalized densities compatible with operation envisioned for ITER. Through the use of strong shaping, QH-mode plasmas have been maintained at high densities, both absolute (?e ? 7 1019 m3) and normalized Greenwald fraction (?e/?G > 0:7) . In these plasmas, the pedestal can evolve to very high pressures and current as the density is increased. Calculations of the pedestal height and width from the EPED model are quantitatively consistent with the experimental observed evolution with density. The comparison of the dependence of the maximum density threshold for QH-mode with plasma shape help validate the underlying theoretical peeling-ballooning models describing ELM stability. High density QH-mode operation with strong shaping has allowed stable access to a previously predicted regime of very high pedestal dubbed \\Super H-mode". In general, QH-mode is found to achieve ELM-stable operation while maintaining adequate impurity exhaust, due to the enhanced impurity transport from an edge harmonic oscillation, thought to be a saturated kink- peeling mode driven by rotation shear. In addition, the impurity confinement time is not affected by rotation, even though the energy confinement time and measured E ? B shear is observed to increase at low toroidal rotation. Together with demonstrations of high beta, high confinement and low q95 for many energy confinement times, these results suggest QH-mode as a potentially attractive operating scenario for ITER's Q=10 mission.

  4. An iterative particle filter approach for coupled hydro-geophysical inversion of a controlled infiltration experiment

    SciTech Connect (OSTI)

    Manoli, Gabriele; Rossi, Matteo; Pasetto, Damiano; Deiana, Rita; Ferraris, Stefano; Cassiani, Giorgio; Putti, Mario

    2015-02-15

    The modeling of unsaturated groundwater flow is affected by a high degree of uncertainty related to both measurement and model errors. Geophysical methods such as Electrical Resistivity Tomography (ERT) can provide useful indirect information on the hydrological processes occurring in the vadose zone. In this paper, we propose and test an iterated particle filter method to solve the coupled hydrogeophysical inverse problem. We focus on an infiltration test monitored by time-lapse ERT and modeled using Richards equation. The goal is to identify hydrological model parameters from ERT electrical potential measurements. Traditional uncoupled inversion relies on the solution of two sequential inverse problems, the first one applied to the ERT measurements, the second one to Richards equation. This approach does not ensure an accurate quantitative description of the physical state, typically violating mass balance. To avoid one of these two inversions and incorporate in the process more physical simulation constraints, we cast the problem within the framework of a SIR (Sequential Importance Resampling) data assimilation approach that uses a Richards equation solver to model the hydrological dynamics and a forward ERT simulator combined with Archie's law to serve as measurement model. ERT observations are then used to update the state of the system as well as to estimate the model parameters and their posterior distribution. The limitations of the traditional sequential Bayesian approach are investigated and an innovative iterative approach is proposed to estimate the model parameters with high accuracy. The numerical properties of the developed algorithm are verified on both homogeneous and heterogeneous synthetic test cases based on a real-world field experiment.

  5. Benchmarking MELCOR 1.8.2 for ITER Against Recent EVITA Results

    SciTech Connect (OSTI)

    Merrill, Brad J

    2007-11-01

    A version of MELCOR 1.8.2 modified for use in ITER Preliminary Safety Report analyses was validated against recent data from the EVITA facility located in Cadarache, France. EVITA Test Series 7 was used for this study to verify MELCOR’s ability to predict the pressures, temperatures, cryoplate ice mass, and vaccum vessel (VV) condensate mass for test conditions in EVITA that include injections of steam, nitrogen, and water in to the EVITA VV after the walls had been heated to 165 ºC and the cryoplate had been cooled to -193 ºC. In general, the ability of MELCOR to predict the VV pressure and wall temperatures for the steam only and water only injection tests was very good. Predicted ice layer masses where larger than reported for the EVITA cryoplate, in particular for the steam only injection tests (~40% too high), and the predicted condensate masses were less that measured in EVITA. Both of these descrpancies can be explained by ice porosity. The modified MELCOR 1.8.2 over predicts the EVITA VV pressure for the co-injection tests (e.g., steam plus nitrogen, or water plus nitrogen injections) by almost a factor of two. Based on parametric runs that where made by increasing the predicted cryoplate condensation rate, it is believed that this pressure over prediction is a result of an under predicted cryoplate condensation rate. The particulars of this study are documented in this report as well as conclusions about the impact this study has regarding the use of this verions of MELCOR for consequence analyses for ITER safety reports.

  6. Pre-Commercial Demonstration of Direct Non-Iterative State Estimator (DNSE+)

    SciTech Connect (OSTI)

    Lelic, Dino

    2015-04-24

    The objective of this DOE co-funded project is to demonstrate functionality and performance of a production-grade Direct Non-iterative State Estimator (DNSE) through its integration with NYPA’s Energy Management System (EMS) and an enhanced Real Time Dynamics Monitoring System (RTDMS) synchrophasor platform from Electric Power Group (EPG). A production-grade DNSE aims to overcome a major obstacle to the operational use of synchrophasor data in Synchro-Phasor Management Systems (SPMS) by providing SPMS applications with a consistent and a complete synchrophasor data foundation in the same way that a traditional EMS State Estimator (SE) provides to EMS applications. Specifically, the DNSE uses synchrophasor measurements and Supervisory Control and Data Acquisition (SCADA) measurements, together with the complete power system model, to simultaneously obtain the complete state of the entire utility’s operating model at rates that are close to the synchrophasor data rates. The full system coverage property is what distinguishes the DNSE from the linear synchrophasor SEs (which cover only parts of the operating model that are visible through synchrophasor measurements), and DNSE differs from traditional EMS SE in that the solution is obtained without iterations, without initial values (hence the “direct” in the name), and at a much higher execution rate. This presentation provides an overview of the project objectives, a brief description of the main tasks including the development work to productize and optimize DNSE from its current MATLAB code base, RTDMS enhancement for interfacing with the DNSE, factory acceptance testing, field installation, testing and demonstration, as well as the current status of the project execution.

  7. Flow distribution analysis on the cooling tube network of ITER thermal shield

    SciTech Connect (OSTI)

    Nam, Kwanwoo; Chung, Wooho; Noh, Chang Hyun; Kang, Dong Kwon; Kang, Kyoung-O; Ahn, Hee Jae; Lee, Hyeon Gon

    2014-01-29

    Thermal shield (TS) is to be installed between the vacuum vessel or the cryostat and the magnets in ITER tokamak to reduce the thermal radiation load to the magnets operating at 4.2K. The TS is cooled by pressurized helium gas at the inlet temperature of 80K. The cooling tube is welded on the TS panel surface and the composed flow network of the TS cooling tubes is complex. The flow rate in each panel should be matched to the thermal design value for effective radiation shielding. This paper presents one dimensional analysis on the flow distribution of cooling tube network for the ITER TS. The hydraulic cooling tube network is modeled by an electrical analogy. Only the cooling tube on the TS surface and its connecting pipe from the manifold are considered in the analysis model. Considering the frictional factor and the local loss in the cooling tube, the hydraulic resistance is expressed as a linear function with respect to mass flow rate. Sub-circuits in the TS are analyzed separately because each circuit is controlled by its own control valve independently. It is found that flow rates in some panels are insufficient compared with the design values. In order to improve the flow distribution, two kinds of design modifications are proposed. The first one is to connect the tubes of the adjacent panels. This will increase the resistance of the tube on the panel where the flow rate is excessive. The other design suggestion is that an orifice is installed at the exit of tube routing where the flow rate is to be reduced. The analysis for the design suggestions shows that the flow mal-distribution is improved significantly.

  8. Application of the Jacobian-Free Newton-Krylov Method to Nonlinear Acceleration of Transport Source Iteration in Slab Geometry

    SciTech Connect (OSTI)

    Dana A. Knoll; H. Park; Kord Smith

    2011-02-01

    The use of the Jacobian-free Newton-Krylov (JFNK) method within the context of nonlinear diffusion acceleration (NDA) of source iteration is explored. The JFNK method is a synergistic combination of Newton's method as the nonlinear solver and Krylov methods as the linear solver. JFNK methods do not form or store the Jacobian matrix, and Newton's method is executed via probing the nonlinear discrete function to approximate the required matrix-vector products. Current application of NDA relies upon a fixed-point, or Picard, iteration to resolve the nonlinearity. We show that the JFNK method can be used to replace this Picard iteration with a Newton iteration. The Picard linearization is retained as a preconditioner. We show that the resulting JFNK-NDA capability provides benefit in some regimes. Furthermore, we study the effects of a two-grid approach, and the required intergrid transfers when the higher-order transport method is solved on a fine mesh compared to the low-order acceleration problem.

  9. The ITER VIS/IR wide angle viewing system: Challenges and on-going R and D

    SciTech Connect (OSTI)

    Travere, J. M.; Aumeunier, M. H.; Joanny, M.; Jouve, M.; Martin, V.; Moncada, V.; Salasca, S.; Marot, L.; Chabaud, D.; Ferme, J. J.; Bremond, F.; Thonnat, M.

    2011-07-01

    The ITER tokamak is the next generation fusion device which will allow studying burning plasma obtained by a Deuterium-Tritium (D-T) fusion reaction during hundreds of seconds. ITER vacuum vessel real-time protection will be mandatory during plasma operation to avoid water leaks and critical plasma facing components degradation. The protection system will be based on a wide angle viewing system (WAVS) composed with 18 visible (VIS) and 18 infrared (IR) cameras covering 80 % of the vacuum vessel which will be one of the major imaging systems of ITER. Compared to protection systems routinely used on current tokamaks and based on imaging (VIS and/or IR), new constraints must be taken into account because of their influence on the system performance: the harsh environment (high neutron flux) and the metallic plasma facing components (both first wall and divertor). In this new demanding context, we have achieved three mandatory R and D studies starting from the understanding of the source of signals by using realistic photonic simulation up to real-time processing strategy taken into account first order optical design constraints to define what type of performance could be reached for ITER vacuum vessel protection. (authors)

  10. Thermodynamic analysis of adsorption refrigeration cycles

    SciTech Connect (OSTI)

    Saha, B.B.; Akisawa, Atsushi; Kashiwagi, Takao

    1997-12-31

    High- and mid-temperature waste heat can be recovered by using existing heat pump technologies. However, heat utilization near environmental temperatures still faces technical hurdles. Silica gel-water adsorption cycles have a distinct advantage over other systems in their ability to be driven by near-ambient temperature heat. Waste heat (above 60 C) can be exploited by using conventional silica gel-water adsorption chiller. The advanced silica gel-water adsorption chiller can operate effectively by utilizing low-grade waste heat ({approximately}50 C) as the driving source with a cooling source of 30 C. In this paper, the effect of operating temperatures on cycle performance is discussed from the thermodynamic viewpoint. The temperature effectiveness and the entropy generation number on cycle time are analyzed. For a comparatively short cycle time, adsorber/desorber heat exchanger temperature effectiveness reaches up to 92% after only 200 sec. The entropy generation number N{sub s} is defined by the ratio between irreversibility generated during a cycle and availability of the heat transfer fluid. The result showed that for the advanced adsorption cycle the entropy generation number N{sub s} is smaller for hot water temperature between 45 to 55 C with a cooling source of 30 C, while for the conventional cycle N{sub s} is smaller for hot water temperature between 65 to 75 C /with the same cooling source temperature.

  11. Waste Stream Analyses for Nuclear Fuel Cycles

    SciTech Connect (OSTI)

    N. R. Soelberg

    2010-08-01

    A high-level study was performed in Fiscal Year 2009 for the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) Advanced Fuel Cycle Initiative (AFCI) to provide information for a range of nuclear fuel cycle options (Wigeland 2009). At that time, some fuel cycle options could not be adequately evaluated since they were not well defined and lacked sufficient information. As a result, five families of these fuel cycle options are being studied during Fiscal Year 2010 by the Systems Analysis Campaign for the DOE NE Fuel Cycle Research and Development (FCRD) program. The quality and completeness of data available to date for the fuel cycle options is insufficient to perform quantitative radioactive waste analyses using recommended metrics. This study has been limited thus far to qualitative analyses of waste streams from the candidate fuel cycle options, because quantitative data for wastes from the front end, fuel fabrication, reactor core structure, and used fuel for these options is generally not yet available.

  12. A combined cycle engine test facility

    SciTech Connect (OSTI)

    Engers, R.; Cresci, D.; Tsai, C.

    1995-09-01

    Rocket-Based Combined-Cycle (RBCC) engines intended for missiles and/or space launch applications incorporate features of rocket propulsion systems operating in concert with airbreathing engine cycles. Performance evaluation of these types of engines, which are intended to operate from static sea level take-off to supersonic cruise or accerlerate to orbit, requires ground test capabilities which integrate rocket component testing with airbreathing engine testing. A combined cycle engine test facility has been constructed in the General Applied Science Laboratories, Inc. (GASL) Aeropropulsion Test Laboratory to meet this requirement. The facility was designed to support the development of an innovative combined cycle engine concept which features a rocket based ramjet combustor. The test requirements included the ability to conduct tests in which the propulsive force was generated by rocket only, the ramjet only and simultaneous rocket and ramjet power (combined cycle) to evaluate combustor operation over the entire engine cycle. The test facility provides simulation over the flight Mach number range of 0 to 8 and at various trajectories. The capabilities of the combined cycle engine test facility are presented.

  13. Public Involvement and Communications Committee Page 1

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

    said he believes the heart of the Plan is in pages 7 to 11. He said the section uses language that is frequently used by the Board, including public involvement for better long...

  14. Public Involvement and Communications Committee Page 1

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

    January 13, 2011 FINAL MEETING SUMMARY HANFORD ADVISORY BOARD PUBLIC INVOLVEMENT & COMMUNICATIONS COMMITTEE MEETING January 13, 2011 Richland, WA Topics in this Meeting Summary Welcome and Introductions ............................................................................................................ 1 State of the Site Meetings ............................................................................................................... 2 Open Government Plan Advice

  15. Strategic Public Involvement Products For Review

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

    Public Involvement Products For Review PIC Discussion September 4, 2013 1 This list is from July 7, 2010 before we had decided on writing advice and is purely for reference for...

  16. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Jones, R.; Carter, J.

    2010-10-13

    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.

  17. FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION

    SciTech Connect (OSTI)

    Carter, J.

    2011-01-03

    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.

  18. Closed Fuel Cycle Waste Treatment Strategy

    SciTech Connect (OSTI)

    Vienna, J. D.; Collins, E. D.; Crum, J. V.; Ebert, W. L.; Frank, S. M.; Garn, T. G.; Gombert, D.; Jones, R.; Jubin, R. T.; Maio, V. C.; Marra, J. C.; Matyas, J.; Nenoff, T. M.; Riley, B. J.; Sevigny, G. J.; Soelberg, N. R.; Strachan, D. M.; Thallapally, P. K.; Westsik, J. H.

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form with encapsulated nano-sized AgI crystals; Carbon-14 immobilized as a CaCO3 in a cement waste form; Krypton-85 stored as a compressed gas; An aqueous reprocessing high-level waste (HLW) raffinate waste immobilized by the vitrification process; An undissolved solids (UDS) fraction from aqueous reprocessing of LWR fuel either included in the borosilicate HLW glass or immobilized in the form of a metal alloy or titanate ceramics; Zirconium-based LWR fuel cladding hulls and stainless steel (SS) fuel assembly hardware super-compacted for disposal or purified for reuse (or disposal as low-level waste, LLW) of Zr by reactive gas separations; Electrochemical process salt HLW incorporated into a glass bonded Sodalite waste form; and Electrochemical process UDS and SS cladding hulls melted into an iron based alloy waste form. Mass and volume estimates for each of the recommended waste forms based on the source terms from a representative flowsheet are reported. In addition to the above listed primary waste streams, a range of secondary process wastes are generated by aqueous reprocessing of LWR fuel, metal SFR fuel fabrication, and electrochemical reprocessing of SFR fuel. These secondary wastes have been summarized and volumes estimated by type and classification. The important waste management data gaps and research needs have been summarized for each primary waste stream and selected waste process.

  19. Decontamination Dressdown at a Transportation Accident Involving

    Office of Environmental Management (EM)

    Radioactive Material | Department of Energy Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to

  20. A Good Neighbor: Community Involvement | NREL

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

    A Good Neighbor: Community Involvement At NREL, we are dedicated environmental stewards and are committed to making positive contributions in our community. NREL's main campus is a model for environmental protection and sustainable building practices. Photo of a volunteer at the Foothills Animal Shelter. Charitable Contributions Employees are very involved in the community, giving their time, money, and energy. As staff levels have grown, so have contributions, making NREL Jefferson County's

  1. FOIASI - Special Inquiry Review of Allegations Involving

    Energy Savers [EERE]

    PotentialMisconduct by a Senior Office of Environmental Management Official | Department of Energy FOIASI - Special Inquiry Review of Allegations Involving PotentialMisconduct by a Senior Office of Environmental Management Official FOIASI - Special Inquiry Review of Allegations Involving PotentialMisconduct by a Senior Office of Environmental Management Official In September 2009, the Office of Inspector General (OIG) received multiple allegations concerning improprieties by a senior

  2. Advances in the Understanding of ELM Suppression by Resonant Magnetic Perturbations (RMPs) in DIII-D and Implications for ITER

    SciTech Connect (OSTI)

    Nazikian, R.

    2014-09-01

    Experiments on DIII-D have expanding the operating window for RMP ELM suppression to higher q95 with dominant electron heating and fully non-inductive current drive relevant to advanced modes of ITER operation. Robust ELM suppression has also been obtained with a reduced coil set, mitigating the risk of coil failure in maintaining ELM suppression in ITER. These results significantly expand the operating space and reduce risk for obtaining RMP ELM suppression in ITER. Efforts have also been made to search for 3D cause of ELM suppression. No internal non-axisymmetric structure is detected at the top of the pedestal, indicating that the dominant effect of the RMP is to produce an n=0 transport modification of the profiles. Linear two fluid MHD simulations using M3D-C1 indicate resonant field penetration and significant magnetic stochasticity at the top of the pedestal, consistent with the absence of detectable 3D structure in that region. A profile database was developed to compare the scaling of the pedestal and global confinement with the applied 3D field strength in ELM suppressed and ELM mitigated plasmas. The EPED pedestal model accurately predicts the measured pedestal pressure at the threshold of ELM suppression, increasing confidence in theoretical projections to ITER pedestal conditions. Both the H-factor (H(sub)98y2) and thermal energy confinement time do not degrade substantially with applied RMP fields near the threshold of ELM suppression, enhancing confidence in the compatibility of ITER high performance operation with RMP ELM suppression.

  3. Updating the LED Life Cycle Assessment

    Energy Savers [EERE]

    Part 2: LED Manufacturing and Performance 7 Goal of the New Study Review new literature on the life- cycle assessment of LED products. Determine if newer A-19 products...

  4. World nuclear fuel cycle requirements 1991

    SciTech Connect (OSTI)

    Not Available

    1991-10-10

    The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs.

  5. Techno-Economics & Life Cycle Assessment (Presentation)

    SciTech Connect (OSTI)

    Dutta, A.; Davis, R.

    2011-12-01

    This presentation provides an overview of the techno-economic analysis (TEA) and life cycle assessment (LCA) capabilities at the National Renewable Energy Laboratory (NREL) and describes the value of working with NREL on TEA and LCA.

  6. Project Profile: Brayton Cycle Baseload Power Tower

    Broader source: Energy.gov [DOE]

    Wilson Solarpower, under the Baseload CSP FOA, is validating a proposed utility-scale, Brayton cycle baseload power tower system with a capacity factor of at least 75% and LCOE of $0.09/kWh.

  7. Energy flow, nutrient cycling, and ecosystem resilience

    SciTech Connect (OSTI)

    DeAngelis, D.L.

    1980-08-01

    The resilience, defined here as the speed with which a system returns to equilibrium state following a perturbation, is investigated for both food web energy models and nutrient cycling models. Previous simulation studies of food web energy models have shown that resilience increases as the flux of energy through the food web per unit amount of energy in the steady state web increases. Studies of nutrient cycling models have shown that resilience increases as the mean number of cycles that nutrient (or other mineral) atoms make before leaving the system decreases. In the present study these conclusions are verified analytically for general ecosystem models. The behavior of resilience in food web energy models and nutrient cycling models is a reflection of the time that a given unit, whether of energy or matter, spends in the steady state system. The shorter this residence time is, the more resilient the system is.

  8. Life-Cycle Analysis of Geothermal Technologies

    Broader source: Energy.gov [DOE]

    The results and tools from this project will help GTP and stakeholders determine and communicate GT energy and GHG benefits and water impacts. The life-cycle analysis (LCA) approach is taken to address these effects.

  9. Applying computationally efficient schemes for biogeochemical cycles

    Office of Scientific and Technical Information (OSTI)

    (ACES4BGC) (Technical Report) | SciTech Connect Applying computationally efficient schemes for biogeochemical cycles (ACES4BGC) Citation Details In-Document Search Title: Applying computationally efficient schemes for biogeochemical cycles (ACES4BGC) NCAR contributed to the ACES4BGC project through software engineering work on aerosol model implementation, build system and script changes, coupler enhancements for biogeochemical tracers, improvements to the Community Land Model (CLM) code and

  10. Carbon Capture (Carbon Cycle 2.0)

    ScienceCinema (OSTI)

    Smit, Berend

    2011-06-08

    Berend Smit speaks at the Carbon Cycle 2.0 kick-off symposium Feb. 3, 2010. We emit more carbon into the atmosphere than natural processes are able to remove - an imbalance with negative consequences. Carbon Cycle 2.0 is a Berkeley Lab initiative to provide the science needed to restore this balance by integrating the Labs diverse research activities and delivering creative solutions toward a carbon-neutral energy future. http://carboncycle2.lbl.gov/

  11. Beowawe Binary Bottoming Cycle | Department of Energy

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

    Project objectives: Demonstrate the technical and economic feasibility of electricity generation from the nonconventional geothermal resources of 205°F by extracting waste heat from the brine to power a binary power plant. PDF icon low_mcdonald_beowawe_binary_bottoming_cycle.pdf More Documents & Publications Dixie Valley Bottoming Binary Cycle track 1: Low Temp | geothermal 2015 peer review Hybrid and Advanced Air Cooling

  12. Obligations Notification Cycle and New Obligations Presentation

    National Nuclear Security Administration (NNSA)

    Obligations Notification Cycle and Obligations Notification Cycle and New Obligations New Obligations Bill Benton, DOE/SO-62 Pat Tana, NRC/NSIR Michelle Romano, NAC/NMMSS Obligations Accounting Implementation Workshop Obligations Accounting Implementation Workshop January 13, 2004 January 13, 2004 Crowne Crowne Plaza Plaza Ravinia Ravinia Atlanta, Georgia Atlanta, Georgia Notifications Notifications * There are issues! - Timeliness - Information (or lack thereof) - Other? * DOE Facilities - Bill

  13. Manager`s views of public involvement

    SciTech Connect (OSTI)

    Branch, K.M.; Heerwagen, J.; Bradbury, J.

    1995-12-01

    Four issues commonly form the framework for debates about the acceptability of proposed projects or technologies--the substantive decision or technological choice; the treatment of the community by the proponent organization; the way the decision-making process has been structured and managed; and the status of institutional safeguards and protection. One of the clear messages of cultural theory is that differences in perspectives are a normal and inevitable part of society, and that attempts to resolve differences by persuasion are not likely to work. These findings are useful when considering the goals and possibilities of public involvement as a decision-making tool, and when designing or evaluating public involvement training programs for managers. The research reported here examines the viewpoints and concerns of managers and decision-makers about the four issues identified above, with particular emphasis on their perspectives and concerns about opening decision-making processes to the public and about managers` roles and responsibilities for structuring and managing open decision-making processes. Implications of these findings for public involvement training for managers is also discussed. The data presented in this paper were obtained from face-to-face interviews with managers and decision-makers with experience managing a variety of hazardous waste management decision-making processes. We conducted these interviews in the course of four separate research projects: needs assessments to support the design and development of a public involvement training program for managers; a study of community residents` and managers` perspectives on the chemical stockpile disposal program; an evaluation of the effectiveness of public involvement training for managers in the Department of Energy; and a study to develop indicators of the benefits and costs of public involvement.

  14. Physics and technology in the ion-cyclotron range of frequency on Tore Supra and TITAN test facility: implication for ITER

    SciTech Connect (OSTI)

    Litaudon, X; Bernard, J. M.; Colas, L.; Dumont, R. J.; Argouarch, A.; Bottollier-Curtet, H.; Bremond, S.; Champeaux, S.; Corre, Y.; Dumortier, P.; Firdaouss, M.; Guilhem, D.; Gunn, J. P.; Gouard, Ph.; Hoang, G T; Jacquot, Jonathan; Klepper, C Christopher; Kubic, M.; Kyrytsya, V.; Lombard, G.; Milanesio, D.; Messiaen, A.; Mollard, P.; Meyer, O.; Zarzoso, D.

    2013-01-01

    To support the design of an ITER ion-cyclotron range of frequency heating (ICRH) system and to mitigate risks of operation in ITER, CEA has initiated an ambitious Research & Development program accompanied by experiments on Tore Supra or test-bed facility together with a significant modelling effort. The paper summarizes the recent results in the following areas: Comprehensive characterization (experiments and modelling) of a new Faraday screen concept tested on the Tore Supra antenna. A new model is developed for calculating the ICRH sheath rectification at the antenna vicinity. The model is applied to calculate the local heat flux on Tore Supra and ITER ICRH antennas. Full-wave modelling of ITER ICRH heating and current drive scenarios with the EVE code. With 20 MW of power, a current of 400 kA could be driven on axis in the DT scenario. Comparison between DT and DT(3He) scenario is given for heating and current drive efficiencies. First operation of CW test-bed facility, TITAN, designed for ITER ICRH components testing and could host up to a quarter of an ITER antenna. R&D of high permittivity materials to improve load of test facilities to better simulate ITER plasma antenna loading conditions.

  15. GREET Development and Applications for Life-Cycle Analysis of...

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

    Development and Applications for Life-Cycle Analysis of VehicleFuel Systems Michael Wang, ... (a.k.a. vehicle cycle) for a complete life-cycle analysis (LCA) Establish a ...

  16. Rapid Cycling Synchrotron Option for Project X (Conference) ...

    Office of Scientific and Technical Information (OSTI)

    Rapid Cycling Synchrotron Option for Project X Citation Details In-Document Search Title: Rapid Cycling Synchrotron Option for Project X This paper presents an 8 GeV Rapid Cycling ...

  17. Millimeter wave experiment of ITER equatorial EC launcher mock-up

    SciTech Connect (OSTI)

    Takahashi, K.; Oda, Y.; Kajiwara, K.; Kobayashi, N.; Isozaki, M.; Sakamoto, K.; Omori, T.; Henderson, M.

    2014-02-12

    The full-scale mock-up of the equatorial launcher was fabricated in basis of the baseline design to investigate the mm-wave propagation properties of the launcher, the manufacturability, the cooling line management, how to assemble the components and so on. The mock-up consists of one of three mm-wave transmission sets and one of eight waveguide lines can deliver the mm-wave power. The mock-up was connected to the ITER compatible transmission line and the 170GHz gyrotron and the high power experiment was carried out. The measured radiation pattern of the beam at the location of 2.5m away from the EL mock-up shows the successful steering capability of 20?40. It was also revealed that the radiated profile at both steering and fixed focusing mirror agreed with the calculation. The result also suggests that some unwanted modes are included in the radiated beam. Transmission of 0.5MW-0.4sec and of 0.12MW-50sec were also demonstrated.

  18. Performance evaluation approach for the supercritical helium cold circulators of ITER

    SciTech Connect (OSTI)

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

    2014-01-29

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

  19. Wide-angle ITER-prototype tangential infrared and visible viewing system for DIII-D

    SciTech Connect (OSTI)

    Lasnier, C. J. Allen, S. L.; Ellis, R. E.; Fenstermacher, M. E.; McLean, A. G.; Meyer, W. H.; Morris, K.; Seppala, L. G.; Crabtree, K.; Van Zeeland, M. A.

    2014-11-15

    An imaging system with a wide-angle tangential view of the full poloidal cross-section of the tokamak in simultaneous infrared and visible light has been installed on DIII-D. The optical train includes three polished stainless steel mirrors in vacuum, which view the tokamak through an aperture in the first mirror, similar to the design concept proposed for ITER. A dichroic beam splitter outside the vacuum separates visible and infrared (IR) light. Spatial calibration is accomplished by warping a CAD-rendered image to align with landmarks in a data image. The IR camera provides scrape-off layer heat flux profile deposition features in diverted and inner-wall-limited plasmas, such as heat flux reduction in pumped radiative divertor shots. Demonstration of the system to date includes observation of fast-ion losses to the outer wall during neutral beam injection, and shows reduced peak wall heat loading with disruption mitigation by injection of a massive gas puff.

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

    DOE Patents [OSTI]

    Lee, Heung-Rae

    1997-01-01

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

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

    DOE Patents [OSTI]

    Lee, H.R.

    1997-11-18

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

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

    SciTech Connect (OSTI)

    Saha, Krishnendu; Straus, Kenneth J.; Glick, Stephen J.; Chen, Yu.

    2014-08-28

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

  3. FEMCAM Analysis of SULTAN Test Results for ITER Nb3SN Cable-conduit Conductors

    SciTech Connect (OSTI)

    Yuhu Zhai, Pierluigi Bruzzone, Ciro Calzolaio

    2013-03-19

    Performance degradation due to filament fracture of Nb3 Sn cable-in-conduit conductors (CICCs) is a critical issue in large-scale magnet designs such as ITER which is currently being constructed in the South of France. The critical current observed in most SULTAN TF CICC samples is significantly lower than expected and the voltage-current characteristic is seen to have a much broader transition from a single strand to the CICC. Moreover, most conductors exhibit the irreversible degradation due to filament fracture and strain relaxation under electromagnetic cyclic loading. With recent success in monitoring thermal strain distribution and its evolution under the electromagnetic cyclic loading from in situ measurement of critical temperature, we apply FEMCAM which includes strand filament breakage and local current sharing effects to SULTAN tested CICCs to study Nb3 Sn strain sensitivity and irreversible performance degradation. FEMCAM combines the thermal bending effect during cool down and the EM bending effect due to locally accumulating Lorentz force during magnet operation. It also includes strand filament fracture and related local current sharing for the calculation of cable n value. In this paper, we model continuous performance degradation under EM cyclic loading based on strain relaxation and the transition broadening upon cyclic loading to the extreme cases seen in SULTAN test data to better quantify conductor performance degradation.

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    1983-01-01

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  1. Nuclear Fuel Cycle Option Catalog SAND2015-2174 W

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  18. Economizer refrigeration cycle space heating and cooling system and process

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