A Fusion Nuclear Science Facility for a fast-track path to DEMO
Abstract
An accelerated fusion energy development program, a fast-track approach, requires proceeding with a nuclear and materials testing program in parallel with research on burning plasmas, ITER. A Fusion Nuclear Science Facility (FNSF) would address many of the key issues that need to be addressed prior to DEMO, including breeding tritium and completing the fuel cycle, qualifying nuclear materials for high fluence, developing suitable materials for the plasma-boundary interface, and demonstrating power extraction. The Advanced Tokamak (AT) is a strong candidate for an FNSF as a consequence of its mature physics base, capability to address the key issues, and the direct relevance to an attractive target power plant. The standard aspect ratio provides space for a solenoid, assuring robust plasma current initiation,and for an inboard blanket, assuring robust tritium breeding ratio (TBR) >1 for FNSF tritium self-sufficiency and building of inventory needed to start up DEMO. An example design point gives a moderate sized Cu-coil device with R/a = 2.7 m/0.77 κ = 2.3, BT= 5.4 T, IP = 6.6 MA, βN = 2.75, Pfus = 127 MW. The modest bootstrap fraction of fBS = 0.55 provides an opportunity to develop steady state with sufficient current drive for adequate control. Lastly,more »
- Authors:
-
- General Atomics, San Diego, CA (United States)
- Univ. of California, Los Angeles, CA (United States)
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
- Columbia Univ., New York, NY (United States)
- University of Wisconsin Madison
- Publication Date:
- Research Org.:
- General Atomics, San Diego, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)
- OSTI Identifier:
- 1358207
- Alternate Identifier(s):
- OSTI ID: 1265972
- Grant/Contract Number:
- FC02-04ER54698; AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Engineering and Design
- Additional Journal Information:
- Journal Volume: 89; Journal Issue: 7-8; Journal ID: ISSN 0920-3796
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Fusion Nuclear Science Facility; fusion materials; steady-state operation; disruptions; power exhaust; breeding blanket
Citation Formats
Garofalo, Andrea M., Abdou, M., Canik, John M., Chan, Vincent S., Hyatt, Alan W., Hill, David N., Morley, N. B., Navratil, Gerald A., Sawan, M. E., Taylor, Tony S., Wong, Clement P.C., Wu, Wen, and Ying, Alice. A Fusion Nuclear Science Facility for a fast-track path to DEMO. United States: N. p., 2014.
Web. doi:10.1016/j.fusengdes.2014.03.055.
Garofalo, Andrea M., Abdou, M., Canik, John M., Chan, Vincent S., Hyatt, Alan W., Hill, David N., Morley, N. B., Navratil, Gerald A., Sawan, M. E., Taylor, Tony S., Wong, Clement P.C., Wu, Wen, & Ying, Alice. A Fusion Nuclear Science Facility for a fast-track path to DEMO. United States. https://doi.org/10.1016/j.fusengdes.2014.03.055
Garofalo, Andrea M., Abdou, M., Canik, John M., Chan, Vincent S., Hyatt, Alan W., Hill, David N., Morley, N. B., Navratil, Gerald A., Sawan, M. E., Taylor, Tony S., Wong, Clement P.C., Wu, Wen, and Ying, Alice. Thu .
"A Fusion Nuclear Science Facility for a fast-track path to DEMO". United States. https://doi.org/10.1016/j.fusengdes.2014.03.055. https://www.osti.gov/servlets/purl/1358207.
@article{osti_1358207,
title = {A Fusion Nuclear Science Facility for a fast-track path to DEMO},
author = {Garofalo, Andrea M. and Abdou, M. and Canik, John M. and Chan, Vincent S. and Hyatt, Alan W. and Hill, David N. and Morley, N. B. and Navratil, Gerald A. and Sawan, M. E. and Taylor, Tony S. and Wong, Clement P.C. and Wu, Wen and Ying, Alice},
abstractNote = {An accelerated fusion energy development program, a fast-track approach, requires proceeding with a nuclear and materials testing program in parallel with research on burning plasmas, ITER. A Fusion Nuclear Science Facility (FNSF) would address many of the key issues that need to be addressed prior to DEMO, including breeding tritium and completing the fuel cycle, qualifying nuclear materials for high fluence, developing suitable materials for the plasma-boundary interface, and demonstrating power extraction. The Advanced Tokamak (AT) is a strong candidate for an FNSF as a consequence of its mature physics base, capability to address the key issues, and the direct relevance to an attractive target power plant. The standard aspect ratio provides space for a solenoid, assuring robust plasma current initiation,and for an inboard blanket, assuring robust tritium breeding ratio (TBR) >1 for FNSF tritium self-sufficiency and building of inventory needed to start up DEMO. An example design point gives a moderate sized Cu-coil device with R/a = 2.7 m/0.77 κ = 2.3, BT= 5.4 T, IP = 6.6 MA, βN = 2.75, Pfus = 127 MW. The modest bootstrap fraction of fBS = 0.55 provides an opportunity to develop steady state with sufficient current drive for adequate control. Lastly, proceeding with a FNSF in parallel with ITER provides a strong basis to begin construction of DEMO upon the achievement of Q ~ 10 in ITER.},
doi = {10.1016/j.fusengdes.2014.03.055},
journal = {Fusion Engineering and Design},
number = 7-8,
volume = 89,
place = {United States},
year = {Thu Apr 24 00:00:00 EDT 2014},
month = {Thu Apr 24 00:00:00 EDT 2014}
}
Web of Science
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