Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Moving beyond ITER toward a demonstration power reactor (Demo) will require the integration of stable high fusion gain in steady-state, advanced methods for dissipating very high divertor heat-fluxes, and adherence to strict limits on in-vessel tritium retention. While ITER will clearly address the issue of high fusion gain, and new and planned long-pulse experiments (EAST, JT60-SA, KSTAR, SST-1) will collectively address stable steady-state highperformance operation, none of these devices will adequately address the integrated heat-flux, tritium retention, and plasma performance requirements needed for extrapolation to Demo. Expressing power exhaust requirements in terms of Pheat/R, future ARIES reactors are projected to operate with 60-200MW/m, a Component Test Facility (CTF) or Fusion Development Facility (FDF) for nuclear component testing (NCT) with 40-50MW/m, and ITER 20-25MW/m. However, new and planned long-pulse experiments are currently projected to operate at values of Pheat/R no more than 16MW/m. Furthermore, none of the existing or planned experiments are capable of operating with very high temperature first-wall (Twall = 600-1000C) which may be critical for understanding and ultimately minimizing tritium retention with a reactor-relevant metallic first-wall. The considerable gap between present and near-term experiments and the performance needed for NCT and Demo motivates the development of the concept for a new experiment -- the National High-power advanced-Torus eXperiment (NHTX) -- whose mission is to study the integration of a fusion-relevant plasma-material interface with stable steady-state high-performance plasma operation.
Physics Design of the National High-power Advanced Torus Experiment
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Moving beyond ITER toward a demonstration power reactor (Demo) will require the integration of stable high fusion gain in steady-state, advanced methods for dissipating very high divertor heat-fluxes, and adherence to strict limits on in-vessel tritium retention. While ITER will clearly address the issue of high fusion gain, and new and planned long-pulse experiments (EAST, JT60-SA, KSTAR, SST-1) will collectively address stable steady-state highperformance operation, none of these devices will adequately address the integrated heat-flux, tritium retention, and plasma performance requirements needed for extrapolation to Demo. Expressing power exhaust requirements in terms of Pheat/R, future ARIES reactors are projected to operate with 60-200MW/m, a Component Test Facility (CTF) or Fusion Development Facility (FDF) for nuclear component testing (NCT) with 40-50MW/m, and ITER 20-25MW/m. However, new and planned long-pulse experiments are currently projected to operate at values of Pheat/R no more than 16MW/m. Furthermore, none of the existing or planned experiments are capable of operating with very high temperature first-wall (Twall = 600-1000C) which may be critical for understanding and ultimately minimizing tritium retention with a reactor-relevant metallic first-wall. The considerable gap between present and near-term experiments and the performance needed for NCT and Demo motivates the development of the concept for a new experiment -- the National High-power advanced-Torus eXperiment (NHTX) -- whose mission is to study the integration of a fusion-relevant plasma-material interface with stable steady-state high-performance plasma operation.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Moving beyond ITER toward a demonstration power reactor (Demo) will require the integration of stable high fusion gain in steady-state, advanced methods for dissipating very high divertor heat-fluxes, and adherence to strict limits on in-vessel tritium retention. While ITER will clearly address the issue of high fusion gain, and new and planned long-pulse experiments (EAST, JT60-SA, KSTAR, SST-1) will collectively address stable steady-state highperformance operation, none of these devices will adequately address the integrated heat-flux, tritium retention, and plasma performance requirements needed for extrapolation to Demo. Expressing power exhaust requirements in terms of Pheat/R, future ARIES reactors are projected to operate with 60-200MW/m, a Component Test Facility (CTF) or Fusion Development Facility (FDF) for nuclear component testing (NCT) with 40-50MW/m, and ITER 20-25MW/m. However, new and planned long-pulse experiments are currently projected to operate at values of Pheat/R no more than 16MW/m. Furthermore, none of the existing or planned experiments are capable of operating with very high temperature first-wall (Twall = 600-1000C) which may be critical for understanding and ultimately minimizing tritium retention with a reactor-relevant metallic first-wall. The considerable gap between present and near-term experiments and the performance needed for NCT and Demo motivates the development of the concept for a new experiment -- the National High-power advanced-Torus eXperiment (NHTX) -- whose mission is to study the integration of a fusion-relevant plasma-material interface with stable steady-state high-performance plasma operation.
Preliminary Physics Motivation and Engineering Design Assessment of the National High Power Torus
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 191
Book Description
In April 2006, Dr. Ray Orbach, Director of the DOE Office of Science, challenged the fusion community to "propose a new facility ... which will put the U.S. at the lead in world fusion science." Analysis of the gaps between expected ITER performance and the requirements of a demonstration power plant (Demo) pointed to the critical and urgent need to develop fusion-relvant plasma-material interface (PMI) solutions consistent with sustained high plasma performance. A survey of world fusion program indicated that present and planned experimental devices do not advance the PMI issue beyond ITER, and a major dedicated experimental facility is warranted. Such a facility should provide the flexibility and access needed to solve plasma boundary challenges related to divertor heat flux and particle exhaust while also developing methods to minimize hydrogenic isotope retention and remaining compatible with high plasma performance.
Publisher:
ISBN:
Category :
Languages : en
Pages : 191
Book Description
In April 2006, Dr. Ray Orbach, Director of the DOE Office of Science, challenged the fusion community to "propose a new facility ... which will put the U.S. at the lead in world fusion science." Analysis of the gaps between expected ITER performance and the requirements of a demonstration power plant (Demo) pointed to the critical and urgent need to develop fusion-relvant plasma-material interface (PMI) solutions consistent with sustained high plasma performance. A survey of world fusion program indicated that present and planned experimental devices do not advance the PMI issue beyond ITER, and a major dedicated experimental facility is warranted. Such a facility should provide the flexibility and access needed to solve plasma boundary challenges related to divertor heat flux and particle exhaust while also developing methods to minimize hydrogenic isotope retention and remaining compatible with high plasma performance.
1978 ERDA Authorization
Author: United States. Congress. House. Committee on Science and Technology
Publisher:
ISBN:
Category : Fossil fuels
Languages : en
Pages : 1392
Book Description
Publisher:
ISBN:
Category : Fossil fuels
Languages : en
Pages : 1392
Book Description
Energy and Water Development Appropriations for 1999
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 1014
Book Description
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 1014
Book Description
1978 ERDA Authorization: February 22, 1977
Author: United States. Congress. House. Committee on Science and Technology. Subcommittee on Fossil and Nuclear Energy Research, Development, and Demonstration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1408
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1408
Book Description
1978 ERDA authorization
Author: United States. Congress. House. Committee on Science and Technology
Publisher:
ISBN:
Category :
Languages : en
Pages : 1394
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 1394
Book Description
Design Innovations of the Next-Step Spherical Torus Experiment and Spherical Torus Development Path
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The spherical torus (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as ITER as it focuses toward the compact Component Test Facility (CTF) and higher toroidal beta regimes to improve the design of DEMO and a Power Plant. To support the ST development path, one option of a Next Step Spherical Torus (NSST) device is examined. NSST is a performance extension (PE) stage ST with a plasma current of 5 - 10 MA, R = 1.5, BT 2.7 T with flexible physics capability to 1) Provide a sufficient physics basis for the design of the CTF, 2) Explore advanced operating scenarios with high bootstrap current fraction / high performance regimes, which can then be utilized by CTF, DEMO, and Power Plants, 3) Contribute to the general plasma / fusion science of high toroidal plasmas. The NSST facility is designed to utilize the TFTR site to minimize the cost and time required for the construction.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The spherical torus (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as ITER as it focuses toward the compact Component Test Facility (CTF) and higher toroidal beta regimes to improve the design of DEMO and a Power Plant. To support the ST development path, one option of a Next Step Spherical Torus (NSST) device is examined. NSST is a performance extension (PE) stage ST with a plasma current of 5 - 10 MA, R = 1.5, BT 2.7 T with flexible physics capability to 1) Provide a sufficient physics basis for the design of the CTF, 2) Explore advanced operating scenarios with high bootstrap current fraction / high performance regimes, which can then be utilized by CTF, DEMO, and Power Plants, 3) Contribute to the general plasma / fusion science of high toroidal plasmas. The NSST facility is designed to utilize the TFTR site to minimize the cost and time required for the construction.
Public Works for Water and Power Development and Energy Research Appropriations for Fiscal Year 1978
Author: United States. Congress. Senate. Committee on Appropriations. Subcommittee on Public Works
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1382
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1382
Book Description
Public Works for Water and Power Development and Energy Research Appropriation Bill, 1978
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Public Works
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 986
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 986
Book Description