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Title: 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 » 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.« less

Authors:
 [1];  [2];  [3];  [1];  [1];  [4];  [2];  [5];  [6];  [1];  [1];  [1];  [2]
  1. General Atomics, San Diego, CA (United States)
  2. Univ. of California, Los Angeles, CA (United States)
  3. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  4. Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
  5. Columbia Univ., New York, NY (United States)
  6. 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}
}

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Works referenced in this record:

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Works referencing / citing this record:

Effects of fast ions produced by ICRF heating on the pressure at EAST
journal, November 2019


Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade
journal, April 2019


Drift effects and up-down asymmetry in balanced double-null DIII-D divertor configurations
journal, June 2018

  • Meier, E. T.; Covele, B.; Guo, H. Y.
  • Contributions to Plasma Physics, Vol. 58, Issue 6-8
  • DOI: 10.1002/ctpp.201700167

Evaluation of CFETR as a Fusion Nuclear Science Facility using multiple system codes
journal, January 2015


Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR
journal, December 2019

  • Huang, J.; Gong, X.; Garofalo, A. M.
  • Plasma Physics and Controlled Fusion, Vol. 62, Issue 1
  • DOI: 10.1088/1361-6587/ab56a5