A fusion nuclear science facility for a fast-track path to DEMO

Garofalo, A. M.; Abdou, M. A.; Canik, John M.; Chan, Vincent S.; Hyatt, A. W.; Hill, D. N.; Morley, N. B.; Navratil, G. A.; Sawan, M. E.; Taylor, T. S.; Wong, C. P. C.; Wu, W.; Ying, Alice

doi:10.1016/j.fusengdes.2014.03.055

A fusion nuclear science facility for a fast-track path to DEMO

Journal Article · Thu Apr 24 00:00:00 EDT 2014 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2014.03.055· OSTI ID:1265972

Garofalo, A. M. ^[1]; Abdou, M. A. ^[2]; Canik, John M. ^[3]; Chan, Vincent S. ^[1]; Hyatt, A. W. ^[1]; Hill, D. N. ^[4]; Morley, N. B. ^[2]; Navratil, G. A. ^[5]; Sawan, M. E. ^[6]; Taylor, T. S. ^[1]; Wong, C. P. C. ^[1]; Wu, W. ^[1]; Ying, Alice ^[2]

General Atomics, San Diego, CA (United States)
Univ. of California, Los Angeles, CA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Columbia Univ., New York, NY (United States)
Univ. of Wisconsin, Madison, WI (United States)

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, B_T= 5.4 T, I_P = 6.6 MA, β_N = 2.75, P_fus = 127 MW. The modest bootstrap fraction of f_BS = 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.

View Accepted Manuscript (DOE)

Research Organization:: General Atomics, San Diego, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)

Grant/Contract Number:: AC05-00OR22725; FC02-04ER54698

OSTI ID:: 1265972

Alternate ID(s):: OSTI ID: 22384952
OSTI ID: 1358207

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: 7-8 Vol. 89; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade Tobita, Kenji; Hiwatari, Ryoji; Sakamoto, Yoshiteru Fusion Science and Technology, Vol. 75, Issue 5 https://doi.org/10.1080/15361055.2019.1600931	journal	April 2019
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