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Title: A Fusion Nuclear Science Facility for a fast-track path to DEMO

Journal Article · · Fusion Engineering and Design
 [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

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.

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:
FC02-04ER54698; AC05-00OR22725
OSTI ID:
1358207
Alternate ID(s):
OSTI ID: 1265972
Journal Information:
Fusion Engineering and Design, Vol. 89, Issue 7-8; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 36 works
Citation information provided by
Web of Science

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Cited By (5)

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
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