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Overview of the fusion nuclear science facility, a credible break-in step on the path to fusion energy

Journal Article · · Fusion Engineering and Design
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  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Univ. of Wisconsin, Madison, WI (United States)
  3. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  4. Univ. of California, Los Angeles, CA (United States)
  5. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  6. Fusion Nuclear Technology Consulting, Linkenheim-Hochstetten (Germany)
  7. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  8. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  9. Univ. of California, San Diego, La Jolla, CA (United States)
  10. Consultant, O'Fallen, MO (United States)

Here the Fusion Nuclear Science Facility (FNSF) is examined as part of a two step program from ITER to commercial power plants. This first step is considered mandatory to establish the materials and component database in the real fusion in-service environment before proceeding to larger electricity producing facilities. The FNSF can be shown to make tremendous advances beyond ITER, toward a power plant, particularly in plasma duration and fusion nuclear environment. A moderate FNSF is studied in detail, which does not generate net electricity, but does reach the power plant blanket operating temperatures. The full poloidal Dual Coolant Lead Lithium (DCLL) blanket is chosen, with alternates being the Helium Cooled Lead Lithium (HCLL) and Helium Cooled Ceramic Breeder/Pebble Bed (HCCB/PB). Several power plant relevant choices are made in order to follow the philosophy of targeted technologies. Any fusion core component must be qualified by fusion relevant neutron testing and highly integrated non-nuclear testing before it can be installed on the FNSF in order to avoid the high probability of constant failures in a plasma-vacuum system. A range of missions for the FNSF, or any fusion nuclear facility on the path toward fusion power plants, are established and characterized by several metrics. A conservative physics strategy is pursued to accommodate the transition to ultra-long plasma pulses, and parameters are chosen to represent the power plant regime to the extent possible. An operating space is identified, and from this, one point is chosen for further detailed analysis, with R = 4.8 m, a = 1.2 m, IP = 7.9 MA, BT = 7.5 T, βN < 2.7, n/nGr = 0.9, fBS = 0.52, q95 = 6.0, H98 ~1.0, and Q = 4.0. The operating space is shown to be robust to parameter variations. A program is established for the FNSF to show how the missions for the facility are met, with a He/H, a DD and 5 DT phases. The facility requires ~25 years to complete its DT operation, including 7.8 years of neutron production, and the remaining spent on inspections and maintenance. The DD phase is critical to establish the ultra-long plasma pulse lengths. The blanket testing strategy is examined, and shows that many sectors have penetrations for heating and current drive (H/CD), diagnostics, or Test Blanket Modules (TBMs). The hot cell is a critical facility element in order for the FNSF to perform its function of developing the in-service material and component database. The pre-FNSF R&D is laid out in terms of priority topics, with the FNSF phases driving the time-lines for R&D completion. A series of detailed technical assessments of the FNSF operating point are reported in this issue, showing the credibility of such a step, and more detailed emphasis on R&D items to pursue. These include nuclear analysis, thermo-mechanics and thermal-hydraulics, liquid metal thermal hydraulics, transient thermo-mechanics, tritium analysis, maintenance assessment, magnet specification and analysis, materials assessments, core and scrape-off layer (SOL)/divertor plasma examinations.

Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC52-07NA27344; AC02-09CH11466; FG02-86ER52123; FC02-99ER54512; AC05-00OR22725; FG02-98ER54462
OSTI ID:
1874543
Alternate ID(s):
OSTI ID: 22850336
Report Number(s):
LLNL-JRNL-836543; 1055949
Journal Information:
Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Vol. 135; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (8)

Insights into fuel start‐up and self‐sufficiency for fusion energy: The case of CFETR journal February 2019
Investigation of light ion fusion reactions with plasma discharges journal November 2019
Thermal and Electromagnetic Transients in Liquid Metal Surfaces of the FNSF journal May 2019
Critical Exploration of Liquid Metal Plasma-Facing Components in a Fusion Nuclear Science Facility journal June 2019
Potential Impacts of Liquid-Metal Plasma-Facing Components on Heating and Current Drive Actuators for a Fusion Nuclear Science Facility journal July 2019
Design and Analysis of the Liquid Metal Free-Surface Divertor Cooling System journal November 2019
The Impacts of Liquid Metal Plasma-Facing Components on Fusion Reactor Safety and Tritium Management journal November 2019
Theoretical analysis of key factors achieving reversed magnetic shear q -profiles sustained with lower hybrid waves on EAST journal February 2019

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